ENS Event | |
|---|---|
01:35 Jun 20, 2014 | |
| Title | Technical Specification Required Shutdown |
| Event Description | At 1435 [CDT] on June 19, 2014 while performing Unit 1 A Train Safeguards Logic Test at power, it was discovered, while testing the Safety Injection Automatic Actuation Relay Logic, that the 1SI-15x, SI RELAY TRAIN A, was not making up the contact to energize 1SI-16x, SI AUX RELAY TRAIN A. As a result, the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> exception for testing allowed under LCO 3.3.2 Condition C no longer applied, and the 6, 12, and 42 hour4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> clocks associated with condition C were entered.
At 2035 [CDT] on June 19, when the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> time limit to complete Condition C.1 action could not be completed operators began preparation to shutdown Unit 1 to Mode 3 by 0235 on 6/20/14. At 2245 [CDT] on June 19, 2014 operators commenced reducing reactor power of Prairie Island Unit 1. As of 0003, June 20, Unit 1 was at 55 percent power and continuing to reduce load. This event is reportable per 10CFR50.72(b)(2)(i) - 'The initiation of any nuclear plant shutdown required by the plant's Technical Specification'. The protection of the health and safety of the public is not affected by this issue. The NRC Resident Inspector has been notified. |
| Where | |
|---|---|
Prairie Island  Minnesota (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-0.45 h-0.0188 days <br />-0.00268 weeks <br />-6.1641e-4 months <br />) | |
| Opened: | Steve Ingalls 01:08 Jun 20, 2014 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | Jun 20, 2014 |
| 50215 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (55 %) |
WEEKMONTHYEARENS 502152014-06-20T01:35:00020 June 2014 01:35:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown ENS 481862012-08-14T08:12:00014 August 2012 08:12:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(iv)(A), System Actuation, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Based on Both Emergency Diesels Being Declared Inoperable ENS 438592007-12-21T10:13:00021 December 2007 10:13:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shutdown Due to Both Edg'S Being Declared Inoperable ENS 423122006-02-05T19:36:0005 February 2006 19:36:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Required T.S. Shutdown Due to Emergency Diesel Generator Inoperability ENS 416062005-04-16T02:30:00016 April 2005 02:30:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Plant Shutdown Required by Technical Specifications - Inoperable Emergency Diesel Generator ENS 415482005-03-30T13:35:00030 March 2005 13:35:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Shutdown Due to Containment Fan Coil Units Declared Inoperable ENS 412042004-11-18T02:50:00018 November 2004 02:50:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Technical Specification Required Shut Down Due to Both Trains of Containment Cooling System Fan Coil Units Inoperable 2014-06-20T01:35:00 | |