NL-15-1761, Response to Request for Additional Information Regarding Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294)
NL-14-1870, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
NL-14-1531, License Amendment Request for Adoption of TSTF-432-A, Rev. 1, Change in Technical Specifications End States (WCAP-16294), Using the Consolidated Line Item Improvement Process
NOC-AE-05001891, License Amendment Request Proposed Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statements
NOC-AE-05001834, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statement
ND-18-1439, Revised Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017R1)
ND-18-0647, Request for License Amendment: Technical Specification Changes for Spent Fuel Pool Level - Low 2 and In-Containment Refueling Water Storage Tank (IRWST) Wide Range Level - Low Operability (LAR-18-017)
ND-20-1005, Supplement to Request for License Amendment: Vacuum Relief Valve Technical Specification Changes (LAR-20-005S1)
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
NSD-NRC-97-5278, Forwards Responses to NRC Reactor Sys Branch RAIs on AP600 Ts,Including Resultant Ssar/Ts Markups
NSD-NRC-97-5059, Forwards Responses to Listed Initial Comments on AP600 Revised Ts,Dtd 961224,as Completion of Open Item Tracking Sys Item 4970
NSD-NRC-97-5156, Responds to Re AP600 TS Completion Times & Surveillance Frequencies & Partial Completion of W Action for Key Licensing Issue 26 TS Review
NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490
NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)
NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)
ND-18-0374, Request for License Amendment: Technical Specification Changes to Support Operability During Mode 5 Vacuum Fill Operations (LAR-18-009)
NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)
05000286/LER-1985-012-01, :on 851130,after Trip,Source Range Nuclear Instrumentation Channel 31 Failed to Reenergize When Reactor Neutron Flux Dropped Below Permissive Setpoint.Caused by Loose Wire Connection.Connection Repaired
NSD-NRC-97-5029, Forwards Response to NRC Re TS Comments
05000499/LER-1993-008-01, :on 930505,heat Removal Motor Operated Valve Inoperable in Excess of Allowable Outage Time.Caused by Failure to Recognize Condition.Condition Corrected by Replacing T Drain
05000499/LER-1993-009-01, :on 930426,Tech Spec Violation Occurred Due to Use of Inappropriate Ref Value Data for RHR Pump Inservice Test.Surveillance Procedures Revised to Include Appropriate Ref Values
05000206/LER-1988-020, :on 881208,determined That Design Requirements of post-TMI Action Plan Item II.E.1.2,Part 2 Not Fully Implemented in Design of Steam Generator wide-range Level Indication Sys.Caused by Weaknesses in Program
05000206/LER-1988-020-01, :on 881208,failure to Fully Implement Design Requirements of NUREG-0737 in Design of Steam Generator wide-range Level Indication Sys Occurred.Cause Under Inquiry.Corrective Actions Will Be Implemented
05000206/LER-1989-012, :on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow
05000206/LER-1987-006, :on 870513,insp Per IE Info Notice 86-104 Found wide-range Containment Water Level Instrumentation in non-environ Qualification Configuration.Caused by Personnel Error.Training Program Initiated
05000206/LER-1987-006-01, :on 870513,during Insp of Environ Qualified Butt Spliced Connections Per IE Info Notice 86-104,one Level Switch Found Missing Raychem Heat Shrink Sleeving.Caused by Requirement Being Deleted During Drawing Rev
NOC-AE-0500, License Amendment Request Proposed One-Time Change to Technical Specification 3.7.4, Essential Cooling Water System, and Associated Supported Systems Limiting Condition for Operation Action Statements
NSD-NRC-96-4739, Forwards Draft Mark Up of Chapter 54 of AP600 Probabilistic Risk Assessment (PRA) Covering Low Power & Shutdown PRA Assessment.Pra Section Revised to Incorporate Commitments Westinghouse Made in Response to RAIs
05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function
NSD-NRC-98-5561, Forwards W Responses to FSER Open Items on AP600.Summary of Encl Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status of Column of Oits, Provided in Table 1