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Assessment of the extension of refueling surveillance intervals for Indian Point-2

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6948235
In a pressurized water reactor several components are tested during refueling shutdowns because they are not accessible during power operation. The plant technical specifications establish maximum limits for refueling surveillance intervals. Any extension of a surveillance interval beyond the specified limits requires approval by the US Nuclear Regulatory Commission (NRC). An economic benefit can be gained if a plant shutdown to recalibrate instrumentation can be deferred to coincide with the planned refueling outage. This paper describes the work performed by Atomic Energy of Canada Limited (AECL): Canada deuterium uranium (CANDU) operations for Consolidated Edison Company of New York to support a request to NRC for a one-time extension of the 1986/87 refueling surveillance intervals at the Indian Point-2 station. The work consisted of assessing the impact on the safety of the plant for extending the surveillance interval of the equipment requiring recalibration prior to the planned 1987 refueling shutdown. The results from this evaluation supported an extension of the surveillance interval for 16 tests for the duration of 2 months; however, the work also indicated that a surveillance interval extension, such as 6 to 12 months, may require a more in-depth analysis in certain areas.
OSTI ID:
6948235
Report Number(s):
CONF-880422-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 56
Country of Publication:
United States
Language:
English