| | Site | Start date | Title | Description |
|---|
| ENS 53999 | Sequoyah | 14 April 2019 07:20:00 | Automatic Reactor Trip Due to Main Feedwater Pump Trip | At 0320 EDT, April 14, 2019, Sequoyah Unit 1 experienced an automatic reactor trip. The event was initiated by the trip of the 1A main feedwater pump. During the automatic unit runback, an automatic reactor trip was initiated due to low-low level in Steam Generator number 3.
The Auxiliary Feedwater System (AFWS) automatically actuated as required when the expected post-trip feedwater isolation actuated. Reactor Coolant System temperature is being maintained by the AFWS and the steam dump system. During this operational cycle, one control Rod Position Indicator (RPI) for core position E-5 in shutdown bank 'A' has been inoperable, and the appropriate Condition and Required Actions of (Technical Specification Limiting Condition of Operation) 3.1.7 were complied with. Due to this inoperable RPI, the associated shutdown rod is conservatively assumed to be full out and untrippable. Consequently, boration was required to establish adequate shutdown margin. All other Control and Shutdown rods fully inserted. All safety systems responded as designed. No primary or secondary safety valves actuated during or after the reactor trip. The unit is currently stable in Mode 3. Unit 1 is in a normal shutdown electrical alignment.
There was no impact on Unit 2.
Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the AFW system.
There was no impact on the health and safety of the public or plant personnel.
The NRC Senior Resident Inspector has been notified." |
| IR 05000272/2019010 | Salem | 4 April 2019 | Biennial Problem Identification and Resolution Inspection Report 05000272/2019010 and 05000311/2019010 | |
| NL-19-0317, Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update | Hatch | 2 April 2019 | Submittal of Fifth Ten-Year Interval Lnservice Testing Program Update | |
| ENS 53967 | Vogtle | 31 March 2019 01:30:00 | Manual Reactor Trip Due to Msiv Failing Closed | At 2130 (EDT) on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.
The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).
Unit 1 was not affected.
There was no impact to the health and safety of the public or plant personnel.
The NRC Resident Inspectors have been notified." |
| ML19063B345 | | 31 March 2019 | NUREG/IA-511 - International Agreement Report - Simulation of ROSA-2 Test-2 Experiment: Application to Nuclear Power Plant. | |
| ML19085A036 | | 31 March 2019 | NUREG/IA-0505, International Agreement Report - Assessment of Trace 5.0 Against ROSA-2 Test 5, Main Stream Line Break with Steam Generator Tube Rupture | |
| ML19085A076 | | 31 March 2019 | NUREG/IA-0512, International Agreement Report - Simulation of ROSA-2 Test 3 Counterpart with TRACE5 - Application to Nuclear Power Plant | |
| ML19095B760 | Nuclear Energy Institute | 31 March 2019 | NEI 00-01 (Rev 4(2)), Guidance for Post Fire Safe Shutdown Circuit Analysis. | |
| ML19064B308 | | 31 March 2019 | NUREG/IA-504, International Agreement Report Assessment of Trace 5.0 Against ROSA-2 Test 3 Counterpart Test to Pkl | |
| ML18347A385 | Harris | 29 March 2019 | Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis | |
