ENS 46744
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ENS Event | |
|---|---|
07:45 Apr 10, 2011 | |
| Title | Manual Reactor Trip While Performing a Technical Specification Required Shutdown |
| Event Description | On April 09, 2011, at 2349 [EDT], Beaver Valley Power Station [BVPS] Unit No. 2 was operating at 15% power while preparing to synchronize the main unit generator to the grid. At that time, the 'A' Auxiliary Feedwater Injection Header was declared inoperable due to a water leak identified from a vent valve fillet weld between the inside and outside Containment Isolation Valves (outside of containment) for containment penetration X-79.
In accordance with Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Condition D, at 0345 [EDT], April 10, 2011, BVPS Unit 2 commenced a Reactor Shutdown to Mode 3. Required action is to be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This event is being reported as a Technical Specification required shutdown pursuant to 10CFR50.72(b)(2)(i), 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification. Repairs are in progress. The following additional shutdown actions may be required from the time the Injection Header/Containment Penetration was declared inoperable: Technical Specification 3.7.5, Condition D, Mode 4 in 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> and Technical Specification 3.6.1, Condition A, Mode 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. This event is also being reported as a degraded condition for Containment pursuant to 10CFR50.72(b)(3)(ii)(A), 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification. Additionally, at 0357 [EDT], during the Reactor Shutdown, at 4.6% Reactor Power, the BVPS Unit 2 Reactor was manually tripped due to reaching a pre-established manual trip criteria of 25% Steam Generator Level for the 21A Steam Generator. This was conservative criteria set above automatic actuation setpoint of 20.5% level. This event is being reported as a RPS Actuation pursuant to 10CFR50.72(b)(2)(iv)(B), 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification. Control room personnel entered Emergency Operating Procedure E-0, 'Response to Reactor Trip and Safety Injection.' Safety systems and equipment functioned as designed following the manual reactor trip. Due to the cooldown and subsequent shrink of level in the 21A Steam Generator, an automatic start of the Steam Driven Auxiliary Feedwater Pump [2FWE-P22] occurred at 20.5%. This event is being reported as an Auxiliary Feedwater System Actuation pursuant to 10CFR50.72(b)(3)(iv)(A), 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification. All control rods fully inserted into the core. The plant electrical system is aligned to normal offsite power sources. Decay heat from the reactor coolant pumps is being directed to atmospheric dump valve. There is no primary to secondary leakage. There was no impact on Unit 1. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Beaver Valley  Pennsylvania (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| Time - Person (Reporting Time:+-1.08 h-0.045 days <br />-0.00643 weeks <br />-0.00148 months <br />) | |
| Opened: | Dan Schwer 06:40 Apr 10, 2011 |
| NRC Officer: | Vince Klco |
| Last Updated: | Apr 10, 2011 |
| 46744 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | Yes, Manual Scram |
| Before | Power Operation (12 %) |
| After | Hot Standby (0 %) |
Beaver Valley 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
WEEKMONTHYEARENS 571322024-05-19T04:30:00019 May 2024 04:30:00
[Table view]10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip ENS 571152024-05-09T12:00:0009 May 2024 12:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Containment Bypass Condition Due to Degraded River Water Piping ENS 570752024-04-13T04:35:00013 April 2024 04:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip ENS 565272023-05-19T12:52:00019 May 2023 12:52:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Actuation of Auxiliary Feedwater System (AFW) ENS 564852023-04-22T23:42:00022 April 2023 23:42:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 559432022-06-15T11:24:00015 June 2022 11:24:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip and Automatic Auxiliary Feedwater Actuation ENS 555862021-11-17T18:13:00017 November 2021 18:13:00 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 Automatic Auxiliary Feedwater Actuation ENS 555722021-11-12T15:07:00012 November 2021 15:07:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Increasing Steam Generator Water Levels ENS 555402021-10-22T05:04:00022 October 2021 05:04:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 555072021-10-05T10:32:0005 October 2021 10:32:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip and Auxiliary Feedwater Actuation ENS 546802020-04-24T05:30:00024 April 2020 05:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (Rcs) Pressure Boundary Degraded ENS 543692019-11-04T10:35:0004 November 2019 10:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation Manual Reactor Trip Due to Steam Dump Transient ENS 543372019-10-17T23:51:00017 October 2019 23:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 537112018-11-01T04:00:0001 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Discovery of Indications That Did Not Meet Acceptance Criteria on One Reactor Vessel Head Penetration ENS 535482018-08-12T04:00:00012 August 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown En Revision Imported Date 8/17/2018 ENS 534192018-05-22T04:00:00022 May 2018 04:00:00 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)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown En Revision Imported Date 6/22/2018 ENS 530562017-11-07T10:04:0007 November 2017 10:04:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unit 1 Automatic Reactor Trip Due to Main Unit Generator Over Current ENS 514532015-10-05T12:15:0005 October 2015 12:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Two Reactor Vessel Head Penetrations Could Not Be Dispositioned as Acceptable ENS 501242014-05-20T12:35:00020 May 2014 12:35:00 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 Reactor Startup ENS 500792014-05-01T20:10:0001 May 2014 20:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Reactor Vessel Head Control Rod Drive Penetration ENS 496972014-01-06T21:59:0006 January 2014 21:59:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Main Transformer Fault ENS 495052013-11-05T23:28:0005 November 2013 23:28:00 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 Notification of Unusual Event Due to Explosion and Fire in the Turbine Building ENS 494132013-10-05T03:24:0005 October 2013 03:24:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unexpected Containment Liner Penetration Found ENS 493922013-09-30T06:38:00030 September 2013 06:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Start of Motor Driven Auxiliary Feedwater Pump ENS 483872012-10-06T20:35:0006 October 2012 20:35:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded One of Sixty Six Reactor Vessel Penetrations Did Not Meet Acceptance Criteria ENS 467442011-04-10T07:45:00010 April 2011 07:45:00 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)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Manual Reactor Trip While Performing a Technical Specification Required Shutdown ENS 454632009-10-23T21:00:00023 October 2009 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Small Circumferential Indications Found on Two Reactor Vessel Head Penetrations ENS 450222009-04-26T14:00:00026 April 2009 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ndt Reveals Circumferential Indications on Rcs Hot Leg Drain Piping ENS 450152009-04-23T14:15:00023 April 2009 14:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Damaged Area in Containment Liner ENS 450002009-04-20T05:15:00020 April 2009 05:15:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Auxiliary Feedwater Actuation on Valid Steam Generator Hi-Hi Signal During Shutdown ENS 445972008-10-23T22:00:00023 October 2008 22:00:00 Information Only, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Information Only Notification Regarding Plant Shutdown ENS 442392008-05-24T13:38:00024 May 2008 13:38:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Steam Generator Level Excursion ENS 428342006-09-08T01:57:0008 September 2006 01:57:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Following Spurious Opening of a Reactor Trip Breaker ENS 426062006-05-26T18:15:00026 May 2006 18:15:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Solid State Protection System Train Inoperable ENS 424912006-04-11T13:24:00011 April 2006 13:24:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 424672006-04-02T18:02:0002 April 2006 18:02:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to a Main Generator Trip ENS 404342004-01-10T06:27:00010 January 2004 06:27:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Initiated and Subsequently Terminated ENS 403202003-11-13T16:35:00013 November 2003 16:35:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip from 100% Power with Cause Being Investigated ENS 402472003-10-15T03:55:00015 October 2003 03:55:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Reactor Trip Due to Low "B" Steam Generator Water Level. 2024-05-09T12:00:00 | |
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