10 CFR 51.52, Environmental effects of transportation of fuel and waste
NL-16-2335, Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
WO 16-0045, Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ULNRC-06230, Response to Request for Additional Information (RAI) Related to License Amendment Request for Emergency Action Level (EAL) Upgrade Adopting NRC-Endorsed NEI 99-01, Revision 6
ULNRC-06227, Response to Request for Additional Information Related to License Amendment Request for Emergency Action Level Upgrade Adopting NRC-Endorsed NEI 99-01, Rev 6
RBG-47852, Response to License Renewal Application NRC Request for Additional Information Set 13
ONS-2017-030, Oconee Nuclear Station Emergency Plan Revision 2017-002. Part 1 of 2
RNP-RA/10-0019, Supplemental Information for Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria
L-2009-209, Response to Request for Additional Information Re License Amendment Request for H*: Alternate Repair Criteria for Steam Generator Tubesheet Expansion Region
0CAN090901, Arkansas, Units 1 and 2, Generic Letter 2004-02 Final Supplemental Response to Request for Additional Information
NL-09-1265, Response to RAI Related to License Amendment Request to Revise TS Sections 5.5.9, Steam Generator (SG) Program and TS 5.6.10,Steam Generator Tube Inspection Report for Permanent Alternate Repair Criteria
CP-200901042, Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria
RS-09-108, Additional Information Supporting License Amendment Request to Revise Technical Specifications (TS) for Steam Generator Permanent Alternate Repair Criteria
NL-16-1128, License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
NEI 99-01, Wolf Creek Generating Station Proposed Revised EAL Technical Basis Document
NEI 99-01, Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RBG-47906, Response to Request for Additional Information for License Amendment Request, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6
GO2-05-099, License Amendment Request to Technical Specifications Associated with AC and DC Electrical Power
L-05-030, Sixteenth Refueling Outage Inservice Inspection Report
NRC-02-0034, Proposed License Amendment for the Revision of Control Room Emergency Filtration System Technical Specification Requirements During Movement of Recently Irradiated Fuel
IA-84-784, Discusses NRC Efforts to Restrict Use of Highly Enriched U Fuel in Univ Research Reactors.Requests Funds from Research Budget as Initial Allocation for Funding Programs Essential to Successful Conversion.Supporting Documentation Encl
IA-97-253, Second & Final Response to FOIA Request for Records.Records in App B Available in Pdr.App C Records Encl & Being Placed in PDR
AECM-86-0275, Application to Amend License NPF-29,revising Tech Specs to Add Inboard Isolation Valve & Two Test Connection Valves to Penetration 71B,to Meet Intent of Reg Guide 1.11.Fee Paid
05000324/LER-1987-004-02, :on 870311,reactor Scram on Low Level Due to Loss of Uninteruptible Power Supply & Subsequent Loss of Feedwater.Caused by Noncompliance W/Procedure to Transfer Power.Motor Replaced & Sys Returned to Normal
LD-88-131, Forwards Rev 1 to Part 2 of C-E Nuclear Fuel Integrated Improvement Progam, W/Status of Commitments as of 881024
05000395/LER-1984-022, :on 840412,w/RCS at Half Pipe,Discharge Valve for Charging Pump a Discovered Closed,Making Boration Flow Path Inoperable.Caused by Personnel Error.One Operable Boration Flow Path Verified in Modes 5 & 6
05000458/LER-1994-032, :on 941214,Division III DG Failed Due to Improper Synchronization Attempt by Operator.Considered Disciplinary Action for Individual Involved & Continued Performance That Monitored Testing of DG
05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits
PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82
L-2022-076, Subsequent License Renewal Application - Appendix E Environmental Report Supplement 2
RA-22-0285, Subsequent License Renewal - Appendix E Environmental Report Supplement 2
RS-15-221, Revisions to License Renewal Application, Applicants Environmental Report - Operating License Renewal Stage