8-18-2016 | On June 19, 2016, while operating at 82% power, two secondary containment access airlock doors were briefly opened simultaneously during a surveillance test. This event was a momentary inoperability of secondary containment integrity, which is an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable event. The Resident Inspector was notified, and an Event Notification made pursuant to 10 CFR 50.72(b)(3)(v)(C). (Reference EN#52022). Following the event, the door controls were adjusted and verified to function properly. On June 29, 2016, at 100% power, workers opened two doors concurrently when entering a secondary containment access airlock. The individuals promptly closed their respective doors. The event was a brief inoperability of secondary containment integrity as above, notifications were made, and repairs completed. (Reference EN#52053) The root causes were determined to be inadequate procedural guidance and equipment design not being able to prevent the simultaneous opening of an inner and outer door at all times, under all possible conditions. Corrective actions include modification of the interlock tests, and replacement of key door interlock components.
These events did not result in a safety system functional failure. There were no radiological releases associated with these events. |
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Category:Letter
MONTHYEARL-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) NG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update ML23137A1672023-05-11011 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report L-2023-029, and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3)2023-03-10010 March 2023 and Point Beach Units 1 and 2 Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22339A0012022-12-22022 December 2022 Acceptance of Requested Licensing Action Amendment Request for Common Emergency Plan IR 05000331/20220032022-12-13013 December 2022 NRC Inspection Report No. 05000331/2022003 (Drss) ML22285A0072022-10-13013 October 2022 NRC Analysis of NextEra Energy Duane Arnold'S Decommissioning Funding Status Report, Docket No. 50-331 IR 05000331/20220022022-07-13013 July 2022 NRC Inspection Report Nos. 05000331/2022002(DNMS) and 07200032/2022002(DNMS) ML22090A1922022-05-26026 May 2022 Letter to B. Coffey, FPL from M. Doell - Duane Arnold Post Shutdown Activities Report Review Letter ML22132A2872022-05-24024 May 2022 ISFSI DQAP Approval Letter ML22111A0332022-05-20020 May 2022 Operating License Page Correction Letter to B. Coffey, Florida Power and Light, from M. Doell NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan ML22089A0492022-05-12012 May 2022 Sfmp Review Letter NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative IR 05000331/20224012022-04-27027 April 2022 Decommissioning Security Inspection Report 05000331/2022401 NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report L-2022-068, NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 22022-04-25025 April 2022 NextEra Energy Duane Arnold Quality Assurance Topical Report (FPL-3) Revision 2 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22080A1822022-03-22022 March 2022 Letter to B. Coffey from M. Doell - Duane Arnold ISFSI QAPD RAI Letter L-2022-012, Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3)2022-03-16016 March 2022 Florida Power & Light Company Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML22059A7462022-03-10010 March 2022 ISFSI-Only Physical Security Plan License Amendment Approval NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks IR 05000331/20220012022-03-0404 March 2022 Subject: NRC Inspection Report Nos. 05000331/2022001(DNMS) and 07200032/2022001(DNMS) NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22007A2722022-02-11011 February 2022 Cover Letter - NRC Duane Arnold Exemption Issuance NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks ML22028A2822022-02-0303 February 2022 Defueled Physical Security Plan License Amendment Approval ML22033A0802022-02-0202 February 2022 Supplement to License Amendment Request (TSCR-188): Proposed Change to the Physical Security Plan for the Post-Shutdown and Permanently Defueled Condition IR 05000331/20210012022-01-25025 January 2022 NRC Inspection Report Nos. 05000331/2021001(DNMS); 07200032/2021001(DNMS); and 07200032/2021002(DNMS) - Duane Arnold Energy Center ML21172A2172022-01-21021 January 2022 Issuance of License Amendment to Adopt ISFSI-Only Technical Specifications NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister 2024-01-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEARNG-18-0040, LER 2018-001-00 for Duane Arnold Energy Center Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box2018-04-0404 April 2018 LER 2018-001-00 for Duane Arnold Energy Center Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box 05000331/LER-2017-0012017-03-27027 March 2017 Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage, LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage NG-17-0072, LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage2017-03-27027 March 2017 LER 17-001-00 for Duane Arnold Energy Center Regarding Condition Prohibited by Technical Specification - Containment Vent and Purge Valve Leakage 05000331/LER-2016-0032016-12-0606 December 2016 Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit, LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit 05000331/LER-2016-0022016-12-0606 December 2016 Unplanned RCIC Inoperability Results in Safety System Functional Failure, LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure NG-16-0225, LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit2016-12-0606 December 2016 LER 16-003-00 for Duane Arnold Energy Center Regarding Main Steam Isolation Valve Leakage Exceeded Technical Specification Limit NG-16-0226, LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure2016-12-0606 December 2016 LER 16-002-00 for Duane Arnold Energy Center Regarding Unplanned RCIC Inoperability Results in Safety Functional Failure 05000331/LER-2016-0012016-08-18018 August 2016 Two Instances of Both Doors in Secondary Containment Airlock Opened Concurrently, LER 16-001-00 for Duane Arnold Energy Center Regarding Two Instances of Both Doors in Secondary Containment Airlock Opened Concurrently 05000331/LER-2015-0062016-02-18018 February 2016 HPCI and RCIC Condensate Storage Tank Suction Transfer Inoperable, LER 15-006-00 for Duane Arnold Regarding HPCI and RCIC Condensate Storage Tank Suction Transfer Inoperable 05000331/LER-2015-0022016-01-28028 January 2016 Unanalyzed Condition Due to Degraded Primary Containment Suppression Pool Coating, LER 15-002-01 for Duane Arnold Regarding Unanalyzed Condition Due to Degraded Primary Containment Suppression Pool Coating NG-15-0236, LERs 15-001-01 and 15-003-01 for Duane Arnold Regarding Both Doors in Secondary Containment Airlock Opened Concurrently2015-06-25025 June 2015 LERs 15-001-01 and 15-003-01 for Duane Arnold Regarding Both Doors in Secondary Containment Airlock Opened Concurrently NG-07-0355, LER 07-S01-00 for Duane Arnold Regarding Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area2007-05-0303 May 2007 LER 07-S01-00 for Duane Arnold Regarding Unauthorized Person Allowed Entry to Duane Arnold Energy Center Protected Area NG-03-0373, LER 03-S01-00, Duane Arnold Unattended Safeguards Information Outside of the Protected Area Caused by Personnel Error2003-05-15015 May 2003 LER 03-S01-00, Duane Arnold Unattended Safeguards Information Outside of the Protected Area Caused by Personnel Error 2018-04-04
[Table view] |
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I. Description of Event:
On June 19, 2016 at 1533, while operating at 82% power, the Control Room Supervisor (CRS) was notified that Door-281 and Door-282, both in Secondary Containment Airlock 153, had been opened concurrently during performance of STP 3.6.4.1-02, "Secondary Containment Airlock Verification," Revision 15, Step 7.1.1.e. This step directed the technician to attempt to open the inner door while the outer door was open The doors being open at the same time caused a failure to meet SR 3.6.4.1.2 to verify that either the outer door(s) or the inner door(s) in each Secondary Containment access opening are closed. The identified condition caused Secondary Containment to be considered inoperable per TS LCO 3.6.4.1. The technician involved immediately closed the doors upon encountering this unexpected condition. This action allowed SR 3.6.4.1.2 to be met, and restored Secondary Containment to an operable status.
On June 29, 2016 at 0940, while operating at 100% power, the CRS was notified that Door- 239A and Door-246, both in Secondary Containment Airlock 222, the Reactor Building Railroad Airlock, had been opened concurrently. The doors being open at the same time caused a failure to meet SR 3.6.4.1.2 to verify that either the outer door(s) or the inner door(s) in each Secondary Containment access opening are closed. The identified condition caused Secondary Containment to be considered inoperable per TS LCO 3.6.4.1. The individuals involved immediately closed their respective doors upon encountering this unexpected condition. This action allowed SR 3.6.4.1.2 to be met, and restored Secondary Containment to an operable status.
Each of the above events resulted in an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reportable event. In both cases, the Resident Inspector was notified, and an Event Notification was made pursuant to 10 CFR 50.72(b)(3)(v)(C). (References EN #52022 and EN #52053). Secondary containment leak tightness is required to ensure that the release of radioactive materials from the primary containment is restricted to those leakage paths and associated leakage rates assumed in the accident analysis and that fission products entrapped within the secondary containment structure will be treated by the Standby Gas Treatment System prior to discharge to the environment.
A Secondary Containment door airlock utilizes an interlock device with an adjustable permanent magnet (mounted on the door), and an electromagnet (on the door frame) arranged in an electrical circuit so that door(s) are held closed and/or are allowed to open after a pushbutton is depressed.
Immediately following the event on June 19, troubleshooting adjusted an interlock magnet and by 1651 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.282055e-4 months <br /> post-maintenance testing had been performed satisfactorily per Surveillance Test Procedure (STP) 3.6.4.1-02, Secondary Containment Airlock Verification.
Duane Arnold Energy Center Immediately following the event on June 29, troubleshooting found the electromagnet on Door-239A was not consistently locking the door due to loose fasteners, and the pushbutton contacts of Door- 246 were fouled, causing intermittent actuation of the door logic. The Door-239A fasteners were tightened and at 1108 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.21594e-4 months <br /> post-maintenance testing was performed satisfactorily per Surveillance Test Procedure (STP) 3.6.4.1-02, Secondary Containment Airlock Verification. The Door-246 pushbuttons were subsequently replaced.
There were no radiological releases associated with these two events. There were no other structures, systems or components inoperable at the start of either event that contributed to the event.
II. Assessment of Safety Consequences:
There were no actual safety consequences associated with these events; the potential safety consequences were minimal. In each case, both doors on the airlock were open simultaneously for less than 10 seconds, and were able to be closed immediately upon discovery of the condition. There were no radiological releases associated with these events.
These events will not be reported as safety system functional failures as engineering analysis has determined the system is capable of performing its safety function during events when the airlock is open for less than 10 seconds. The site's post-LOCA dose calculation does not credit secondary containment integrity for mitigation of on-site and off-site doses for the first 5 minutes of the event.
Therefore, these events are bounded by the existing dose calculation.
Neither event resulted in a safety system functional failure. There were no automatically or manually initiated safety system responses.
III. Cause of Event:
Technical Specifications Surveillance Requirement SR 3.6.4.1.2 requires one inner or one outer secondary containment airlock door to be closed at all times. A Root Cause Evaluation was conducted in August 2016 which determined the root causes of the events on June 19 and 29, 2016 were:
- (June 19) Inadequate procedural guidance which directed the user to attempt to open one airlock door while the other was already open (i.e., in effect, the user was instructed to actively challenge the door interlocks).
- (June 29) The secondary containment breach due to simultaneous opening of airlock doors was attributed to the equipment design not being able to prevent the simultaneous opening of one inner and one outer door at all times, under all possible conditions.
In general, the root cause noted that in recent plant history the most common resolution activity identified for the above and similar airlock events was re-adjustment of the permanent magnet, with magnet rotation being cited as one issue.
IV. Corrective Actions:
The corrective actions to preclude recurrence of the June 19, 2016 event have been completed.
These are:
- Modification of STP 3.6.4.1-02, the Secondary Containment Airlock Verification surveillance procedure, to perform the interlock test with one of the two doors closed at all times.
- Removal of the airlock interlock logic testing from STP 3.6.4.1-02.
Additional corrective actions will include development of new Preventive Maintenance (PM) actions that will perform the interlock logic testing and maintenance removed from STP 3.6.4.1-02 (above) without challenging the secondary containment. Implementation of this PM will be on a schedule and frequency commensurate with door use.
As noted, for the June 29, 2016 event the Door-239A fasteners were tightened, which allowed for successful completion of the surveillance test. Interim and compensatory corrective actions for the event have also been completed. These were replacement of the Door-246 pushbuttons and the installation of cameras at the Railroad Airlock (Airlock 222) doors, with monitors showing the view of the opposite camera. Personnel had been previously instructed on how to use the monitors when they were installed at the Reactor Building Access Control Airlock in 2015.
The corrective actions to preclude recurrence of the June 29, 2016 event will be the following:
- Door entry pushbuttons and key logic relays at high traffic airlocks will be replaced.
- Enamel will be added to permanent magnets at high traffic doors to assist in reducing/preventing magnet rotation.
Completion of the above actions will be tracked by the site Corrective Action Program.
V. Additional Information:
Previous Similar Occurrences:
A review of DAEC Licensee Event Reports from the past five years identified six similar occurrences meeting reportability requirements: reference LER 2013-006, LER 2014-002, EIIS System and Component Codes:
I EL Interlock Reporting Requirements:
These two events are each being reported pursuant to 10CFR50.73(a)(2)(v)(C).