RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
Information Notice 2013-03, Recent Issue with the Definition of Core Quadrant
Information Notice 2013-03, Recent Issue With the Definition of Core Quadrant
TMI-11-103, License Amendment Request to Revise Technical Specifications to Incorporate Administrative Changes
DCL-16-081, 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm).
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
L-09-031, Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control
GO2-09-011, License Amendment Request to Revise Control Rod Notch Testing Frequency Using the Consolidated Line Item Improvement Process (CLIIP) for TSTF-475
BSEP 08-0126, Withdrawal of Request for License Amendment - Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation
RBG-46690, License Amendment Request, Application for Technical Specification Changes Using the Consolidated Line Item Improvement Process (CLIIP)
PLA-6330, Proposed Amendment Nos. 300 and 270: Request for Adoption of TSTF-475, Rev. 1, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action, Using the Consolidated Line Item Improvement Process (CLIIP)
BSEP 08-0082, Request for License Amendment - Adoption of TSTF-475, Revision 1 - Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
GNRO-2008/00014, License Amendment Request, Application to Technical Specification Changes Using the Consolidated Line Item Improvement Process - TSTF-475 Control Rod Notch Testing
RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I
JAFP-08-0011, License Amendment Request Application for Technical Specification Changes Using the Consolidated Line- Item Improvement Process (CLIIP)
L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation
NRC-08-0001, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency and a Clarification of a Frequency Example Using the Consolidated Line Item Improvement Process
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
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
RBG-46179, Revisions to the Technical Requirements Manual and the Technical Specification Bases
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
BSEP-97-0532, Responds to 971107,17 & 19 RAIs Re 961101 & 971013 Amend Requests for Conversion to Improved Ts,Per NUREG-1433,Rev 1. Requested Info Encl
BVY-99-104, TS Proposed Change 223 to License DPR-28,revising Reactor Core Spiral Reloading Pattern to Begin Around Srm.Submittal Entirely Supersedes Proposed Change 211 to TS
U-602417, Application for Amend to License NPF-62,changing TS 3.8.2, 3.8.5 & 3.8.8 to Revise Operability Requirements for Div 3 DG & Divs 3 & 4 Batteries,Battery Chargers & Inverters to Apply Only When HPCS Required to Be Operable
ULNRC-05938, Enclosure 1: Callaway Plant Unit 1 - Responses to RAI Set 17 and Amendment 17 to the Callaway LRA
W3P86-3379, Forwards Response to Request for Addl Info Re Tech Spec Change Requests to Implement Bypass for nonsafety-related High Speed Generator Level Trip & to Support Cycle 2 Operation
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
05000461/LER-2021-002-01, Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications
05000461/LER-2021-002, Core Alteration with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications
05000366/LER-1997-006, :on 970407,TS Surveillance on Source Range Monitors Was Missed.Caused by Data Entry Error.Control Rod Exercises Suspended Until SRM Surveillance Was Successfully Perfomed
05000461/LER-1996-019, :on 961120,inadequate Surveillance Procedures Were Noted Due to Misinterpretation of TS Bases Results in Source Range Monitor Reactor Period Display Not Verified. Procedures CPS 9031.13 Will Be Revised
05000289/LER-1991-008-01, :on 911223,discovered Misfiled Surveillance Notification Form Specifying Core Flood Tank Monthly Boron Sample Days Beyond Latest Date.Caused by Personnel Error. Surveillance Tracking Practice Revised
05000261/LER-1983-002-03, /03L-0:on 830215,safety Injection Pump a Tripped After Being Started for Routine Filling of Accumulators. Caused by Faulty Pump Breaker.Overcurrent Trip Device Replaced.Evaluation of Event Continuing
05000327/LER-1982-108-03, /03L-0:on 820907,during Mode 1,level Channel LT-63-50 on Refueling Water Storage Tank Declared Inoperable.Caused by Transmitter Out of Tolerance Due to Instrument Drift.Loop Recalibr
05000261/LER-1981-024-03, /03L-0:on 811028,heat Tracing for Motor Operated Valves on Discharge Line of Boron Injection Tank Found Failed.Caused by Short to Ground Resulting from Insulation Repairs.Personnel Cautioned Re Insulation
05000261/LER-1981-023-03, /03L-0:on 811022,at 50% Power,Safety Injection Pump Started from Control Room for Routine Filling of Accumulators & Circuit Breaker Tripped.Cause Unidentified. No Further Action Considered Necessary
05000261/LER-1983-011-03, /03L-0:on 830605,circuit Breaker for Boron Injection Tank Heater Channel B Tripped.Caused by Component Failure Due to Normal End of Life.Failed Heater Replaced
05000369/LER-1981-067, Forwards LER 81-067/03L-0.Detailed Event Analysis Encl
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
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
05000302/LER-1978-035-03, /03L-0:on 780710,during Performance of SP-322, Cable Tunnel Pump Sump Operability Procedure,Two North Sump Pumps Failed to Start.Caused by Personnel Error in Securing Power to North Pumps at Substation.Switches to Be Tagged
L-PI-09-133, License Amendment Request for Measurement Uncertainty Recapture - Power Uprate
05000324/LER-2009-002, (Bsep), Unit 1 Regarding Valid System Actuations Due to Loss of Power to Emergency Bus E2
BSEP 08-0081, Response to Request for Additional Information Regarding Request for License Amendment - Technical Specification 3.3.1.2, Source Range Monitor Instrumentation
BSEP 07-0080, Request for License Amendment Re Technical Specification 3.3.1.2, Source Range Monitor (SRM) Instrumentation
05000324/LER-2007-001, For Brunswick, Unit 2, Regarding Operation Prohibited by Technical Specification 3.3.1.2, Source Range Monitor Instrumentation
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
05000249/LER-2004-004, Re Unit 3, Shutdown Due to Inoperable Source Range Monitor
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
05000387/LER-1998-017, :on 981103,incomplete Channel Functional Test of SRM Channels Occurred.Caused by Lack of Having Indication Portion of SRM Channels as Part of Acceptance Criteria for Channel.Srm Channel Completed.With
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update
05000461/LER-2021-002-02, Core Alterations with Source Range Monitor Inoperable Results in Condition Prohibited by Technical Specifications
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