ENS 43808
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ENS Event | |
|---|---|
12:32 Nov 28, 2007 | |
| Title | Reactor Scram and Eccs Injection |
| Event Description | A reactor scram occurred at full power due to either a main turbine trip or loss of feedwater (cause is still under investigation). All rods fully inserted. RCIC started as expected but tripped shortly thereafter on a preliminary indication of low suction pressure. The Digital Feedwater System backup motor driven feedwater pump did not function as required and reactor water level decreased to level 2 ( 130 inches). High Pressure Core Spray (HPCS) started automatically at level 2 and restored water level. Currently reactor water level is at 188 inches and reactor pressure is at 927 PSI. Decay heat is being removed via the turbine bypass valves. No other significant equipment was out of service at the time of the scram. The scram had no impact on offsite or onsite power availability.
The licensee attempted to restore RCIC a second time and experienced another trip. In addition, the licensee attempted to restore the digital feedwater and was unsuccessful. Feedwater continues to be supplied as needed via the HPCS while the licensee attempts to restore RCIC and Digital Feedwater System. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000440/LER-2007-004 |
| Time - Person (Reporting Time:+-3.88 h-0.162 days <br />-0.0231 weeks <br />-0.00531 months <br />) | |
| Opened: | Alan Rabenold 08:39 Nov 28, 2007 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Nov 28, 2007 |
| 43808 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | A/R |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
Perry with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge | |
WEEKMONTHYEARENS 566732023-08-10T04:39:00010 August 2023 04:39:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Trip ENS 562982023-01-05T17:42:0005 January 2023 17:42:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram ENS 551722021-04-06T01:49:0006 April 2021 01:49:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Protection System (RPS) Actuation at Zero Percent Power ENS 541852019-07-27T23:29:00027 July 2019 23:29:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Main Turbine Trip ENS 538962019-02-25T05:24:00025 February 2019 05:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Generator Trip ENS 517292016-02-11T20:04:00011 February 2016 20:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Start of Emergency Diesel Generator and Loss of Shutdown Cooling ENS 517162016-02-08T20:03:0008 February 2016 20:03:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Following Spurious Opening of Two Safety Relief Valves ENS 516792016-01-24T02:22:00024 January 2016 02:22:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Required Shutdown Due to Unidentified Leakage in Drywell ENS 506012014-11-07T13:47:0007 November 2014 13:47:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram Due to Loss of Feedwater ENS 505512014-10-20T06:18:00020 October 2014 06:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Scram on Loss of Feedwater ENS 486882013-01-22T08:32:00022 January 2013 08:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Automatic Reactor Protection System Actuation ENS 477102012-03-01T05:00:0001 March 2012 05:00:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Protection System Actuation Due to Automatic Turbine Runback ENS 459182010-05-12T03:18:00012 May 2010 03:18:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Manual Reactor Scram Due to Loss of Control Rod Drive Charging Water Header Pumps ENS 454402009-10-16T04:48:00016 October 2009 04:48:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 451472009-06-21T21:50:00021 June 2009 21:50:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Related to a Main Turbine Trip ENS 438082007-11-28T12:32:00028 November 2007 12:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(iv)(A), System Actuation - ECCS Discharge Reactor Scram and Eccs Injection ENS 433632007-05-15T04:58:00015 May 2007 04:58:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram During Testing ENS 430492006-12-13T09:35:00013 December 2006 09:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram - Loss of Instrument Air Resulting in Feedwater Transient and Manual Reactor Scram ENS 413102005-01-06T06:12:0006 January 2005 06:12:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Scram Due to Reactor Recirculation Pump Trip ENS 412902004-12-24T04:54:00024 December 2004 04:54:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Reactor Scram Following Down Shift of Both Recirc Pumps from Fast to Slow Speed 2023-08-10T04:39:00 | |
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