IR 05000409/2006001

IR 05000409-06-001, on 5/24/2006, La Crosse Boiling Water Reactor (LACBWR)

ML061720113
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/19/2006
From:	Jamnes Cameron NRC/RGN-III/DNMS/DB
To:	Berg W Dairyland Power Cooperative
References
IR-06-001
Download: ML061720113 (10)

Text

une 19, 2006

SUBJECT:

NRC INSPECTION REPORT 050-00409/06-001(DNMS) -

LA CROSSE BOILING WATER REACTOR (LACBWR)

Dear Mr. Berg:

On May 24, 2006, 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 May 24, 2006, 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 by G. McCann/

Jamnes L. Cameron, Chief Decommissioning Branch Docket No. 050-00409 License No. DPR-45

Enclosure:

Inspection Report 050-00409/06-001(DNMS)

REGION III==

Docket No.: 050-00409 License No.: DPR-45 Report No.: 050-00409/06-001(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: March 21 through 23, 2006, and May 23 through 24, 2006 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 050-00409/06-001(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 was in compliance with the requirements of 10 CFR 50.59.

(Section 1.1)

• The inspector determined that the licensees audit and corrective action programs were adequately implemented in accordance with its Quality Assurance Program, and met regulatory requirements. (Section 1.2)

• The inspector determined that the conditions of the facility and equipment were adequate and capable of performing decommissioning activities. (Section 1.3)

Radiological Safety

• The inspector determined that the licensee continued to be effective in controlling workers personal exposure. (Section 2.1)

• The inspector determined that the licensee adequately implemented its effluent monitoring program. (Section 2.2)

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 3.1)

Report Details1 Summary of Plant Activities The licensees current activities were focused on routine operations regarding the safe storage of spent fuel in the fuel pool, preparations for removal of the reactor pressure vessel and Class C waste shipments of fuel shrouds, control rod blades, and beryllium source assemblies from the spent fuel pool.

1.0 Facility Management and Control 1.1 Safety Reviews, Design Changes and Modifications (37801)

a. Inspection Scope The inspector reviewed safety screening reviews performed by the licensees for the reactor pressure vessel (RPV) grouting, and the Class C waste shipment activities.

The licensees reviews were performed pursuant to Title 10, Code of Federal Regulations (CFR) Part 50, Licensing of Production and Utilization Facilities, Section 50.59, Changes, Tests, and Experiments. The inspector evaluated the licensees conclusions regarding the need for conducting these safety reviews.

b. Observations and Findings The licensees safety review process, which is described in La Crosse Boiling Water Reactor (LACBWR) Administrative Control Procedure (ACP)-06.4, was consistent with the requirements of 10 CFR 50.59. The licensee conducted safety screening reviews of RPV grouting and Class C waste shipment activities per ACP-06.4. None of the design changes required a formal 10 CFR 50.59 safety evaluation.

c. Conclusions The inspector determined that the licensees process for evaluating the safety impacts of design changes 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 audits of the licensees Offsite Dose Calculation Manual/Environmental Monitoring Program, and the Health Physic/Chemistry Program for the year 2005. Selected corrective action work orders associated with identified deficiencies were also reviewed..

NOTE: A list of acronyms used in the report is included at the end of the report.

b. Observations and Findings The licensees 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 licensees audit and corrective action programs were adequately implemented in accordance with its Quality Assurance Program, and met regulatory requirements.

1.3 Decommissioning Performance and Status Review at Permanently Shut Down Reactors (71801)

a. Inspection Scope The inspector performed a plant tour to observe and evaluate the licensees activities related to the grouting of the reactor pressure vessel (RPV) and the crushing/shearing of the fuel shrouds in the spent fuel pool.

b. Observations and Findings The workers involved in the RPV grouting and crushing/shearing operations wore appropriate protective equipment and followed established procedures. During the inspection, the licensee successfully completed grouting the RPV and placed 23 zirconium fuel shrouds in the liner.

The RPV and spent fuel pool areas were clear and free of obstacles and hazards. No fire hazards were observed. Installed fire suppression equipment was well identified and accessible. The plant was maintained in good condition and all radiological areas were adequately marked.

c. Conclusions The inspector determined that the conditions of the facility and equipment were adequate and decommissioning activities were performed adequately.

2.0 Radiological Safety 2.1 Occupational Radiation Exposure (83750)

a. Inspection Scope The inspector reviewed external exposure records for licensee and contractor personnel involved with operations to grout the RPV, the crushing/shearing of fuel shrouds and control rod blades in the spent fuel pool. The inspector reviewed air sampling results obtained during operations to cut recirculation piping, to install grout injection points, and during the grouting of the RPV.

b. Observations and Findings The licensee installed high efficiency particulate air filter-equipped (HEPA) filtration systems in the vicinity of the work areas during the cutting of the recirculation piping, and the installation of the grout injection points to reduce potential worker intake of radioactive materials. Also, a HEPA system was installed to create a negative pressure inside the RPV during grouting operations.

The results of air sampling did not indicate any potential intake of radioactive material for workers during the grouting operations. Air sampling data indicated that during recirculation pipe cutting and during he installation of grout injection points that the workers internal doses were less than 2.5 millirem (mrem). The results of personnel monitoring reviewed did not identify any exposures in excess of 10 percent of any applicable occupational limit in 10 CFR Part 20.

Review of external exposure records for workers involved with operations relating to the cutting of the recirculation piping, installing the grout injection points in the lower cavity, and during crushing and shearing of the fuel shrouds and control rod blades in the spent fuel pool, demonstrated that the doses were below the licensees radiation work permit dose limits of 2,000 and 100 mrem, respectively for these operations.

c. Conclusions The inspector determined that the licensee continued to be effective in controlling workers personal exposure.

2.2 Radioactive Waste Treatment, and Effluent and Environmental Monitoring (84750)

a. Inspection Scope The inspector evaluated the licensees activities to effectively control, monitor, and quantify releases of radioactive materials in liquid, gaseous, and particulate forms to the environment. The inspector reviewed the licensees 2005 Effluent and Environmental Monitoring Reports, and the Offsite Dose Calculation Manual (ODCM).

b. Observations and Findings The licensees gaseous effluent monitors and waste water effluent monitor were calibrated and checked for proper operation in accordance with station procedures.

The licensee participates in a cross check program with an off-site laboratory to confirm the quality of its analytical data. Results of a cross checked completed in calendar year 2005 indicated agreement in all analytical data.

The ODCM was comprehensive and contained the requirements listed in the licensees technical specifications. The effluent monitoring data indicated that release concentrations were consistent with limits specified in10 CFR Part 20, Appendix B, Table 2, and that doses to the general public were in conformance with Appendix I of 10 CFR Part 50. Further, environmental sampling results indicated only background radiation levels with no distinct contribution from the shutdown reactor.

c. Conclusions The inspector determined that the licensee adequately implemented its effluent monitoring program.

3.0 Spent Fuel Safety 3.1 Spent Fuel Pool Safety at Permanently Shutdown Reactors (60801)

a. Inspection Scope The inspector reviewed the licensees activities to ensure the safe wet storage of spent fuel in the Fuel Element Storage Well (FESW). The review included the verification of water temperature, and water level requirements of Technical Specification (TS) 4.1.2, the surveillance requirements of TS 5.1.2, and the water chemistry and cleanliness control requirements of the licensees Health and Safety Procedure HSP-7.2, for the period of January through May 2006 b. Observations and Findings All parameters reviewed were consistent with limits specified in HSP-7.2, Sampling of Fuel Element Storage Well. The FESW water level and temperature met the requirements of TS 4.1.2. The FESW water level and temperature had been monitored daily according to the surveillance requirements of TS 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.

4.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on May 24, 2006. 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 70801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 83750: Occupational Radiation Exposure IP 84750: Radwaste Treatment, Effluent, and Environmental Monitoring IP 60801: Spent Fuel Pool Safety at Permanently Shutdown Reactors 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 Opened None Closed None Discussed None INITIALISMS AND ACRONYMS ACP Administrative Control Procedure ADAMS Agencywide Documents Access and Management System CFR Code of Federal Regulations DNMS Division of Nuclear Materials Safety FESW Fuel element storage well LACBWR La Crosse Boiling Water Reactor

mrem Millirem NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual PARS Publicly Available Records RPV Reactor Pressure Vessel TS Technical Specifications 8