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WAIS Document Retrieval [Federal Register: January [Notices] [Page 2237 -2241] From the Federal Register [DOCID:frl3ja99 -81] 13, 1999 (Volume 64, Number 8)] Online via GPO Access [wais.access.gpo.gov] ----------------------------------------------------------------------- UNITED STATES NUCLEAR REGULATORY COMMISSION [Docket No. 50 -400] Carolina Power & Light; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF -63 issued to Carolina Power & Light (CP &L or the licensee) for operation of the Shearon Harris Nuclear Power Plant [[Page 2238]] located in Wake and Chatham Counties, North Carolina. The proposed amendment would support a modification to the plant tc increase the spent fuel storage capacity by adding rack modules to spent fuel pools (SFPs) ''C'' and ''D'' and placing the pools in service. In order to activate the pools, CP &L requests that the NRC review and approve the following: i. Revised Technical Specification 5.6 to identify PWR burnup restrictions, BWR enrichment limits, pool capacities, heat load limitations and nominal center -to- center distances between fuel assemblies in the racks to be installed in SFPs 'C' and 'D.' ii. 10 CFR 50.55a Alternative Plan to demonstrate acceptable level of quality and safety in the completion of the component cooling water (CCW) and SFP 'C' and 'D' cooling and cleanup system piping. The cooling system for SFPs 'C' and 'D' cannot be N stamped in accordance with ASME Section III since some installation records are not available, a partial turnover was not performed when construction was halted following the cancellation of Unit 2 and CP &L's N certificate program was discontinued following completion of Unit 1. iii. Unreviewed safety question for additional heat load on the CCW system. The acceptability of the 1.0 MBtu /hr heat load from SFPs 'C' and 'D' was demonstrated by the use of thermal - hydraulic analyses of the CCW system under various operating scenarios. The dynamic modeling used in the thermal - hydraulic analyses identified a decrease in the minimum required CCW system flow rate to the residual heat removal heat exchangers. This change has not been previously reviewed by the NRC and is deemed to constitute an unreviewed safety question. Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of Page 1 of 8 http: / /frwebgate2. acces ... /waisgate.cgi ?WAISdocID= 341284846 +0 +0 +0 &WAISaction = retriev 1/14/99