7/14/14 Page loaded ~ Hot Standby & Steam Dumps ~ Power Reactor Event Number: 50278 Facility: WATTS BAR Region: 2 State: TN Unit: [1] MANUAL REACTOR TRIP DUE TO AUTOMATIC FEEDWATER HEATER ISOLATION On July 13, 2014 at 1937 [EDT], Watts Bar Nuclear Plant Unit 1 reactor was manually tripped due to automatic isolation of all low pressure feedwater heaters. Concurrent with the reactor trip the Auxiliary Feedwater system actuated as designed. All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater, steam dumps and the main condenser. The station is in a normal shutdown electrical alignment. The cause is currently under investigation. This is being reported under 10CFR 50.72(b)(3)(iv)(A) and 10CFR 50.72 (b)(2)(iv)(B). The NRC Senior Resident [Inspector] has been notified. Initial indications are that a level switch failed on the #7 heater drain tank which caused the heater drain tank pumps to trip. When the high level tank setpoint was reached, the feedwater system isolated. Hot Shutdown ~ Power Reactor Event Number: 50270 Facility: OYSTER CREEK Region: 1 State: NJ Unit: [1] MANUAL SCRAM DUE TO LOSS OF MAIN CONDENSER VACUUM Today at approximately 0312 [EDT on 7/11/14], during a planned reactor power ascension with reactor power at approximately 55 percent of rated thermal power, main condenser vacuum began to lower. In accordance with the abnormal operating procedure for degrading vacuum, Operators inserted a manual scram of the reactor at 0314 [EDT]. The cause of the degraded vacuum is currently under investigation. All rods inserted into the core and all systems functioned as expected during the scram. No electromatic (EMRVs) or safety relief valves lifted during the transient. This event is reportable within 4 hours per 10CFR50.72(b)(2)(iv)(B) - any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation. The scram was uncomplicated, normal offsite power is available, and plant is being cooled down to cold shutdown. The cause of the degraded condenser vacuum is suspected condenser boot degradation. The licensee has informed the NRC Resident Inspector. HA, so much for their retraction, that is listed today too~ !!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!! Power Reactor Event Number: 50261 Facility: OYSTER CREEK Region: 1 State: NJ Unit: [1] TECHNICAL SPECIFICATION REQUIRED SHUTDOWN On July 7, 2014 at approximately [2040 EDT], an issue was discovered with currently removed Electromatic Relief Valves (EMRVs) that calls the operability of the currently installed EMRVs into question. Based on this new information, all 5 of the currently installed EMRVs were conservatively declared inoperable. With the potential of 5 EMRVs inoperable a Technical Specification shutdown is required under Technical Specification 3.4.b, whereby reactor pressure shall be reduced to 110 psig or less within 24 hours. This event is immediately reportable under: 50.72(b)(2)(i), The initiation of any nuclear plant shutdown required by the plants Technical Specifications. 50.72(b)(3)(v)(D), Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to: (D) Mitigate the consequences of an accident. The licensee notified the NRC Resident Inspector. The licensee will notify the State of New Jersey and issue a press release. * * * RETRACTION AT 1745 EDT ON 7/11/2014 FROM CHARLES SPAGNUOLO TO MARK ABRAMOVITZ * * * The original concern and July 7, 2014 EN [report] was caused by abnormal wear found on removed Electromatic Relief Valve actuators. However, on July 8, 2014, upon completion of in situ testing as well as visual examination of the installed EMRV actuators, it was determined that the 5 currently installed EMRVs were fully operable and capable of performing their safety function. Therefore, Oyster Creek is retracting the notifications made under 50.72(b)(2)(i) and 50.72(b)(3)(v)(D). The licensee notified the NRC Resident Inspector and the State will be notified. The licensee will be issuing a press release. Fuel Cycle Facility Event Number: 50276 Facility: GLOBAL NUCLEAR FUEL - AMERICAS RX Type: URANIUM FUEL FABRICATION Comments: LEU CONVERSION (UF6 TO UO2) LEU FABRICATION LWR COMMERICAL FUEL Region: 2 City: WILMINGTON State: NC County: NEW HANOVER ITEMS RELIED ON FOR SAFETY ASSOCIATED WITH THE DRY SCRAP RECYCLE OPERATIONS NOT MEETING REQUIREMENTS It was determined at 1200 [EDT] on 7/13/14, that one of the Items Relied on for Safety (IROFS) associated with the Dry Scrap Recycle operation failed to meet performance requirements. At approximately 1730 [EDT] on July 12, 2014, a potable water line (1/2 inch poly) failed and resulted in a release of approximately 10 gallons of water into the area. The leak was contained and cleaned up. However, this water release is a failure of IROFS 900-03 for Moderation Restriction. Although the second IROFS (Process Equipment Barriers IROFS 301) prevented moderation intrusion into equipment and containers, it alone was not sufficient to meet performance requirements. The affected equipment has been shut down. At no time was an unsafe condition present. Special Nuclear Material (SNM) was not impacted by the leak. No water escaped the area or travelled to non-contaminated areas. While this did not result in an unsafe condition, the event is being reported pursuant with the reporting requirements of 10CFR70 Appendix A(b)(1) within 24 hours of discovery. Additional corrective actions, extent of condition, and the cause of the failure are being determined. The licensee will notify NRC Region 2, State of North Carolina Radiation Protection, and New Hanover County Emergency Management. And other reportable event..... nrc.gov/reading-rm/doc-collections/event-status/event/en.html
Posted on: Mon, 14 Jul 2014 12:14:17 +0000
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