RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-14-006, Updated Safety Analysis Report, Revision 16, CPS Operational Requirements Manual
RS-13-009, Operational Requirements Manual (Orm) 2013
LR-N17-0044, Hope Creek - License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
TSTF-07-19, Response to NRC Request for Additional Information (RAI) Regarding TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Dated February 28, 2007
W3F1-2021-0041, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Digital Upgrade to the Core Protection Calculator and Control Element Assembly Calculator System
W3F1-2021-0032, Revised License Amendment Request - Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System
B13151, Proposed Tech Specs 3/4.1, Reactivity Control Sys
AECM-84-0047, Responds to NRC Re Violations Noted in IE Insp Rept 50-416/83-51.Util Denies Alleged Violation.Addl Guidance Added to Operating Procedures to Ensure Proper Control Maintained When Bypassing Control Rods
2CAN049504, Application for Amend to License NPF-6,deleting Requirement Associated W/Part Length CEAs (Plceas) from TS & Replacing Plceas W/Full Length,Full Strength CEAs
RA-22-0270, Response to Request for Additional Information Regarding License Amendment Request to Address Technical Specifications Mode Change Limitations
RA-22-0057, License Amendment Request to Address Technical Specifications Mode Change Limitations
RBG-38262, Requests Waiver of Compliance Re TS 3.1.4.2, Rod Pattern Control Sys (Rpsc), Which Requires That Rpsc Be Operable So That Certain Sequence Restraints Imposed on Control Rod Groups,Based Upon Thermal Power Levels
RBG-40863, Forwards Application for Amend to License NPF-47,changing TS 3.10.2, Special Test Exceptions - Rod Pattern Control Sys
GNRO-2010/00042, Technical Specification Bases & Technical Requirements Manual Update
05000295/LER-1987-013-05, :on 870621,outer Door on Containment Personnel Hatch Malfunctioned.Caused by Out of Adjustment Cam & Follower Mechanism.Hatch Outer Door Repaired by Mechanical Maint on 870621
05000362/LER-1983-087-01, /01T-0:on 831026,plant Monitoring Sys Computer Failed While Entering Limiting Condition of Operation 3.10.2.Caused by Moving Head Disk Error in Computer.Cause of Disk Error Unknown
05000250/LER-1985-007-01, :on 850221,discovered Plant Procedures Did Not Include All Flowpath Valves Which Should Be Visually Verified Periodically for Position & Functionally Cycled,Per Tech Specs Re Fire Protection Sys
05000244/LER-1994-005, :on 940217,turbine Runback Occurred Due to Lost Offsite Power Circuit 751 Causing Low Voltage on Safeguard Busses 14 & 18.Circuit 751 Restored by Automatic Reclosure of Transformer Breaker
05000335/LER-1993-005-02, :on 930529,discovered That One CEA of Dual Element/Control Element Drive Mechanism Potentially Unlatched.Possibly Caused by Personnel Error.Cea Relatched & Latching Procedure Modified
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
RBG-41698, Submits Info Re LAR-93-14 Conversion to TS Based on NUREG-1434, Improved Ts,Rev 0
2CAN039007, Application for Amend to License NPF-6,modifying Tech Spec 4.10.2.2 & 3.10.2 Re Special Test Exception
U-602836, Forwards Rev 7 to Clinton Power Station Usar.Attached Clinton Power Station 10CFR50.59 Rept Identifies All Safety Evaluations for Implemented Changes Affecting USAR for Period of 950430-970630
L-09-218, Submittal of Technical Specification Bases, Revision 7