Overhead Crane Handling Systems for Nuclear Power Plants
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 14, Initial Test Program
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
L-2010-022, Request to Amend License Proposed Changes to the Technical Specifications (TS) for the Removal of Two TS That Restrict Movements of Heavy Loads Over the Spent Fuel Pools
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
CY-02-010, Proposed Technical Specification Change Response to Request for Additional Information
LIC-18-0018, Independent Spent Fuel Storage Installation - Emergency Plan Update
NL-04-126, License Amendment Request, Fuel Storage Building Single-Failure-Proof Gantry Crane
NOC-AE-04001734, Commitment Change Summary Report
NG-03-0168, Request for Operating License Change Single-Failure-Proof Reactor Building Crane
ST-HL-AE-1862, Forwards Revised Pages to Control of Heavy Loads Rept, Reflecting 2,500 Lbs as Weight Recognized as Heavy Load. Value Consistent W/Design Criteria for Spent Fuel Racks Designed to Prevent Rack Deformation
ST-HL-AE-1465, Forwards Response to Draft Ser/Fsar Item 9.1-1 Re Update of Section 9.1 Concerning Spent Fuel Rack Configuration.Encl marked-up FSAR Page Will Be Incorporated Into Future FSAR Amend
NG-96-1637, Provides Addl Info on Single Failure Proof Status of DAEC Reactor Building Crane in Effort to Have This Safety Issue Resolved.Daec Considers Crane Single Failure Proof & Requests NRC Concurrence
ST-HL-AE-1031, Forwards Response to Generic Ltr 81-07, Control of Heavy Loads. Deviations from Established Load Paths Will Require Written Alternatives Approved by Plant Safety Review Committee
RBG-16-356, Forwards Responses to Draft SER Open items,w/marked-up FSAR Pages.Changes Will Be Incorporated Into Next FSAR Amend
RBG-16-354, Forwards Responses to Draft SER Open Items Re Mechanical Fracturing Analysis & Fuel Assembly Damage by External Forces.Response to Item 10 Re TMI Item II.F.2, Inadequate Core Cooling, Will Be Provided by Dec 1983
TXX-4306, Forwards Addl Info for Resolution of Open Items Re Handling of Heavy Loads,Per NRC 840830 & 0906 Requests Re NUREG-0612, Phase II
TXX-3659, Forwards Final Response to NUREG-0612, Control of Heavy Loads at Nuclear Power Plants
GO2-97-134, Provides Staff W/Results of Detailed Review of Reactor Bldg Crane Design in Response to RAI Re NRC Bulletin 96-002, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor or Over SR Equipment
ST-HL-AE-5015, Errata to Application for Amends to Licenses NPF-76 & NPF-80 Incorporating Changes to Updated FSAR to Reflect Increase in Spent Fuel Pool Heat Loads