*Power Reactor Event Number: 49306 Facility: COLUMBIA GENERATING STATION Region: 4 State: WA Unit: [2] MALFUNCTION OF STACK RADIATION MONITOR SUPPORTING EQUIPMENT "At 1614 hours PDT on August, 24, 2013 the Reactor Building Stack Radiation Monitor - High Range and Reactor Building Stack Radiation Monitor - Intermediate Range detectors were declared non-functional due to a loss of supporting equipment. Corrective actions are being pursued to restore the affected monitors to functional status. "To compensate for the loss of assessment capability due to the non-functioning Radiation Monitoring Equipment, an additional Health Physics (HP) Technician trained to acquire offsite dose assessment information on offsite releases is available. The additional personnel are pre-staged in support of the Radiation Monitoring System outage and will be mobilized in accordance with guidance in the compensatory measure instructions. "This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii). A follow up notification will be made when the Equipment has been returned to service. and on 8/26 LOSS OF SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE "Reactor Building (Secondary Containment) pressure increased to above the Technical Specification Surveillance requirement of 0,25 inches vacuum water gauge. This event is reportable as an event that could have prevented fulfillment of a safety function needed to control the release of radiation and mitigate the consequences of an accident. The Reactor Building differential pressure controller was placed in manual operation and Secondary Containment pressure was restored to normal (greater than 0.25 inches vacuum water gauge) returning Secondary Containment to operable status. Secondary Containment pressure was outside the allowable Technical Specification requirement for 4 minutes. "There were no radiological releases associated with the event. "No safety system actuations or isolations occurred." "The licensee has notified the NRC Resident Inspector." *Part 21 Event Number: 49303 Rep Org: WESTINGHOUSE ELECTRIC CORPORATION Licensee: WESTINGHOUSE ELECTRIC CORPORATION Region: 1 City: State: PA PART-21 NOTIFICATION - AP-1000 TIME RESPONSE FOR THE SAFETY ANALYSIS CANNOT BE DIRECTLY MEASURED "Several technical specifications were identified in a Corrective Action Report (CAR) as having a time response surveillance requirement that cannot be directly measured due to logic pathways where overlap with another protective function occurs. Westinghouse is now determining what other reactor trip and engineered safeguards actuation system protective functions have a credited time response in the Safety Analysis for the AP1000 plant and therefore should be assigned a time response surveillance requirement in the Technical Specifications. The evaluation will address the safety implication of the items identified in the CAR as well as confirm that all other protective functions where a time response was credited in the safety analysis have a measurable surveillance requirement in the Techni.cal Specifications. "The safety significance evaluation for the AP1000 plant is still in process and a determination of the potential to create a substantial safety hazard is not yet complete." Affected licensees: Summer Units 2 and 3 Vogtle Units 3 and 4 Levy Units 1 and 2 Harris Units 2 and 3 Lee Units 1 and 2 Turkey Points Units 6 and 7 Bellefonte Units 3 and 4 Point of contact: James Gresham 412-720-0754 Westinghouse letter: LTR-NRC-13-62 *Part 21 Event Number: 49302 Rep Org: BALDOR ELECTRIC CO. Licensee: BALDOR ELECTRIC CO. Region: 1 City: FLOWERY BRANCH State: GA PART-21 NOTIFICATION - MOTORS MAY HAVE A POINT FOR FOREIGN MATERIAL ENTRY The following information was received via fax: "This is a reportable 10CFR21 notification because some 1E motors in frame sizes 360, 400, and 440 may have been shipped by Baldor Electric, which contain an entry point for blast media to enter the motor during post shipment paint treatment preparations. During a recent inspection of a returned motor, some foreign materials were discovered inside the motor which appeared to consist of two types of blast media. One type of blast media found is used during the manufacturing process to clean the rotor end ring area before applying an end ring coating. This media is non-conductive and is typically cleaned away as part of the treatment process. The presence of blast media is a key inspection point at rotor final inspection. In mid 2008 this type of blast media was eliminated from Baldor processes and substituted with C02 blast media. "The other blast media found inside the motor is not used during the motor manufacturing process at Baldor. It was a metallic bead media and used during a paint preparation process after leaving Baldor. The entry point of this material was found to be through a small window in the frame casting that normally is closed with weld after the stator is assembled into the frame. In this instance, one of the stator weld notches was aligned with one (of the two) small windows in the frame casting. This allowed the blast media to enter and travel along the OD [outside diameter] of the stator core weld notch and into the motor. "Engineering and Quality reviewed all nuclear orders to verify the frame sizes that may have used the weld slot construction. The frames were determined to be 360, 400, and 440 during the time frame when the welds may not have been verified. The date range was established as 2002 thru 2013. "The motors identified as possibly having this non-conformance should be inspected for the following: a. The frame weld windows on identified 360,400 or 440 frame motors show no weld. and b. The stator core weld notch is visible in at least one (of the two) frame weld windows." If both issues exist, then remediation is recommended. Customers who have received these motors: Areva, Inc. David Brown Union Pumps Co. Duke Energy Corp. Enertech First Energy First Energy Service Co. Flowserve Pump Division - Spain Georgia Power Howden North America Inc. Limitorque Spencer Turbine Co. Taiwan Power Company Westinghouse Electric Company Point of Contact: James Thigpen, 678-947-7272 nrc.gov/reading-rm/doc-collections/event-status/event/en.html
Posted on: Mon, 26 Aug 2013 12:35:46 +0000
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