LIC-17-0024, Supplemental Information Needed for Acceptance of Requested Licensing Action Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC No. MF9067). (Non-Proprietary)(Part 4 of 4)
PLA-3150, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1988
PNP 2014-074, Relief Request Number RR 4-20 Proposed Alternative, Use of Alternate ASME Code Case N-716
W3F1-2014-0023, Entergy Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Wa
NOC-AE-12002850, Submittal of Radioactive Effluent Release Report for the Year 2011
NOC-AE-10002607, License Renewal Application, Environmental Report
NOC-AE-10002536, Submittal of Radioactive Effluent Release Report for 2009
NRC-10-0007, Enrico Fermi Atomic Power Plant, Unit 1, License Termination Plan, Revision 2
NG-09-0514, Response to Request for Additional Information Regarding Severe Accident Mitigation Alternatives
RBG-46922, Request for Alternative - Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
NRC-08-0031, Fermi 2- 2007 Annual Radioactive Effluent Release and Radiological Environmental Operating Report for the Period of January 1, 2007 Through December 31, 2007
L-08-081, Reply to Request for Additional Information Regarding Severe Accident Mitigation Alternatives License Renewal
SECY-11-0124, Station Blackout Mitigation Strategies, Final Regulatory Basis - Revision 3
NL-06-056, Offsite Dose Calculation Manual (ODCM)
RS-05-135, Additional Information Supporting the Request for License Amendment Related to Extending the Completion Time for Nuclear System Protection System Inverters
NRC-93-0100, Provides Modified Values for Derived Air Concentration & Annual Limit on Intake.Fermi Will Use Values for Implementation of Revised 10CFR20.Lists Basis for Modifying Values
RS-03-065, Units 1 & 2, Request for License Amendment for One-Time Extension of Essential Service Water Train Completion Time
GNRO-2003/00029, One Time Extension on Integrated Leak Rate Test & Drywell Bypass Test Interval
NL-03-0108, Response to Request for Additional Information Technical Specification Revision Request Integrated Leakage Rate Testing Interval Extension
NOC-AE-04001720, Radioactive Effluent Release Report for 2003
L-2002-070, Part 2 of 2, St. Lucie, Unit 1 - FPL Response to Request for Additional Information for 10CFR50 Appendix R K1 Exemption Clarification/Request, Appendix a Cable Tray Fuel Load Calculations
WO 02-0019, Annual Radioactive Effluent Release Report - Report 25
IA-85-465, Partial Response to FOIA Request for Five Specified Summaries of Idcor/Nrc Technical Exchange Meetings.Forwards App a Documents.Records Placed in Pdr.Search Continuing for Other Meeting Summaries
BSEP-82-1754, Semiannual Environ & Effluent Release Rept,Jan-June 1982
BSEP-84-0392, Semiannual Environ & Effluent Release Rept,Jul-Dec 1983
PY-CEI-NRR-0430, Rev 2 to Operations Manual OM12D, Offsite Dose Calculation Manual
05000293/LER-1991-018, :on 910710,setpoints of Degraded Voltage Relays Discovered Too Low Probability Degraded Voltage Conditions. Cause Unknown.Mods Planned to Replace Applicable Control Power Transformers
PM-80-171, Semiannual Rept,Plant Radioactive Effluent Releases, Jul-Dec 1979
PLA-2993, Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1987. W/
PLA-3739, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991
PLA-3529, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1990
GO2-88-049, Semiannual Effluent Rept for July-Dec 1987
GO2-86-150, Semiannual Effluent Rept,Jul-Dec 1985
GO2-84-465, Semiannual Effluent Rept,Jan-June 1984
L-93-021, ERS-ATL-93-021, Rev. 4, Process Alarm Setpoints for Liquid Effluent Monitors
RS-15-185, County - Supplemental Information Regarding Seismic Hazard Risk Evaluation and Seismic Hazard Prioritization Results - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near
NOC-AE-110027, Supplemental Response to Requests for Additional Information for the South Texas Project License Renewal Application - SAMA
HNP-09-094, Third Response to Request for Additional Information License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor..
05000317/LER-2006-004, Re Reactor Trip Due to Loose Wire During Maintenance on Turbine Control System
NRC-2009-0435, Comment (12) of Barbara A. Oneal on Draft Environmental Assessment and Finding of No Significant Impact for Nuclear Fuel Services, Inc., Erwin, Tn, for 40-Year License Renewal
L-03-111, Emergency Preparedness Plan Implementing Procedures