RA-17-055, License Amendment Request to Implement BWRVIP-18, Revision 2-A
NLS2105025, 10 CFR 50.55a Requests for Fifth Ten-Year Inservice Inspection Interval
RS-14-151, Dresden, Units 2 and 3 - Attachment 4, Kld TR-634, Rev. 0, Development of Evacuation Time Estimates. Part 3 of 4
NLS2008065, Inservice Inspection Summary Report for the Spring 2008 Refueling Outage
RS-07-134, Co. and Amergen Energy Co., LLC, Response to Request for Additional Information Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements
L-PI-06-037, Annual Radiological Environment Environmental Monitoring Program (REMP) Report
NL-18-1480, Response to NRC Request for Additional Information on Alternative Request (HNP-ISI-ALT-05-04)
NLS2005049, Inservice Inspection Summary Report
ET 10-0014, Application to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1
NLS2002040, Inservice Inspection Summary Report for Cooper Nuclear Station
NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included
NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
IA-86-776, Forwards Grant for Financial Assistance for Acs Symposium Entitled Chemical Phenomena Associated W/Radioactivity Releases During Severe Nuclear Plant Accidents, for Execution
ST-HL-AE-1897, Forwards marked-up Draft Rev 2 to Tech Specs Re Reactivity Control Sys,Esfas Instrumentation Trip Setpoints & Eccs. Changes Include Transmittal of Values & Rewording for Some Limiting Conditions of Operation
0CAN048509, 1984 Annual Environ Radiological Monitoring Rept
RBG-37720, Special Rept:On 921013,Div I EDG Automatically Shutdown During Regular Monthly Surveillance Test.Caused by Failure of Shutdown Control Valve P-4.Valve Replaced & Surveillance Test Completed Approx 12 H After Valid Failure
B11111, Forwards Response to Draft SER Open Items
NL-08-014, Clarifications to Reactor Vessel Surveillance Program and Neutron Embrittlement Time-Limited Aging Analyses and Audit Item 105; and Revision to License Renewal Regulatory Commitment List
05000328/LER-1996-004-02, :on 960919,reactor Trip Breaker Was Removed After It Was Found to Have Inoperable Auxiliary Contacts. Caused by Inadequate Procedure.Revised Breaker Procedure & Reemphasized Requirements for Working Steps Out of Sequence
05000416/LER-1992-004, :on 920414,discovered That Both Divs of Drywell Purge Sys Inoperable.Caused by Incomplete Component Designation Stencilled on Valve.Incomplete Stencil Corrected & Operator Training Program Revised
05000482/LER-1990-007, :on 900510,feedwater Isolation Signal Occurred Due to Surveillance Test Requiring High Feed Rate.Caused by Feedwater Flow Rate Higher than Steam Flow.Rev to Surveillance Test Procedures Clarified
AECM-81-278, Forwards Updated Info Re Fsar,In Response to NRC Questions Raised During 810518 Meeting.Proposed FSAR Changes Will Be Incorporated Into Next Available Amend to License
ELV-01105, Special Rept 50-424/1989-003:on 891030,31 & 1107,tendon Grease Deficiencies Noted During Combined Tendon Surveillances.No Corrosion or Cracks Found.Tensile Test Results for Strand Samples Expected by End of Dec 1989
05000455/LER-1990-006-11, :on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure Revised
L-89-235, Forwards marked-up FSAR Pages W/Changes Expected from Adoption of Revised Tech Specs in 890605 License Amend Request.Encl Changes to FSAR Would Facilitate Completion of NRC SER
GO2-94-292, Forwards Updated Response to Deviations Noted in EOPs Insp Rept 50-397/91-27,satifying Commitment Made in 940425 Response to Insp Rept 50-397/94-01
GO2-15-045, Seismic Hazard and Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
CNL-14-038, Tennessee Valley Authoritys Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acci
U-603625, Examination Outline Submittal with NRC Comments for the Clinton Initial Examination - January 2004
3F0294-15, Forwards Response to NRC 931021 RAI Re GL 92-08, Thermo-Lag 330-1 Fire Barriers, 10CFR50.54(f)
NUREG/CR-5176, Updated Board Notification 89-01 Re Lll NUREG/CR-5176, Seismic Failure & Cask Drop Analyses of Spent Fuel Pools at Two Representative Nuclear Power Plants
PY-CEI-NRR-0706, Startup Rept,Supplemental - 2
PY-CEI-NRR-0661, Startup Rept,Supplemental - 1
05000455/LER-1990-006, :on 910930,reactor Containment Fan Cooler 2C Low Speed Breaker Did Not Close.Caused by Miscommunication & Procedural Deficiency.Procedure Revised to Include Emergency Exit Section