IR 05000016/2010010

IR 050-00016/10-10(DNMS) and 050-00016/10-12(DNMS) - Enrico Fermi Unit 1

ML103550406
Person / Time
Site:	Fermi
Issue date:	12/20/2010
From:	Christine Lipa NRC/RGN-III/DNMS/DB
To:	Jennifer Davis Detroit Edison
References
IR-10-012, IR-10-010
Download: ML103550406 (9)

Text

ber 20, 2010

SUBJECT:

NRC INSPECTION REPORTS 050-00016/10-10(DNMS) AND 050-00016/10-12(DNMS) - ENRICO FERMI UNIT 1

Dear Mr. Davis:

On November 22, 2010, 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. At the conclusion of the onsite portion of the inspection on July 15, 2010, the NRC inspector discussed the findings with members of your staff. A final exit meeting was conducted on November 22, 2010, following a further review of information provided to the NRC during and after the onsite portion of the inspection, and the analysis and review of samples collected by the NRC during the inspection.

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 included a review of final status surveys conducted in support of decommissioning. Within these areas, the inspection consisted of a selective examination of procedures and representative records, interviews with personnel, and the conducting of independent radiological confirmatory surveys and sample collection.

Based on the results of this inspection, the NRC did not identify any violations.

In accordance with Title 10 of the Code of Federal Regulations (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 NRC's Agencywide Document Access and Management system (ADAMS), 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 George M. McCann acting for/

Christine A. Lipa, Chief Materials Control, ISFSI, and Decommissioning Branch Docket No. 050-00016 License No. DPR-9

Enclosure:

Inspection Reports 050-00016/10-10(DNMS)

and 050-00016/10-12(DNMS)

REGION III==

Docket No. 050-00016 License No. DPR-9 Report Nos. 050-00016/10-10(DNMS) and 050-00016/10-12(DNMS)

Licensee: Detroit Edison Company Facility: Enrico Fermi Unit 1 Location: 6400 North Dixie Highway Newport, MI 48166 Inspection Dates: July 12, 2010 through November 22, 2010 Inspector: William G. Snell, Senior Health Physicist Observer: Stephen J. Giebel, Health Physicist, FSME Approved by: Christine A. Lipa, Chief Materials Control, ISFSI, and Decommissioning Branch Division of Nuclear Materials Safety Enclosure

EXECUTIVE SUMMARY Enrico Fermi Unit 1 NRC Inspection Reports 050-00016/10-10(DNMS) and 050-00016/10-12(DNMS)

This special decommissioning inspection included an in-process review of the licensees final status surveys conducted in support of decommissioning. A four person team from the Oak Ridge Institute for Science and Education (ORISE) assisted the NRC in the conduct of the inspection.

Final Status Surveys Surface scans of the selected areas within the Turbine Building, Steam Generator Building, West Sodium Gallery, Waste Gas Building and East Sodium Gallery did not identify radiation levels distinguishable from background. Scan surveys in the basement of the Waste Gas Building identified four remaining pipes that had been disconnected and capped with residual activity at levels three times greater than background for that room.

Results of exterior open land scan measurements were at or less than two times background for areas on the south and southwest sides of Fermi 1. Scans exposed to the Fermi 2 reactor, located north of Fermi 1, resulted in gamma scan count rates in excess of four times the typical instrument site background. Similar results were identified for the seventh floor Turbine Building roof survey. However, the inspectors determined that gamma radiation shine from the Fermi 2 reactor caused the observed elevated direct gamma radiation.

All confirmatory measurement results, including soil, tar, and gravel sample activities, were determined to be below the Derived Concentration Guideline Level (DCGL) values as specified in the Final Status Survey Plan. (Section 1.1)

Procedures The licensees Final Status Survey (FSS) data packages accurately and adequately described the sequence of FSS activities and the radiological conditions at the site. Procedures and methodologies employed to conduct the FSSs were adequate and appropriate. (Section 1.2)

2 Enclosure

Report Details1 Summary of Plant Activities During the inspection period the licensee was conducting routine decommissioning activities.

1.0 Review of Final Status Surveys 1.1 Final Status Surveys (IP 83801)

a. Inspection Scope The inspectors performed visual inspections, confirmatory measurements, sample collection, and side-by-side measurement comparisons of the ongoing decommissioning activities to evaluate the accuracy and adequacy of the licensees FSS results.

Additionally, the inspectors compared the radiological conditions of the locations surveyed to the DCGL values specified in the licensees License Termination Plan, Revision 2, dated march 23, 2010 (ML100910332).

b. Observations and Findings Confirmatory surveys were conducted in the Turbine Building, Steam Generator Building, West Sodium Gallery, Waste Gas Building, and the open land areas within the Fermi 1 footprint. An in-process inspection was conducted in the East Sodium Gallery.

Interior surfaces, including floors, lower walls, and other accessible surfaces were scanned using either large-area or hand-held gas proportional detectors for direct alpha and alpha plus beta radiation and for gamma radiation using a sodium iodide (NaI)

detector. Scans of the Fermi 1 footprint land areas and three building roofs were performed using NaI scintillation detectors for direct gamma radiation. Direct measurements to quantify total alpha and/or alpha plus beta activities on interior survey units were performed at selected licensee final status survey locations, at other locations selected by the inspectors, and locations where elevated direct radiation were detected by scans. One surface soil sample was collected from the exterior land areas. Two samples of miscellaneous roofing materials, consisting of the tar and gravel build-up, were collected from rooftops of the Turbine Buildings fourth and seventh floors.

Scans were focused in areas with the highest potential for contamination (i.e. cracks and joints in the floor and walls, other horizontal surfaces, surface run-off pathways, etc.).

The ORISE assisted the NRC in the inspection activities. The analytical results of the analysis of the samples collected during the inspection, a summary of scan results, and additional discussion of inspection activities is documented in the ORISE report, Report No. 1: Independent Confirmatory Survey Summary and Results for the Enrico Fermi Atomic Power Plant, Unit 1, Newport, Michigan, dated October 13, 2010 (ML102940178).

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

3 Enclosure

c. Conclusions Surface scans of the selected areas within the Turbine Building, Steam Generator Building, West Sodium Gallery, Waste Gas Building and East Sodium Gallery did not identify radiation levels distinguishable from background. Scan surveys in the basement of the Waste Gas Building identified four remaining pipes that had been disconnected and capped with residual activity at levels three times greater than background for that room.

Results of exterior open land scan measurements were at or less than two times background for areas on the south and southwest sides of Fermi 1. Scans exposed to the Fermi 2 reactor, located north of Fermi 1, resulted in gamma scan count rates in excess of four times the typical instrument site background. Similar results were identified for the seventh floor Turbine Building roof survey. However, it was determined that gamma radiation shine from the Fermi 2 reactor caused the observed elevated direct gamma radiation.

All confirmatory measurement results, including soil, tar, and gravel sample activities, were determined to be below the DCGL values as specified in the Final Status Survey Plan.

1.2 Procedures (83801)

a. Inspection Scope The inspectors reviewed the Enrico Fermi Atomic Power Plant, Unit 1 Final Status Survey Report (FSSR) and the Final Status Survey Package (FSSP) in Detroit Edison Companys Fermi 1 License Termination Plan (LTP). The FSSP was reviewed to identify the sites Radionuclides of Concern (ROCs) and associated DCGLs. Also reviewed were the licensees survey design and data quality objectives, adequacy of instrumentation used, instrument calibration data, the survey measurement methods to be used during the FSS, and FSS data packages of completed surveys. All documents and data were reviewed for adequacy and appropriateness taking into account the LTP and Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM) guidance.

b. Observations and Findings The FSSR, FSSP and LTP were observed to be consistent in their approach and implementation of the methodologies and practices described. The survey designs and data quality objectives, the instrumentation used, the instrument calibration results, and the survey measurement methods used during the FSS, and FSS data packages of completed surveys, were determined to be adequate and consistent with the governing documents. The FSSR and FSSP were determined to be appropriately implementing MARSSIM.

c. Conclusions The licensees FSS data packages accurately and adequately described the sequence of FSS activities and the radiological conditions at the site. Procedures and methodologies employed to conduct the FSSs were adequate and appropriate.

4 Enclosure

2.0 Exit Meetings The inspector presented the inspection results to members of the licensees staff at the conclusion of the onsite portion of the inspection on July 15, 2010. The results of the further review of information provided to the NRC during and after the onsite inspection, and the analysis and review of samples collected by the NRC during the inspection, were discussed with the Manager, Fermi 1, Ms. L. Goodman, by telephone on November 22, 2010. The inspectors confirmed that none of the potential report input discussed was considered proprietary.

ATTACHMENT: SUPPLEMENTAL INFORMATION 5 Enclosure

SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED

• ° L. Goodman, Manager, Fermi 1

• M. Erickson, License Termination Manager

• E. Kokosky, Radiation Protection Manager

• R. La Burn, Assistant Radiation Protection Manager

• ° K. Lindsey, Health Physicist

• M. Rennhack, Final Status Survey Engineer

• C. Aldridge-Nunn, Office Administrator