ML20307A483
| ML20307A483 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/02/2020 |
| From: | Dave Hills Division of Nuclear Materials Safety III |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Edwards R | |
| References | |
| IR 2020001 | |
| Download: ML20307A483 (13) | |
Text
November 2, 2020 Mr. Bryan C. Hanson Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NRC INSPECTION REPORT NO. 05000010/20200001 (DNMS) - DRESDEN NUCLEAR POWER STATION, UNIT 1
Dear Mr. Hanson:
On October 15, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed inspection activities at the permanently shut down Dresden Nuclear Power Station, Unit 1. The purpose of the inspection was to determine whether decommissioning activities were conducted safely and in accordance with NRC requirements. The enclosed report presents the results of this inspection, which were discussed with Mr. P. Boyle and other members of your staff on October 15, 2020.
During the inspection, the NRC inspector reviewed the following aspects of decommissioning activities: safety reviews, design changes, and modifications; self-assessments, audits, and corrective actions; performance and status review; occupational radiation exposure; radioactive waste treatment, and effluent and environmental monitoring; and transportation of radioactive material. The inspection consisted of an examination of activities at the site 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 and interviews with personnel.
Based on the results of this inspection, no violations of NRC requirements were identified.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
B. Hanson 2
Room in accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, David E. Hills, Chief Materials Control, ISFSI, and Decommissioning Branch Division of Nuclear Materials Safety Docket No.50-010 License No. DPR-2
Enclosure:
IR 05000010/20200001 (DNMS) cc: Distribution via LISTSERV David E. Hills Digitally signed by David E. Hills Date: 2020.11.02 13:18:02
-06'00'
B. Hanson 3
Letter to Bryan Hanson from David Hills dated November 2, 2020.
SUBJECT:
NRC INSPECTION REPORT NO. 05000010/20200001 (DNMS) - DRESDEN NUCLEAR POWER STATION, UNIT 1 DISTRIBUTION w/encl:
Dave Pelton Christine Lipa Kenneth Riemer April Nguyen Roy Elliott Alan Barker Harral Logaras Jason Draper MCID Inspectors Bruce Watson Zahira Perez Cruz ADAMS Accession Number: ML20307A483 OFFICE RIII DNMS C RIII DNMS C RIII RIII NAME REdwards:brt RAE DHills DATE 10/30/2020 11/02/2020 OFFICIAL RECORD COPY
Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION III Docket No:
050-00010 License No:
DPR-2 Report No:
05000010/2020001 EPID No:
I-2020-001-0084 Licensee:
Exelon Generation Company, LLC Facility:
Dresden Nuclear Power Station, Unit 1 Location:
Morris, IL Dates:
October 5 - 15, 2020 Inspector:
Rhex Edwards, Senior Health Physicist Approved by:
David E. Hills, Chief Materials Control, ISFSI, and Decommissioning Branch Division of Nuclear Materials Safety
2 EXECUTIVE
SUMMARY
Dresden Nuclear Power Station, Unit 1 U.S. Nuclear Regulatory Commission (NRC) Inspection Report 05000010/2020001 The Dresden Nuclear Power Station Unit 1 is a permanently shut down and defueled power reactor that has been maintained in a safe storage condition (SAFSTOR). Decommissioning activities occur periodically and as warranted by radiological, material, or structural conditions.
This safety inspection reviewed the overall effectiveness of the licensees programs for continued SAFSTOR of Unit 1.
Safety Reviews, Design Changes, and Modifications The licensees processes were adequate to perform appropriate safety evaluations or screenings, design change evaluations, and assessments of decommissioning impacts of various work activities as required by Title 10 of the Code of Federal Regulations (CFR) 50.59. The remaining aspects of this program are inspected by the NRC through the Reactor Oversight Process (ROP) for Units 2 and 3. (Section 1.0)
Self-Assessment, Auditing, and Corrective Action Issues were identified by the licensee at appropriate thresholds and entered into the Corrective Action Program (CAP). Issues were screened and prioritized commensurate with safety significance. Licensee evaluations determined the significance of issues and included appropriate remedial corrective actions. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3. (Section 2.0)
Decommissioning Performance and Status Review The inspectors determined that the licensee conducted SAFSTOR activities in accordance with the regulations and license requirements. (Section 3.0)
Occupational Radiation Exposure Radiation surveys were performed adequately, and postings and barriers were appropriate to the hazards present. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3. (Section 4.0)
Radioactive Waste Treatment, and Effluent and Environmental Monitoring The licensee maintained effluent and environmental monitoring and control systems as required. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3. (Section 5.0)
Solid Radioactive Waste Management and Transportation of Radioactive Materials The licensee maintained radioactive material in accordance with requirements. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3. (Section 6.0)
3 Report Details Summary of Plant Activities During the inspection period, the licensee-maintained Dresden Unit 1 in SAFSTOR conditions.
Licensees activities primarily involved routine surveillance and maintenance to support continued SAFSTOR dormancy.
1.0 Safety Reviews, Design Changes, and Modifications (Inspection Procedure (IP) 37801) 1.1 Inspection Scope The inspector reviewed documents and interviewed plant personnel to assess the licensees performance as it related to the following areas:
Determination that licensee procedures and processes conform to 10 CFR 50.59 and associated guidance; Procedures that control and implement design changes and modifications to assess that the procedures provided adequate guidance for implementation, review, and approval; Verification that the design change process followed approved procedures and applicable changes were effectively implemented in the field and in plant procedures, drawings, and training programs, if applicable; Verification that changes to preventive maintenance, corrective maintenance, and operational procedures for required equipment were implemented in accordance with the licensees processes and procedures; and Verification whether maintenance activities caused a change to the facility.
The inspector verified that when issues were identified licensee personnel appropriately documented the issues in the CAP.
1.2 Observations and Findings The inspector reviewed the licensees programs for changes. There were no changes to the decommissioning facility that required an evaluation according to the provision of 10 CFR 50.59. At the time of the NRC inspection, the licensee was performing 5-year structural integrity inspections of Unit 1 structures required to maintain the facility in a SAFSTOR condition. The inspectors reviewed the results of the licensees structural inspections completed to date; however, the remaining results will be reviewed, once available, during the next NRC inspection.
The design change and modification process for Unit 1 is controlled by the licensee under the same program as the operating units, Units 2 and 3. Similarly, the NRC
4 inspects this program through the NRCs ROP for Units 2 and 3. As such, the NRC uses the ROP to provide additional oversight of design changes and modifications.
No findings were identified.
1.3 Conclusions The licensees processes were adequate to perform appropriate safety evaluations or screenings, design change evaluations, and assessments of decommissioning impacts of various work activities as required by 10 CFR 50.59.
2.0 Self-Assessment, Auditing, and Corrective Action (IP 40801) 2.1 Inspection Scope The inspector conducted document reviews and interviews with plant personnel to assess the licensees performance as it related to the following areas:
Administrative procedures prescribed actions for the identification, evaluation, and resolution of problems; Licensee procedures prescribed thresholds for the performance of self-assessments, audits, and surveillances; Licensee management reviewed self-assessments, audits, and corrective actions to remain knowledgeable of plant performance; Self-assessments were conducted with technically qualified personnel and sufficient independence from the licensee; Issues or problems were identified and corrected in accordance with the licensees CAP; and Quality assurance personnel audited changes in the status of decommissioning and licensee organization.
The inspector reviewed CAP documents to determine if a sufficiently low threshold for problem identification existed; the quality of follow-up evaluations, including extent-of-condition; and if the licensee assigned timely and appropriate prioritization for issue resolution commensurate with the significance of the issue.
2.2 Observations and Findings The inspector determined that issues were identified by the licensee at an appropriate threshold within various functional areas of the site and entered into the CAP. Issues were effectively screened, prioritized, and evaluated commensurate with safety significance. The scope and depth of evaluations were adequate in that the evaluations reviewed addressed the significance of issues and assigned an appropriate course of remedial action.
5 The CAP is controlled by the licensee under the same program as the operating units, Units 2 and 3. Similarly, the NRC inspects this program through the NRCs ROP for Units 2 and 3. As such, the NRC uses the ROP to provide additional oversight of CAP.
No findings were identified.
2.3 Conclusions Issues were identified by the licensee at appropriate thresholds and entered into the CAP. Issues were screened and prioritized commensurate with safety significance.
Licensee evaluations determined the significance of issues and included appropriate remedial corrective actions. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3.
3.0 Decommissioning Performance and Status Review (IP 71801) 3.1 Inspection Scope The inspectors reviewed documents and interviewed plant personnel to assess the licensees performance in the following areas:
Status of ongoing decommissioning activities and planning for future activities; Performance of the plant staff and the contracted workforce, as applicable, and their control and conduct of maintaining the facility in SAFSTOR; Technical Specification (TS) requirements, and licensee actions described in the Decommissioning Safety Analysis Report (DSAR), and the Post-Shutdown Decommissioning Activities Report (PSDAR), are met and implemented; and The material integrity of structures, systems, and components necessary for the conduct of SAFSTOR.
The inspector verified that when issues were identified licensee personnel appropriately documented the issues in the CAP.
3.2 Observations and Findings The inspectors determined through a plant tour performed on October 5, 2020, that the licensee-maintained Unit 1 in accordance with regulatory requirements and plant procedures. The general condition of the facility was found to be well maintained and consistent with good housekeeping practices. Fire protection equipment was found to be in good material condition and appropriate for the SAFSTOR condition of the facility.
The inspectors also verified that the licensee performed SAFSTOR operations in accordance with TSs, the DSAR, and the PSDAR.
No findings were identified.
6 3.3 Conclusions The inspectors determined that the licensee conducted SAFSTOR activities in accordance with the regulations and license requirements.
4.0 Occupational Radiation Exposure (IP 83750) 4.1 Inspection Scope The inspector reviewed documents, made observations, and interviewed plant personnel to assess whether the licensees:
Management and administrative controls of external radiation exposure met requirements and were designed to keep exposures As Low as Is Reasonably Achievable (ALARA);
Processes or engineering controls were used to the extent practicable to limit concentrations of airborne radioactive materials; Survey and monitoring activities were performed as required; Control of radioactive materials and contamination met requirements; ALARA program was effectively implemented; Initiatives to implement operational methods and practices-maintained doses ALARA; and Issues, events, or problems were identified and resolved, so as to help prevent future problems in the area of radiological controls.
The inspector verified that when issues were identified, licensee personnel appropriately documented the issues in the CAP.
4.2 Observations and Findings Measures were established in the Unit 1 containment building to adequately prevent the creation of airborne hazards; control the spread of contamination; and to reduce external dose. A review of selected radiological surveys did not identify any unusual radiological conditions. During tours of Unit 1, radiological postings and barriers were found to be in good condition and located where required.
Occupational radiation exposure is controlled by the licensee under the same program as the operating units, Units 2 and 3. Similarly, the NRC inspects this program through the NRCs ROP for Units 2 and 3. As such, the NRC uses the ROP to provide additional oversight of the occupational radiation exposure program.
No findings were identified.
7 4.3 Conclusions Radiation surveys were performed adequately, and postings and barriers were appropriate to the hazards present. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3.
5.0 Radioactive Waste Treatment, and Effluent and Environmental Monitoring (IP 84750) 5.1 Inspection Scope The inspector conducted document reviews and interviews with plant personnel to assess the licensees performance as it related to the following areas:
Radioactive waste treatment systems were maintained and operated to keep offsite doses ALARA; The licensee effectively controlled, monitored, and quantified releases of radioactive materials in liquid, gaseous, and particulate forms to the environment; and The radiological environmental monitoring programs were effectively implemented to ensure effluent releases were being adequately performed as required to minimize public dose.
The inspector verified that when issues were identified licensee personnel appropriately documented the issues in the CAP.
5.2 Observations and Findings The inspector noted that during a review of past Annual Radiological Effluent Release Reports, no anomalous results, unexpected trends, or abnormal releases were identified in association with Unit 1 activities.
Effluent and environmental monitoring is controlled by the licensee under the same program as the operating units, Units 2 and 3. Similarly, the NRC inspects this program through the NRCs ROP for Units 2 and 3. As such, the NRC performs inspections through the ROP to provide additional oversight of the effluent and environmental monitoring program.
No findings were identified.
5.3 Conclusions The licensee maintained effluent and environmental monitoring and control systems as required. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3.
6.0 Solid Radioactive Waste Management and Transportation of Radioactive Materials (IP 86750)
8 6.1 Inspection Scope The inspector reviewed documents and interviewed plant personnel to determine whether radioactive material is properly processed, packaged, and shipped by the licensee in accordance with NRC and Department of Transportation regulations.
6.2 Observations and Findings The inspectors interviewed plant personnel and determined that no shipments of radioactive material occurred since the last inspection. During a facility tour, the inspectors found that radioactive material contained in Unit 1 was controlled in accordance with requirements.
The storage and transportation of radioactive materials is controlled by the licensee under the same program as the operating units, Units 2 and 3. Similarly, the NRC inspects this program through the NRCs ROP for Units 2 and 3. As such, the NRC uses the ROP to provide additional oversite of the management and transportation of radioactive waste.
No findings were identified.
6.3 Conclusions The licensee maintained radioactive material in accordance with requirements. The remaining aspects of this program are inspected by the NRC through the ROP for Units 2 and 3.
7.0 Exit Meeting The inspector presented the results of the inspection to Mr. P. Boyle and other members of the licensee staff at an exit meeting on October 15, 2020. The licensee acknowledged the results presented and did not identify any of the information discussed as proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION
Attachment SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED D. Walker, Senior Regulatory Specialist INSPECTION PROCEDURES (IPs) USED IP 37801 Safety Reviews, Design Changes, and Modifications at Permanently Shutdown Reactors IP 40801 Self-Assessment, Auditing and Corrective Action at Permanently Shutdown Reactors IP 71801 Performance and Status Review IP 83750 Occupational Radiation Safety IP 84750 Radioactive Waste Treatment, and Effluent and Environmental Monitoring IP 86750 Solid Radioactive Waste Management and Transportation of Radioactive Materials ITEMS OPENED, CLOSED, AND DISCUSSED Opened Type Summary None Closed Type Summary None Discussed Type Summary None
2 PARTIAL LIST OF DOCUMENTS REVIEWED The following is a partial list of documents reviewed during the inspection. Inclusion on this list does not imply that the NRC inspector reviewed the documents in their entirety, but rather that selected sections of portions of the documents were evaluated as part of the overall inspection effort. Inclusion of a document on this list does not imply NRC acceptance of the document or any part of it, unless this is stated in the body of the inspection report.
2020-078029; Radiological Survey Map - DRE 1; 08/17/2020 2020-080881; Radiological Survey Map - DRE 1; 09/28/2020 2020-076066; Radiological Survey Map - DRE 1; 07/15/2020 2020-078787; Radiological Survey Map - DRE Out; 08/31/2020 AR 04306565; Potential Safety Hazard in Unit 1 Reactor Building; 12/29/2019 AR 04345130; Zone Owner Area Walk-down Unit 1; 06/21/2020 AR 04365481; Monthly Zone Owner Walk-Down Unit 1; 08/25/2020 Defueled Safety Analysis Report Update; Revision 10 DTS 0010-01; Integrity Surveillance for Unit 1 Structures; Revision 7 NOSA-DRE-19-11; Decommissioned Units Audit Report; 11/26/2019 WO 01878295; D1 5Y COM Crib House/Intake Structural Integrity Inspection; 09/15/2020 WO 01878292; D1 5Y COM Boiler House Structural Integrity Inspection; 09/14/2020 WO 01878179; D1 5Y COM Boiler Room "C" Structural Integrity Inspection; 09/14/2020 LIST OF ACRONYMS USED ADAMS Agencywide Documents Access and Management System ALARA As Low As Is Reasonably Achievable CAP Corrective Action Program CFR Code of Federal Regulations DNMS Division of Nuclear Materials Safety DSAR Decommissioning Safety Analysis Report IP Inspection Procedure NRC U.S. Nuclear Regulatory Commission PSDAR Post-Shutdown Decommissioning Activities Report ROP Reactor Oversight Process SAFSTOR Safe Storage TS Technical Specification