Information Notice No. 82-22: Failures in Turbine Exhaust Lines
SSINS No.: 6835 IN 82-22 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C. 20555 July 9, 1982 Information Notice No. 82-22: FAILURES IN TURBINE EXHAUST LINES Addressees: All nuclear power reactor facilities holding an operating license or construction permit. Purpose: This information notice is provided as an early notification of events that may have safety significance. It is expected that recipients will review the information for applicability to their facilities. No specific action or response is required at this time. Description of Circumstances: On June 28, 1982, Duke Power Company's Oconee Unit 2, while operating at 95% power, experienced a 4-ft2 rupture of a 24-in.-diameter, long-radius elbow in the feedwater heat extraction line which is supplied steam from the high-pressure turbine exhaust. The rupture has been attributed to piping degradation that results from steam erosion. The operator, upon hearing steam noise and observing the absence of main steam (turbine header) line pressure, believed a streamline break had occurred and manually tripped the reactor. The main turbine automatically tripped as a result of the reactor trip. Systems and related parameters responded as expected following the reactor trip and subsequent recovery. The steam jet destroyed a non-safety-related electrical load center in the lower elevation of the turbine building and certain non-safety-related instrumentation in the vicinity, but did not render any essential equipment inoperable. Two persons suffered steam burns, serious enough to be hospitalized overnight. Initial indication of extraction streamline degradation at the Oconee facility was discovered in 1976 when a pinhole leak occurred on a similar line in Unit 3. Subsequent to this discovery, a maintenance surveillance program utilizing ultrasonic examination of extraction steam lines was begun. In 1980, two elbows on Unit 3 identical to the failed elbow on Unit 2 were replaced because, of steam erosion. In March 1982, prior to the failure, ultrasonic inspection revealed substantial erosion of the Unit 2 elbow in the extraction, line; however, the erosion was less than the licensee's criterion for rejection. The licensee theorizes that 8204210392 . IN 82-24 July 9, 1982 Page 2 of 2 sustained reduced power operation and resultant lower quality steam contributed to accelerated erosion and failure of the elbow. Additionally, the previous inspection program may not have identified the section where the line was thinnest. The failed elbow and the identical elbow on the other "C" feedwater heater supply line have been replaced. The two corresponding 24-in. elbows on Oconee Unit 1 were ultrasonically inspected on July 1, 1982. The inspection revealed that a 4-in.2 area in one of the elbows had been reduced in thickness from 0.375 in. to 0.100 in. Power operation was subsequently adjusted to 80% and the "C" feedwater heaters isolated so that the affected steam line was maintained at 125 psig with no steam flow. The factor of safety based on material yield at the above pressure is slightly greater than two. Elbow replacement will be performed on Unit 1 after returning Unit 2 to power. In addition, the Institute of Nuclear Power Operations (INPO) has identified four other similar failures of steamlines also apparently resulting from steam erosion. These failures resulted in plant shutdown. They are Vermont Yankee on 1/27/82; Trojan 1 on 1/9/82; Zion 1 on 2/12/82; and Browns Ferry 1 on 6/24/82. For example, in Vermont Yankee, a leak occurred in the 12-in.-diameter drain line between the "C" moisture separator and the heater drain tank, blowing steam into the heater bay area. On Zion 1 a steam leak occurred in the 150 psig high-pressure exhaust steam line from the' Unit 1 turbine. The leak originated from an 8-in, crack on a weld joining 24-in.-diameter piping with the 37.5-in.-diameter high pressure steam exhaust pipe leading to the moisture separator reheater. INPO will issue a Significant Event Report on Nuclear Notepad shortly and is preparing a Significant Operating Experience Report which is expected to contain recommendations on this subject. If you have any questions regarding this matter please contact the Regional Administrator of the appropriate NRC, Regional Office, or this office. Edward L. Jordan, Director Division of Engineering and Quality Assurance Office of Inspection and Enforcement Technical Contact: O. Merrill 301-492-4513 Attachment: List of Recently Issued IE Information Notices
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021