LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
NL-06-123, Initial Licensed Operator Examination Post-Examination Submittal - Facility Comments
L-76-119, Letter Request to Amend Appendix a of Facility Operating Licenses. Proposes Technical Specification Changes Relating to Surveillance of Safety-Related Hydraulic Snubbers
LR-N15-0124, Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systmens
BECO-91-123, Requests NRC Review & Approval of Encl Engineeing Evaluation of Elevated Tailpipe Temp on Safety Relief Valve 203-3D Discovered on 910814.Operation W/Leakage Will Not Cause Setpoint Drift in Excess of Drift Permitted by Tech Specs
IA-86-413, Listings of Recipient Files,Including Listing of Mfgs & Radiological Devices
B16626, Application for Amend to License NPF-49,changing TS Bases Section 2.2 to Clarify Function of P-6 Interlock for Increasing as Well as Decreasing Reactor Power
B13061, Provides Listed Info Re Util Cable Vault Water in-leakage, Including Substantial Safety Hazards Evaluation CY-87-02,per 880908 Request.W/Eight Oversize Drawings
NPL-98-0004, Discusses Main Control Board Wiring Separation for Units 1 & 2.Attachment B Copy of Work Package List & Wire/Sys Designators for Each Package
AECM-88-0107, Forwards Computer Tape of Hourly Meteorological Data for 1987.Note Tape Formatted Similar to Tape Sent Earlier by Ltr Except That Ebcdic Format Rather than Ascii Format Used.Sample Tape Dump Printout Also Encl
PY-CEI-NRR-0946, Application for Amend to License NPF-58.Amend Adds Ref to Encl Dcrdr - First Refuel Hed Revs Repts, Attachment 1. Encl Supersedes Rept Sheets Encl W/Attachment 2 of Util
A98034, 1997 Annual 10CFR50.59 Summary Rept
05000315/LER-1986-002, :on 860217,discovered That Three Reactor Trip Sys Interlock Setpoints Not Set Per Tech Spec Requirements. Caused by Misinterpretation of Tech Specs.Procedures Revised to Agree W/Tech Specs
05000445/LER-1991-027, :on 911107,source-range Flux Doubling Signal Initiated,Actuating Inadvertent Boron Dilution Mitigation Function.Caused by Circuit Response to Power Supply Switchover.Procedure Changed
05000445/LER-1992-029, :on 921208,discovered Temporary Power Supply Lost to Panel 1PC1.Caused by Personnel Error.Engineering Will Hold Annual Training in self-verification for All Engineering Personnel
05000272/LER-1990-020-01, :on 900608,identified That maint-I&C Procedures for Setting Intermediate Range Excore Nuclear Instrumentation Sys Permissive P-6 Not Correct.Caused by Inadequate Procedure Control
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
RS-14-067, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the
PNP 2014-033, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the
RNP-RA/03-0074, Supplemental Information Regarding License Renewal Application