Second Salem Plant Severely Threatened During Polar Vortex Emergency

How close to the precipice was NJ with a tremendous amount of grid capacity severely threatened during a Polar Vortex event. Salem 1&2 and Hope Creek are a three plant facility. The three plants are the second largest nuclear facility in the nation. Would there be blackout?

This three plant facility is heading towords perminant shutdown in a few years. Are they spending enough money on the facility???  

What about grid resilience???  

Power Reactor	Event Number: 53852
Facility: SALEM Region: 1     State: NJ Unit: [] [2] [] RX Type: [1] W-4-LP,[2] W-4-LP NRC Notified By: JASON MORGAN HQ OPS Officer: MARK ABRAMOVITZ	Notification Date: 01/31/2019 Notification Time: 04:23 [ET] Event Date: 01/31/2019 Event Time: 03:01 [EST] Last Update Date: 01/31/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): BRICE BICKETT (R1DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

2

M/R

Y

100

Power Operation

0

Hot Standby

Event Text

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.