05000263/LER-2011-011, Regarding Failure to Lock Mode Switch in Refuel Position During Control Rod Exercise
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
PLA-4565, Forwards Request for Amend to ITS Approving Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315
L-MT-15-088, Technical Requirements Manual, Technical Specification Bases, Affected Pages, Revision 39
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
LR-N15-0080, Supplement to License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)
LR-N14-0185, License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)
CNS-14-079, Technical Specification Bases Changes
0CAN021403, Units 1 and 2 - 10 CFR 50.59 Summary Report and Commitment Change Summary Report
GO2-13-138, License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360
NUREG-1432, Request for Additional Information, Round 3, Request to Revise Technical Specifications to Eliminate Use of the Term Core Alteration Consistent w/TSTF-471 and NUREG-1432, Rev. 3 (TAC ME8160-ME8162)
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
2CAN071201, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
LR-N12-0107, License Amendment Request - APRM Operability Requirements in Opcon 5
2CAN041201, License Amendment Request, Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
NG-12-0034, Supplemental Information to an Application to Adopt Technical Specifications Task Force Traveler TSTF-425, Revision 3, to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 8 of 9
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 3 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
RS-12-221, Braidwood, Units 1 and 2 and Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 15.0 - Accident Analyses
RS-11-159, Quad Cities, Units 1 and 2 - Technical Specification Bases
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
LR-N10-0355, Attachment 1 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Strike-out Version)
NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NOC-AE-10002554, Technical Specification Bases Control Program (Section 6.8.3.m)
ULNRC-05682, Application for Amendment, Revision of Technical Specification 3.3.9
L-10-046, Withdrawal of a License Amendment Request to Exclude the Source Range Neutron Flux Instrument Channel Preamplifier from the TS Channel Calibration Requirements
L-09-294, Response to a Request for Additional Information Related to a License Amendment Request to Exclude the Source Range Neutron Flux Instrument Channel Preamplifier from the Channel Calibration Requirements of Tech Specs (TS) 3.3.9 & TS 3.9.2
LR-N09-0193, License Amendment Request to Adopt TSFT-475, Revision 1, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
ULNRC-05633, Revision of Technical Specification 3.3.9
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
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
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis
NL-07-1709, Technical Specifications Revision Request to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process
ULNRC-05366, Correction for Previously Submitted Letters with Improper Unsworn Declarations for Satisfying Oath or Affirmation Requirements (Based on Regulatory Issue Summary 2001-18)
NRC 2006-0040, License Amendment Request 246 - Deletion of Core Alterations
1CAN080601, License Amendment Request Regarding the Relocation of Inverter Y-28 and Panel C-540 Requirements from TSs to TRM
ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
LR-N19-0047, License Amendment Request to Relocate Technical Specifications (TS) 3.9.3 and 3.9.12 to the Technical Requirements Manual (TRM)
2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432
LR-N05-0220, Request for Change to Technical Specifications Refueling Operations and Special Test Exceptions
NLS2005061, Letter to Provide Changes to Plant Technical Specification Bases Implemented Without NRC Approval
05000346/LER-1980-029-03, /03L-0:on 800419,breaker HBBF2 on Bus B Opened, Allowing Two Buses to de-energize.Caused by Ground Fault Relay Actuated from Mechanical Vibration & Electrical Lineup for Maint.Decay Heat Pump Was Vented & Restarted
WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
LR-N15-0224, Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)
NL-03-1140, Changes to Technical Specification Bases
NG-03-0272, March 2003 Monthly Operating Report for Duane Arnold Energy Center
GO2-02-173, License Amendment Request - Technical Specification Change to Section 5.0, Administrative Controls
W3F1-2002-0095, License Amendment Request NPF-38-243 Reactivity/Boron Concentration Changes
NRC-02-0043, Proposed Technical Specification Change (License Amendment) - Refueling Equipment Interlocks
ULNRC-04721, Technical Specification Bases Revision 3
HL-6190, Request to Revise Technical Specifications: Change to Intermediate Range Monitor Limiting Condition for Operation
RA-20-0012, License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
1CAN030201, License Amendment Request Re Proposed Change to Support Implementation of ANO-1 Improved Technical Specifications
RA-20-0178, Supplement to License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices
U-601430, Responds to NRC Re Violations Noted in Insp Rept 50-461/89-020.Corrective Actions:Procedure 8117.05 Revised to Address Area Radiation Monitor Interlock on Polar Crane & to Include Actions to Be Taken in Event of Alarm
0CAN089801, Revises 961219 Submittal to Incorporate New Control Room Duct Radiation Monitor.Util Requests That Effective Date for Change Be within 30 Days of NRC Approval
NSD-NRC-96-4833, Forwards Roadmap for Content of AP600 Tech Specs Vs NUREG-1431 & Description of General or Overall Changes Whose Explanations Apply to Multiple TS
3F0885-08, Responds to Violations Noted in Insp Rept 50-302/85-27. Corrective Actions:Fuel Movement Suspended Until Restoration of Audible Control Room Indication.Vol Control Knob Readjusted & Procedure Revised
BSEP-96-0414, Application for Amends to Licenses DPR-71 & DPR-62,revising TSs to Format Consistent w/NUREG-1433,rev 1.Vols 1-15 of Improved TSs Encl
RS-21-006, Application to Incorporate Licensing Topical Report NEDE-33885P-A, Revision 1, GNF CRDA Application Methodology
2CAN112104, Response to Request for Additional Information 2 Related to License Amendment Request to Adopt a Safety Function Determination Program (SFDP)
0CAN129603, Submits Proposed TS Change Request Re Control Room Ventilation Sys
3F0985-10, Forwards Supplemental Response to Violations Noted in Insp Rept 50-302/85-29.Corrective actions:short-term Instruction Issued W/Applicable Offsite Dose Calculation Manual Requirements & SP-220 Performed Satisfactorily
ET-NRC-93-3795, Forwards Responses to NRC RAIs on AP600 from Ltrs 920923, 1001 & 09.Remainder of RAIs Contained in NRC Ltrs of 920923 & 1001 Will Be Provided Prior to 930123
U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling
HL-5115, Ei Hatch Nuclear Plant - Units 1 & 2 Annual Operating Rept 1995
AECM-84-0282, Responds to NRC Re Violations Noted in Insp Rept 50-416/84-11.Corrective Actions:Tech Spec Review Program Implemented to Certify Accurate Reflection of Plant,Fsar & SER Analyses
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
0CAN049501, Application for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys
ST-HL-AE-4926, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3.9.2 to Permit Substitution of Extended Range Neutron Flux Monitor for One Source Range Neutron Flux Monitor During Refueling Operations
NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)
AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation
NRC-94-4181, Submits Responses to NRC Requests for Addl Info Re AP600
PY-CEI-NRR-2155, Application for Amend to License NPF-58,revising TS Surveillance Requirements 3.9.1.1 & 3.9.2.2,extending SR Frequency on Refueling Equipment & one-rod-out Interlocks
NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)
TSTF-04-10, TSTF-476, Revision 0, Improved BPWS Control Rod Insertion Process (NEDO-33091)
CP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel
05000327/LER-1980-016-03, /03L-0:on 800307,at Completion of Fuel Loading & W/Core Alterations Still underway,SI-65 Was Not Performed. Caused by Misinterpretation of Tech Specs by Personnel.No Corrective Actions Necessary
ST-HL-AE-4923, Application for Amends to Licenses NPF-76 & NPF-80,revising TS 3.9.4,permitting Personnel Airlock Doors to Be Open While Moving Fuel During Refueling Operations
NL-03-1563, TS Revision to Allow Fuel Movement with Refueling Interlock Inoperable
GNRO-2019/00003, Application to Revise Technical Specification (TS) 3.3.1.1, Reactor Protection System (RPS) Instrumentation, and TS 3.3.4.1, End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8
05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement
05200025/LER-2022-003, Unborated Water Flowpath Not Secured Per Technical Specification 3.9.2 Due to Inadequate Procedure Change
05000368/LER-2021-001, Non-Compliance with Technical Specifications Resulting in Lack of Nuclear Instrumentation Audible Indication
NL-24-0217, License Amendment Request: Source Range Neutron Flux Doubling Function Applicability
05000313/LER-2024-001, Source Range Nuclear Instrument Failure Resulting in Condition Prohibited by Technical Specifications
ND-22-0831, Comments on AP1000 Standard Technical Specifications (STS) – Draft NUREG-2194, Revision 1
05000250/LER-2020-005-01, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1)
CP-200800057, Supplement to License Amendment Request (LAR) 07-004, Revision to the Operating License and Technical Specification 1.0, Use and Application to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt
05000440/LER-1989-007, :on 890227,source-range Monitor Signal/Noise Ratio Not Verified Prior to Entering Operation Condition 5. Caused by Personnel Error.Personnel Counseled & Note Added to Tech Spec Rounds to Clarify Applicability Requirements
05000313/LER-1987-008, :on 871119,leakage Pathway for Unfiltered Air Identified in Control Room Emergency Ventilation Sys.Caused by Inadequate Design & Review of Mod to Sys in Mar 1977. Opening Sealed
05000302/LER-1987-023, :on 870930,Mode 6 Entered Before Neutron Flux Monitor Audible Indication in Control Room & Containment re-energized as Required by Tech Specs.Caused by Defective Procedures.Procedures Revised
05000461/LER-1989-007, :on 890122,incorrect Operability Determination Due to Insufficient Review of Source Range Monitor Status Results in Core Alterations W/O Required Two Operable Source Range Monitors.Shift Supervisor Counselled
05000366/LER-1998-004-01, :on 981005,noted That full-in Position Indicating Light Did Not Extinguish as Expected When CR 38-15 Was Withdrawn.Caused by Personnel Error.Jumper Was Removed from RPIS Circuit Card for Rod 38-15
05000446/LER-1997-003-01, :on 971108,core Alterations Were Performed Before Completing All Prerequisites.Caused by Inadequate Compliance of Ts.Core Off Load Was Suspended & All Prerequistes of Core Off Load Was Completed
05000373/LER-1986-016-02, :on 860425,fuel Bundle Loaded Into Core W/O Operable source-range Monitor in Corresponding Core Quadrant.Caused by Breakdown in Communications.Personnel Trained.Speaker Phones Installed
05000366/LER-1998-004-04, :on 981005,condition Prohibited by TS Was Noted.Caused by Personnel Error.Coached Involved Personnel & Briefed Other Technicians on Event.With
05000338/LER-1997-003-01, :on 970516,positive Reactivity Addition During Refueling Was Determined.Caused by Personnel Error.Control Room Crews Were Coached on Positive Reactivity Effect of Filling Cavity from R ST When RCS Is Greater
05000353/LER-1997-001-02, :on 970207,condition Prohibited by TS in That Control Rods Were Removed from Core W/Source Range Monitors Were Inoperable.Caused by Personnel Error.Will Revise pre-outage Training for Affected Personnel
05000295/LER-1985-031-04, :on 850814,penetration Pressurization Low Pressure Alarm Received & Zone 4 Pressure Observed Below Required 47 Psig.Caused by Leaking Weld Channels & Relief Valve.Channels Isolated & Valve Repaired
05000341/LER-1985-009, :on 850426,CRD Friction Testing Performed W/O Reactor Protection Sys Shorting Links Being Removed,Per Tech Specs.Shorting Links Removed & Testing Continued.Tech Spec Change Will Be Requested
05000369/LER-1985-014-01, :on 850507,core Alterations Started W/O Completion of Required Surveillance on Source Range Neutron Flux Monitors While in Mode 6.Caused by Administrative/ Procedural Deficiency.New Procedure Planned
05000295/LER-1992-022-02, :on 921204,multiple Svc Water Leaks Developed in Pressurizer Penetration.On 921207,air Compressor Aftercooler Drain Valve Found Throttled Open Two Turns.Cause Not Determined.Cr Drawings Enhanced
05000461/LER-1996-005, :on 960411,failure to Follow Procedures During Completion of one-rod-out Interlock Test Results in Reactor Mode Switch Not Locked in Refuel During Control Rod Exercising as Required by TS
05000454/LER-1984-020, :on 841125 & 28,source Range Channel N32 Indicated Noise Spikes on Four Occasions,Resulting in Containment Evacuation Alarms.Cause Under Investigation. Source Range Channel Modified
05000362/LER-1992-002-01, :on 920219,determined That Source Range Neutron Flux Monitor Was Not Providing Audible Indication,Per TS 3.9.2.Caused by Audible Count Rate Booster Amplifer Being in Off Position.Subj Amplifer re-energized
05000354/LER-1995-035, :on 951120,failed to Lock Reactor Mode Switch in Opcon 5,missed SRM Surveillance & Missed Suppression Chamber Level Surveillance Due to Inadequate Procedures. Revised Procedures
05000443/LER-1991-001-01, :on 910810,source Range Neutron Flux Audible Monitors Discovered Inoperable.Caused by Personnel Error. Request for Engineering Svcs Initiated to Evaluate Feasibility of Design Change
05000250/LER-1983-014-03, /03L-0:on 830816,while Sampling Gas Contents from Vol Control Tank,Unplanned Release Occurred in Auxiliary Bldg & Atmosphere Via Plant Vent.Caused by Insufficient Instructions on Valve lineup.w/830915 Ltr
05000457/LER-1994-008-10, :on 941111,failure to Open Breakers During Digital Rod Position Indication Occurred.Caused by Combination of Personnel Errors & Programmatic Deficiency. Personnel Involved Counselled
05000327/LER-1982-131-03, /03L-0:on 821109,during Mode 6,nuclear Instrumentation Sys Source Range Detector N-32 Declared Inoperable Due to Spiking.Caused by Heat Gun Used in Work on Penetration Junction Boxes.Penetration Work Suspended
05000483/LER-1990-012, :on 901003,Tech Spec 3.9.2 Violation Occurred Due to Performance of Core Alteration When Source Range Nuclear Instrument Inoperable Due to Personnel Error. W/
05000455/LER-1993-006-08, :on 930924,identified That Surveillance for Source Range Instrumentation Missed Due to Incorrect Computer Status Update.Changes Made to Update Process.W/
A09702, Provides Response to Allegation RI-91-A-0077 Re Wiring Diagram for HPSI Pumps B & C Common Discharge Header Isolation Valve Found Not to Reflect Actual Plant Conditions.Related Info Encl
05000302/LER-1981-070-03, /03L-0:on 811013,during Refueling Surveillance, Source Range Neutron Flux Monitoring Requirements Not Met on 811031,14 & 27.Caused by Instrument Drift & Grounded Cable. Instruments Recalibr & Cable Replaced
05000250/LER-1983-013-03, /03L-0:on 830802,unplanned Gas Release Occurred from Vol Tank to Auxiliary Bldg & Atmosphere.Caused by Improper Valve Lineups.Vol Control Tank Isolated from Gas Analyzer
05000424/LER-1990-004-01, :on 900301,failure to Comply W/Tech Spec 3.0.4 Occurred on Entry Into Mode 6.Caused by Cognitive Personnel Error.Util Complied W/Action Requirements for Tech Spec 3.9.2
05000346/LER-1990-003, :on 900212,station Entered Mode 6,refueling,w/o Operable Audible Source Range Indication.Caused by Personnel Error.Individual Counseled
05000315/LER-1981-018-03, /03L-0:on 810609,source Range Detector Experienced Loss of Voltage When Crid 2 Was Switched from Alternative to Normal Supply.Caused by Momentary Loss of Ac to Drawer. Fuses Removed & Reinstalled
05000369/LER-1981-005-03, /03L-0:on 810202,power Supply to Both Excore Range Monitors Was Interrupted.Caused by Maint Personnel Cutting Off Power to Investigate Steam Generator Status Lights & lo-lo Level Alarms.Personnel Instructed
3F0190-03, Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedure FP-203 Re Refueling & Defueling Operations Revised to Address Concerns in NRC Info Notice 89-051
05000400/LER-2019-003, Both Source Range Nuclear Instruments Inoperable
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
LR-N10-0355, Attachment 2 to LR-N10-0355, Hope Creek Generating Station, Emergency Action Level Technical Bases Document (Clean Version)
AEP-NRC-2024-11, Unit 2 - Response to Request for Additional Information on Requested Change Regarding Neutron Flux Instrumentation
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
05000346/LER-1980-054-03, /03L-0:on 800627,NI-1 Output Failed to Zero During Fuel Assembly Movement.Assembly Removed & Put in Support Rack.Cause Unknown But May Be Intermittent Grounding Problem or Component Failure.Ground Problems Under Investigatio
05000346/LER-1980-045-03, /03L-0:on 800609,while Preparing to Perform ST 5091.01,NI-2 Found Partially Disconnected from Equipment in Control Room.Apparently Caused by Personnel Error.Info Tags Hung on Coax Cables to Insure Proper Connection
05000346/LER-1980-041-03, /03L-0:on 800511,during Performance of ST 5091.01 Source Range Functional Test,Source Range Channel 1 Found Out of Tolerance & Declared Inoperable.Caused by Component Failure in Test Module.New Module Installed
05000327/LER-1980-036-03, /03L-0:on 800413,when Source Range N-31 Was Removed from Svc,Action Statement LCO 3.9.2 Was Initiated Due to Only One Source Range Channel Being in Svc.Caused by Need to Inspect for Possible Water Damage
05000327/LER-1980-005-03, /03L-0:on 800311,while Performing SI-247.605, Reactor Solid State Protection Sys Was Placed in Input Inhibit Mode,Removing High Voltage from Source Range Channel N31.Caused by Removal of Fuses from Voltage Cut Out Relay
05000530/LER-2024-003, Violation of Technical Specifications 3.9.2 and 3.3.12
05000302/LER-1979-049-03, /03L-0 on 790509:count-rate Amplifier & Rate of Change Amplifier for Nuclear Source Range Instrument NI-1 Were Inoperable.Caused by Amplifiers Being Out of Tolerance Due to Instrument Drift.Amplifiers Recalibr
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000302/LER-1979-050-03, /03L-0 on 790510:count-rate Amplifier & Rate of Change Amplifier for Nuclear Source Range Instrument NI-2 Found Inoperable.Caused by Amplifiers Being Out of Tolerance Due to Instrument Drift.Amplifiers Recalbr & Returned to
05000260/LER-1999-002-02, :on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With
05000250/LER-1992-011-01, :on 921008,Unit 3 Source Range Neutron Detector N-31 Declared Out of Svc.Caused by Lack of Design Info/Plant Procedures Which Dictate Proper Gasket Matl.Source Range Neutron Detectors N-31 & N-32 Replaced
05000244/LER-1997-006, :on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
05000335/LER-1996-005-01, :on 960514,wide Range Nuclear Instrumentation Channel Rendered Inoperable When Required to Be in Svc for Fuel Movement.Caused by Personnel Error.Applicable Personnel Counseled & Surveillance Procedure Revised
05000335/LER-1996-006-01, :on 960601,loss of Containment Audible Count Rate Indication Occurred.Caused by Procedural Inadequacy. Revised Electrical Bus Removal Procedure & Revised Plant Breaker List & Circuitry Drawing
L-80-152, Responds to NRC Re Violations Noted in IE Insp Rept 50-335/80-08.Corrective Actions:Interim Measures Taken to Supply Audible Flux Count to Refueling Area
05000461/LER-2015-003, Regarding Condition Prohibited by Technical Specification 3.9.4 for Failing to Disarm Control Rod Drive Prior to Fuel Moves in Modes 5 with One Control Rod Position Indication Channel Inoperable
05000305/LER-2012-003, For Kewaunee Power Station, Regarding Nuclear Instruments Inoperable for Longer Period than Allowed by Technical Specifications
05000321/LER-2012-001, Regarding Non-Compliance with Technical Specification 3.9.4 for Control Rod Position Indication During Shutdown
LR-N16-0093, License Amendment Request to Extend the Implementation Period for Salem, Unit 1 License Amendment No. 311 and Salem, Unit 2 License Amendment No. 292
ULNRC-05837, Regarding Inadvertent Non-Compliance with TS 3.9.2, Unborated Water Source Isolation Valves
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation
05000263/LER-2007-003, From Monticello Nuclear Generating Plant Re Failure to Enter a Required Technical Specification Action During Control Rod Drive Exercising
ULNRC-05345, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms)
ULNRC-05069, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves to Revise and Rename Specification 3.9.2 Dilution Source Isolation Valves and Associated Revision to Technical Specification 3.3.9 Boron
TSTF-04-07, TSTF-475, Revision 0, Control Rod Notch Testing Frequency and SRM Insert Control Rod Action
05000331/LER-2003-002, Inadequate Procedure Leads to Failure to Remove Key from Mode Switch When Locked in Refuel Position During Control Rod Movement as Required by Technical Specifications
ULNRC-04883, Proposed Revision to Technical Specification (TS) 3.9.2, Unborated Water Source Isolation Valves, to Revise & Rename Specification 3.9.2, Dilution Source Isolation Valves & Associated Revision to TS 3.3.9, Boron Dilution.
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
3F0506-05, 2005 Technical Specifications Bases Control Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
L-08-240, Improved Technical Specification Conversion License Amendment Request, Volume 14, Revision 1, ITS Section 3.9, Refueling Operations
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update
RA-20-0287, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protectiv
NL-02-160, Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, & 5.0 of Improved TS
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
05000245/LER-1981-031, Forwards LER 81-031/03L-0.Detailed Event Analysis Encl
2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471
05000313/LER-1996-003-02, :on 960313,charcoal Filter Sample Analysis Was Not Conducted in Accordance W/Literal Requirements of TS as Result of Misinterpretation of Requirements Necessary to Achieve Compliance W/Specs.Revised Procedures
05000341/LER-1994-006, :on 940903,discovered That SRMs & IRMs Inoperable During Core Alterations.Caused by Cable Connectors Becoming Separated Due to Stress.Procedure 82.000.04 Will Be Modified
CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
L-09-218, Submittal of Technical Specification Bases, Revision 7
L-25-160, Emergency License Amendment Request for Technical Specification 3.3.9 to Allow Use of Alternate Neutron Instrumentation