Junk Plant Columbia Going Down the Tubes

Recent Events

1) Whistleblower discloses Columbia hiding plant decline.

2) Special inspection on transferring radioactive materials six times the allowed levels.

3) The hard scram uncovered a lot of degraded and failed components.

Power Reactor	Event Number: 52442
Facility: COLUMBIA GENERATING STATION Region: 4 State: WA Unit: [2] [ ] [ ] RX Type: [2] GE-5 NRC Notified By: JEFFERY KUETHER-ULBERG HQ OPS Officer: JEFF HERRERA	Notification Date: 12/18/2016 Notification Time: 18:13 [ET] Event Date: 12/18/2016 Event Time: 11:24 [PST] Last Update Date: 12/18/2016
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION	Person (Organization): RAY KELLAR (R4DO) MIKE KING (NRR) BERNARD STAPLETON (IRD)

Unit	SCRAM Code	RX CRIT	Initial PWR	Initial RX Mode	Current PWR	Current RX Mode
2	A/R	Y	100	Power Operation	0	Hot Shutdown

Event Text

AUTOMATIC SCRAM DUE TO LOAD REJECT FROM SUBSTATION "On December 18, 2016 at time 1124 PST the plant experienced a full reactor scram. Preliminary investigations indicate that the scram was caused by a load reject from the Bonneville Power Administration (BPA) Ashe substation. Further investigations continue. The following conditions have occurred: "Turbine Governor valve closure Reactor high pressure trip +13 inches reactor water level activations E-TR-B (backup transformer) supplying E-SM-7/SM-8 (vital power electrical busses) Complete loss of Reactor Closed Cooling (RCC) E-TR-S (Startup transformer) supplying SM-1/2/3 (non-vital power electrical busses) E-DG-1/2/3 (emergency diesel generators) auto start Low Pressure Core Spray (LPCS) and Residual Heat Removal (RHR) A/B/C initiation signals Main Steam Isolation Valves (MSIV) are closed "Reactor Core Isolation Cooling (RCIC) RCIC and High Pressure Core Spray (HPCS) were manually activated and utilized to inject and maintain reactor water level. Pressure control is with Safety Relief Valves (SRV) in, manual. Level control is with RCIC and Control Rod Drive (CRD). RCIC has experienced an over speed trip that was reset so that level control could be maintained by RCIC. "This event is being reported under the following: 10 CFR 50.72(b)(2)(iv)(A) which requires a 4 hour notification for Emergency Core Cooling System (ECCS) discharge into the reactor coolant system. 10 CFR 50.72(b)(2)(iv)(B) which requires a 4 hour notification for any event or condition that results in actuation of the Reactor Protection System (RPS) when the reactor is critical. 10 CFR 50.72(b)(3)(iv)(A) which requires an 8 hours notification for actuation of ECCS systems. "All control rods fully inserted. "The NRC Resident Inspector has been informed." The licensee indicated that no increase in radiation levels were detected.