Brunswick Nuclear Plant, Large Primary Coolant Leak

Update April 1

Sill no discloser what caused the leak here. It this the new way the NRC does the public business"

Could be the end nuclear power?

ower Reactor	Event Number: 53961
Facility: BRUNSWICK Region: 2     State: NC Unit: [1] [] [] RX Type: [1] GE-4,[2] GE-4 NRC Notified By: DEREK WATSON HQ OPS Officer: JEFF HERRERA	Notification Date: 03/28/2019 Notification Time: 15:07 [ET] Event Date: 03/28/2019 Event Time: 14:50 [EDT] Last Update Date: 03/29/2019
Emergency Class: UNUSUAL EVENT 10 CFR Section: 50.72(a) (1) (i) - EMERGENCY DECLARED 50.72(b)(2)(i) - PLANT S/D REQD BY TS	Person (Organization): BRIAN BONSER (R2DO) JEFFERY GRANT (IRD) JOEL MUNDAY (R2) HO NIEH (NRR)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

100

Power Operation

58

Power Operation

Event Text

UNUSUAL EVENT DECLARED DUE TO RCS UNIDENTIFIED LEAKAGE At 1450 EDT on March 28, 2019, the licensee observed that the Unit 1 unidentified Reactor Coolant System (RCS) leakage was greater than 10 gallons per minute (gpm) for greater than or equal to 15 minutes. The licensee declared an Unusual Event in accordance with their EAL SU 5.1. The licensee initiated a unit shutdown in accordance with their procedures and the unit was approximately 58 percent reactor power at 1507 EDT, with unit shutdown in progress. The licensee also received an alarm due to increasing Drywell Pressure at 1.7 pounds drywell pressure. At 1600 EDT the licensee called with an update. Unit 1 was still in an Unusual Event with the unit at 37 percent power with the shutdown continuing. Drywell Pressure had decreased to 0.8 pounds. At 1603 the licensee scrammed Unit 1. Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email). * * * UPDATE ON 3/28/2019 AT 1808 EDT FROM MARK TURKAL TO THOMAS KENDZIA * * * "At 1437 EDT on March 28, 2019, with Unit 1 in Mode 1 at approximately 100 percent power, a Technical Specification-required shutdown was initiated due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours. "It is expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i). "There was no impact on the health and safety of the public or plant personnel. "The NRC Resident Inspector has been notified." * * * UPDATE ON 03/29/19 AT 0302 EDT FROM TOM FIENO TO BETHANY CECERE * * * At 0259 EDT on March 29, 2019, the Unusual Event was terminated because RCS leakage was reduced to less than 10 gallons per minute. The most recent leakage rate measured at 0225 EDT was 3.9 gpm. The source of the leak will be identified when plant conditions allow containment entry. No elevated radiation levels were observed during this event. Drywell pressure is currently 0.0 psig. Unit 1 is in Mode 4. The licensee notified the NRC Resident Inspector. Notified R2DO (Bonser), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).