IR 05000409/2006002

IR 05000409-06-002; on 09/12-14/06, Dairlyland Power Cooperative; La Crosse Boiling Water Reactor

ML062770477
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/04/2006
From:	Jamnes Cameron NRC/RGN-III/DNMS/DB
To:	Berg W Dairyland Power Cooperative
References
IR-06-002
Download: ML062770477 (9)

Text

ber 4, 2006

SUBJECT:

NRC INSPECTION REPORT 050-00409/06-02(DNMS) -

LA CROSSE BOILING WATER REACTOR (LACBWR)

Dear Mr. Berg:

On September 14, 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, and radiological safety. At the conclusion of the inspection on September 14, 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 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 050-00409/06-02(DNMS)

REGION III==

Docket No.: 050-00409 License No.: DPR-45 Report No.: 050-00409/06-02(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: September 12 through 14, 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 050-00409/06-01(DNMS)

This routine decommissioning inspection covered aspects of facility management and control, decommissioning support activities, and radiological 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 the requirements of 10 CFR 50.59. (Section 1.1)

• The inspector determined that the licensee had conducted the proper training and met the requirements of the Decommissioning Plan. (Section 1.2)

Decommissioning Support Activities

• The licensees maintenance and surveillance activities were conducted in accordance with the maintenance rule, as stated in 10 CFR 50.65. (Section 2.1)

Radiological Safety

• The inspector determined that the licensee continued to be effective in controlling workers personal exposure. (Section 3.1)

• The inspector determined that the licensee complied with regulatory requirements for shipping radioactive materials. (Section 3.2)

2 Enclosure

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 and preparations for removal of the reactor pressure vessel.

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 reviews of the Reactor Building modification and restoration, and Biological Shield cutting for the preparation of the reactor removal 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 safety screening reviews of Reactor Building modification and restoration, and Biological Shield cutting per ACP-06.4 and determined that formal 10 CFR 50.59 safety evaluations were not required.

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 Organization, Management and Cost Controls (36801)

a. Inspection Scope The inspector reviewed the training program and training records for the year 2006, including the fuel handler training, radiation protection training, and general employee training. The inspector also reviewed the training for the contractor workers working in the restricted areas without the escort from the licensee personnel.

b. Observations and Findings Review of the training program and training records identified that the workers had received the required training specified in the Decommissioning Plan.

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

3 Enclosure

c. Conclusions The inspector determined that the licensee had conducted the proper training and met the requirements of the Decommissioning Plan.

2.0 Decommissioning Support Activities 2.1 Maintenance and Surveillance (62801)

a. Inspection Scope The inspector reviewed the licensees maintenance requests and surveillances for 2005 and 2006, and periodic assessment of maintenance effectiveness of structures, systems, and components (SSCs) during 2004 and 2005, to verify that maintenance and surveillance for 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 program implementing the 10 CFR 50.65 Maintenance Rule. Based on the risk assessment of SSCs, the licensee established 13 functional goals and associated monitoring and frequency for each goal. The licensees periodic assessments indicated that all functional goals of the SSCs were met.

c. Conclusions The licensees maintenance and surveillance activities were conducted in accordance with the maintenance rule, as stated in 10 CFR 50.65.

3.0 Radiological Safety 3.1 Occupational Radiation Exposure (83750)

a. Inspection Scope The inspector reviewed external exposure records for licensee and contractor personnel involved with the crushing/shearing of fuel shrouds and control rod blades in the spent fuel pool.

b. Observations and Findings Review of external exposure records for workers involved with crushing and shearing of the fuel shroud cans and control rod blades in the spent fuel pool, demonstrated that the doses were below the licensees radiation work permit dose limit of 100 millirem total effective dose equivalent.

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

4 Enclosure

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 two waste shipments since the last inspection, one on June 12, 2006, and the other on July 28, 2006. The shipments contained Class C waste of fuel shroud cans, control rod blades, and beryllium source assemblies. The licensee shipped the radiological waste to Barnwell Waste Management Facility in Barnwell, South Carolina. The licensees shipping manifest showed that personnel packaged, labeled, and marked each shipping container according to the DOT and 10 CFR Part 71 transportation requirements. The licensee verified that the results of radiation and removable contamination levels were within applicable limits. The waste manifest included all required information.

c. Conclusions The inspector determined that the licensee complied with regulatory requirements for shipping radioactive materials.

4.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on September 14, 2006. The licensee did not identify any of the documents or processes reviewed by the inspector as proprietary.

ATTACHMENT: SUPPLEMENTAL INFORMATION 5 Enclosure

SUPPLEMENTAL INFORMATION 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 36801: Organization, Management and Cost Controls IP 83750: Occupational Radiation Exposure IP 86750: Transportation of Radioactive Materials 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 Opened None Closed None Discussed None Attachment

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 LACBWR La Crosse Boiling Water Reactor mrem Millirem NRC Nuclear Regulatory Commission PARS Publicly Available Records 2 Attachment