ONS-2015-072, Updated Final Safety Analysis Report, Revision 24, Chapter 9 - Auxiliary Systems
RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11
ONS-2014-086, Updated Final Safety Analysis Report, Revision 23, Chapter 9, Auxiliary Systems
CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis
ONS-2016-039, Oconee, Units 1, 2, and 3 - Annual Radioactive Effluent Release Report for 2015
RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15-i - 15.3-76
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6
NL-06-020, Application for a Technical Specification Change to Add Spent Fuel Cask Loading Requirements
1CAN110302, Supplement to Amendment Request to Changes for the Spent Fuel Pool Loading Restrictions
RNP-RA/03-0038, Request for Technical Specifications Change Re Credit for Spent Fuel Storage Pool Dissolved Boron
2CAN010304, Arkansas, Unit 2, License Amendment Request to Change Spent Fuel Pool Loading Restrictions
AECM-88-0206, Provides Addl Info Re Cycle 4 Reload,Per NRC Request. Criticality Analysis for 8x8 Cycle 4 Reload Fuel Encl. Criticality Analysis for 9x9 Test Assemblies Will Be Submitted by 881115
3F1098-15, Rev 0 to LAR 245 to License DPR-72,to Change Methodology for Sf Pool B Criticality Analysis.Change Is Necessary Due to Boraflex Degradation in Sf Pool B.Proposed Revs to USAR, TS & Holtec Rept,Encl
LD-89-124, Forwards Response to 891019 Request for Addl Info Re 890501 Application for Amend to License SNM-33,including Responses to Specific Questions,Change Page Numbers & Replacement Pages
CP-201300083, License Amendment Request 12-06, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage and 5.5 Programs and Manuals
RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality
RA-19-0424, 2 to Updated Final Safety Analysis Report, Chapter 4, Reactor
DCL-85-306, Applicant Exhibit A-2,consisting of Forwarding Reracking of Spent Fuel Pools,Diablo Canyon Units 1 & 2, Dtd Sept 1985.Unit 1 Refueling Outage Could Occur as Early as Jul 1986