IR 05000409/2005002
| ML052560143 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 09/12/2005 |
| From: | Jamnes Cameron NRC/RGN-III/DNMS/DB |
| To: | Berg W Dairyland Power Cooperative |
| References | |
| IR-05-002 | |
| Download: ML052560143 (10) | |
Text
ber 12, 2005
SUBJECT:
NRC INSPECTION REPORT 050-00409/05-002(DNMS) -
LA CROSSE BOILING WATER REACTOR (LACBWR)
Dear Mr. Berg:
On August 25, 2005, the NRC completed an inspection at the La Crosse Boiling Water Reactor (LACBWR) facility. The purpose of the inspection was to determine whether decommissioning activities were conducted safely and in accordance with NRC requirements in the areas of facility management and control, decommissioning support, radiological safety, and spent fuel safety. At the conclusion of the inspection on August 25, 2005, the NRC inspector discussed the findings with members of your staff.
The inspection consisted of an examination of activities at the facility as they relate to safety and compliance with the Commissions rules and regulations. Areas examined during the inspection are identified in the enclosed report. Within these areas, the inspection consisted of a selective examination of procedures and representative records, field observations of activities in progress, and interviews with personnel.
Based on the results of this inspection, the NRC did not identify any violations.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). The NRCs document system is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
We will gladly discuss any questions you have concerning this inspection.
Sincerely,
/RA/
Jamnes L. Cameron, Chief Decommissioning Branch Docket No. 050-00409 License No. DPR-45
Enclosure:
Inspection Report 050-00409/05-002(DNMS)
See Attached Distribution:
DOCUMENT NAME:E:\Filenet\ML052560143.wpd X Publicly Available G Non-Publicly Available G Sensitive X Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME Lee:mb Cameron DATE 09/08/05 09/09/05 OFFICIAL RECORD COPY
REGION III==
Docket No.: 050-00409 License No.: DPR-45 Report No.: 050-00409/05-002(DNMS)
Licensee: Dairyland Power Cooperative 3200 East Avenue South La Crosse, WI 54602 Facility: La Crosse Boiling Water Reactor Location: La Crosse Site Genoa, Wisconsin Dates: August 23 through 25, 2005 Inspector: Peter J. Lee, Ph.D., CHP, Health Physicist Approved by: Jamnes L. Cameron, Chief Decommissioning Branch
EXECUTIVE SUMMARY La Crosse Boiling Water Reactor (LACBWR)
NRC Inspection Report 050-00409/05-002(DNMS)
This routine decommissioning inspection covered aspects of facility management and control, decommissioning support activities, radiological safety, and spent fuel safety.
Facility Management and Control
- The inspector determined that the licensees process for evaluating the safety impacts of design changes and modifications was in compliance with 10 CFR 50.59.
(Section 1.1)
- The inspector determined that the licensee conducted audits that were appropriate for the activities being conducted, and implemented adequate and timely corrective actions in response to audit findings. (Section 1.2)
Decommissioning Support Activities
- The inspector determined that the licensee implemented its maintenance and surveillance programs in accordance with its Operation Manual and Health Safety Procedures. (Section 2.1)
Radiological Safety
- The inspector determined that the licensee continued to be effective in controlling personal exposures and preventing the spread of contamination. (Section 3.1)
- The inspector determined that the licensee complied with NRC and Department of Transportation regulatory requirements for shipping radioactive materials.
(Section 3.2)
- The inspector concluded that the licensee adequately implemented the effluent monitoring program. (Section 3.3)
Spent Fuel Safety
- The inspector determined that the licensee properly maintained the fuel element storage well water level, temperature, chemistry, and cleanliness to ensure the safe wet storage of the spent fuel. (Section 4.1)
Report Details1 Summary of Plant Activities The current licensees activities were focused on routine operations regarding the safe storage of spent fuel in the fuel pool and removal of concrete shield blocks from the lower cavity of the reactor vessel and pipes from the main steam system.
1.0 Facility Management and Control 1.1 Safety Reviews, Design Changes and Modifications (37801)
a. Inspection Scope The inspector reviewed the licensees 10 CFR 50.59 safety screening program and the safety reviews completed since March 2005 to assess the licensees conclusions regarding the need for safety evaluations.
b. Observations and Findings The inspector verified that the safety review process stated in LACBWR Administrative Control Procedure (ACP)-06.4 was consistent with the requirements of 10 CFR 50.59.
The licensee conducted several safety screening reviews of facility changes per ACP-06.4 and determined that none of the changes required a formal 10 CFR 50.59 safety evaluation.
Licensee personnel responsible for the screening reviews had completed an annual refresher training course on the 10 CFR 50.59 screening and evaluation process, and were competent in technical or administrative matters related to the activities being reviewed. The licensee also had provided the 10 CFR 50.59 screening and evaluation process training to the contractor personnel participating in the reactor vessel removal project.
c. Conclusions The inspector determined that the licensees process for evaluating the safety impacts of design changes and modifications was in compliance with the requirements of 10 CFR 50.59.
1.2 Self Assessment, Auditing, and Corrective Actions (40801)
a. Inspection Scope The inspector reviewed Quality Assurance (QA) Audits to determine the effectiveness of the licensees self-assessment program and the effectiveness of corrective actions that were initiated to improve licensee performance.
NOTE: A list of acronyms used in the report is included at the end of the report.
All of the audits completed since the last inspection were minimally reviewed, while the following two audits which were pertinent to current activities were reviewed in depth:
1. QA Audit No. 70-04-03, ODCM/Environmental Monitoring dated January 3 -
February 9, 2005.
2. QA Audit No. 70-04-02, Emergency Planning (EP)/Meteorological Monitoring, dated January - February 2005.
b. Observations and Findings The audits were appropriately focused in both scope and level of detail. In all cases, the licensee initiated appropriate corrective actions in a timely manner to resolve the audit findings.
c. Conclusions The inspector determined that the licensee conducted audits that were appropriate for the activities being conducted, and implemented adequate and timely corrective actions in response to audit findings.
2.0 Decommissioning Support Activities 2.1 Maintenance and Surveillance (62801)
a. Inspection Scope The inspector reviewed the work orders for routine maintenance and surveillance from January 2005 to August 2005 to verify that maintenance and surveillance for structures, systems, and components (SSCs) were conducted in a manner that resulted in the safe storage of spent fuel.
b. Observations and Findings All the maintenance and surveillance for SSCs were conducted in accordance with the licensees Operation Manual and Health Safety Procedures. Thirteen functional goals were established based on the SSC safety significance. No incident reports were generated by the licensee related to the safe storage of spent fuel since its last assessment of maintenance effectiveness conducted on March 10, 2004, which confirmed that all functional goals had been met since then.
c. Conclusions The inspector determined that the licensee implemented its maintenance and surveillance programs in accordance with its Operation Manual and Health Safety Procedures.
3.0 Radiological Safety 3.1 Occupational Radiation Exposure (83750)
a. Inspection Scope The inspector reviewed the external exposure records for the second quarter of 2005 for licensee and contractor personnel. The inspector reviewed the direct radiation survey and smear sample results from the reactor building and the turbine building for the period of April 2005 to August 2005.
b. Observations and Findings Review of personnel external exposure records identified that three contract workers received external exposures of around 1800 millirem (mrem) during the removal of asbestos insulation from the reactor vessel, recirculation piping, and steam piping in the lower cavity. This work was performed in preparation for the removal of the reactor vessel planned for the Winter/Spring of 2007. The doses received were under the 2000 mrem limit as stated in the radiation work permit.
The results of the licensees direct radiation and removable contamination surveys indicated that the licensee appropriately controlled contaminated areas, and contamination levels within the facility had been kept to a minimum.
c. Conclusions The inspector determined that licensee continued to be effective in controlling personal exposures and preventing the spread of contamination.
3.2 Transportation of Radioactive Materials (86750)
a. Inspection Scope The inspector reviewed the radioactive materials shipping program and applicable shipping documents. The inspector evaluated whether the licensee was in compliance with NRC and Department of Transportation (DOT) shipping requirements.
b. Observations and Findings The licensee has processed five radiological waste shipments since the last inspection.
The waste contained concrete shield blocks from around the reactor vessel and metal pipes from the main steam system. The licensee shipped the radiological waste to GTS Duratek in Oak Ridge, Tennessee. The licensee properly prepared the documents for each shipment, including the waste stream analysis for 10 CFR Part 61, the loaded waste shipment radiation surveys, and NRC Forms 540 and 541 for shipment of low-level radioactive waste. The licensee conducted audits of the shipments by reviewing all documents and signed off the checklist before the material left the site.
c. Conclusions The inspector determined that the licensee complied with NRC and DOT regulatory requirements for shipping radioactive materials.
3.3 Radioactive Waste Treatment, and Effluent and Environmental Monitoring (84750)
a. Inspection Scope The inspector examined and evaluated aspects of the effluent monitoring program, including a review of calibration procedures for liquid, gaseous, and air particulate radiation monitors. The inspector also reviewed effluent release data for calendar year (CY) 2005 to verify it met the requirements of Technical Specification (TS) 6.4.2.3, Radioactive Effluent Controls Program.
b. Observations and Findings Review of the applicable records indicated that the primary and secondary stack air effluent monitors, and waste water effluent monitors were properly calibrated and checked for operation in accordance with station procedures. Review of the effluent release data in CY 2005 indicated that the licensee effluent control program met the requirements of TS 6.4.2.3.
c. Conclusions The inspector concluded that the licensee adequately implemented the effluent monitoring program.
4.0 Spent Fuel Safety 4.1 Spent Fuel Pool Safety at Permanently Shutdown Reactors (60801)
a. Inspection Scope The inspector verified the safe wet storage of spent fuel in the Fuel Element Storage Well (FESW). The review included the verification of the March through August 2005 water temperature, level, chemistry, and cleanliness control against the surveillance requirements of TS 5.1.2.1.
b. Observations and Findings All reviewed parameters were within procedural limits. Cleanliness control in the area of the FESW was adequate. The FESW water level and temperature had been monitored daily according to the surveillance requirements of Technical Specification 5.1.2.1.
c. Conclusions The inspector determined that the licensee properly maintained the FESW water level, temperature, chemistry, and cleanliness to ensure the safe wet storage of the spent fuel.
5.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on August 25, 2005. The licensee did not identify any of the documents or processes reviewed by the inspector as proprietary.
PARTIAL LIST OF PERSONS CONTACTED
- R. Christians, Plant Manager
- R. Cota, Training/Security Supervisor
- J. Henkelman, Quality Assurance Specialist
- M. Johnsen, Tech Support Engineer
- L. Nelson, Health and Safety Supervisor
- S. Rafferty, Reactor Engineer
- M. Moe, Captain, Burns Security
- D. Egge, Quality Assurance Supervisor
- R. Lewton, Electrician & Instrument Technician
- J. McRill, Tech Support Engineer
- Persons present at the exit meeting.
INSPECTION PROCEDURES USED IP 37801: Safety Reviews, Design Changes and Modifications IP 40801: Self Assessment, Auditing, and Corrective Actions IP 83750: Occupational Radiation Exposure IP 84750: Radwaste Treatment, Effluent, and Environmental Monitoring IP 86750: Solid Radwaste Management and Transportation of Radioactive Materials IP 60801: Spent Fuel Pool Safety at Permanently Shutdown Reactors IP 62801: Maintenance and Surveillance LIST OF DOCUMENTS REVIEWED The licensee documents reviewed and utilized during the course of this inspection are specifically identified in the Report Details above.
ITEMS OPENED, CLOSED, AND DISCUSSED None
INITIALISM AND ACRONYMS ACP Administrative Control Procedure ADAMS Agencywide Documents Access and Management System CFR Code of Federal Regulations DNMS Division of Nuclear Materials Safety DOT Department of Transportation FESW Fuel element storage well LACBWR La Crosse Boiling Water Reactor NRC Nuclear Regulatory Commission PARS Publicly Available Records QA Quality Assurance SSC Structures, systems, and components TS Technical Specifications 8