ENS 53222: Difference between revisions
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| event date = 02/16/2018 08:55 EST | | event date = 02/16/2018 08:55 EST | ||
| last update date = 02/21/2018 | | last update date = 02/21/2018 | ||
| title = Technical Specifications Violation Due | | title = Technical Specifications Violation Due to Incorrectly Calibrated Reactor Trip Instrumentation | ||
| event text = On 2/16/18, the calorimetric portion of Surveillance Requirement (SR) 3.2.3.3 for Limiting Condition for Operations (LCO) 3.2.3.1 was performed in accordance with University of Florida Test Reactor (UFTR) procedures. Reactor power was stabilized at an indicated power of approximately 94 percent with actual thermal power (calculated by heat balance) at approximately 98kW (98 percent RTP) [rated thermal power]. Indicated power was then adjusted to approximately 99 percent to ensure adequate margin to the license limit of 100kW thermal steady-state (100 percent RTP). At no time was actual reactor power allowed to exceed the license limit. The reactor was then shutdown and secured to perform post-calorimetric verifications. SR 3.2.2.1 and 3.2.3.1 were performed satisfactorily just prior to operation to verify the High Reactor Power trip function and setpoint. Reactor Power Channel 1 was set to actuate at 110 percent and Reactor Power Channel 2 was set to actuate at 108 percent. | | event text = On 2/16/18, the calorimetric portion of Surveillance Requirement (SR) 3.2.3.3 for Limiting Condition for Operations (LCO) 3.2.3.1 was performed in accordance with University of Florida Test Reactor (UFTR) procedures. Reactor power was stabilized at an indicated power of approximately 94 percent with actual thermal power (calculated by heat balance) at approximately 98kW (98 percent RTP) [rated thermal power]. Indicated power was then adjusted to approximately 99 percent to ensure adequate margin to the license limit of 100kW thermal steady-state (100 percent RTP). At no time was actual reactor power allowed to exceed the license limit. The reactor was then shutdown and secured to perform post-calorimetric verifications. SR 3.2.2.1 and 3.2.3.1 were performed satisfactorily just prior to operation to verify the High Reactor Power trip function and setpoint. Reactor Power Channel 1 was set to actuate at 110 percent and Reactor Power Channel 2 was set to actuate at 108 percent. | ||
At about 1400 on 2/19/18, during review of surveillance parameters and discussion with the operators, UFTR management determined that Limited Safety System Setting 2.2.1 and LCO 3.2.2.1 had been violated. The Technical Specifications allowable value for the automatic High Reactor Power trip function is less than or equal to 110 percent RTP. There was a period of approximately 5 hours of operation prior to adjustment of the power channels, however, during which actual thermal power was greater than indicated power (but less than 100kW thermal). During this period, if a power excursion had occurred, the High Reactor Power trip would have actuated at approximately 114 percent RTP. This condition is reportable in accordance with Sections 6.7.2.a.3 and 6.7.2.a.4 of the UFTR Technical Specifications. As described above, this condition was corrected by adjusting indicated power on both reactor power channels to greater than actual thermal power. | At about 1400 on 2/19/18, during review of surveillance parameters and discussion with the operators, UFTR management determined that Limited Safety System Setting 2.2.1 and LCO 3.2.2.1 had been violated. The Technical Specifications allowable value for the automatic High Reactor Power trip function is less than or equal to 110 percent RTP. There was a period of approximately 5 hours of operation prior to adjustment of the power channels, however, during which actual thermal power was greater than indicated power (but less than 100kW thermal). During this period, if a power excursion had occurred, the High Reactor Power trip would have actuated at approximately 114 percent RTP. This condition is reportable in accordance with Sections 6.7.2.a.3 and 6.7.2.a.4 of the UFTR Technical Specifications. As described above, this condition was corrected by adjusting indicated power on both reactor power channels to greater than actual thermal power. | ||
Latest revision as of 21:40, 1 March 2018
| Where | |
|---|---|
| Univ Of Florida Gainesville, Florida (NRC Region 0) | |
| License number: | R-56 |
| Reporting | |
| Non | |
| Time - Person (Reporting Time:+98.83 h4.118 days <br />0.588 weeks <br />0.135 months <br />) | |
| Opened: | Dan Cronin 16:45 Feb 20, 2018 |
| NRC Officer: | David Aird |
| Last Updated: | Feb 21, 2018 |
| 53222 - NRC Website | |