RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
ONS-2017-019, Technical Specification Bases Change 2015-09
RA-16-0028, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers
LR-N16-0003, License Amendment Request to Amend the Accident Monitoring Instrumentation Technical Specifications
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change
NL-16-0630, Resubmittal of Clean-Typed Pages for Multiple Technical Specifications Task Force Traveler Adoption
HNP-16-029, Response to Request for Additional Information Regarding License Amendment Request for Main Steam Safety Valve Lift Setting Tolerance Change
NL-15-094, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements
ONS-2014-064, Technical Specification (TS) Bases Change
AEP-NRC-2014-24, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits
LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual
NL-13-001, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements
PNP 2012-097, Report to NRC of Changes to Technical Specifications Bases
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-15-014, Indian Point, Unit 3 - Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
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-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
PLA-6076, Proposed License Amendment No. 285 for Unit 1 and Proposed License Amendment No. 253 for Unit 2, Extended Power Uprate Application - Supplement
L-07-010, License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion, Draft Amendment and Safety Evaluation Comments
ULNRC-05315, Application for License Amendment to Revise Technical Specification 5.6.6; Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions
05000255/LER-1989-017, :on 890721,discovered That Portion of Test Procedure Required Three Containment Air Cooler Fans Be Secured.Caused by Inadequate Procedural Review.Test Performance Immediately Suspended
ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ND-18-1005, Request for License Amendment: Technical Specification Changes for Physics Tests Exceptions and Nomenclature (LAR-18-020)
PLA-4055, Forwards Proposed Amend 117 to License NPF-22 Re Power Uprate W/Increased Flow
L-PI-03-042, Supplement to License Amendment Request (LAR) Dated 03/25/2003, Safety Analyses Transition
NL-03-1140, Changes to Technical Specification Bases
NRC 2002-0051, License Amendment Request 228, Technical Specifications LCO 3.1.8 Physics Tests Exceptions - Mode 2
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12
2CAN069804, Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves
3F1097-14, Forwards Rev 1 to Pressure/Temp Limits Rept, Per Requirements of TS 5.6.2.19.Rept Revised to Provide Consistency W/Normal & Emergency Plant Operating Procedures. TR BAW-2241P Has Been Submitted for Review.Commitments,Encl
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
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
GO2-86-643, Application for Amend to License NPF-21,changing Safety/ Relief Valve Setpoint Capabilities from +/-1% to +1%/-3% Based on GE Reanalysis Using Odyn Code.List of Justifications Encl.Fee Paid
2CAN129804, Forwards Corrected TS Page to 980629 Application for Amend to License NPF-6.Amend Request Corrections Were Determined to Be Necessary,Per Subsequent Conversations with Staff & Listed
CEO-89-196, Responds to NRC Re Violations Noted in Insp 50-312/89-01.Corrective Actions:Temporary Piping Removed Under Work Request 154927 on 890303,prior to Leaving Cold Shutdown on Mar 7
2CAN069206, Requests Deferral of 911220 Application for Amend to License NPF-6,changing TS 3.4.2 Re Mode 4 Overpressure Protection Until NRC Approves Low Power Overprotection Spec
U-602499, Application for Amend to License NPF-62,requesting Proposed Change to TS 3.4.2, Flow Control Valves, to Delete Requirement to Verify Average Rate of Movement of Each Reactor Recirculation Sys
PLA-2122, Monthly Operating Rept for Feb 1984
2CAN079004, Application for Amend to License NPF-6,modifying Tech Spec 3.4.2 to Clarify That Requirement Met During Mode 5 W/ Equivalent RCS Pressure Relief Capabilities
PLA-4428, Forwards Application for Amends to Licenses NPF-14 & NPF-22, Revising TSs Re HPCI Pump Automatic Transfer to Suppression Pool Logic Elimination
CNL-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28)
NOC-AE-030014, Proposed Change to Loss of Power and AC Sources Technical Specifications
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat
05000324/LER-1997-004, :on 971003,results Identified That Five of Eleven Valves Were Found to Lift at Pressures Outside TS Limits.Caused by Oxide Accumulation on Pilot Disc Seat. Replaced SRV Pilot Valve Assemblies
05000352/LER-1989-036, :on 890525,pressure Setpoint Testing of 14 Reactor Main Steam Sys Target Rock Corp Pilot Operated two- Stage Safety Relief Valves Revealed That Only One Valve Lifted within Tech Specs Limit
05000352/LER-1987-034, :on 870715,four Safety Relief Valves Discovered 3% Over Setpoint Drift.Caused by Corrosion Bonding Between Stellite Pilot Valve,Seat & Labyrinth Seal Clearance Restriction.Valves Replaced & Refurbished
05000353/LER-1999-004-02, :on 990701,determined That Thirteen MSRVs Failed to Meet 1% Setpoint Tolerance Due to Setpoint Drift.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.All Fourteen Srvs Pilot Valves Were Replaced
05000395/LER-1987-005, :on 870331,all Three Pressurizer Safety Valve Setpoints Tested Outside of Psig Tech Spec Limit.Caused by Differences in Test Methods to Measure Setpoints.Setpoints Verified & in Situ Testing of Valves Performed
05000325/LER-1987-011-01, :on 870323,safety Relief Valve SRV F013H Would Not Lift at Test Pressure & SRV F013C,E,F,G,J,K & L Lifted at Pressure Above Plus/Minus 1% Tolerance Allowed by Tech Specs.Caused by Corrosion Bonding
05000324/LER-1997-004-02, :on 971003,safety Relief Valves Exceeded TS Setpoint Limits,Was Identified.Caused by Formation of Oxide Bond Between Pilot Seat & Disc.Valves Will Be Disassembled & Inspected During First Quarter 1998
05000324/LER-1986-001, :on 860107,discovered That 10 of 11 Safety Relief Valves Tested Exhibited Symptoms of higher-than- Allowed Setpoint Drift.Caused by Pilot disc-to-seat Sticking & High Friction.Maint Program Revised
05000324/LER-1988-005-02, :on 880204,safety Relief Valves Setpoints Exceeded During Testing at Wyle Labs.Caused by Corrosion Induced Bonding of Pilot Valve Disc to Seat Surface.Valves Refurbished.Maint Personnel Counseled
05000324/LER-1986-001-01, :on 860107,testing of Safety Relief Valves Revealed That 10 Valves Exhibited Symptoms of Setpoint Drift.Caused by High Friction in Labyrinth Seal Area.Valves Refurbished & Recertified.Discs Replaced
05000338/LER-1997-002-02, :on 970515,set Pressure for One MSSV Was Found Outside Setpoint Tolerance Due to Setpoint Variance.Mssv That Failed Was Disassembled,Inspected,Repaired,Reassembled & Tested Satisfactorily
05000353/LER-1997-003-02, :on 970429,several Main Steam Sys Relief Valves Had Setpoint Drifts Due to Corrosion Induced Bonding Between Pilot Disc & Seat.Licensee Is Participating in BWROG Setpoint Drift Committee
05000325/LER-1985-033, :on 850520,testing Revealed That 9 of 11 Safety Relief Valves Actuated at Higher than Allowed Setpoints. Caused by Friction in Valve Labyrinth Seal Guide Areas. Valves Refurbished,Recertified & Reinstalled
05000338/LER-1993-002, :on 930120,as-found Set Pressures for One Pressurizer Safety Valve & Two MSSVs Found Outside TS Setpoint Tolerances.Caused by Setpoint Drift.Valves Will Be Refurbished at Wyle Labs
05000352/LER-1992-016, :on 920828,during Pressure Setpoint Testing of 14 Reactor Main Steam Sys Target Rock pilot-operated Valves, Only Two Valves Lifted within TS Limit.Caused by Corrosion Induced Bonding.Switch Options Reviewed
05000353/LER-1992-010-02, :on 920828,main Steam Safety Valves Setpoint Drifted Due to Corrosion Induced Bonding within Valves. Affected SRVs Removed for Setpoint Testing.Srv Setpoint Drift Pending Conclusion of Ongoing Testing
05000352/LER-1996-009-01, :on 960422,main Steam System Safety Relief Valve Setpoint Drift Occurred.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.Installed Special Modified Pilot Disc in Several SRVs
05000338/LER-1996-001-01, :on 960216,MS & Pressurizer SV Setpoints Out of Tolerance Due to Setpoint Drift.Adjusted Pressurizer SVs 01-RC-SV-1551A & 01-RC-SV-1551C
05000339/LER-1992-003-02, :on 920306,as-found Set Pressures for Three Pressurizer Safety Valves & 8 of 15 MSSV Found Outside of TS Setpoint Tolerances.Caused by Setpoint Drift.Pressurizer Loop Seal Modified & Setpoint May Be Increased
05000338/LER-1992-002-01, :on 920110, as Found Set Pressure for a Pressurizer Safety Valve Found Outside Setpoint Tolerence Due to Setpoint Drift.Safetyvalves Will Be Repaired & Readjusted as Necessary
05000461/LER-1995-006, :on 950801,lack of Appropriate Post Maint Testing Due to Personnel Errors Resulted in Inoperable Reactor Recirculation Flow Control Valve.Replaced Components Removed During Maint Work
05000339/LER-1995-001-03, :on 950403,MS & Pressurizer Safety Valve Setpoints Out of Tolerance Due to Setpoint Drift. Refurbished & Retested Safety Valves to within Allowable Limits of TS at Wyle Labs
05000346/LER-1983-072-03, /03L-0:on 831217,120-volt Ac Essential Bus Y1, Reactor Protection Sys Channel 1 & Safety Features Actuation Sys Channel 1 Deenergized.Caused by Personnel Error. Personnel Counseled
05000289/LER-1983-026-01, /01T-0:on 830919,while Testing Main Steam Safety Valves,All Valves Except One Lifted Above Allowed Lift Setpoint Tolerance of +1%.Caused by Personnel Error Which Resulted in Defective Procedure
05000352/LER-1991-015-01, :on 910528,pressure Setpoint Drift of Main Steam Sys Safety Relief Valves Occurred.Caused by Corrosion Induced Bonding.Two Parallel Paths Being Taken,One Involves Design,Testing & Implementation of Hydrogen
05000287/LER-1983-006-03, /03L-0:on 830513,during Attempt to Replace Cell in Battery 3PB,power Lost from Emergency Feedwater Pump Turbine Auxiliary Oil Pump.Caused by Personnel Failure to Follow Procedure.Personnel Counseled
05000338/LER-1991-002, :on 910125,two Pressurizer Safety Valves & 7 of 15 Main Steam Safety Valves Foud Outside Setpoint Tolerances Allowed by Tech Specs.Caused by Setpoint Drift.Safety Valves Repaired & Readjusted
05000339/LER-1990-005-02, :on 901005,pressurizer & Main Steam Safety Valve Setpoints Found Out of Tolerance Due to Setpoint Drift
05000373/LER-1993-019-03, :on 931204,TS Surveillance Missed Due to Inoperability of SRVs 1B21-F013B & 1B21-F013J.Caused by Misinterpretation of TS Requirements.Correct ASME XI Section Determined & Procedures Revised
05000373/LER-1993-002-04, :on 930126,Unit 1 Manual Scram Due to a SRV Being Stuck Open Due to Duct Tape Being Over Actuators Air Valve Manifold Exhaust Port.Maint Procedures That Involve Cleanliness Reviewed
AECM-90-0089, Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant
05000324/LER-1981-076-01, /01T-0:on 810804,following Reactor Scram,Safety Relief Valve 2-B21-F013B,Model 67,failed to Manually Close After Being Manually Opened.Cause Unknown.Pilot Valve F013B Replaced
05000325/LER-1981-001-01, /01T-0:on 810103,feed Pump Tripped on High Vessel Level Due to safety-relief Valve B21-F013G,Model 67F,lift. Caused by High Second Stage & Pilot Leakage in Valve.Pilot Valve Temporarily Replaced Until Next Scheduled Outage
05000324/LER-1980-070-03, /03L-0:on 800910,during Performance of Automatic Depressurization Sys (ADS) Valve Test,Ads Valve 2-B21-F013E Did Not Actuate.Caused by Broken Valve Actuator Solenoid Coil Wire.Coil Replaced
CP-201101065, Comanche Peak Units 1 & 2 Final Safety Analysis Report (Fsar), Amendment 104, Technical Specifications Bases
05000289/LER-1979-009-03, /03L-0 on 790410:during Surveillance Testing on turbine-driven Emergency Feedpump,Steam Regulating Valve Found Closed.Caused by Maint Procedure Not Specifying Opening of Valve
3F1089-23, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 174 Re Proposed Heatup,Cooldown & Inservice Leak & Hydrostatic Testing Pressure/Temp Limits. Rept Re Low Temp Overpressure Protection Withheld
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
RAIO-0119-64281, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
05000255/LER-2088-005-01, Inadequate Procedure Results in Valve Testing During Prohibited Conditions
LR-N18-0065, Safety Relief Valve (SRV) As-Found Setpoint Failure
05000255/LER-1990-015, :on 900706,inservice Test Not Run & Appropriate Pump Performance Values Not Reconfirmed within 7 Day Limiting Condition of Operation Period of Tech Spec 3.4.2. Caused by Personnel Error
05000255/LER-1988-005, :on 880304,stroking of Svc Water Containment Isolation Valves Occurred During Prohibited Conditions. Caused by Procedural Deficiencies.Administrative Procedure 9.21 Revised & Tech Spec Tests Reviewed
05000255/LER-1979-038-03, /03L-0:on 790829,pump Discharge Valve Failed to Open During Attempt to Operate Svc Water Pump P-7C.Caused by Corrosion of Valve Hinge Pins.Repairs and Futher Insp Planned
05000529/LER-1990-004, :on 900504,discovered That Pressurizer Code Safety Valves as-found Setpoints Out of Tolerance.Caused by Performance Limitation of Pressurizer Safety Valves.Valves Adjusted & Retested Satisfactorily
GO2-91-215, Application for Amend to License NPF-21,changing TS 3.4.2 Re Safety Relief Valves & Table 3.3.7.5-1 Re Accident Monitoring Instrumentation to Permit Acoustic Monitor to Be Inoperable Until Plant Shuts Down for Next Outage
GO2-84-212, Confirms Info Provided in 840410 Telcon W/R Auluck,F Churney & R Li Re Listed Facility Sys Having High Pressure/Low Pressure Interface Features.Info Provided to Expedite Review of 840120 Request to Amend Tech Spec 3.4.2
GO2-90-025, Application for Amend to License NPF-21,changing Tech Spec 3.4.2 Re Safety Relief Valve & Tables 3.3.7.5-1 & 4.3.7.5.-1 Re Accident Monitoring Instrumentation to Permit Acoustic Monitor to Be Inoperable Until Next Shutdown
GO2-90-038, Application for Amend to License NPF-21,revising Tech Spec 3.4.2, Safety Relief Valves & Tables 3.3.7.5-1 & 4.3.7.5-1, Accident Monitoring Instrumentation, to Allow Monitor on Safety Valves to Be Inoperable Until Shutdown
GO2-92-032, Responds to Licensee Ltr Re Performance of Acoustic Monitors Used on Facility for Safety Relief Valve Position Indication
05000244/LER-1996-001, :on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled
GO2-94-247, Application for Amend to License NPF-21,revising TSs to Relocate Safety/Relief Valve Position Indication Instrumentation Requirements
05000244/LER-1987-006, :on 871130,standby Auxiliary Feedwater Pump 1D Deemed Inoperable Beyond Tech Spec Limit.Caused by Cooling Unit 1B Ac Electrical Breaker Found in Off Position Due to Unaware Operator.Breaker Turned to on Position
L-17-223, Application to Revise Technical Specifications to Adopt TSTF-547-A, Revision 1, Clarification of Rod Position Requirements
RS-16-008, Response to NRC Regulatory Issue Summary 2015-16, Revision 1, Planned Licensing Action Submittals for All Power Reactor Licensees
05000206/LER-1989-033, :on 900131,discovered That RCS Sample for Gross Activity Determination Not Taken Prior to Entry Into Mode 4 on 890624.Caused by Failure to Incorporate New Chemistry Procedure.Procedures Revised & Incorporated
ONS-2015-033, Technical Specification (TS) Bases Change
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
L-96-003, License Amendment Request: Adoption of GL 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits and TSTF-419-A, Rev. 0, Revise PTLR Definition
TSTF-04-04, TSTF-467, Revision 0, Add Restriction for Lowest Loop T(Ave) During Mode 2 Physics Testing
ULNRC-04742, Revision to Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
ET 02-0033, Revision to Technical Specification 3.1.6, Physics Tests Exceptions - Mode 2
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RAIO-0917-56153, LLC Response to NRC Request for Additional Information No. 156 (Erai No. 9031) on the NuScale Design Certification Application
05000255/LER-2077-046, To Replace Improper Terminology Seal Bladder with Term Seal Ring, LER 1977-046-00 & LER 1977-048-00 Re Service Water Pump Check Valve Failure
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
AEP-NRC-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
05000325/LER-1998-003-02, :on 980515,identified That Four of Eleven SRVs Exceeded TS Setpoint Limits.Cause of Setpoint Drift Being Evaluated.Srv Pilot Valve Assemblies Replaced W/Certified Spares Prior to Startup of Unit 1
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
05000328/LER-1988-016-01, :on 880402,found That Three Relief Valves Exceeded Tech Spec Lift Setting.Caused by Using Different Methodologies to Determine Valve Lift Setting Between Bench & Inservice Tests.Consistent Method to Be Used
GO2-96-132, Requests Amend to Ts,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of Nhsc or Environ Assessment Provided in Rev a
05000352/LER-1995-009-01, :on 951113,pressure Setpoint Drift of Ms Sys Safety Relief Valves Occurred.Caused by Corrosion Induced Bonding Between Pilot Disc Seating Surfaces.Several Modified SRV Pilot Discs Installed
05000324/LER-1983-019-01, /01T-0:on 830210,while Performing Drywell Insp, Instrument Air Tubing to Safety Relief & ADS Valve Accumulators Inadequately Supported.Caused by Inadequate Controls to Ensure Support Design Compliance
05000352/LER-1996-009, :on 960314,five of Six as-found Setpoint Tests on Main Steam Sys SRVs Found Outside Required Pressure Ranges.Caused by Setpoint Drift Due to Corrosion Induced Bonding.Modified Pilot Disc Installed in SRVs
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years