Similar Documents at Fermi |
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Category:Enforcement Action
MONTHYEARIR 05000341/20204042020-07-15015 July 2020 Notice of Violation, NRC Investigation Report No. 3-2019-004; NRC Inspection Report No. 05000341/2020404 IR 05000034/20170112017-05-11011 May 2017 EA-17-012 Final Significance Determination of a White Finding and Notice of Violation; NRC Inspection Report 0500034/2017011;Fermi Nuclear Power Plant IR 05000341/20170112017-05-11011 May 2017 EA-17-012 Final Significance Determination Of A White Finding And Notice Of Violation; NRC Inspection Report 0500034/2017011;Fermi Nuclear Power Plant IR 05000341/20170092017-02-24024 February 2017 NRC Inspection Report 05000341/2017009 and Preliminary White Finding IR 05000341/20100042010-10-20020 October 2010 IR 05000341-10-004, on 07/01/2010 - 09/30/2010; Detroit Edison Company; 07/01/2010 - 09/30/2010; Fermi Power Plant, Unit 2, Routine Integrated Inspection Report IR 05000016/19660102010-07-0101 July 2010 IR 05001666-10-201, on May 25 - June 1, 2010, University of Maryland 2020-07-15
[Table view] Category:Letter
MONTHYEARIR 05000341/20240122024-11-0101 November 2024 Commercial Grade Dedication Inspection Report 05000341/2024012 IR 05000341/20245012024-10-0808 October 2024 – Emergency Preparedness Inspection Report 05000341/2024501 ML24276A2032024-10-0303 October 2024 FEMA Level 1 Finding Transmittal Letter ML24268A0992024-10-0101 October 2024 Power Plant – Audit Summary for License Amendment Request and Regulatory Exemptions for a Risk Informed Approach to Address ECCS Strainer Performance IR 05000341/20240132024-09-30030 September 2024 Phase 2 Post Approval License Renewal Report 05000341/2024013 ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24257A1652024-09-13013 September 2024 FEMA Region 5 Fermi 2 Nuclear Power Plant Level 1 Finding September 2024 ML24254A3562024-09-0909 September 2024 FEMA Level 1 Finding for Fermi 2024 Biennial Exercise ML24240A3532024-08-27027 August 2024 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval Update IR 05000341/20240052024-08-22022 August 2024 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2024005) IR 05000341/20244042024-08-21021 August 2024 Public-Fermi Power Plant, Unit 2 - Material Control and Accounting Program Inspection Report 05000341/2024404 IR 05000341/20240022024-08-14014 August 2024 Integrated Inspection Report 05000341/2024002 ML24199A2182024-07-25025 July 2024 Enrico Fermi Atomic Power Plant, Unit 1 - NRC Position on Continuation of Possession-Only License No. DPR-9 Past the Current Expiration Date (Docket No. 50-016) ML24169A4092024-07-18018 July 2024 Relief Request RR-A25, Alternative to Reactor Vessel Circumferential Shell Weld Examination IR 05000341/20243022024-07-0909 July 2024 NRC Initial License Reexamination Report 05000341/2024302 ML24173A1012024-06-14014 June 2024 Retake Exam Post-Exam Cover Letter & Comments ML24155A0852024-06-11011 June 2024 Operator Licensing Reexamination Approval Letter - Fermi Power Plant, June 2024 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000341/20244022024-05-30030 May 2024 Security Baseline Inspection Report 05000341/2024402 ML24143A1852024-05-29029 May 2024 – Regulatory Audit in Support of LAR to Adopt TSTF-505, Rev. 2, TSTF-439, Rev. 2, and TSTF-591, Rev. 0 ML24141A2072024-05-20020 May 2024 Plant—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 05000341/LER-2024-002, Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications2024-05-16016 May 2024 Primary Containment Isolation Valve Declared Inoperable for a Period Prohibited by Technical Specifications 05000341/LER-2024-001, Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-222024-05-15015 May 2024 Automatic RPS Scram on High RPV Pressure While Attempting to Lower Generator Output During RF-22 IR 05000341/20240102024-05-0606 May 2024 NRC Inspection Report 05000341/2024010 ML24052A2772024-04-30030 April 2024 Issuance of Amendment No. 229 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 IR 05000341/20240012024-04-30030 April 2024 Integrated Inspection Report 05000341/2024001 ML24107B1372024-04-18018 April 2024 Confirmation of Initial License Reexamination June 2024 ML24101A3732024-04-11011 April 2024 Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000341/2024012 ML24100A8422024-04-0909 April 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection: Inspection Report 05000341/2024013 IR 05000341/20234022024-04-0808 April 2024 Reissue - Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402 (Public) ML24088A2162024-04-0404 April 2024 Change in Estimated Review Schedule and Level of Effort for License Amendment Request for Risk Informed Approach to ECCS Strainer Performance ML24086A5732024-04-0101 April 2024 Response to Disputed Non-Cited Violation Documents in Fermi Power Plant, Unit 2 - Cyber Security Inspection Report 05000341/2023402-01 Withdrawal of Non-Cited Violation (Public) IR 05000341/20243012024-04-0101 April 2024 NRC Initial License Examination Report 05000341/2024301 IR 05000341/20244012024-03-22022 March 2024 – Security Baseline Inspection Report 05000341/2024401 (Public) IR 05000341/20240112024-03-0808 March 2024 Nbsp;Safety Conscious Work Environment Issue of Concern Follow-up Inspection Report 05000341/2024011 ML24002B1812024-03-0404 March 2024 Issuance of Amendment No. 228 Regarding Revision of Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage IR 05000341/20230062024-02-28028 February 2024 Annual Assessment Letter for Fermi Power Plant, Unit 2 (Report 05000341/2023006) ML24019A1842024-02-16016 February 2024 Exemption from Select Requirements of 10 CFR Part 73 Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24045A1602024-02-14014 February 2024 Operator Licensing Examination Approval - Fermi Power Plant, February 2024 IR 05000341/20230042024-02-0505 February 2024 Integrated Inspection Report 05000341/2023004 IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 IR 05000341/20230032023-11-0707 November 2023 Integrated Inspection Report 05000341/2023003 and 07200071/2023001 ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) ML23311A3482023-10-20020 October 2023 DTE Electric Company (DTE) - Submittal of the Renewed Fermi 3 Michigan Department of Environmental, Great Lakes, and Energy (EGLE) National Pollutant Discharge Elimination System (NPDES) Permit No. MI0058892 ML23272A1552023-10-10010 October 2023 – Letter to Licensee and Federal Register Notification of Amendment to Renewed Facility Operating License and Proposed No Significant Hazards Consideration Determination (Exigent Circumstances) (EPID L-2023-LLA-0134) (Letter) 2024-09-09
[Table view] Category:Notice of Violation
MONTHYEARIR 05000034/20170112017-05-11011 May 2017 EA-17-012 Final Significance Determination of a White Finding and Notice of Violation; NRC Inspection Report 0500034/2017011;Fermi Nuclear Power Plant IR 05000341/20170112017-05-11011 May 2017 EA-17-012 Final Significance Determination Of A White Finding And Notice Of Violation; NRC Inspection Report 0500034/2017011;Fermi Nuclear Power Plant IR 05000016/19660102010-07-0101 July 2010 IR 05001666-10-201, on May 25 - June 1, 2010, University of Maryland IR 05000341/20090112010-01-15015 January 2010 IR 05000341-09-011, (Drs), on 08/14/2009 - 10/23/2009, for Fermi, Unit 2 ML0710905902007-04-19019 April 2007 EA-07-069, Fermi 1, Non-Cited Violation (NRC Office of Investigations Report No. 3-2006-029) 2017-05-11
[Table view] |
Inspection Report - Fermi - 2017011 |
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May 11, 2017
EA-17-012 Mr. Paul Fessler, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166
SUBJECT: FERMI POWER PLANT, UNIT 2 - FINAL SIGNIFICANCE DETERMINATION OF A WHITE FINDING AND NOTICE OF VIOLATION; NRC INSPECTION REPORT 05000341/2017011 AND ASSESSMENT FOLLOWUP LETTER
Dear Mr. Fessler:
This letter provides you the final significance determination of the preliminary White finding discussed in Inspection Report 05000341/2017009, dated February 24, 2017. The report is available in the U.S. Nuclear Regulatory Commission's (NRC) Agencywide Documents Access and Management System (ADAMS) at Accession Number ML17055C090. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. The finding involved the licensee's failure to maintain the effectiveness of the Fermi Unit 2 Emergency Plan and to use adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency.
In letter dated April 4, 2017, you provided a response to the NRC staff preliminary determination regarding the finding. A copy of the letter can be found in ADAMS, under accession number ML17094A745. In your response you indicated that you agreed with the preliminary significance determination of White for the finding and associated violation. Your response indicated that you believed that the NRC should consider enforcement discretion and a deviation from the NRC's Action Matrix. The response stated that the error occurred in the 1980s, limited opportunities existed to identify the error, and effective corrective actions were rapidly put into place following identification. You also indicated that the root cause of the event is not indicative of current licensee performance.
We have reviewed your response and have carefully considered your requests for a deviation from the Action Matrix and enforcement discretion. Regarding a deviation from the Action Matrix, as part of our evaluation, we determined that you had opportunities to identify and correct the performance deficiency. However, your staff failed to understand the radiological environment that would be present during postulated accident conditions and the impact these conditions would have upon the monitor and upon your staff's ability to correctly determine Emergency Action Levels (EALs) and protective action recommendations (PARs). Specifically, when Fermi performed the design reconstitution project in 1996, your staff identified a discrepancy between the configuration of the monitor and its description in the Final Safety Analysis Report (FSAR), which included the description of a background subtraction feature that was not installed. The staff chose to revise the FSAR instead of correcting the issue with the monitor. More recently, our inspectors identified the issue to your staff, and the staff initially evaluated the monitor, based on the radiological conditions expected during normal operating conditions, which demonstrated an ongoing deficiency with your staff's understanding of the emergency preparedness implications. While we acknowledge that you have taken action to correct the issue, we also understand that NRC action was necessary to facilitate your understanding of the implications of the issue. Your staff continued to demonstrate a lack of understanding of the emergency planning considerations. Regarding enforcement discretion, in your April 4, 2017, letter you referenced considerations outlined in the NRC Enforcement Policy pertaining to the application of enforcement discretion. However, those references are related to Section 2.3.4 of the Enforcement Policy, which is associated with civil penalties, which is not applicable in this case. Nonetheless, we also evaluated this issue with respect to possible discretion under Section 3.2 of the Enforcement Policy. However, for discretion to be given for an old design issue all of the following criteria must be met: (1) it was identified by the license as a result of a voluntary initiative; (2) it was or will be corrected; and (3) it was unlikely to be identified by efforts such as normal surveillances or routinely scheduled Quality Assurance activities. This issue was NRC-identified. Therefore, we concluded that this issue does not meet the criteria for discretion for either civil penalties or old design issues.
As a result of our review, we concluded that neither deviation from the Action Matrix nor enforcement discretion is warranted. Therefore, after considering the information developed during the inspection and the additional information you provided in your letter, dated April 4, 2017, the NRC has concluded that the finding is appropriately characterized as White, a finding of low-to-moderate risk significance.
The NRC determined that the failure to maintain the effectiveness of the emergency plan and use adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency was a performance deficiency within your ability to foresee and correct. Specifically, the failure to maintain the ability to accurately declare an EAL for a General Emergency classification and to develop and issue accurate PARs for the public during the implementation of the site's Emergency Plan in response to a rapidly progressing accident is a violation of Title 10 of the Code of Federal Regulations (CFR) 50.54(q)(2). The failure to accurately analyze the effect of increasing background radiation on the site's Standby Gas Treatment System (SGTS) accident range radiation monitor (AXM) indications based on the installed configuration of the AXM is a violation of 10 CFR 50.47(b)(9).
As configured, the AXM would provide inaccurate indications of radioactive releases that are used as the licensee's basis for determining EAL classification and development of PARs. The circumstances surrounding the violation were described in detail in the subject inspection report. In accordance with the NRC Enforcement Policy, the Notice is considered an escalated enforcement action because it is associated with a White finding. No cross-cutting aspect was assigned since the cause of the performance deficiency (i.e. initial design) associated with this finding does not reflect current licensee performance.
The NRC has concluded that the information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in Inspection Report 05000341/2017009, and your April 4, 2017, letter. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position. As a result of our review of Fermi Power Plant, Unit 2 performance, including this White finding, we have assessed the Fermi Power Plant to be in the Regulatory Response column of the NRC's Action Matrix, effective the first quarter of 2017. Therefore, we plan to conduct a supplemental inspection using Inspection Procedure 95001, "Supplemental Inspection Response to Action Matrix Column 2 Inputs," when your staff has notified us of your readiness for this inspection. This inspection procedure is conducted to provide assurance that the root cause and contributing causes of risk significant performance issues are understood, the extent of condition and the extent of cause are identified, and the corrective actions are sufficient to prevent recurrence.
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, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
Sincerely,/RA by Darrell J. Roberts acting for/
Cynthia D. Pederson Regional Administrator Docket No. 50-341 License No. NPF-43
Enclosure:
Notice of Violation cc: Distribution via LISTSERV