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==SUBJECT:== | ==SUBJECT:== | ||
NRC INSPECTION REPORT 050-00016/08-01(DNMS) ENRICO FERMI UNIT 1 | NRC INSPECTION REPORT 050-00016/08-01(DNMS) | ||
ENRICO FERMI UNIT 1 | |||
==Dear Mr. Plona:== | ==Dear Mr. Plona:== | ||
On April 2, 2008, 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 | On April 2, 2008, 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 April 2, 2008, 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. | 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 | 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. | ||
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 | |||
Sincerely, | Sincerely, | ||
/RA/ | /RA/ | ||
Patrick L. Louden, Chief Decommissioning Branch | Patrick L. Louden, Chief Decommissioning Branch Docket No. 050-00016 License No. DPR-9 | ||
Docket No. 050-00016 License No. DPR-9 | |||
===Enclosure:=== | ===Enclosure:=== | ||
Inspection Report 050-00016/08-01(DNMS) | Inspection Report 050-00016/08-01(DNMS) | ||
REGION III== | REGION III== | ||
Docket No.: 050-00016 License No.: DPR-9 Report No. : 050-00016/08-01(DNMS) | |||
Licensee: Detroit Edison Company Facility: Enrico Fermi Unit 1 Location: 6400 North Dixie Highway Newport, MI 48166 Inspection Dates: April 1 and 2, 2008 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 050-00016/08-01(DNMS) | |||
This routine decommissioning inspection included reviews of facility management and control, and radiological safety. | This routine decommissioning inspection included reviews of facility management and control, and radiological safety. | ||
Facility Management and Control The inspector determined that the | 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) | ||
The inspector determined that the licensee maintained adequate staffing levels and training to continue the decommissioning process. (Section 1.2) | |||
The inspector determined that the licensee maintained adequate staffing levels and training to continue the decommissioning process. (Section 1.2) | The inspector concluded that the conditions of the facility and equipment were adequate and capable of supporting sodium removal activities. (Section 1.3) | ||
The inspector concluded that the conditions of the facility and equipment were adequate and capable of supporting sodium removal activities. (Section 1.3) | |||
The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program. (Section 1.4) | The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program. (Section 1.4) | ||
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) | 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. (Section 2.2) | The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits. (Section 2.2) | ||
The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive waste. (Section 2.3) | The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive waste. (Section 2.3) | ||
2 Enclosure | |||
Enclosure | |||
Report Details1 Summary of Plant Activities During the inspection period, the licensee was employing a steaming process on the reactor vessel to remove the residual sodium from the vessel metal. | |||
a. Inspection Scope The inspector reviewed the | 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 Part 50.59. The review included selected screening reviews completed since October 2007. | |||
b. Observations and Findings The | b. Observations and Findings The licensees Administrative Controls and Surveillance Procedures Manual, Section 1.6 was consistent with the NRCs requirements for 10 CFR Part 50.59 screening reviews. | ||
The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 50.59 safety evaluation. | The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 50.59 safety evaluation. | ||
c. Conclusions The inspector determined that the | 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 Part 50.59. | ||
1.2 Organization, Management and Cost Controls (36801) | 1.2 Organization, Management and Cost Controls (36801) | ||
a. Inspection Scope The inspector evaluated the | a. Inspection Scope The inspector evaluated the licensees decommissioning staffing to determine whether the licensee maintained adequate staffing levels to effectively conduct its decommissioning activities. The inspector reviewed records of the required training for contractor workers that the licensee recently hired. | ||
safety. | b. Observations and Findings The licensee conducted training for the licensee personnel and the contractor workers in accordance with the provisions of the licensees training program. The training included radiation protection, sodium handling safety, asbestos awareness, and confined space safety. | ||
¹A list of acronyms used and all documents reviewed in these | ¹A list of acronyms used and all documents reviewed in these Details are provided at the end of the report. | ||
Enclosure | 3 Enclosure | ||
c. Conclusions The inspector determined that the licensee maintained adequate staffing levels and training to continue the decommissioning process. | |||
a. Inspection Scope (71801) | 1.3 Decommissioning Performance and Status Review at Permanently Shut Down Reactors a. Inspection Scope (71801) | ||
The inspector toured the Reactor Building to assess the working conditions of processing of the residual sodium in the reactor vessel. | The inspector toured the Reactor Building to assess the working conditions of processing of the residual sodium in the reactor vessel. | ||
| Line 110: | Line 86: | ||
1.4 Self-Assessment, Auditing, and Corrective Action (40801) | 1.4 Self-Assessment, Auditing, and Corrective Action (40801) | ||
a. Inspection Scope The inspector reviewed the licensees audit of its radiation protection program (Audit 07-002) conducted from November 29, 2007, through January 25, 2008. Selected corrective action work orders associated with identified deficiencies were also reviewed. | |||
a. Inspection Scope The inspector reviewed the | |||
b. Observations and Findings The audit of the radiation protection program (Audit 07-002) was appropriately focused in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve the audit findings. The findings identified were programmatic in nature and had no impact on the quality of products. | b. Observations and Findings The audit of the radiation protection program (Audit 07-002) was appropriately focused in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve the audit findings. The findings identified were programmatic in nature and had no impact on the quality of products. | ||
| Line 117: | Line 92: | ||
c. Conclusions The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program. | c. Conclusions The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program. | ||
Enclosure | 4 Enclosure | ||
2.1 Occupational Radiation Exposure (83750) | 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 November 2007 to March 2008, during the removal of neutron source from the reactor, sodium residue from piping and control rods, to determine whether the licensee adequately controlled doses to workers. | |||
a. Inspection Scope The inspector reviewed the results of air sampling, direct radiation surveys, and | |||
contamination surveys performed from November 2007 to March 2008, during the removal of neutron source from the reactor, sodium residue from piping and control rods, to determine whether the licensee adequately controlled doses to workers. | |||
b. Observations and Findings 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. | b. Observations and Findings 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 and direct radiation surveys from the work areas did not indicate any spread of | The results of contamination surveys and direct radiation surveys from the work areas did not indicate any spread of contamination and 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. | 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) | 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 November 2007 to March 2008 to verify that the licensee met 10 CFR | a. Inspection Scope The inspector reviewed the analytical data of gaseous effluent releases for particulates and tritium from November 2007 to March 2008 to verify that the licensee met 10 CFR Part 20 effluent release limits. | ||
Part 20 effluent release limits. | |||
b. Observations and Findings Air sampling at the effluence release points did not indicate any positive results from particulates and tritium. | b. Observations and Findings Air sampling at the effluence release points did not indicate any positive results from particulates and tritium. | ||
| Line 140: | Line 110: | ||
c. Conclusions The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits. | c. Conclusions The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits. | ||
Enclosure | 5 Enclosure | ||
b. Observations and Findings On February 6, 2008, the licensee made one radioactive material low specific activity (LSA-II) shipment of depleted neutron source irradiated metal to Barnwell Waste Management Facility, Barnwell, South Carolina. On February 21, 2008, the licensee made one LSA-II shipment of processing liquid to Bear Creek Corporation in Oak Ridge, Tennessee. The | 2.3 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750) | ||
a. Inspection Scope The inspector reviewed radioactive waste shipping documents and conducted interviews of the responsible individual to ensure compliance with NRC and U.S. Department of Transportation (DOT) regulations. | |||
b. Observations and Findings On February 6, 2008, the licensee made one radioactive material low specific activity (LSA-II) shipment of depleted neutron source irradiated metal to Barnwell Waste Management Facility, Barnwell, South Carolina. On February 21, 2008, the licensee made one LSA-II shipment of processing liquid to Bear Creek Corporation in Oak Ridge, Tennessee. The licensees shipping manifests 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 had complied with NRC and Department of Transportation regulations for shipments of radioactive waste. | c. Conclusions The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive waste. | ||
3.0 Exit Meeting The inspector presented the inspection results to members of the | 3.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on April 2, 2008. The licensee did not identify any of the documents or processes reviewed by the inspector as proprietary. | ||
ATTACHMENT: SUPPLEMENTAL INFORMATION 6 Enclosure | |||
SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED | |||
* L. Goodman, Manager, Fermi 1 (Custodian) | |||
* K..Lindsey, Radiation Protection Supervisor | |||
* T. Brown, Manager, Radiation Protection D. Breiding, Fermi 1 Project Coordinator D. Swindle, Sodium Project Manager | |||
* C. Aldridge-Nunn, Office Administration | |||
* L. Davis, Office Specialist | |||
* Present at the April 2, 2008, exit meeting. | * Present at the April 2, 2008, 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 IP 86750: Solid Radioactive Waste Management and Transportation of Radioactive Materials IP 71801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 36801: Organization, Management and Cost Controls IP 40801: Self-Assessment, Auditing, and Corrective Action | 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 IP 86750: Solid Radioactive Waste Management and Transportation of Radioactive Materials IP 71801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 36801: Organization, Management and Cost Controls IP 40801: Self-Assessment, Auditing, and Corrective Action LIST OF ACRONYMS USED ADAMS Agency Document and Management System CFR Code of Federal Regulations DOT Department of Transportation DNMS Division of Nuclear Materials Safety LSA-II Low Specific Activity Class II 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. | ||
LIST OF ACRONYMS USED | |||
ADAMS Agency Document and Management System CFR Code of Federal Regulations DOT Department of Transportation DNMS Division of Nuclear Materials Safety LSA-II Low Specific Activity Class II NRC Nuclear Regulatory Commission LICENSEE DOCUMENTS REVIEWED Licensee documents reviewed and utilized during the course of this inspection are specifically identified in the | |||
None | ITEMS OPENED, CLOSED, AND DISCUSSED None Attachment | ||
}} | }} | ||
Latest revision as of 18:28, 14 November 2019
| ML081160077 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/24/2008 |
| From: | Louden P NRC/RGN-III/DNMS/DB |
| To: | Plona J Detroit Edison |
| References | |
| IR-08-001 | |
| Download: ML081160077 (9) | |
Text
ril 24, 2008
SUBJECT:
NRC INSPECTION REPORT 050-00016/08-01(DNMS)
ENRICO FERMI UNIT 1
Dear Mr. Plona:
On April 2, 2008, 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 April 2, 2008, 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/
Patrick L. Louden, Chief Decommissioning Branch Docket No. 050-00016 License No. DPR-9
Enclosure:
Inspection Report 050-00016/08-01(DNMS)
REGION III==
Docket No.: 050-00016 License No.: DPR-9 Report No. : 050-00016/08-01(DNMS)
Licensee: Detroit Edison Company Facility: Enrico Fermi Unit 1 Location: 6400 North Dixie Highway Newport, MI 48166 Inspection Dates: April 1 and 2, 2008 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 050-00016/08-01(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)
The inspector determined that the licensee maintained adequate staffing levels and training to continue the decommissioning process. (Section 1.2)
The inspector concluded that the conditions of the facility and equipment were adequate and capable of supporting sodium removal activities. (Section 1.3)
The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program. (Section 1.4)
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. (Section 2.2)
The inspector determined that the licensee had complied with NRC and Department of Transportation regulations for shipments of radioactive waste. (Section 2.3)
2 Enclosure
Report Details1 Summary of Plant Activities During the inspection period, the licensee was employing a steaming process on the reactor vessel to remove the residual sodium from the vessel metal.
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 Part 50.59. The review included selected screening reviews completed since October 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 Part 50.59 screening reviews.
The licensee conducted several safety screening reviews of facility changes and none of the changes required a formal 10 CFR Part 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 Part 50.59.
1.2 Organization, Management and Cost Controls (36801)
a. Inspection Scope The inspector evaluated the licensees decommissioning staffing to determine whether the licensee maintained adequate staffing levels to effectively conduct its decommissioning activities. The inspector reviewed records of the required training for contractor workers that the licensee recently hired.
b. Observations and Findings The licensee conducted training for the licensee personnel and the contractor workers in accordance with the provisions of the licensees training program. The training included radiation protection, sodium handling safety, asbestos awareness, and confined space safety.
¹A list of acronyms used and all documents reviewed in these Details are provided at the end of the report.
3 Enclosure
c. Conclusions The inspector determined that the licensee maintained adequate staffing levels and training to continue the decommissioning process.
1.3 Decommissioning Performance and Status Review at Permanently Shut Down Reactors a. Inspection Scope (71801)
The inspector toured the Reactor Building to assess the working conditions of processing of the residual sodium in the reactor vessel.
b. Observations and Findings The contract workers involved in sodium removal operations wore appropriate protective equipment and followed established procedures. The licensee maintained the work place with adequate shielding, personnel barriers, and enclosures with HEPA exhaust systems, all to minimize worker doses. All radiological areas were adequately marked and posted.
c. Conclusions The inspector concluded that the conditions of the facility and equipment were adequate and capable of supporting sodium removal activities.
1.4 Self-Assessment, Auditing, and Corrective Action (40801)
a. Inspection Scope The inspector reviewed the licensees audit of its radiation protection program (Audit 07-002) conducted from November 29, 2007, through January 25, 2008. Selected corrective action work orders associated with identified deficiencies were also reviewed.
b. Observations and Findings The audit of the radiation protection program (Audit 07-002) was appropriately focused in both scope and level of detail, and the licensee initiated appropriate corrective actions to resolve the audit findings. The findings identified were programmatic in nature and had no impact on the quality of products.
c. Conclusions The inspector determined that the licensee adequately implemented the audits of radiation protection in accordance with its Quality Assurance Program.
4 Enclosure
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 November 2007 to March 2008, during the removal of neutron source from the reactor, sodium residue from piping and control rods, to determine whether the licensee adequately controlled doses to workers.
b. Observations and Findings 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 and direct radiation surveys from the work areas did not indicate any spread of contamination and 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 November 2007 to March 2008 to verify that the licensee met 10 CFR Part 20 effluent release limits.
b. Observations and Findings Air sampling at the effluence release points did not indicate any positive results from particulates and tritium.
c. Conclusions The inspector verified that the licensee maintained effluent releases well below the 10 CFR Part 20 release limits.
5 Enclosure
2.3 Solid Radioactive Waste Management and Transportation of Radioactive Materials (86750)
a. Inspection Scope The inspector reviewed radioactive waste shipping documents and conducted interviews of the responsible individual to ensure compliance with NRC and U.S. Department of Transportation (DOT) regulations.
b. Observations and Findings On February 6, 2008, the licensee made one radioactive material low specific activity (LSA-II) shipment of depleted neutron source irradiated metal to Barnwell Waste Management Facility, Barnwell, South Carolina. On February 21, 2008, the licensee made one LSA-II shipment of processing liquid to Bear Creek Corporation in Oak Ridge, Tennessee. The licensees shipping manifests 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 had complied with NRC and Department of Transportation regulations for shipments of radioactive waste.
3.0 Exit Meeting The inspector presented the inspection results to members of the licensees staff at the conclusion of the inspection on April 2, 2008. The licensee did not identify any of the documents or processes reviewed by the inspector as proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION 6 Enclosure
SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED
- L. Goodman, Manager, Fermi 1 (Custodian)
- K..Lindsey, Radiation Protection Supervisor
- T. Brown, Manager, Radiation Protection D. Breiding, Fermi 1 Project Coordinator D. Swindle, Sodium Project Manager
- C. Aldridge-Nunn, Office Administration
- L. Davis, Office Specialist
- Present at the April 2, 2008, 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 IP 86750: Solid Radioactive Waste Management and Transportation of Radioactive Materials IP 71801: Decommissioning Performance and Status Review at Permanently Shut Down Reactors IP 36801: Organization, Management and Cost Controls IP 40801: Self-Assessment, Auditing, and Corrective Action LIST OF ACRONYMS USED ADAMS Agency Document and Management System CFR Code of Federal Regulations DOT Department of Transportation DNMS Division of Nuclear Materials Safety LSA-II Low Specific Activity Class II 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 Attachment