IR 05000409/2007002

IR 05000409-07-02, on 08/29/2007 for La Crosse Boiling Water Reactor

ML072610721
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	09/18/2007
From:	Louden P NRC/RGN-III/DNMS/DB
To:	Berg W Dairyland Power Cooperative
References
IR-07-002
Download: ML072610721 (7)

Text

ber 18, 2007

SUBJECT:

NRC INSPECTION REPORT 050-00409/07-02(DNMS) -

LA CROSSE BOILING WATER REACTOR (LACBWR)

Dear Mr. Berg:

On August 29, 2007, 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 August 29, 2007, 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/

Patrick L. Louden, Chief Decommissioning Branch Docket No. 050-00409 License No. DPR-45

Enclosure:

Inspection Report 050-00409/07-02(DNMS)

REGION III==

Docket No.: 050-00409 License No.: DPR-45 Report No. : 050-00409/07-02(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: August 28 through 29, 2007 Inspector: Peter J. Lee, Ph.D., CHP, Health Physicist Approved by: Patrick L. Louden, Chief Decommissioning Branch Enclosure

EXECUTIVE SUMMARY La Crosse Boiling Water Reactor (LACBWR)

NRC Inspection Report 050-00409/07-02 (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 licensee staffing was adequate for the decommissioning activities being performed, and that the training requirements of the Decommissioning Plan were being met. (Section 1.1)

Decommissioning Support Activities

• The licensees maintenance and surveillance activities were conducted in accordance with the maintenance rule, as stated in 10 CFR Part 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)

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 the dry fuel storage project.

1.0 Facility Management and Control 1.1 Organization, Management and Cost Controls (IP 36801)

a. Inspection Scope The inspector evaluated the licensees decommissioning staffing and reviewed the training program and training records for the current calendar year, including the fuel handler training, radiation protection training, and general employee training. The inspector also reviewed the training for the contract workers who were granted unescorted access to conduct work in the restricted area.

b. Observations and Findings The licensees staffing was adequate for the level of work being performed and met requirements of Technical Specifications. A review of the training program and training records identified that the workers had received the required training specified in the Decommissioning Plan.

c. Conclusions The inspector determined that the licensee staffing was adequate for the decommissioning activities being performed, and that the training requirements of the Decommissioning Plan were being met.

2.0 Decommissioning Support Activities 2.1 Maintenance and Surveillance (62801)

a. Inspection Scope The inspector reviewed the licensees maintenance requests and surveillances completed during 2007 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.

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

Enclosure

b. Observations and Findings All the maintenance and surveillance for SSCs were conducted in accordance with the licensees program that implemented 10 CFR Part 50.65 (the Maintenance Rule.)

Based on the risk assessment of SSCs, the licensee established 13 functional goals and developed associated monitoring and frequency for each goal. The licensee had not generated any incident reports related to the safe storage of spent fuel since its last assessment of maintenance effectiveness conducted in March 2006.

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

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 2007 for licensee and contractor personnel. The inspector reviewed the As-Low-As-is-Reasonably-Achievable (ALARA) reviews and radiation work permits for the cutting and removal of upper and lower recirculation loops. The inspector verified that the licensee had established procedures, and engineering work controls that were based on sound radiation protection principles in order to achieve occupational exposures that were ALARA.

b. Observations and Findings The licensee provided sufficient shielding of radiation sources in a practical manner.

Also, to reduce potential intakes of radioactive materials, the licensee installed high efficiency particulate air filter-equipped (HEPA) filtration systems in the vicinity of the work areas, and workers also wore half-face mask respirators in the reactor lower cavity area.

Based on the review of external exposure records, workers received doses less than the dose limits specified in radiation work permits and 10 CFR Part 20. Based on the breathing zone air sampling results, workers received no significant internal doses.

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

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 four waste shipments since the last inspection. The waste contained concrete shield blocks from around the reactor vessel. The licensee shipped the radiological waste to Energy Solutions burial site in Clive, Utah. 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 August 29, 2007. The licensee did not identify any of the documents or processes reviewed by the inspector as proprietary.

ATTACHMENT: SUPPLEMENTAL INFORMATION 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

• D. Tesar, Security Supervisor

• 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 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 NRC Nuclear Regulatory Commission PARS Publicly Available Records ALARA As Low As is Reasonably Achievable Attachment