ENS 45918
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ENS Event | |
|---|---|
03:18 May 12, 2010 | |
| Title | |
| Event Description | On May 11, 2010, at approximately 2318 hours0.0268 days <br />0.644 hours <br />0.00383 weeks <br />8.81999e-4 months <br />, a manual Reactor Protection System (RPS) actuation was initiated as required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.1.5 'Control Rod Scram Accumulators.' Control Rod Drive (CRD) charging water header pressure was less than 1520 psig (i.e., no CRD pumps operating) and there were multiple accumulator faults on withdrawn control rods. At the time of the event, the plant was in Mode 1 at 100% power. All control rods are inserted into the core and the plant is currently stable, in Mode 3 (Hot Shutdown) with reactor pressure at approximately 930 psig. No Emergency Core Cooling Systems were required or utilized to respond to the event and there were no other 10 CFR 50.72 reportable actuations. Reactor coolant level is being maintained in its normal band by the feedwater system and decay heat is being removed by the condenser. The plant is in a normal electrical line-up with all three Emergency Diesel Generators operable and available if needed.
The cause of the event initiator, an invalid Division 2 Loss of Coolant Accident (LOCA), i.e., High Drywell Pressure/Low Reactor Vessel Water Level, signal, is currently under investigation. Prior to the manual RPS Actuation, the invalid LOCA signal resulted in invalid actuations of Division 2 equipment and systems including, the Division 2 Emergency Diesel Generator (EDG), (which started but did not load onto the bus), Low Pressure Coolant Injection B and C subsystems (which started the pumps but did not inject into the vessel), discharge of the Suppression Pool Makeup subsystem B into the suppression pool, startup of the Control Room Emergency Recirculation subsystem B, and isolation of Group 2B Containment isolation valves which included the Nuclear Closed Cooling System Containment Return Isolation valve that was not already closed. The affected equipment is being restored in accordance with plant procedure. The NRC Resident Inspector has been notified. The licensee experienced an instrumentation rack loss of power which appears to have resulted in the inadvertent Division 2 initiation. The initiator of this event also and led to a loss of power to both control rod drive charging water header pumps resulting in charging water header pressure less than required and related accumulator faults which placed the licensee in a technical specification required shutdown condition. The action statement allows only 20 minutes to restore the condition which was insufficient time for the licensee to correct the condition so a manual scram was initiated from 100% power. The scram was characterized as an uncomplicated scram and all system responses (not related to the initial instrument fault) functioned as required. |
| Where | |
|---|---|
Perry  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation | |
| LER: | 05000440/LER-2010-003 |
| Time - Person (Reporting Time:+-0.1 h-0.00417 days <br />-5.952381e-4 weeks <br />-1.3698e-4 months <br />) | |
| Opened: | Dave Duesing 03:12 May 12, 2010 |
| NRC Officer: | Bill Huffman |
| Last Updated: | May 12, 2010 |
| 45918 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| 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)(2)(i), Tech Spec Required Shutdown | |
WEEKMONTHYEARENS 571362024-05-23T08:00:00023 May 2024 08:00:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 566732023-08-10T04:39:00010 August 2023 04:39:00 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 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 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 530002017-10-04T06:50:0004 October 2017 06:50:00 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Perry Commenced Technical Specification Required Shutdown 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 498042014-02-07T11:00:0007 February 2014 11:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specifications Due to Containment Isolation Valve Over Leak Rate Limit ENS 491212013-06-16T04:00:00016 June 2013 04:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Technical Specification Shutdown Due to Small Reactor Coolant Leak on a Recirculation Flow Control Valve Vent Line 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 473122011-10-02T05:00:0002 October 2011 05:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Shutdown Required by Technical Specifications Due to Transformer Fault 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 454342009-10-15T16:25:00015 October 2009 16:25:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Unit Commenced Shutdown Due to Inoperable Division 2 Emergency Service Water System 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 416572005-05-02T10:11:0002 May 2005 10:11:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown - Reactor Vessel Level Instrumentation 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 ENS 410852004-10-02T19:00:0002 October 2004 19:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Power Being Reduced Due to Entering Ts 3.0.3 Because of Inopeable Recirc Vent System ENS 407672004-05-21T20:00:00021 May 2004 20:00:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown 2024-05-23T08:00:00 | |
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