Clarify Application of Setpoint Methodology for LSSS Functions
TSTF-493 + Approved
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TSTF-493 + Withdrawn
TSTF-493 + Open
TSTF-493
TSTF-493 PROJ0753
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TSTF-493# QUERYff4685b7cd9fc4d904dfd3cf6dc000c0
TSTF-493# QUERY8b4bcbbfc6d2cbd95cb768bfd54aaa68
TSTF-493# QUERYd5b5089d0ff0b8bf4def719d67dc2b60
NRC Region 1 false
TSTF-493# QUERYb9ee36ccdeec3fa80e46949fdbbd1f4d
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NRC Region 2 false
NRC Region 2 true
NRC Region 3 false
NRC Region 3 true
TSTF-493# QUERY34609f0fa1f49fdb2d720a81cffadc4a
NRC Region 4 false
NRC Region 4 true
ONS-2017-019, Technical Specification Bases Change 2015-09
CNL-17-026, Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04)
CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
CNS-16-031, Technical Specification Bases Changes
LR-N16-0057, Supplement for License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
CNS-16-015, Technical Specification Bases Changes
MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
RIS 2006-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specification, with Respect to Limiting Safety System Settings (LSSS) During Periodic Testing and Calibration of Instrument Channels
CNS-15-098, Technical Specification Bases Changes
CNL-15-138, Tennessee Valley Authority Nuclear Power Group Response to NRC Regulatory Issue Summary 2014-13 Planned Licensing Action Submittals for All Power Reactor Licensees
MNS-15-022, Renewed Facility Operating License Nos. NPF-35 and NPF-52 Removal of Superseded Technical Specification (TS) Requirements
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
HNP-15-046, Transmittal of Technical Specifications Bases
NLS2015055, Correction to License Amendment Request to Revise Technical Specifications to Add Residual Heat Removal System Containment Spray Function
LR-N15-0021, License Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systems
RA-15-0005, Duke Energy - Response to Regulatory Issue Summary (RIS) 2014-13, Planned Licensing Action Submittals for All Power Reactor Licensees
GO2-14-164, Response to NRC Request for Additional Information Re License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
GO2-14-157, Response to Second Request for Additional Information Related to License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High
HNP-14-108, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
MNS-14-056, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049 (TAC Nos. MF2741, 2742)
GO2-14-103, Proposed Revision to License Amendment Request to Adopt TSTF-493, Revision 4, Option a, and Response to Request for Additional Information
HNP-14-043, License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
WO 14-0043, Supplemental Information in Support of the License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis Methodologies
GO2-14-043, License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level-High
WO 14-0031, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
ULNRC-06070, RAI Respose to Application for Amendment, (LDCN 12-0015), Revision to Technical Specification 3.7.9
GO2-13-138, License Amendment Request for Adoption of TSTF-493, Revision 4, Option a
LR-N13-0197, Intent to Submit License Amendment Request to Install Power Range Neutron Monitor (Prnm) in Accordance with Interim Staff Guidance, Digital I&C-ISG-06
GO2-13-111, Response to Request for Additional Information Related to License Amendment Request to Implement Prnm/Arts/Mellla
GO2-13-075, Response to Request for Additional Information Regarding License Amendment to Implement Prnm/Arts/Mellla
GO2-13-059, Response to Request for Additional Information Regarding License Amendment Request to Implement Prnm/Arts/Mellla
GNRO-2012/00146, Technical Requirements Manual and Technical Specification Bases Update
HNP-12-116, License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values
GNRO-2012/00132, License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell Isolation Instrumentation Function 3.c RCIC Steam Supply Line Pressure - Low
L-MT-12-091, Extended Power Uprate: Supplement to Revise Technical Specification Setpoint for the Automatic Depressurization System Bypass Timer
GO2-12-135, Response to Request for Additional Information Regarding License Amendment Request to Implement Prnmiarts/Mellla
NLS2012100, Response to Request for Additional Information Regarding License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
NLS2012039, Supplement to License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
NLS2012033, Enclosure 4 - Calculation Nedc 11-109, Rev. 0, Instrument Drift Analysis for NBI-PS-51A/B/C/D (Barksdale B2T-M12SS)
L-MT-12-028, License Amendment Request: Revise Allowable Value for the Automatic Depressurization System Bypass Timer
DCL-12-030, Response to Items Contained in NRC Acceptance Review of License Amendment Request for Digital Process Protection System Replacement
L-2012-068, Response to NRC Instrumentation and Control Engineering Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
HNP-12-002, Request for License Amendment Measurement Uncertainty Recapture Power Uprate Supplemental Information
GO2-12-017, License Amendment Request to Change Technical Specification in Support of Prnm/Arts/Mellla Implementation
L-2012-034, Response to NRC Instrumentation and Control Engineering Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205, Cover Letter & Attachment 1 (Non-Proprietary)
L-2012-033, Response to NRC Instrumentation and Control Engineering Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205
HNP-11-097, Request for License Amendment - Measurement Uncertainty Recapture Power Uprate Supplemental Information
GNRO-2011/00089, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
GNRO-2011/00066, Response to NRC Request for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
NLS2011071, License Amendment Request for Implementing a 24-Month Fuel Cycle and Adoption of TSTF-493, Revision 4, Option a
GNRO-2011/00072, Technical Requirements Manual and Technical Specification Bases Update
L-2011-302, Response to NRC RAI Regarding EPU LAR No. 205 Technical Specification and Instrumentation and Control Issues
RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation
GNRO-2011/00055, Request for Additional Information Regarding Extended Power Uprate
GNRO-2011/00042, Responses to NRC Requests for Additional Information Re License Amendment Request for Power Range Neutron Monitoring System
GNRO-2011/00032, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
NL-11-0280, License Amendment Request for Steam Generator Water Level High-High Setpoint Change
DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)
LR-N17-0044, Hope Creek - License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 7, Instrument and Control
LR-N15-0178, Hope Creek - License Amendment Request, Digital Power Range Neutron Monitoring (Prnm) System Upgrade
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
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 1 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-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 5 of 8
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
DCL-11-072, LAR-11-006 - Revision to Technical Specification 3.3.5. Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
L-2011-190, Turkey Point, Units 3 and 4 - Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Instrumentation and Controls Issues
L-2010-259, St. Lucie, Unit 1 - Extended Power Uprate Licensing Report, Attachment 5; Appendix E, Supplement to Licensing Report Section 2.4.1 Reactor Protection, Engineered Safety Features Actuation and Control Systems
L-2010-113, Turkey Point, Units 3 and 4 - License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Operating License, Technical Specifications, and Licensing Basis Changes
GNRO-2010/00067, License Amendment Request to Implement TSTF-493 for Condensate Storage Tank Low Level Setpoint
TSTF-10-21, Invitation to Participate in Industry Workshop on TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions
NRC 2010-0157, License Amendment Request 261, Supplement 10 Extended Power Uprate
RBG-47062, Unit 1, Response to Request for Additional Information on License Amendment Request 2009-05, 24-Month Fuel Cycles
GNRO-2010/00040, Responses to NRC Requests for Additional Information Pertaining to License Amendment Request for Power Range Neutron Monitoring System
TSTF-10-07, Transmittal of TSTF-493, Revision 4, Errata, Clarify Application of Setpoint Methodology for LSSS Functions
RS-10-002, Request for License Amendment Re Measurement Uncertainty Recapture Power Uprate
RS-10-001, LaSalle, Units 1 and 2, Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate
TSTF-09-24, Technical Specification Task Force Recommended Changes to Be Incorporated in Revision 4 of the Standard Technical Specifications, NUREG-1430 Through 1434
DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15
L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009
PLA-6501, Amendment Request Nos. 296 and 266, Emergency Cooling System Instrumentation - Technical Specification Table 3.3.5.1-1 and Supplemental Information
BVY 09-009, Technical Specifications Proposed Change No. 273, Supplement 7 Response to Request for Additional Information
L-MT-09-041, Supplement to License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function
TSTF-09-07, Industry Plan to Resolve TSTF-493, Clarify Application of Setpoint Methodology for LSSS Functions
L-MT-08-049, Submittal of Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade
L-MT-08-044, Extended Power Uprate: Withdrawal of Proposed License Amendment
NG-08-0366, Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value Affected Technical Specification: Section 3.3.8.1
NLS2008046, Response to Request for Additional Information for License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate
L-08-056, Reactor Protection System High Flux Trip Setpoint Calculation
TSTF-07-35, Revision to Scheduled Response Date for NRC Request for Additional Information Regarding TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions, Dated July 25, 2007
TSTF-07-31, Revision to Scheduled Response Date for NRC Request for Additional Information Regarding TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions Dated July 25, 2007
TSTF-07-14, TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
DCL-07-075, Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information
NRC 2007-0061, Commitment to Revise Nonconservative Technical Specifications License Amendment Request 250 Regulatory Commitment Change
RS-07-066, Request for License Amendment to Revise Turbine Condenser Vacuum - Low Scram Instrumentation Function
L-MT-07-009, License Amendment Request: Revision to the Allowable Values and Surveillance Intervals for the Low Pressure Coolant Injection Loop Select Logic Time Delay Relays
NRC 2006-0083, Commitment to Revise Nonconservative Technical Specifications
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
NRC-2014-0010, Federal Register Notice, Withdrawal of License Amendment Request, Adoption of TSTF-493-A, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions, Option a
NRC-2014-0144, Federal Register Notice Withdrawing Regulatory Guide 10.1, Compilation of Reporting Requirements for Persons Subject to NRC Regulations.
NRC-2014-0054, FRN, Withdrawal of License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term
NRC-2014-0028, Biweekly Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 18, 2014
NRC-2011-0111, Vogtle Units 1 and 2 (Vegp) - Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed NSHC Determination, and Opportunity for a Hearing and Order Imposing Procedures for Document Access to SUNSI
NRC-2010-0309, FRN: General Notice. Biweekly Notice, Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations, NRC-2010-0309
RA-18-0282, Technical Specification Bases Changes
TSTF-19-07, TSTF Handout for October 16, 2019, Meeting: Elimination of Commitment to Adopt TSTF-493
ET 14-0017, Withdrawal of License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
ET 14-0009, Response to Request for Additional Information Regarding License Amendment Request for the Transition to Westinghouse Core Design and Safety Analysis
3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
LR-N15-0124, Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request Regarding Replacement of Source Range and Intermediate Range Neutron Monitoring Systmens
CNL-19-095, Application to Modify the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (SQN-TS-19-04)
LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation
CNL-22-003, Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010)
RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition
RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure
HNP-15-043, Response to Request for Additional Information 4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
HNP-14-119, Response to Request for Additional Information 2 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
HNP-15-005, Response to Request for Additional Information 3 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
NLS2024001, Application to Modify the Allowable Value for Cooper Nuclear Station Technical Specifications High Pressure Coolant Injection Pump Discharge Low Flow
TSTF-24-07, PRM-50-126 - Petition for Rulemaking to Amend 10 CFR 50.36, Technical Specifications from Brian D. Mann on Behalf of the Technical Specifications Task Force
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
GNRO-2019/00028, Supplement 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-19-0698, License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function SNC Response to NRC Request for .
LR-N18-0127, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement
RAIO-0119-64111, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
CNS-15-086, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start
CNS-15-075, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start
CNS-15-068, Response to NRC Request for Additional Information Regarding License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and .
GO2-15-075, Exigent License Amendment Request - Extension of Implementation Period for Amendment 232 Changing Technical Specification Table 3.3.1.1-1 Function 7 Scram Discharge Volume Water Level-High
05000298/LER-2015-002, Regarding Failure of Main Steam Differential Pressure Indicating Switches Results in a Condition Prohibited by Technical Failure of Main Steam Differential Pressure Indicating Switches Results in a Condition
CNS-15-002, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable
CNS-14-128, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable
GO2-14-076, Supplemental Information Regarding License Amendment Request for Changing Technical Specification Table 3.3.1.1-1 Function 7, Scram Discharge Volume Water Level - High
MNS-14-043, (Mns), Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049
GNRO-2013/00001, Response to Electronic Request for Additional Information Supporting Completion of Safety Evaluation for the License Amendment Request for Revision of Technical Specification Allowable Value for Primary Containment and Drywell.
NRC-13-0004, License Amendment Request for Measurement Uncertainty Recapture (MUR) Power Uprate
TSTF-10-19, Technical Specification Task Force - Request for NRC Information to Support Plant-Specific Adoption of Option B of TSTF-493, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions
GNRO-2008/00006, To Amendment Request Condensate Storage Tank Setpoint Change, Grand Gulf Nuclear Station, Unit 1
TSTF-08-01, Response to NRC June 25, 2007 Request for Additional Information Regarding TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions
NG-08-0709, Request to Withdraw Portions of the Information Submitted Regarding Technical Specification Change Request (TSCR-106): 4160 Volt Emergency Bus Undervoltage (Degraded Voltage) Maximum Allowable Value
DCL-07-002, Response to Request for Additional Information on License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement
TSTF-07-08, Schedule for Submittal TSTF-493, Revision 2, Clarify Application of Setpoint Methodology for LSSS Functions
TSTF-06-34, Request to Extend Acceptance Review Schedule for TSTF-493, Revision 1, Clarify Application of Setpoint Methodology for LSSS Functions
CPSES-200600097, Revision to Technical Specifications 3.3.1, Reactor Trip System Instrumentation, 3.3.2, ESFAS Instrumentation, 3.4.5, RCS Loops-Mode 3, 3.4.6, RCS Loops-Mode 4, and 3.4.7, RCS Loops-Mode 5, Loops Filled
TSTF-06-03, TSTF-493, Revision 0, Clarify Application of Setpoint Methodology for LSSS Functions
NUREG-1433, Regulatory Audit in Support of Review of the License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5
RA-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes
LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
TSTF-21-03, TSTF Response to NRC Questions on TSTF-576, Revision 0, Revise Safety/Relief Valve Requirements and Submittal of Revision 1
LR-N25-0015, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 2
JAFP-19-0105, Response to Request for Supplemental Information to Revise the Allowable Value for Reactor Water Cleanup (RWCU)
CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System
LR-N24-0029, Enclosure 1: Contents of the Hope Creek Improved Technical Specifications (ITS) Submittal