Information Notice No. 82-11:Potential Inaccuracies in Wide Range Pressure Instruments Used in Westinghouse Designed Plants
SSINS No.: 6835 IN 82-11 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 April 9, 1982 Information Notice No. 82-11: POTENTIAL INACCURACIES IN WIDE RANGE PRESSURE INSTRUMENTS USED IN WESTINGHOUSE DESIGNED PLANTS Addressees: All nuclear power reactor facilities holding an operating license or a construction permit. (This information was transmitted by facsimile on April 9, 1982 to Westinghouse designed nuclear power plants holding an operating license.) Purpose: This Information Notice is provided as an early notification of a potentially significant problem pertaining to wide range pressure instruments used in Westinghouse nuclear power plans. 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: By telephone calls on April 7 and 8, 1982, Westinghouse notified the NRC of information it had conveyed to its customers regarding the results of recent qualification tests in post-accident high energy line break environment on the wide range pressure instruments supplied by Westinghouse. Westinghouse stated that when combining transmitter, signal conditioning and indicator allowances for errors due to calibration uncertainty, drift and environmental effects that the qualification tests indicated that the RCS wide range pressure channels exhibited ambiguities in their accuracy which could potentially result in inappropriate operator actions. Westinghouse stated that post-accident accuracy ambiguities for RCS wide range pressure instruments under certain plant accident conditions have the potential for maximum accumulated inaccuracies of +/- 363 psig actuation and +/- 390 psig indication. Accordingly, the inaccuracy of RCS wide range pressure measurements could lead to pressurizer power operated relief valves being lifted prior to the termination of safety injection (SI) and to a greater number of valve challenges, thereby increasing the probability of a small break loss-of-coolant accident due to a valve failing to close. Likewise, the inaccuracy of the wide range pressure instruments could lead to the termination of SI without adequate reactor coolant subcooling. In addition, the inaccuracies could lead to premature or late tripping of the RCS pumps during the course of a small break loss-of-coolant accident. . IN 82-11 Page 2 of 2 Westinghouse further stated that it is reviewing the design and operational bases for the wide range pressure instrumentation, that it will advise its customers of appropriate actions, and that continued safe plant operation has been demonstrated by prior analyses. 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 Attachment: Recently Issued IE Information Notices
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021