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Category:Letter
MONTHYEARML24318C5082024-11-13013 November 2024 Condition Prohibited by Technical Specifications IR 05000498/20240032024-11-0707 November 2024 Integrated Inspection Report 05000498/2024003 and 05000499/2024003 IR 05000498/20253012024-11-0707 November 2024 Notification of NRC Initial Operator Licensing Examination 05000498/2025301; 05000499/2025301 ML24304B0512024-10-30030 October 2024 Cycle 26 Core Operating Limits Report IR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24290A1162024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal ML24249A3372024-09-0404 September 2024 Inservice Inspection Summary Report - 2RE23 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24234A0912024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24213A0842024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update NOC-AE-240040, Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML24318C5082024-11-13013 November 2024 Condition Prohibited by Technical Specifications 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-02-0505 February 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water 05000499/LER-2023-002, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2024-01-30030 January 2024 Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2023-001, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-15015 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-01-0909 January 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open2023-07-26026 July 2023 Supplement to Pressurizer Power Operated Valve Failed to Open 05000498/LER-2023-001, Pressurizer Power Operated Relief Valve Failed to Open2023-06-12012 June 2023 Pressurizer Power Operated Relief Valve Failed to Open 05000499/LER-2021-002-01, Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2022-07-0505 July 2022 Supplement to Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2022-001, From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus2022-03-0303 March 2022 From South Texas Project Unit 2, Automatic Actuation of Emergency Diesel Generator Due to Lockout of Switchyard Electrical Bus 05000499/LER-2021-002, Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System2021-12-21021 December 2021 Re Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Core Cooling System and Containment Spray System 05000499/LER-2021-001, Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve2021-09-0909 September 2021 Condition Prohibited by Technical Specifications Due to Inoperable Containment Isolation Valve 05000498/LER-2021-001, Frozen Common Sensing Line Results in Loss of Two Main Feedwater Pumps Leading to Automatic Reactor Protection and Auxiliary Feedwater Systems Actuations Due to Low Steam Generator Level2021-04-15015 April 2021 Frozen Common Sensing Line Results in Loss of Two Main Feedwater Pumps Leading to Automatic Reactor Protection and Auxiliary Feedwater Systems Actuations Due to Low Steam Generator Level 05000498/LER-2017-0022018-01-22022 January 2018 Unit 1 Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil, LER 17-002-00 for South Texas Project, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil 05000498/LER-2017-0012017-05-11011 May 2017 Unit 1 failure of a timing relay during a Technical Specification surveillance, LER 17-001-00 for South Texas, Unit 1, Regarding Failure of a Timing Relay During a Technical Specification Surveillance 05000498/LER-2016-0022016-06-29029 June 2016 Unit 1 Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip due to Generator Lockout, LER 16-002-00 for South Texas Project, Unit 1, Regarding Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip Due to Generator Lockout 05000498/LER-2016-0012016-03-22022 March 2016 Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed, LER 16-001-00 for South Texas Project, Unit 1, Regarding Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed NOC-AE-05001865, LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak2005-04-0505 April 2005 LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak NOC-AE-04001681, LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B2004-02-18018 February 2004 LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B NOC-AE-00000840, 1,Unauthorized Entry Into Protected Area,Safeguards Event Report2000-05-0404 May 2000 1,Unauthorized Entry Into Protected Area,Safeguards Event Report 2024-09-19
[Table view] |
LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat
10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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October 22, 2024 NOC-AE-24004074 10 CFR 50.73 STI: 35653612 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Unit 2 Docket No. STN 50-499 Licensee Event Report 2024-003-00 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Functions Pursuant to reporting requirements in 10 CFR 50.73(a)(2)(i)(B), 10 CFR 50.73(a)(2)(v)(B), and 10 CFR 50.73(a)(2)(v)(D), STP Nuclear Operating Company (STPNOC) hereby submits the attached South Texas Project (STP) Unit 2 Licensee Event Report 2024-003-00.
The event did not have an adverse effect on the health and safety of the public.
There are no commitments in this submittal.
If there are any questions regarding this submittal, please contact Zachary Dibbern at 361-972-4336 or me at 361-972-8945.
Jason R. Tomlinson Site Vice President Enclosure: Unit 2 LER 2024-003-00, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Functions cc:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511 Jason R Tomlinson Digitally signed by Jason R Tomlinson Date: 2024.10.22 16:53:49 -05'00'
NOC-AE-24004074 Enclosure Enclosure Unit 2 LER 24-003-00 Unit 2 LER 2024-003-00, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Functions
Abstract
South Texas Unit 2 I
00499 6
Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Functions 08 24 2024 2024 003 00 10 22 2024 1
100%
Zachary Dibbern, Licensing Engineer 361-972-4336 B
CC ISV R344 Yes
On July 24, 2024, at 0959 CDT a level alarm for the Unit 2 Reactor Containment Building Chilled Water Expansion Tank was received coincident with Component Cooling Water (CCW) lineup changes. On August 29, 2024, at 0820 CDT, Train 'C' CCW system was declared inoperable for planned maintenance on Containment Isolation Valve 2R202T-CC-0199. It was discovered that 2R202T-CC-0199 had stem-to-disk separation due to missing taper pins and had been inoperable for almost 39 days. The past inoperability resulted in multiple Technical Specification Limiting Conditions of Operations not being met and was determined to be reportable as a condition prohibited by Technical Specifications and as a condition that could have prevented fulfillment of a safety function. The missing taper pins were determined to be the result of the pins not being secured. Corrective and extent of condition actions include: (1) 2R202T-CC-0199 was repaired, (2) planned internal inspection of two similar valves.
, two trains of systems being out that supported Residual Heat Removal (RHR) heat exchanger and mitigating the consequences of an accident (Reactor Containment Fan Coolers (RCFCs)).
B. Plant Operating Conditions Prior to Event Prior to the event on August 24, 2024, Unit 2 was in MODE 1 at 100% power.
C. Status of Structures, Systems, and Components That Were Inoperable At the Start of the Event and That Contributed To the Event There were no inoperable Structures, Systems, or Components at the start of the event that contributed to the event.
D. Narrative Summary of the Event Timeline (Note: All times are Central Daylight Time) 07/24/24 (0959) - Received level alarm 22M1/D3 for Reactor Containment Building (RCB) Chilled Water Expansion Tank Level HI/LO and ICS point LD9606. [Later determined to be firm evidence that there was stem-to-disk separation.]
2 6
South Texas Unit 2 00499 2024 003 00 IPage of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 III. Analysis of Event A. Safety System Responses that Occurred No safety systems responses occurred because of this event.
B. Duration of Safety System Inoperability Train C of the CCW was determined to be inoperable from 09:59, July 24, 2024, to 09:22, September 1, 2024, when the CCW Train C was declared OPERABLE following repair. This was a total of 38 days, 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />, and 23 minutes.
C. Safety Consequences and Implications A risk evaluation was performed to estimate the Incremental Core Damage Probability (ICDP) associated with this event.
The calculated ICDP from the inoperability of Train 2C CCW was determined to be a very small change in risk and is of very low safety significance. The event did not result in any offsite release of radioactivity or increase of offsite dose rates and there were no personnel injuries or damage to any other safety-related equipment associated with this event.
Therefore, there was no adverse effect on the health and safety of the public.
IV. Cause of Event The 2R202T-CC-0199 isolation valve of the Train C CCW showed no indications that the tapered pins, that are used to secure the valve stem to the disk, were ever secured through staking or tack welding. The valve had not received any internal work since installation during construction. Therefore, the tapered pins would have worked loose overtime, and then on July 24, 2024, when the hydraulic transient occurred, the pin(s) ejected, allowing stem-to-disk separation and inoperability of the isolation valve. It is considered likely that one pint had ejected prior to this event due to the unlikelihood of two pins working loose and ejecting simultaneously.
V. Corrective Actions On September 9, 2024, the containment isolation valve 2R202T-CC-0199 repair was complete, and the valve was declared OPERABLE. Extent of condition actions are scheduled to look at the state of tapered pins in the similar valves 1-MOV-0199 and 2-MOV-0137 which are from the same purchase order.
VI. Previous Similar Events There were no previous recent similar events identified.
VII. Attachment
- 1. Equipment History Timeline 6
6 South Texas Unit 2 00499 2024 003 00 I
LER 2024-003-00 Equipment History Timeline Start End Duration (dd:hh:mm)
Inoperable Equipment Applicable Technical Speci"cations (TS) 07/24/24 0959 09/01/24 0922 38:23:23 Train C ECCS TS 3.5.2, 3.5.6, 3.6.2.3, 3.6.3, 3.7.3 action a, TS 07/27/24 0111 07/27/24 0127 00:00:16 Train A ECCS TS 3.5.2 action a 07/27/24 0129 07/27/24 0144 00:00:15 Train B ECCS TS 3.5.2 action a 07/29/24 0200 08/02/24 0204 04:00:04 Train 2A ECW TS 3.5.2, TS 3.5.6, TS 3.6.2.3, TS 3.7.3 action a 08/05/24 0400 08/06/24 1047 01:06:47 Train 2B ECW TS 3.5.2, TS 3.5.6, TS 3.6.2.3, TS 3.7.3 action a 08/07/24 0400 08/07/24 1429 00:10:29 Train B ECCS TS 3.5.2 action a 08/08/24 2309 08/11/24 1631 02:17:22 Train B Sequencer TS 3.7.3, TS 3.5.2, TS 3.7.14, TS 3.6.2.3, TS 3.6.2.1 08/20/24 2010 08/22/24 1128 01:15:18 Train B ECW TS 3.7.14, TS 3.5.2 action a 08/23/24 0127 08/23/24 0247 00:01:20 Train A ECCS TS 3.5.2 action a 08/23/24 0248 08/23/24 0335 00:00:47 Train B ECCS TS 3.5.2 action a
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05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators | Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators | Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators | | 05000498/LER-2024-001, Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function | Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump | Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps | Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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