[Federal Register Volume 63, Number 4 (Wednesday, January 7, 1998)] [Notices] [Page 896] From the Federal Register Online via the Government Publishing Office [www.gpo.gov] [FR Doc No: 98-372] ----------------------------------------------------------------------- NUCLEAR REGULATORY COMMISSION Degradation of Steam Generator Internals; Issue AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance. ----------------------------------------------------------------------- SUMMARY: 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 amended, and 10 CFR 50.54(f). The generic letter is available in the NRC Public Document Room under accession number 9712180168. DATES: The generic letter was issued on December 30, 1997. ADDRESSEES: Not applicable. FOR FURTHER INFORMATION CONTACT: Stephanie M. Coffin, at (301) 415- 2778. SUPPLEMENTARY INFORMATION: This generic letter does not constitute a backfit as defined in 10 CFR 50.109(a)(1) since it does not impose modifications of or additions to structures, systems or components or to design or operation of an addressee's facility. It also does not impose an interpretation of the Commission's rules that is either new or different from a previous staff position. The staff, therefore, has not performed a backfit analysis. Dated at Rockville, Maryland, this 30th day of December 1997. For the Nuclear Regulatory Commission. David B. Matthews, Acting Director, Division of Reactor Program Management, Office of Nuclear Reactor Regulation. [FR Doc. 98-372 Filed 1-6-98; 8:45 am] BILLING CODE 7590-01-P