05000333/LER-2006-001, Inoperable Reactor Building-To-Suppression Chamber Vacuum Breaker in Excess of Technical Specifications Allowed Out of Service Time
L-2017-028, Submittal of Special Report of Containment Tendon Corrosion Protection Medium Volume Reduction
L-2017-060, License Amendment Request 249: Elimination of Certain Technical Specification Reporting Requirements, Revised Action for Emergency Core Cooling System, and Changes to Administrative Technical Specifications
L-2017-069, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3
GO2-15-108, Provides Affected Technical Specification Pages Supporting License Amendment Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-423, Revision 1, Using the Consolidated Line Item Improvement Process
GNRO-2014/00058, Letter GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update (ML12361A330)
RBG-47322, Submittal of Request for Amendment to the Technical Specifications
GNRO-2012/00096, License Amendment Request for Implementing a 24-Month Fuel Cycle, Grand Gulf Nuclear Station, Unit 1
NRC-12-0044, Response to Request for Additional Information Regarding Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves
L-2012-090, Special Report - Containment Tendon Corrosion Protection Medium Volume Reduction
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Technical Specification Bases
2CAN031006, Inservice Testing Plan for the Fourth 10-Year Interval
BSEP 08-0167, Response to Request for Additional Information Regarding Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers
NLS2007036, Technical Specification Bases Changes
RS-06-141, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
U-603781, Transmittal of Revision 10 to the Clinton Power Station Technical Specifications Bases
L-2020-003, License Amendment Request 268, Request to Extend Containment Leakage Rate Test Frequency
05000366/LER-1979-111-03, /03L-0:on 791009,drywell Pressure Exceeded 0.75 Psig Limit of Tech Spec 3.6.1.6.Caused by Personnel Error. Design Change Request Submitted to Change One Primary Containment hi-low Press Annunciator to Two Annunciators
TSTF-19-09, Technical Specifications Task Force - Transmittal of TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements
RS-02-175, Request for Technical Specification Changes Related to Main Steam Safety Valve Operability Requirements
05000498/LER-1998-001, Forwards LER 98-001-00 Re Failure to Perform an Adequate TS Surveillance Re Containment Structural Integrity.Licensee Commitments Are Found in CA Section
B12571, Responds to NRC Re Violations Noted in Insp Rept 50-245/87-05.Corrective Actions:Amend Request Submitted on 870428 Adding Eight Automatic Isolation Valves Used to Obtain Containment Atmosphere Samples
RBG-45077, Application for Amend to License NPF-47 to Change TS to Extend Operation of RBS from Current Licensed Power Level of 2894 Mwt to Uprated Power Level 3039 Mwt.Encl Proprietary GE Rept NEDC-32778P Withheld
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
BSEP-97-0533, Provides Addl Info Re small-break LOCA Analysis Discussion Contained within 970612 Lar,Proposing Changes to TS 3.6.1.6 to Require Monitoring Drywell Average Air Temp Rather than Primary Containment Average Air Temp
NOC-AE-000250, Special Rept:Discovered That Tendon Filler Grease Voids in Excess of SR Max of 5% of Net Duct Vol Existed.Caused by Shrinkage of Grease & Spaces Existing Between Wires in Tendon Wires.Installed Grease Throughout Tendon Ducts
NOC-AE-000304, Special Rept Re Evaluation of Units 1 & 2 Containment Tendon Conditions.Grease Voids Were in Excess of 5% in Two Tendons. Voids of 20% or Less Are Considered Reasonable.Containment Integrity Assured
SNRC-1464, Forwards Comments W/Supporting Documentation Re post-NRC Written Operator Exams,To Assist in Evaluating Responses to Exam Questions
HL-5230, Application for Amends to Licenses DPR-57 & NPF-5,revising SRs 3.1.7.7 & 3.4.3.1 & LCOs 3.4.3,3.5.1 & 3.6.1.6 to Increase Nominal Mechanical Pressure Relief Setpoints for All SRVs & Allow Operation W/One SRV
ST-HL-AE-4064, Special Rept:Discovered That Tendon Filler Grease Voids Exceeded Surveillance Requirement 4.6.1.6.1.d.2 Max of 5% Net Duct Vol.Caused by Spaces in Tendon Bubble.Adequate Grease Protection Exists for Tendons
ST-HL-AE-4037, Special Rept Re Evaluation of Unit 2 Third Yr Containment Tendon Surveillance.Refilling of Grease Accomplished Simultaneously W/Discoveries of Voids as Result of Insp Process Used
ELV-03200, Special Rept 1-91-5:on 911008,discovered That Amount of Grease Injected Into Vertical Tendon V10-102 Significantly Larger than Amount of Grease Removed from Tendon.Caused by Voids in Tendons.Tendon Retensioned
ELV-03155, Special Rept 50-425/1991-003:on 910912,vent Valve on Grease Can for Horizontal Tendon H-96 at Butress 2 Found Broken Off & Grease Leaked from 15 Locations on Exterior Surface. No Degradation Occurred in Tendons or Containment
AECM-84-0286, Forwards Rev 29 to Tech Spec Problem Sheets.Rev Transmitted Specifically as Update
JSP-442-91, Application for Amend to License NPF-62,changing Tech Spec 3/4.3.2 Re Containment & Reactor Vessel Isolation Control Sys
2CAN049101, Provides follow-up to 910403 & 04 Verbal Discussions Re Temporary Waiver of Compliance from Limiting Condition for Operation 3.0.4 for Containment Purge Isolation Valves Until Tech Specs Can Be Developed & Processed
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
2CAN109101, Application for Amend to License NPF-6,deleting Two Containment Isolation Valves from TS Table 3.6-1,per NRC Info Notice 88-073 Re direction-dependent Leak Characteristics of Containment Purge Valves
NRC-12-0004, Proposed License Amendment to Modify Technical Specification Surveillance Requirements for Safety Relief Valves
NRC-13-0001, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line Item Improvement Process
05000498/LER-1998-001-01, :on 980122,failure to Perform an Adequate TS Surveillance Re Containment Structural Integrity.Caused by Ineffective Performance.Training on New Calculation Procedure Has Been Provided
BSEP 05-0049, Request for License Amendments Regarding Suppression Chamber-to-Drywell Vacuum Breaker Surveillance Testing
05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
3F0788-05, Forwards Rept Re Containment Leakage Test Pressure,Per Tech Specs.Tech Specs Will Be Revised to Increase Pressure to 52.6 Psig to Assure Allowable Limits
05000341/LER-1991-022, :on 911211,primary Containmnt Negative Pressure Occurred During Plant Shutdown.Caused by Reverse Flow Through Safety Relief Valves.Staff Training Will Be Completed by First Quarter 1992
05000368/LER-1991-010, :on 910407,containment Purge Isolation Valve Declared Inoperable Due Excessive Leakage.Caused by Inadequate Design Info from Valve Mfg.Valve Will Be Replaced or Rotated,Per Evaluation of Feasibility
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
ULNRC-03057, Special Rept 94-02:on 940803,05 & 18,during Tenth Yr Inservice Surveillance Acceptance Criteria of TS 4.6.1.6.1.b.1 Not Met.Observed Tendon Conditions & Voids Do Not Indicate Significant Degradation of post-tensioning Sys
05000325/LER-1982-091-03, /03L-0:on 820802,review of Surveillance Testing Procedure for Calculating Drywell Average temp,PT-16.2, Determined That One of Five Points Used to Obtain Temp at Plus/Minus 90 Ft Was at 86 Ft Level.Procedures Revised
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-1981-057-03, During Computation of Containment Volumetric Average Air Temp,Temp of 135.57 F Was Revealed.Caused by Dust Accumulation in Cooler Air Louvres.Dust Was Removed & Air Flows Balanced
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
ELV-01105, Special Rept 50-424/1989-003:on 891030,31 & 1107,tendon Grease Deficiencies Noted During Combined Tendon Surveillances.No Corrosion or Cracks Found.Tensile Test Results for Strand Samples Expected by End of Dec 1989
ST-HL-AE-3212, Application for Amends to Licenses NPF-76 & NPF-80,revising Tech Spec Surveillances 4.6.1.6.1,4.6.1.6.2 & 4.6.1.6.3 Following Guidance of Reg Guide 1.35 Proposed Rev 3 & Tech Spec 3.6.1.6 Re Tendon Surveillance
05000324/LER-1989-008, :on 890605,unplanned LOCA Initiation Signal Occurred During Routine Maint Surveillance Testing of ECCS, Resulting in Autostarting of Core Spray a & B & RHR LPCI Pumps A,B,C & D.Caused by Spurious Trip
BSEP-96-0337, Application for Amends to Licenses DPR-62 & DPR-71,updating TS 3.6.1.6 to Support Upgrade to Containment Average Air Temp Limit Associated W/Conversion to Improved Tss.Encl Proprietary Rept & TSs Withheld
05000317/LER-1980-003-03, /03L-0:on 800108,during Routine Containment Air Lock Surveillance,Emergency Escape Lock Leakage Found Greater than Allowed.Caused by Excessive Leaking of Packing Glands for Doors Handwheels.Packing Tightened
05000324/LER-1979-080-03, /03L-0:on 790830,primary Containment Ambient Temp Exceeded Tech Spec Limits,Causing Small Steam Leak.Caused by Leakage & Steam Cut of King Pin Cover on Feedwater Check Valve B21-F010B.Leak Repaired & Leakage Decreased
LR-N970150, Application for Amends to Licenses DPR-70 & DPR-75, Correcting Editorial & Administrative Errors in Ts,Which Existed Since Initial Issuance
LR-N970298, Forwards Description of Proposed TS Changes Identified by Pse&G Which Do Not Impact Restart or Operation of Units
HNP-96-064, Application for Amend to License NPF-63,proposing to Implement Change to Bases for TSs 3/4.6.1.4 & 3/4.6.1.6 Revising Calculated Peak Pressure for MSLB Event
L-92-330, Special Rept:On 921106 & 12,20th Yr Tendon Insp Determined That lift-off Value for Hoop Tendon 13H54 & Dome Tendon 1D40 Below Min Design Prestress Force.Tendons Restored to Required Level.Addl Rept to Be Submitted by 930129
L-92-223, Special Rept:On 920706,hoop Tendon Group Found to Have Measured Normalized lift-off Force Below Predicted Lower Limit.Cause Under investigation.Lift-off Forces in Tendons 42H31,42H32 & 42H33 Restored to Required Level
CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and to
BSEP 16-0087, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A
L-92-203, Special Rept:Three Surveillance Tendons,Inspected on 920612, 19 & 29 Found W/Measured Normalized lift-off Force Below Predicted Lower limit.Lift-off Forces Restored to Required Level of Integrity.Addl Rept Will Be Sent by 920915
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
05000254/LER-2010-001, Regarding Electromatic Relief Valve Main Disc Failure
BSEP-09-0026, Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers
BSEP 08-0069, Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers
RS-07-118, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
PLA-6114, Proposed Amendment Nos. 281 and 251 to Licenses NPF-22 and NPF-22, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67.
RS-07-074, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
HL-6328, Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6
NUREG-1433, Part 1- Edwin I. Hatch, Units 1 & 2, License Amendments, Replace Current Technical Specification & Associated Bases
RS-07-117, Application for Technical Specification Change TSTF-423, Risk Informed Modification to Selected Required Action End States for BWR Plants, Using the Consolidated Line Item Improvement Process
LR-N04-0343, Revised Request for Changes to Technical Specifications Containment Systems - Containment Cooling System
RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications
05000251/LER-1992-009, :on 921117,measured Prestress Force on Containment Tendon Lower than Predicted Lower Limit.Caused by Increased Tendon Wire Steel Relaxation Loss at Higher Tendon temp.Lift-off Forces Restored
RS-05-104, Revised Technical Specification Pages for License Amendment Related to Revision of Instrument Channel Trip Setpoint Allowable Values
B18696, License Basis Document Change Request 2-17-02, Containment Systems
05000324/LER-1989-008-03, :on 890605,unplanned LOCA Initiation Signal Occurred During Routine Maint Testing of ECCS Resulting in Auto Starting of LPCI Core Spray & RHR Pumps.Caused by Spurious Trip of ECCS Trip Unit.Unit Replaced
JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info
L-2018-191, Supplemental Responses Requests for Additional Information (RAI) Set 7 Subsequent License Renewal Application Safety Review
JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
2CAN112005, Unit 2 - Inservice Testing Plan for the Fifth 10-Year Interval
CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line.
NRC-16-0034, Fermi, Unit 2, Submittal of Revision 20 Updated Final Safety Analysis Report, 10CFR50.59 and 10CFR72.48 Evaluation Summary Reports, Commitment Management Report & Revisions to Technical Requirements Manual & Technical Specifications Base
L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program
TSTF-23-06, TSTF Response to NRC Request for Additional Information on TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements
TSTF-23-04, Technical Specifications Taskforce Transmittal of TSTF-576, Revision 2, Revise Safety/Relief Valve Requirements