Energia i regulacje · 7.01.1998
Degradation of Steam Generator Internals; Issue
The Nuclear Regulatory Commission (NRC) has issued Generic Letter (GL) 97-06 to all holders of operating licenses for pressurized- water reactors, except those who have permanently ceased operations and have certified that fuel has been permanently removed from the reactor vessel, to (1) again alert addressees to the previously communicated findings of damage to steam generator internals, namely, tube support plates and tube bundle wrappers, at foreign PWR facilities; (2) alert addressees to recent findings of damage to steam generator tube support plates at a U.S. PWR facility; (3) emphasize to addressees the importance of performing comprehensive examinations of steam generator internals to ensure steam generator tube structural integrity is maintained in accordance with the requirements of Appendix B to 10 CFR Part 50; and (4) require all addressees to submit information that will enable the NRC staff to verify whether addressees' steam generator internals comply with and conform to the current licensing bases for their respective facilities. This generic letter only requests information from the addressees under the provisions of Section 182a of the Atomic Energy Act, as amende