ENS 41209
ENS Event | |
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16:07 Nov 19, 2004 | |
Title | Automatic Reactor Trip Due to Turbine Trip on Main Generator Trip |
Event Description | The following information was obtained from the licensee via facsimile:
1. SYSTEMS AFFECTED: Reactor trip, Aux feed water actuation. 2. ACTUATIONS AND THEIR INITIATING SIGNALS: Reactor trip - Loss of Load Turbine Trip, Aux Feed Water (AFW) - 21% [on the narrow range indication] in Steam Generators. 3. CAUSES: Reactor tripped due to an undetermined cause in the main generator end of the secondary plant. AFW started as expected on EFAS [Emergency Feedwater Actuation Signal] at 21% from a trip at 100%. 4. EFFECT OF EVENT ON PLANT: Plant is stable at 545F [and] 2250 [psi] hot standby conditions and will remain here until cause determination made as to cause of trip. 5. ACTIONS TAKEN OR PLANNED: Maintain hot standby conditions for post trip review. CONTINUATION SHEET: 1) Remain in Mode 3 for cause determination post-trip review to provide actual mode required. 2) Estimate restart date pending cause determination and any repairs required. 3) All rods inserted, no primary or secondary reliefs lifted, electrical grid stable, all safety systems performed as expected, no effect on Unit 3. Electrical power supplied from offsite power. Decay heat removal is via steam dump to condenser. The licensee has notified the NRC Resident Inspector. |
Where | |
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San Onofre ![]() California (NRC Region 4) | |
Reporting | |
10 CFR 50.72(b)(2)(iv)(B), RPS Actuation 10 CFR 50.72(b)(3)(iv)(A), System Actuation | |
Time - Person (Reporting Time:+-3.7 h-0.154 days <br />-0.022 weeks <br />-0.00507 months <br />) | |
Opened: | Jon Braisted 12:25 Nov 19, 2004 |
NRC Officer: | Howie Crouch |
Last Updated: | Nov 19, 2004 |
41209 - NRC Website
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Unit 2 | |
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Reactor critical | Critical |
Scram | A/R |
Before | Power Operation (100 %) |
After | Hot Standby (0 %) |
San Onofre ![]() | |
WEEKMONTHYEARENS 476282012-02-01T01:30:0001 February 2012 01:30:00
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