Semantic search
| Entered date | Event description | |
|---|---|---|
| ENS 51733 | 13 February 2016 14:45:00 | On 2/10/2016 at 1000 PST, Columbia entered a planned evolution to perform channel functional tests on the RadWaste Building noble gas monitor (WEA-RIS-14). Compensatory measures were implemented per station procedures. The station is experiencing equipment issues and the monitor has not been restored within 72 hours (2/13/2016 at 1000 PST) from the start of the outage. The extended outage of this radiological monitoring instrument is, therefore, being reported as a major loss of radiological assessment capability in accordance with regulation 10 CFR 50.72(b)(3)(xiii). Compensatory measures will remain in place until the WEA instrument is restored. The NRC Resident Inspector has been notified. Note: Reactor Power is 75 percent due to a planned plant downpower for unrelated scheduled work with a planned return to 100 percent at 1900 PST on 2/14/16. |
| ENS 48101 | 12 July 2012 23:29:00 | At 13:15 PDT on 7-12-2012, during the performance of an annual surveillance, power supply ARM-E/S-603A was discovered to have out of tolerance voltage readings. ARM-E/S-603A was declared non-functional. This resulted in a loss of the ability to monitor and quantify radiological conditions in multiple areas of the reactor building, due to the loss of ARM-RIS-1 thru 10 (area radiation monitor radiation indicating switches 1 thru 10). The loss of ability to monitor and quantify radiological conditions in multiple areas of the reactor building represents a major loss of emergency assessment capability per 10 CFR 50.72(b)(3)(xiii). As directed by station procedures, compensatory measures have been enacted to have Health Physics personnel tour the affected areas once per shift to document and trend the radiological conditions. ARM-RIS-1 and 4 thru 10 are used for EAL determinations. Work to return the ARM-E/S-603A to service is underway and is a high priority. The licensee has notified the NRC Resident Inspector. |
| ENS 45169 | 26 June 2009 23:45:00 | At 1949 PDT, a small fire was observed between the #1 and #2 bearings on the main turbine involving some lube oil leakage and lagging. The fire brigade was dispatched and at 1953 PDT, the reactor was manually scrammed. At 2005 PDT, the licensee declared an Unusual Event (EAL 9.2.U.1) based on a fire lasting greater than 15 minutes. At 2006 PDT, the fire was reported out. The manual scram was uncomplicated and all systems functioned as required. The reactor is being cooled by normal feedwater and discharging decay heat to the condenser. The licensee is cooling down the reactor to Mode 4. Currently reactor pressure is 495 psi. The licensee has stationed a re-flash watch at the fire location and is assessing any damage that may have occurred. The only damage currently reported involves lagging at the fire location. The NRC Resident Inspector, State and local authorities have been notified.
The licensee terminated the NOUE at 2159 PDT. The termination criteria was the fire is out, a re-flash watch stationed and the plant is stable and transitioning to Mode 4. The licensee has made State and local notifications and has notified the NRC Resident Inspector. Notified R4DO (Powers), IRD (Grant), NRR ET (Lubinski), FEMA (Casto) and DHS (Vestal). |