ENS 43752
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ENS Event | |
|---|---|
04:59 Oct 28, 2007 | |
| Title | Manual Scram Due to Lowering Intake Level |
| Event Description | High winds (in excess of 40 MPH) resulted in significant debris at the plant intake. Traveling screens had been placed in 'Fast' speed and continuous wash on the previous shift in anticipation of predicted high wind conditions. As the debris entered the intake, high traveling screen differential pressure and lowering intake level prompted the operating crew to enter the appropriate Abnormal Operating Procedure (AOP).
Efforts to manually clean the screens were ineffective, and at 0059 hours6.828704e-4 days <br />0.0164 hours <br />9.755291e-5 weeks <br />2.24495e-5 months <br />, the crew inserted a manual scram as directed by procedure at 240 foot intake level. On scram, as expected, reactor vessel level lowered to the low level scram setpoint (177 inches above top of active fuel). At this point, as expected, an automatic Reactor Protection System (RPS) actuation, and a Group 2 Primary Containment Isolation System (PCIS) isolation occurred with no anomalies noted. During plant cooldown reactor level lowered to 177 inches above TAF. This resulted in a valid RPS actuation and a PCIS Group 2 isolation signal. All systems responded as expected. Operators were able to maintain reactor vessel level above the actuation setpoint for High Pressure Coolant Injection (HPCI) and Reactor Core Isolation Cooling (RCIC) systems, and these systems were not required to operate. The cause of the failure of the traveling screens to maintain intake level is under investigation. All control rods are fully inserted and the plant is stable in Mode 3, Hot Shutdown. Decay heat is being removed via the turbine bypass valves to the main condenser. No SRVs lifted during the transient. The plant is in a normal shutdown electric plant lineup. The licensee notified the NRC Resident Inspector and the New York Public Service Commission. |
| Where | |
|---|---|
Fitzpatrick  New York (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000333/LER-2007-002 |
| Time - Person (Reporting Time:+-1.58 h-0.0658 days <br />-0.0094 weeks <br />-0.00216 months <br />) | |
| Opened: | David Richardson 03:24 Oct 28, 2007 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Oct 28, 2007 |
| 43752 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (100 %) |
| After | Hot Shutdown (0 %) |
FitzPatrick with 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
WEEKMONTHYEARENS 573332024-09-23T11:20:00023 September 2024 11:20:00
[Table view]10 CFR 50.72(b)(2)(xi), Notification to Government Agency or News Release, 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram Due to Generator Trip ENS 563732023-02-19T06:05:00019 February 2023 06:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation ENS 561192022-09-26T07:06:00026 September 2022 07:06:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram ENS 545032020-01-31T10:55:00031 January 2020 10:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram Due to Main Turbine Trip ENS 520422016-06-24T16:15:00024 June 2016 16:15:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Scram Due to Reactor Recirculation Pumps Degradation ENS 516802016-01-24T03:41:00024 January 2016 03:41:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Scram Due to Lowering Intake Level ENS 486762013-01-16T02:12:00016 January 2013 02:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of a 4160 Volt Bus While Performing Testing ENS 485012012-11-11T08:55:00011 November 2012 08:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration Reactor Scram Due to Turbine Trip Followed by Unusual Event Declared Due to Main Transformer and Bus Duct Fire ENS 484792012-11-05T02:53:0005 November 2012 02:53:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Automatic Reactor Scram from Full Power Following Turbine Trip ENS 483862012-10-05T17:03:0005 October 2012 17:03:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(3)(xiii), Loss of Emergency Preparedness Rps and Pciv Actuation Due to Loss of Offsite Power ENS 445462008-10-07T10:35:0007 October 2008 10:35:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Specified System Actuation Due to Loss of Power During Testing ENS 437522007-10-28T04:59:00028 October 2007 04:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Scram Due to Lowering Intake Level ENS 436352007-09-12T10:35:00012 September 2007 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Reactor Scram Following Intake Structure Traveling Screen Fouling ENS 419872005-09-14T06:13:00014 September 2005 06:13:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Scram on Low Reactor Vessel Water Level During Planned Maintenance ENS 400722003-08-14T20:26:00014 August 2003 20:26:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(a)(1)(i), Emergency Class Declaration, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unusual Event Declared Due to a Loss of Offsite Power. 2024-09-23T11:20:00 | |
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