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Agenda - 01-19-1999 - 9b1
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Agenda - 01-19-1999 - 9b1
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8/5/2015 11:28:59 AM
Creation date
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BOCC
Date
1/19/1999
Meeting Type
Regular Meeting
Document Type
Agenda
Agenda Item
9b1
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Minutes - 19990119
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\Board of County Commissioners\Minutes - Approved\1990's\1999
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WAIS Document Retrieval <br />is not created. <br />3. Involve a significant reduction in the margin of safety. <br />The function of the Spent Fuel Pool is to store the fuel <br />assemblies in a subcritical and coolable configuration through all <br />environmental and abnormal loadings, such as an earthquake or fuel <br />assembly drop. The new rack design must meet all applicable <br />requirements for safe storage and be functionally compatible with <br />Pools 'C' and 'D'. <br />CP &L has Addressed the Safety Issues Related to the Expanded Pool <br />Storage Capacity in the Following Areas: <br />1. Material, mechanical and structural considerations. The <br />mechanical, material, and structural designs of the new racks have <br />been reviewed in accordance with the applicable provisions of the <br />NRC Guidance entitled, "Review and Acceptance of Spent Fuel Storage <br />and Handling Applications''. The rack materials used are compatible <br />with the spent fuel assemblies and the Spent Fuel Pool environment. <br />The design of the new racks preserves the proper margin of safety <br />during normal and abnormal loads. It has been shown that such loads <br />will not invalidate the mechanical design and material selection to <br />safely store fuel in a coolable and subcritical configuration. <br />2. Nuclear Criticality <br />The methodology used in the criticality analysis of the expanded <br />Spent Fuel Pool meets the appropriate NRC guidelines and the ANSI <br />standards (GDC 62, NUREG 0800, Section 9.1.2, the OT Position for <br />Review and Acceptance of Spent Fuel Storage and Handling <br />Applications, Reg. Guide 1.13, and ANSI /ANS 8.17). The margin of <br />safety for subcriticality is maintained by having the neutron <br />multiplication factor equal to, or less than, 0.95 under all <br />accident conditions, including uncertainties. This criterion is the <br />same as that used previously to establish criticality safety <br />evaluation acceptance and remains satisfied for all analyzed <br />accidents. <br />3. Thermal - hydraulic and Pool Cooling <br />The thermal - hydraulic and cooling evaluation of the pools <br />demonstrated that the pools can be maintained below the specified <br />thermal limits under the conditions of the maximum heat load and <br />during all credible accident sequences and seismic events. The pool <br />temperature will not exceed 137 deg.F during the highest heat load <br />conditions. The maximum local water temperature in the hot channel <br />will remain below the boiling point. The fuel will not undergo any <br />significant heat up after an accidental drop of a fuel assembly on <br />top of the rack blocking the flow path. A loss of cooling to the <br />pool will allow sufficient time ( >13 hours) for the operators to <br />intervene and line up alternate cooling paths and the means of <br />inventory make -up before the onset of pool boiling. The thermal <br />limits specified for the evaluations performed to support the <br />proposed activity are the same as those that were used in the <br />previous evaluations. It has also been demonstrated that adequate <br />margin exists in the Unit 1 CCW system to support near term <br />operation of the pools subject to the requirements of the proposed <br />changes to the Technical Specifications. <br />Based on the preceding discussion it is concluded that this <br />activity does not involve a significant reduction in the margin of <br />safety. <br />The NRC staff has reviewed the licensee's analysis and, based on <br />this review, it appears that the three standards of 10 CFR 50.92(c) are <br />satisfied. Therefore, the NRC staff proposes to determine that the <br />Page 5 of 8 <br />http: / /frwebgate2. acces ... /waisgate.cgi ?WAISdocID= 341284846 +0 +0 +0 &WAISaction = retriev 1/14/99 <br />
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