ENS 40114
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ENS Event | |
|---|---|
06:03 Aug 29, 2003 | |
| Title | Catawba Unit 1 Automatic Reactor Trip Due to Reactor Protection System Actuation |
| Event Description | Unit 1 tripped on Over Temperature - Delta Temperature (OTDT) protection. Channel 1 OTDT was in a trip condition due to a reactor coolant hot leg temperature problem. Per Technical Specifications, this required Channel 1 OTDT to be placed in the tripped condition. Channel 2 Pressurizer pressure failed low at 0203 EDT. This input (Channel 2 Pressurizer Low Pressure) caused Channel 2 OTDT to enter a trip condition. With 2 of 4 OTDT Channels in the trip condition, a reactor trip signal was generated by the reactor protection system resulting in an automatic reactor trip. After the reactor trip occurred, RCS (Reactor Coolant System) letdown was lost on the chemical and volume control system due to low Pressurizer level. 1NV-1A (Reactor Coolant Letdown Isolation Valve) did not close as required. This necessitated the alignment of the excess letdown flowpath to maintain the desired Pressurizer level. ESF (Engineered Safety Features) operated as designed. Auxiliary feedwater automatically started and main feedwater isolated as designed.
All control rods fully inserted on the reactor trip. Station service electrical systems, emergency diesel generators, and ESF equipment are available. Catawba Unit 2 was unaffected by the trip of Unit 1. The licensee has notified the NRC Resident Inspector and will be notifying state and local officials. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+4.4 h0.183 days <br />0.0262 weeks <br />0.00603 months <br />) | |
| Opened: | Mike Lee 10:27 Aug 29, 2003 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Aug 29, 2003 |
| 40114 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (95 %) |
| After | Hot Standby (0 %) |
Catawba with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 570262024-03-13T01:11:00013 March 2024 01:11:00
[Table view]10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Power to Containment Radiation Monitors ENS 561772022-10-24T12:57:00024 October 2022 12:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Auxiliary Feedwater System Actuation ENS 558562022-04-23T06:24:00023 April 2022 06:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip During Control Rod Testing ENS 555492021-10-27T18:29:00027 October 2021 18:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of the 1B EDG Load Sequencer on Bus Undervoltage Condition ENS 552292021-05-01T11:55:0001 May 2021 11:55:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Actuation of the Auxiliary Feedwater System ENS 548882020-09-08T13:25:0008 September 2020 13:25:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Trip on Over Power Delta Temperature ENS 545232020-02-12T23:00:00012 February 2020 23:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 543072019-10-02T08:15:0002 October 2019 08:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Actuation of Containment Spray System ENS 532712018-03-19T07:29:00019 March 2018 07:29:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Actuation of Auxiliary Feedwater System During Maintenance ENS 467802011-04-23T13:21:00023 April 2011 13:21:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Valid Auxiliary Feedwater Pump Start While Cooling Down Reactor ENS 435972007-08-25T14:58:00025 August 2007 14:58:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Autostart of All Emergency Diesel Generators Due to a Grid Disturbance ENS 412462004-12-06T02:35:0006 December 2004 02:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Turbine Trip/Reactor Trip Due to Moisture Separator Reheater (Msr) High Level Trip Signal. ENS 411542004-10-28T04:52:00028 October 2004 04:52:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip After Shutdown Bank Dropped Into Core ENS 405382004-02-22T22:30:00022 February 2004 22:30:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Manually Tripped After the "B" Sg Feedwater Isolation Valve Failed Closed ENS 401142003-08-29T06:03:00029 August 2003 06:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Catawba Unit 1 Automatic Reactor Trip Due to Reactor Protection System Actuation 2024-03-13T01:11:00 | |
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