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 SiteStart dateTitleDescription
ML19038A483Watts Bar7 February 2019Application 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 05000247/2018004Indian Point7 February 2019Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018004 and 05000286/2018004
ML19042A117McGuire5 February 2019Proposed 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
ML19036A523Davis Besse5 February 2019License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition
ML19025A2575 February 2019IMC 0608 Performance Indicator Program
IR 05000336/2018004Millstone5 February 2019Millstone Power Station - Integrated Inspection Report 05000336/2018004 and 05000423/2018004
ML18346A358Cook5 February 2019Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Issuance of Amendments 343 and 325 Regarding the Battery Monitoring and Maintenance Program
ENS 53852Salem31 January 2019 08:01:00Manual Reactor Trip - Circulating Water Icing ConditionsAt 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.
ML19015A02731 January 2019NUREG/IA-0487 International Agreement Report - Simulation of the PKL-G7.1 Experiment in a Westinghouse Nuclear Power Plant Using RELAP5/Mod3.3.
IR 05000272/2018004Salem30 January 2019Salem Nuclear Generating Station, Unit Nos. 1 and 2: Integrated Inspection Reports 05000272/2018004 and 05000311/2018004