|ML19038A483||Watts Bar||7 February 2019||Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)|
|IR 05000247/2018004||Indian Point||7 February 2019||Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018004 and 05000286/2018004|
|ML19042A117||McGuire||5 February 2019||Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS|
|ML19036A523||Davis Besse||5 February 2019||License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition|
|ML19025A257||5 February 2019||IMC 0608 Performance Indicator Program|
|IR 05000336/2018004||Millstone||5 February 2019||Millstone Power Station - Integrated Inspection Report 05000336/2018004 and 05000423/2018004|
|ML18346A358||Cook||5 February 2019||Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendments 343 and 325 Regarding the Battery Monitoring and Maintenance Program|
|ENS 53852||Salem||31 January 2019 08:01:00||Manual Reactor Trip - Circulating Water Icing Conditions||At 0301 (EST) on 1/31/19, with Unit 2 in Mode 1 at 100% power, the reactor was manually tripped due to icing conditions requiring the removal of 4 Circulating Water Pumps from service. The trip was not complex, with all systems responding normally post-trip. 21 CFCU (Containment Fan Cooler Unit) was inoperable prior to the event for a planned maintenance window and did not contribute to the cause of the event and did not adversely impact the plant response to the trip. An actuation of the Auxiliary Feedwater System occurred following the manual reactor trip. The reason for the Auxiliary Feed Water System auto-start was due to low level in a steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the Main Steam Dumps and Auxiliary Feedwater System.
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). This event is also being reported as an eight hour non-emergency notification in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the Auxiliary Feed Water System. There was no impact on the health and safety of the public or plant personnel.
The NRC Resident Inspector has been notified.
The icing condition was described as frazil ice.
Unit-1 reduced power to 88% because one circulating water pump was shutdown.|
|ML19015A027||31 January 2019||NUREG/IA-0487 International Agreement Report - Simulation of the PKL-G7.1 Experiment in a Westinghouse Nuclear Power Plant Using RELAP5/Mod3.3.|
|IR 05000272/2018004||Salem||30 January 2019||Salem Nuclear Generating Station, Unit Nos. 1 and 2: Integrated Inspection Reports 05000272/2018004 and 05000311/2018004|