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Similar Documents at Fermi |
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Category:Letter
MONTHYEARIR 05000341/20240032024-11-0606 November 2024 Integrated Inspection Report 05000341/2024003 IR 05000341/20240122024-11-0101 November 2024 Commercial Grade Dedication Inspection Report 05000341/2024012 IR 05000016/20240012024-11-0101 November 2024 Enrico Fermi Atomic Power Plant, Unit 1, NRC Inspection Report 05000016/2024001 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 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 ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 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) 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000341/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 05000341/LER-2023-002, Technical Specification Completion Time Exceeded Due to Repairs on the MDCT Fan D2023-09-15015 September 2023 Technical Specification Completion Time Exceeded Due to Repairs on the MDCT Fan D 05000341/LER-2023-001-01, Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability2023-06-23023 June 2023 Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability 05000341/LER-2023-001, Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability2023-05-22022 May 2023 Loss of Mechanical Draft Cooling Tower Fan Brakes During High Speeds Leads to Loss of Safety Function and Inoperability 05000341/LER-2022-004, Containment Isolation Valve Actuator Found Disconnected from Its Bonnet Resulting in Condition Prohibited by Technical Specifications2022-10-31031 October 2022 Containment Isolation Valve Actuator Found Disconnected from Its Bonnet Resulting in Condition Prohibited by Technical Specifications 05000341/LER-2022-003, Turbine Trip and Subsequent Reactor Trip Due to Mayflies2022-08-23023 August 2022 Turbine Trip and Subsequent Reactor Trip Due to Mayflies 05000341/LER-2022-002, Unexpected High Pressure Coolant Injection Turbine Trip2022-07-0606 July 2022 Unexpected High Pressure Coolant Injection Turbine Trip 05000341/LER-2022-001, Reactor Scram on Low Reactor Pressure Vessel Level2022-04-0404 April 2022 Reactor Scram on Low Reactor Pressure Vessel Level 05000341/LER-2021-002-01, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure2022-03-15015 March 2022 Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure 05000341/LER-2021-003, High Pressure Coolant Injection Inoperable Due to Contact Oxidation2021-12-29029 December 2021 High Pressure Coolant Injection Inoperable Due to Contact Oxidation 05000341/LER-2021-002, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure2021-10-21021 October 2021 Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure 05000341/LER-2021-001, Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis2021-07-0101 July 2021 Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis 05000341/LER-2020-002, Valid Actuation of Emergency Diesel Generators During Partial Loss of Offsite Power2020-08-31031 August 2020 Valid Actuation of Emergency Diesel Generators During Partial Loss of Offsite Power 05000341/LER-2020-001, Secondary Containment Inoperable Due to Both Airlock Doors Open2020-04-22022 April 2020 Secondary Containment Inoperable Due to Both Airlock Doors Open 05000341/LER-2019-006, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction2020-02-14014 February 2020 Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction 05000341/LER-2019-005, Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction2019-11-22022 November 2019 Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Damper Malfunction NRC-19-0071, Division 2 Mechanical Draft Cooling Tower Fan D Tripped When Placed in High Speed Due to a Blown Fuse2019-09-30030 September 2019 Division 2 Mechanical Draft Cooling Tower Fan D Tripped When Placed in High Speed Due to a Blown Fuse 05000341/LER-2019-003, Secondary Containment Declared Inoperable Due to Opening Both Airlock Doors2019-07-26026 July 2019 Secondary Containment Declared Inoperable Due to Opening Both Airlock Doors 05000341/LER-2019-002, Secondary Containment Airlock Doors Opened at the Same Time Resulting in a Condition Prohibited by Technical Specifications2019-04-22022 April 2019 Secondary Containment Airlock Doors Opened at the Same Time Resulting in a Condition Prohibited by Technical Specifications 05000341/LER-2019-001, Unplanned Loss of Safety Function of Gland Seal Exhauster Trip During Planned Maintenance Due to Inadequate Procedure2019-03-0101 March 2019 Unplanned Loss of Safety Function of Gland Seal Exhauster Trip During Planned Maintenance Due to Inadequate Procedure 05000341/LER-2018-007, Reactor Building to Suppression Chamber Vacuum Breaker Condition Prohibited by Technical Specifications2019-02-0404 February 2019 Reactor Building to Suppression Chamber Vacuum Breaker Condition Prohibited by Technical Specifications 05000341/LER-2018-006, Emergency Diesel Generator Load Sequencer Inhibits Automatic Start of Residual Heat Removal Pumps Under Certain Scenarios Due to Unrecognized Original Design Defect2018-12-14014 December 2018 Emergency Diesel Generator Load Sequencer Inhibits Automatic Start of Residual Heat Removal Pumps Under Certain Scenarios Due to Unrecognized Original Design Defect 05000341/LER-2018-005, Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function2018-09-29029 September 2018 Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function 05000341/LER-2018-004, Re Inoperability of Reactor Water Cleanup System Isolation Differential Flow-High Function2018-07-25025 July 2018 Re Inoperability of Reactor Water Cleanup System Isolation Differential Flow-High Function 05000341/LER-2018-002, Loss of Division 1 Offsite Power Causes Partial Loss of Feedwater Leading to ECCS Injection and Reactor Scram2018-06-12012 June 2018 Loss of Division 1 Offsite Power Causes Partial Loss of Feedwater Leading to ECCS Injection and Reactor Scram 05000341/LER-2018-001, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC System Manipulation2018-02-23023 February 2018 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC System Manipulation 05000341/LER-1917-005, Regarding Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function2017-11-0303 November 2017 Regarding Non-Functional Mechanical Draft Cooling Tower Fan Brakes Leads to HPCI Being Declared Inoperable and Loss of Safety Function 05000341/LER-1917-004, Regarding Inadequate Procedural Guidance for Residual Heat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss of Safety Function2017-10-0909 October 2017 Regarding Inadequate Procedural Guidance for Residual Heat Removal Complex Ventilation Systems Leads to Condition Prohibited by Technical Specifications and Loss of Safety Function 05000341/LER-1917-003, Regarding Division 2 Residual Heat Removal Service Water System (RHRSW) Inoperable Due to an Inoperable RHRSW Flow Control Valve2017-07-21021 July 2017 Regarding Division 2 Residual Heat Removal Service Water System (RHRSW) Inoperable Due to an Inoperable RHRSW Flow Control Valve NRC-17-0040, (LER) SER 17-S01-00 for Fermi 2 Regarding Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility2017-05-15015 May 2017 (LER) SER 17-S01-00 for Fermi 2 Regarding Unescorted Access Granted for Individual Subsequent to Being Denied Unescorted Access at Another Nuclear Facility 05000341/LER-2016-003, Cancellation of Licensee Event Reports (Lers) for Secondary Containment Wind Events: LER-16-003, LER 16-004, LER 16-007, Er 16-008, LER 16-010, LER 16-013; LER 16-014, LER 15-015, LER 16-016 and LER 16-0172017-03-17017 March 2017 Cancellation of Licensee Event Reports (Lers) for Secondary Containment Wind Events: LER-16-003, LER 16-004, LER 16-007, Er 16-008, LER 16-010, LER 16-013; LER 16-014, LER 15-015, LER 16-016 and LER 16-017 05000341/LER-2017-002, Regarding High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to Be Inoperable2017-03-16016 March 2017 Regarding High Water Level Indications at Low Reactor Pressures Causes Some Functions of High Pressure Coolant Injection System and Reactor Core Isolation Cooling System to Be Inoperable 05000341/LER-2017-001, Regarding Loss of Reactor Protection System Scram Function During the Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box2017-03-0606 March 2017 Regarding Loss of Reactor Protection System Scram Function During the Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box 05000341/LER-2016-017, Regarding Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds2017-02-0303 February 2017 Regarding Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds 05000341/LER-2016-015, Regarding Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds2017-02-0303 February 2017 Regarding Secondary Containment Pressure Exceeded Technical Specification During Reactor Building HVAC Restart Due to High Winds 05000341/LER-2016-016, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather2017-02-0303 February 2017 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather 05000341/LER-2016-014, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather2017-01-10010 January 2017 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather 05000341/LER-2016-013, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather2017-01-10010 January 2017 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather 05000341/LER-2016-009, Regarding Emergency Diesel Generator Inoperable Due to Open Circuit on Loss of Power Instrumentation2016-12-20020 December 2016 Regarding Emergency Diesel Generator Inoperable Due to Open Circuit on Loss of Power Instrumentation 05000341/LER-2016-012, Regarding Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power2016-12-20020 December 2016 Regarding Unanalyzed Condition for Control Rod Drop Accident at Low Reactor Power 05000341/LER-2016-010, For Fermi, Unit 2, Regarding Secondary Containment Pressure Exceeding Technical Specification Due to Adverse Weather2016-12-20020 December 2016 For Fermi, Unit 2, Regarding Secondary Containment Pressure Exceeding Technical Specification Due to Adverse Weather 05000341/LER-2016-011, Regarding Standby Liquid Control Inoperable Due to Sodium Pentaborate Concentration Outside of Technical Specifications2016-12-20020 December 2016 Regarding Standby Liquid Control Inoperable Due to Sodium Pentaborate Concentration Outside of Technical Specifications 05000341/LER-2016-008, Regarding Past Instances of Secondary Containment Pressure Exceeding Technical Specifications Due to Adverse Weather2016-11-15015 November 2016 Regarding Past Instances of Secondary Containment Pressure Exceeding Technical Specifications Due to Adverse Weather 05000341/LER-2016-006, Regarding Inadequate Interpretation of Technical Specifications Related to Mechanical Draft Cooling Tower Fan Brake System Leads to Condition Prohibited by Technical Specifications, Loss of Safety Function, and Unanalyzed2016-10-20020 October 2016 Regarding Inadequate Interpretation of Technical Specifications Related to Mechanical Draft Cooling Tower Fan Brake System Leads to Condition Prohibited by Technical Specifications, Loss of Safety Function, and Unanalyzed. 05000341/LER-2016-007, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather2016-10-20020 October 2016 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather 05000341/LER-2016-005, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Restart During High Winds2016-09-30030 September 2016 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Reactor Building HVAC Restart During High Winds 05000341/LER-2016-004, Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather2016-09-12012 September 2016 Regarding Secondary Containment Pressure Exceeded Technical Specification Due to Adverse Weather ML16138A3352016-05-17017 May 2016 ASP Screening Analysis - Reject Fermi Unit 2 (341-15-002) 05000341/LER-2015-006-01, Regarding Reactor Scram Due to Loss of Turbine Building Closed Cooling Water2016-04-15015 April 2016 Regarding Reactor Scram Due to Loss of Turbine Building Closed Cooling Water 2024-05-16
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Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Electric Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4153 Fax: 734.586.1431 Email: peter.dietrich@dteenergy.com 10 CFR 50.73 July 1, 2021 NRC-21-0035 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Licensee Event Report (LER) No. 2021-001 Pursuant to 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(ii)(B), 10 CFR 50.73(a)(2)(v), 10 CFR 50.73(a)(2)(vii), and 10 CFR 50.72(a)(2)(ix)(A), DTE Electric Company (DTE) is submitting LER No. 2021-001, Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis.
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact Mr. Ertman L.
Bennett III, Manager - Nuclear Licensing, at (734) 586-4273.
Sincerely, Peter Dietrich Senior Vice President and Chief Nuclear Officer Enclosure: Licensee Event Report No. 2021-001, Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis cc:
NRC Project Manager NRC Resident Office Regional Administrator, Region III
Enclosure to NRC-21-0035 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Licensee Event Report (LER) No. 2021-001 Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis
Abstract
The Fermi 2 Reactor Building Steam Tunnel (RBST) has a normally closed door which is credited as a hazard barrier for certain high energy line break (HELB) scenarios. On May 3, 2021, while Fermi 2 was operating at 100% reactor power in MODE 1, it was determined that the RBST door had been open on seven occasions within the past three years for longer than required for ingress/egress and that this condition was not bounded by site analyses. If a postulated HELB had occurred while the door was open during those seven occasions, equipment outside the RBST may have been adversely impacted by the post-HELB conditions. It was determined that the conditions were reportable as a condition prohibited by Technical Specifications (TS), loss of safety functions, an unanalyzed condition, a common cause inoperability, and a single cause preventing safety functions in different systems. Due to the door being open for only a short time in each case, a bounding risk evaluation determined that the safety significance was very low. There were no radiological releases associated with this event.
The cause of this event was the failure of Operations personnel to properly follow site procedures which prohibited the opening of the door (other than during ingress/egress) without prior evaluation by site engineering. Immediate corrective action was taken to restrict opening of the RBST door to ingress/egress only. Additional longer-term corrective actions are planned to perform new HELB analyses that establish specific conditions under which the RBST door may remain open.
below, while written specifically for the more recent (i.e., April 2021) occurrences, is also generally applicable to these older occurrences.
Indications of a steam leak in the RBST led to the decision for personnel to access the RBST and investigate the source of the leak and perform repairs if possible. Since door R1-11 opens into the room, a steam leak in the room could pressurize the room and make it difficult to open from the inside. For this reason, station personnel made the decision to leave the R1-11 door open while any personnel were inside the room. Door R1-11 was not disabled from closing but remained open to facilitate personnel safety to allow for prompt egress if needed.
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- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
The reason for leaving the RBST door open in April of 2021 was as a safety precaution while personnel were inside the RBST to investigate a potential steam leak. The steam leak was identified and repaired during the week of May 17, 2021. The repairs were performed while the plant was shut down, which eliminated concerns regarding the RBST door being open. Repair of the steam leak has eliminated the need for entry to the RBST in the foreseeable future. This will allow the door to remain in its closed position, consistent with analysis assumptions.
In addition, further investigation is being performed under the Fermi 2 Corrective Action Program (CAP) to determine if other doors (i.e., other than R1-11) have also been improperly controlled during maintenance activities. The investigation is ongoing.
PREVIOUS OCCURRENCES
There have been no other previous reportable events concerning the RBST door. However, this report did include documentation of the previous occurrences in the past three years. As described above, an investigation is ongoing under the Fermi 2 CAP to determine if there may have been previous occurrences of a similar nature associated with other similar doors.
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05000341/LER-2021-001, Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis | Unrecognized Impact of Opening of Barrier Doors on High Energy Line Break Analysis | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000341/LER-2021-002-01, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure | Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000341/LER-2021-002, Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure | Unplanned Inoperability of High Pressure Coolant Injection System Due to an Inverter Circuit Failure | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000341/LER-2021-003, High Pressure Coolant Injection Inoperable Due to Contact Oxidation | High Pressure Coolant Injection Inoperable Due to Contact Oxidation | 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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