IR 05000016/2007009

IR 05000016-07-009, on 09/25/2007 - 09/26/2007, Enrico Fermi Unit 1, Decommissioning Inspection Included Reviews of Facility Management and Control, and Radiological Safety

ML072850189
Person / Time
Site:	Fermi
Issue date:	10/11/2007
From:	Louden P NRC/RGN-III/DNMS/DB
To:	Plona J Detroit Edison
References
IR-07-009
Download: ML072850189 (8)

Text

ber 11, 2007

SUBJECT:

NRC INSPECTION REPORT 050-00016/07-09 (DNMS)

ENRICO FERMI UNIT 1

Dear Mr. Plona:

On September 26, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at the Enrico Fermi Unit 1 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, and radiological safety. At the conclusion of the inspection on September 26, 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 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 W. Snell Acting for/

Patrick L. Louden, Chief Decommissioning Branch Docket No. 050-00016 License No. DPR-9

Enclosure:

Inspection Report 050-00016/07-09(DNMS)

REGION III==

Docket No. 050-00016 License No. DPR-9 Report No. 050-00016/07-09(DNMS)

Licensee: Detroit Edison Company Facility: Enrico Fermi Unit 1 Location: 6400 North Dixie Highway Newport, MI 48166 Dates: September 25-26, 2007 Inspector: Peter J. Lee, Ph.D., CHP, Health Physicist Approved by: Patrick L. Louden, Chief Decommissioning Branch Enclosure

EXECUTIVE SUMMARY Enrico Fermi Unit 1 NRC Inspection Report 050-00016/07-09(DNMS)

This routine decommissioning inspection included reviews of facility management and control, and radiological safety.

Facility Management and Control The inspector determined that the licensees process for evaluating the safety impacts of facility changes was in compliance with the requirements of 10 CFR 50.59. (Section 1.1)

Radiological Safety The inspector determined that the licensee continued to be effective in preventing the spread of contamination and in maintaining dose to workers well below the regulatory limits. (Section 2.1)

The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits. The inspector determined that no detectable licensed materials were found from monitoring wells around the perimeter of the plant.

(Section 2.2)

2 Enclosure

Report Details1 Summary of Plant Activities During the inspection period, the licensee was disassembling the rotating shielding plug and preparing for sodium removal from the reactor.

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

a. Inspection Scope The inspector reviewed the licensees safety screening reviews to verify that completed reviews were consistent with the requirements of 10 CFR 50.59. The review included selected screening reviews completed since January 2007.

b. Observations and Findings The licensees Administrative Controls and Surveillance Procedures Manual, Section 1.6 was consistent with the NRCs requirements for 10 CFR 50.59 screening reviews. The licensee conducted several safety screening reviews of facility changes and none of the 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 facility changes was in compliance with the requirements of 10 CFR 50.59.

2.0 Radiological Safety 2.1 Occupational Radiation Exposure (83750)

a. Inspection Scope The inspector reviewed the results of air sampling, direct radiation surveys, and contamination surveys performed from July 2007 to September 2007, during the removal of graphite blocks from the rotating shielding plug, to determine whether the licensee adequately controlled doses to workers. The inspector reviewed the radiation work permits (RWP) and ALARA reviews for the disassembly of rotating shielding plug to evaluate the potential radiation exposure to the workers.

¹A list of acronyms used and all documents reviewed in these Details are provided at the end of the report.

Enclosure

b. Observations and Findings The ALARA review provided the administrative controls to minimize or avoid unnecessary dose to the workers. The engineering controls such as enclosures with additional HEPA ventilation and shielding, were effectively controlling the workers internal and external exposures, and the spread of contamination.

The results of air sampling did not indicate any potential intake of radioactive material by the workers. The results of personnel monitoring indicated all exposures were less than 10 percent of any applicable occupational limit in 10 CFR Part 20.

The results of contamination surveys did not indicate any spread of contamination during processing removal of graphite shielding blocks from the rotating shielding plug. The direct radiation surveys from the work areas did not indicate any significant potential exposure for the workers.

c. Conclusions The inspector determined that the licensee continued to be effective in preventing the spread of contamination and in maintaining dose to workers well below the regulatory limits.

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

a. Inspection Scope The inspector reviewed the analytical data of gaseous effluent releases for particulates and tritium from July 2007 to September 2007 to verify that the licensee met 10 CFR Part 20 effluent release limits. The inspector reviewed analytical data of groundwater samples taken on April 20, 2007, responding to the flood water release from Fermi 2 on April 14, 2007. The inspector reviewed the routine semiannual analytical data of groundwater samples taken during July 2007 from monitoring wells around the perimeter of the plant.

b. Observations and Findings Both air sampling at the effluence release points and routine ground water sampling from monitoring wells around the perimeter of the plant did not indicate any positive results from particulates and tritium.

In support of cable vault maintenance, approximately 8,400 gallons of flood water was released to the storm sewer. The water showed detectable levels of tritium up to 3,000 picrocuries per liter. However, the groundwater sampling on April 20, 2007, did not indicate any positive result of tritium.

4 Enclosure

c. Conclusions The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits. The inspector determined that no detectable licensed materials were found from monitoring wells around the perimeter of the plant.

3.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on September 26, 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

• L. Goodman, Manager, Fermi 1 (Custodian)

• K.. Lindsey, Radiation Protection Supervisor

• W. Lipton, Principal Engineer, Fermi 2 D. Breiding, Fermi 1 Project Coordinator D. Swindle, Sodium Project Manager

• C. Aldridge-Nunn, Office Administration

• L. Davis, Office Specialist

• Present at the September 26, 2007 exit meeting.

LIST OF PROCEDURES USED IP 37801: Safety Reviews, Design Changes, and Modifications IP 83750: Occupational Radiation Exposure IP 84750: Radioactive Waste Treatment and Effluent and Environmental Monitoring LIST OF ACRONYMS USED ADAMS Agency Document and Management System CFR Code of Federal Regulations DNMS Division of Nuclear Materials Safety NRC Nuclear Regulatory Commission LICENSEE DOCUMENTS REVIEWED 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 6 Enclosure