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{{#ask: [[Generic letter::NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)]] [[Site::Crystal River]]
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    "query_string": "[[Generic letter::NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04)]] [[Site::Crystal River]]",
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	Issue date	Title	From	To
3F0285-02, Requests Exemption from Portion of 10CFR50,App A,Gdc 4, Per Provisions of 10CFR50.12.Meeting W/Nrc & B&W Requested to Clearly Define Staff Needs for Info to Support Approval of Request.Fee Paid	1 February 1985	Requests Exemption from Portion of 10CFR50,App A,Gdc 4, Per Provisions of 10CFR50.12.Meeting W/Nrc & B&W Requested to Clearly Define Staff Needs for Info to Support Approval of Request.Fee Paid	Duke Energy Westafer G	NRC OFFICE OF ADMINISTRATION (ADM) Office of Nuclear Reactor Regulation Harold Denton
ML20133D993	30 July 1985	Notification of 850805 Meeting W/Util & B&W in Bethesda,Md to Discuss Proposed Exemption to GDC 4 for Reactor Coolant Pump Supports.Draft Agenda Encl	Office of Nuclear Reactor Regulation Silver H	Stolz J Office of Nuclear Reactor Regulation
ML20135F872	3 September 1985	Summary of 850805 Meeting W/Util & B&W in Bethesda,Md Re Proposed Exemption to GDC 4 for Reactor Coolant Pump Supports.Viewgraphs Encl	Mozafari B Office of Nuclear Reactor Regulation	Office of Nuclear Reactor Regulation
ML20132F556	12 September 1985	Safety Balance Assessment for Elimination of RCS Main Loop Pipe Break Protective Devices	BABCOCK & WILCOX CO.
ML20134A008	25 October 1985	Assessment of Crystal River 3 Reactor Coolant Leak Detection Sys	Duke Energy BABCOCK & WILCOX CO. Iwachow R Little P Maseda J
ML20137Y069	12 December 1985	Forwards Topical Rept Evaluation of B&W Owners Group Topical Repts Dealing W/Elimination of Postulated Pipe Breaks in PWR Primary Main Loops.Acceptable Basis Provided to Eliminate Effects of Large Ruptures in Main Loop Piping	Crutchfield D Office of Nuclear Reactor Regulation	Energy Northwest Oakes L BABCOCK & WILCOX OPERATING PLANTS OWNERS GROUP
ML20138M389	12 December 1985	Topical Rept Evaluation of Rev 1 to BAW-1847, Leak Before Break Evaluation of Margins Against Full Break for Rcs.... Rept Presents Acceptable Justification to Eliminate Dynamic Effects of Large Ruptures in Piping	Office of Nuclear Reactor Regulation
ML20137E719	13 January 1986	Evaluation of RCS Components & Component Supports for Optimized Reactor Coolant Pump Support Configuration Loadings	BABCOCK & WILCOX CO.
ML20137Y058	18 February 1986	Requests facility-specific Info Re Requests for Exemption from GDC 4,concerning Protection Against Dynamic Loads Resulting from Postulated Breaks of Primary Main Loop Piping.Info Re Leakage Detection Sys Should Be Included	Stolz J Office of Nuclear Reactor Regulation	Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT
ML20137Y043	18 February 1986	Discusses Safety Evaluation of B&W Owners Group Repts Dealing W/Elimination of Postulated Pipe Breaks in PWR Primary Main Loops.Exemption from GDC 4 & Demonstration That Leakage Sys in Compliance W/Reg Guide 1.45 Needed	Stolz J Office of Nuclear Reactor Regulation	Duke Energy Wilgus W
ML20154M259	18 February 1986	Discusses SER of Rev 1 to BAW-1847 & BAW-1889P Re Elimination of Postulated Pipe Breaks in PWR Primary Main Loops.Repts Acceptable.Leakage Detection Sys Info Requested	Berkow H Office of Nuclear Reactor Regulation	Jackie Cook Consumers Energy
NRC Generic Letter 1989-21	19 October 1989	NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements	Partlow J Office of Nuclear Reactor Regulation
ML20154C153	30 September 1998	LAR 238 to License DPR-72,correcting RCS Leakage Detection Capability of RB Atmosphere Gaseous Radioactivity Monitor Described in ITS Bases & FSAR	Duke Energy
ML092650272	18 September 2009	Response to Requests for Additional Information for the Review of the License Renewal Application and Amendment #3	Progress Energy Co Franke J	Office of Nuclear Reactor Regulation Document Control Desk

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