ENS 43042
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ENS Event | |
|---|---|
00:08 Dec 11, 2006 | |
| Title | |
| Event Description | On December 10, 2006, at 1608 PST, operators manually tripped the reactor while it was subcritical. This is an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification per 10 CFR 50.72(b)(3)(iv)(A) for actuation of the reactor protection system while subcritical. On December 10, 2006, with Unit 2 operating in Mode 1 at 100% power, operators initiated an unplanned reactor shutdown due to indications of increasing stator temperature on reactor coolant pump 2-2. In accordance with plant procedures, when the reactor coolant pump stator temperature reached 300 degrees Fahrenheit, operators manually tripped the reactor and tripped the coolant pump 2-2. The reactor was subcritical at the time of the reactor trip but all rods had not been fully inserted.
All control rods fully inserted in response to the reactor trip and all systems functioned as required. The auxiliary feedwater system was already in service as part of the shutdown. The grid is stable and with the exception of RCP 2-2, all major equipment including the 3 emergency diesel generators remain operable. Unit 2 electrical loads are being supplied by the normal startup power. The other 3 RCPs are maintaining forced circulation of the reactor coolant system. Investigations into the high RCP stator temperature are ongoing, the unit will remain in Mode 3 pending the results of these investigations. An estimated restart date is not known at this time. The NRC Resident Inspector has been informed and was onsite at the time of the trip. Unit 1 is unaffected and remains in Mode 1. The licensee stated that a press release related to this event is likely.
Licensee believes the cause of the high RCP stator temperature was due to a failed RTD.
Unit 2 was in Mode 3 (Hot Standby) at 0 percent power at the time of the manual trip. At the time of the Initial notification, all procedural requirements for declaring Mode 3 had not been met, but upon further review, PG&E has verified K effective was less than 0.99. The licensee notified the NRC Resident Inspector. Notified R4DO (Proulx). The original report was modified by this change. The 'RX Crit' field was changed from 'Y' to 'N'. The 'Init Power' field was changed from '5' to '0'. The 'Curr Power' field was changed from 'Startup' to 'Hot Standby'. |
| Where | |
|---|---|
Diablo Canyon  California (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
| LER: | 05000323/LER-2006-003 |
| Time - Person (Reporting Time:+0.38 h0.0158 days <br />0.00226 weeks <br />5.20524e-4 months <br />) | |
| Opened: | Steve Hackleman 00:31 Dec 11, 2006 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Dec 14, 2006 |
| 43042 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | Yes, Manual Scram |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 567692023-10-01T03:14:0001 October 2023 03:14:00
[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 555262021-10-16T00:49:00016 October 2021 00:49:00 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 537642018-12-01T08:00:0001 December 2018 08:00:00 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 Trip of Unit 2 Due to a Load Rejection ENS 519652016-05-30T16:30:00030 May 2016 16:30:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Opening of Reactor Trip Breakers Due to Rod Position Error Greater than 12 Steps ENS 505862014-11-01T00:40:0001 November 2014 00:40:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Automatic Emergency Diesel Generator Start Due to Loss of Offsite 230Kv Startup Power Supply ENS 497862014-02-02T19:29:0002 February 2014 19:29:00 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 Unit 2 Automatic Reactor Trip ENS 492872013-08-16T01:24:00016 August 2013 01:24:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Startup Power Results in Valid Starts of All Three Emergency Diesel Generators ENS 491842013-07-10T16:50:00010 July 2013 16:50:00 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 Unit 2 Automatic Reactor Trip ENS 491432013-06-24T04:20:00024 June 2013 04:20:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of 230 Kv Offsite Power Results in the Automatic Start of Emergency Diesel Generators ENS 487962013-03-01T05:54:0001 March 2013 05:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Bus Inadvertently De-Energized with Unit Defueled ENS 484002012-10-11T19:08:00011 October 2012 19:08:00 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 Unit 2 Experienced an Automatic Reactor Trip on a 500Kv Line Differential Relay Actuation ENS 469002011-05-27T19:12:00027 May 2011 19:12:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Unit 1 Startup Power Results in Starting All Emergency Diesel Generators ENS 468942011-05-26T09:26:00026 May 2011 09:26:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Loss of Startup Power Due to Fault in Switchyard Causes All Edgs to Start ENS 468562011-05-17T16:54:00017 May 2011 16:54:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generators Start Due to Maintenance Activities ENS 467012011-03-26T21:49:00026 March 2011 21:49:00 10 CFR 50.72(b)(2)(iv)(B), RPS System Actuation, 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip When a Loss of the 2-1 Main Feedwater Pump Occurred ENS 445882008-10-22T03:51:00022 October 2008 03:51:00 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 Unit 2 Manual Reactor Trip Due to Jellyfish Intrusion ENS 444192008-08-17T07:12:00017 August 2008 07:12:00 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 Fire in Main Bank Tranformer ENS 433932007-05-29T05:50:00029 May 2007 05:50:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generator Actuation Due to Momentary Undervoltage Condition ENS 433912007-05-27T18:17:00027 May 2007 18:17:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Manual Reactor Trip in Mode 3 During Control Rod Testing ENS 433602007-05-12T17:25:00012 May 2007 17:25:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Emergency Diesel Generators Start Due to Loss of Off Site Start Up Power ENS 430472006-12-12T21:22:00012 December 2006 21:22:00 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 Circulating Water Pump Failure Causes Explosion in Intake Structure ENS 430422006-12-11T00:08:00011 December 2006 00:08:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rapid Shutdown and Manual Reactor Trip Due to High Reactor Coolant Pump Stator Temperature ENS 421572005-11-19T23:51:00019 November 2005 23:51:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Diesel Generator Starts on a Vaild Bus Undervoltage Signal ENS 412502004-12-09T10:04:0009 December 2004 10:04:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Rps Actuation While Shutdown Due to Failed Fuse ENS 411682004-11-02T19:05:0002 November 2004 19:05:00 10 CFR 50.72(b)(3)(iv)(A), System Actuation Unplanned Diesel Generator Start on a Valid Bus Undervoltage Signal 2023-10-01T03:14:00 | |
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