The Reactor Water Cleanup (RWCU) is the filtration system for the reactor vessel. (Its kinda like a pool filter) Its primary safety function is to isolate if needed. Filtering is not needed for safe shutdown but it is good to keep clean water in the vessel to avoid contaminates that may become radioactive or mitigating corrosion on various components.
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| | Site | Start date | Title | Description |
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| NMP2L2699, License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate | Nine Mile Point | 31 May 2019 | License Amendment Request to Revise Technical Specifications Main Steam Isolation Valve Leak Rate | | | ML19084A218 | Grand Gulf | 23 May 2019 | Issuance of Amendment No. 218 to Revise Technical Specification to Adopt Technical Specification Task Force Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control | | | IR 05000387/2019001 | Susquehanna | 13 May 2019 | Integrated Inspection Report 05000387/2019001 and 05000388/2019001 | | | ML19122A289 | Peach Bottom | 2 May 2019 | Response to NRC Requests for Additional Information, Set 1, Dated April 10, 2019 Related to Plant Subsequent License Renewal Application | | | ML19092A140 | Cooper | 29 April 2019 | Proposed Inservice Inspection Alternative PR5-02 | | | ML19122A386 | Millstone | 28 April 2019 | Annual Radiological Environmental Operating Report | | | NG-19-0044, Submittal of 2018 Annual Radioactive Material Release Report | Duane Arnold | 25 April 2019 | Submittal of 2018 Annual Radioactive Material Release Report | | | L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. | Monticello | 25 April 2019 | Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. | | | ENS 54016 | Brunswick | 22 April 2019 03:07:00 | Automatic Reactor Trip and Specified System Actuation | At 2307 EDT on April 21, 2019, in Mode 1 at approximately 100 percent reactor power, Unit 1 automatically tripped due to a Main Turbine Trip. The Main Turbine Trip was a result of two out of three level instruments sensing a false high reactor water level. All control rods inserted as expected during the scram. Safety Relief Valves G and K lifted per design. The same level instruments that failed also tripped both Reactor Feed Pumps. As a result, reactor water level dropped below the Low Level 1 and 2 actuation setpoints. Per design, the Low Level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations. The Low Level 2 signals resulted in Group 3 (i.e. Reactor Water Cleanup) isolation, a secondary containment isolation signal, and an auto start of Standby Gas Treatment and Control Room Emergency Ventilation. Also, the Low Level 2 resulted in (high pressure coolant injection) HPCI and (reactor core isolation cooling system) RCIC automatically starting and injecting into the vessel.
All systems responded as designed.
This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for RPS actuation and 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System.
There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified.
Decay heat is currently being removed via the turbine bypass valves. Condensate and feed water are maintaining water level. The reactor is still at saturation temperature and 475 psi, lowering slowly. The reactor is still in a normal electrical lineup.
There was no impact to Unit 2 as a result of this event.
- * * UPDATE ON 04/22/19 AT 0220 EDT FROM ALAN SCHULTZ TO JEFFREY WHITED * * *
The licensee updated the event report to include a 4-Hr Non-Emergency Notification in accordance with 10 CFR 50.72(b)(2)(iv)(A) for Emergency Core Cooling System, HPCI, Discharge to the Reactor Coolant System.
Notified R2DO (Dickson), NRR EO (Miller) and IR MOC (Gott). | | ML19108A428 | Peach Bottom | 10 April 2019 | RAIs Slra Set 1_ERO(Rev 1) | |
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