2-18-2016 | On July 23, 2015, while operating at 100% power, with no structures, systems, or components inoperable that contributed to this event, during the performance of Surveillance Test Procedure ( STP) 3.5.3-05, RCIC/HPCI Suction Transfer Interlock, the Condensate Storage Tank ( CST) Low Level HPCI and RCIC Suction Swap Relay, E41A-K059, as-found time to trip was 19.86 seconds. This was outside the relay design band of 0.0-5.0 seconds. This condition resulted in the HPCl/RCIC CST suction swap function being inoperable. Technical Specification (TS) require HPCI and RCIC to be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the discovery of the inoperable support feature. HPCI and RCIC were not declared inoperable and therefore, this
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities NG-24-0004, 2023 Annual Radiological Environmental Operating Report2024-05-0808 May 2024 2023 Annual Radiological Environmental Operating Report NG-24-0003, Submittal of 2023 Annual Radioactive Material Release Report2024-04-24024 April 2024 Submittal of 2023 Annual Radioactive Material Release Report ML24072A0292024-03-29029 March 2024 Nextera Energy Duane Arnold, Llc. Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) NG-24-0001, 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update2024-03-0606 March 2024 2024 Annual Decommissioning and Spent Fuel Management Funding Status Report and Independent Spent Fuel Storage Installation (ISFSI) Decommissioning Financial Assurance Update NG-24-0002, 2023 Annual Exposure Report - Form 5s2024-03-0606 March 2024 2023 Annual Exposure Report - Form 5s L-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 ML22066A7632022-04-25025 April 2022 ISFSI-Only Emergency Plan License Amendment Approval 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 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) 2024-09-04
[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] |
Reported lessons learned are incorporated into the licensing process and fed back to industry.
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I. Description of Event:
On July 23, 2015, while operating at 100% power, with no structures, systems, or components inoperable that contributed to this event, during the performance of Surveillance Test Procedure (STP) 3.5.3-05, RCIC/HPCI Suction Transfer Interlock, the Condensate Storage Tank (CST) Low Level HPCI (High Pressure Coolant Injection) and RCIC (Reactor Core Isolation Cooling) Suction Swap Relay, E41A-K059, as-found time to trip was 19.86 seconds. This was outside the relay design band of 0.0-5.0 seconds and the STP acceptance band of 1.50-2.00 seconds. This condition resulted in the HPCl/RCIC CST suction swap function being inoperable. At the time, this failure was considered a non-TS failure. The relay was recalibrated to meet the STP acceptance band. On October 2, 2015, during the performance of STP 3.5.3-05, the relay once again was found out of tolerance. The relay was tested a second time and was found within the acceptable band.
An immediate operability evaluation determined the suction swap function was operable and an operability evaluation was requested. As compensatory measure, HPCI was aligned to the Torus. While performing troubleshooting on October 8, 2016, it was determined that the suction swap relay was inoperable.
Technical Specification Requirements Technical Specification (TS) 3.3.5.1, Action D.1 requires HPCI to be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the discovery of a loss of the HPCI suction transfer capability if not aligned to the suppression pool.
TS 3.3.5.2, Action D.1 requires RCIC to be declared inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from the discovery of a loss of the HPCI suction transfer capability if not aligned to the suppression pool.
TS 3.5.1, Action F.2 requires HPCI to be restored to operable status within 14 days. If this action is not completed, TS require the plant to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of exceeding the 14 days.
TS 3.5.3, Action A.1 requires RCIC to be restored to operable status within 14 days. If this action is not completed, TS require the plant to be in Mode 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of exceeding the 14 days.
Duane Arnold Energy Center Since the suction of RCIC and HPCI are normally aligned to the CST, the inoperability of the suction source swap function makes the supported SSCs (RCIC and HPCI) inoperable from July 23, 2015 until the suction source was manually swapped to the Torus. When this condition was discovered on October 2, 2015, HPCI suction was manually transferred to the Suppression Pool. However, RCIC suction was not transferred to the Suppression Pool and was therefore inoperable from July 23, 2015 until the condition was corrected on October 8, 2015. Both RCIC and HPCI inoperability times exceeded their LCO duration of 14 days. Therefore, this condition meets the reporting requirements of 10CFR50.73(a)(2)(i)(B) and 10CFR50.73(a)(2)(v)(A) and (D).
IL Assessment of Safety Consequences:
The safety significance of instrumentation used to initiate transfer of HPCI system or RCIC system suction source from the CSTs to the suppression pool is low because the CSTs have a sufficient supply of water for meeting the transient and accident requirements of these systems. Both CSTs are required to be maintained above 8 feet to ensure 75,000 gallons is held in reserve for the HPCI system and RCIC system and to maintain HPCI and RCIC keep fill requirements. At a minimum level of 8 feet there is adequate storage capacity for both HPCI and RCIC to operate at design flow for 35 minutes before the Lo-Lo level is reached. Using additional conservatism, when the CST level reaches 6 feet the condensate service pumps trip to ensure no other systems are drawing down the CST. Even at a volume corresponding to a starting point of 6 feet both HPCI and RCIC could operate at design flow for 25 minutes before the Lo-Lo level is reached. Under the bounding condition for operation of HPCI, it is assumed during a small break LOCA that the reactor is depressurized after 10 minutes by operator action via a rapid depressurization using SRVs (Ref. 18). Thus it is expected that the suction transfer would not be required before the operators depressurize the reactor.
In addition, if the Lo-Lo CST level is reached, three annunciators are expected.
Annunciator 1CO3C (D-3) is activated via the time delay relay E41A-K059. However, annunciators 1C06A (C-8) and (C-9) will also occur when CST level reaches the Lo- Lo CST set point. While not credited as a required operator action, the Annunciator Response Procedure for 1C06A (C-8) and (C-9) direct an operator action to verify that the Suppression Pool Suction valves for HPCI and RCIC have cycled open. This step directs the operators to open the valves if the automatic function did not occur.
III. Cause of Event:
An Apparent Cause Evaluation (ACE) was completed. The ACE determined that the control room operators failed to address the current licensing basis with respect to the CST suction swap time delay.
IV. Corrective Actions:
Immediate Corrective Action On October 8, 2015, the time delay relay was replaced and subsequently tested satisfactorily.
Corrective Actions for Cause of Event STP 3.5.3-05 was revised to include the current licensing basis for the time delay relay.
V. Additional Information:
Previous Similar Occurrences:
A review of NextEra Energy Duane Arnold Licensee Event Reports from the previous three years found no other instances of events related to the CST suction swap relay failure.
EIIS System and Component Codes:
KA - Condensate Storage and Transfer System Reporting Requirements:
This activity is being reported pursuant to the requirements of 10CFR50.73(a)(2)(i)(B) (for both HPCI and RCIC) and 10CFR50.73(a)(2)(v)(A) and (D) (for HPCI).