05000244/LER-2008-001, R. E. Ginna Nuclear Power Plant Plant Heatup with Required Residual Heat Removal Loops Inoperable Due to Personnel Error (Voluntary Report)
ULNRC-06350, Pressure and Temperature Limits Report
LR-N17-0032, License Amendment Request to Amend the Technical Specifications (TS) to Revise and Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
CNS-17-033, Technical Specification Bases Changes
1CAN071701, License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process
ONS-2017-052, Technical Specification Bases Change 2017-03
NLS2017048, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control
L-MT-17-058, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 9
CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time
RS-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
RS-16-218, Response to Request for Additional Information License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time to Support 2A SX Pump Repair
ONS-2016-082, Technical Specification Bases Change for TS Bases 3.4.16, Steam Generator Tube Integrity
RS-16-197, License Amendment Request for a One-Time Extension of the Essential Service Water (SX) Train Completion Time to Support 2A SX Pump Repair
ONS-2016-071, Duke Energy Carolinas, LLC - Oconee Nuclear Station, Docket Numbers 50-269, 50-270, and 50-287 - Technical Specification (TS) Bases Change
L-PI-16-054, Pressure and Temperature Limits Report, Revision 5
CNL-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)
CNL-16-045, Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information
MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System
ONS-2015-107, Updated Final Safety Analysis Report (Ufsar), Selected Licensee Commitments Change
CNL-15-170, Responses to NRC Audit Review Questions for Essential Raw Cooling Water and Component Cooling Water System License Amendment Request
L-PI-15-030, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13)
CNL-15-121, Shutdown Technical Specifications for Component Cooling System and Essential Raw Cooling Water System to Support Dual Unit Operation
3F0515-05, Technical Specifications Bases Control Program
ONS-2015-047, License Amendment Request (LAR) to Add High Flux Trip for 3 Reactor Coolant Pump Operation, License Amendment Request No. 2014-05
L-PI-15-034, Pressure and Temperature Limits Report (PTLR) Revision 4
NL-15-0421, J. M. Farley, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement P
NL-15-0422, License Amendment Request to Revise Technical Specifications Regarding Generic Letter 2008-01, Managing Gas Accumulation in Accordance with TSTF-523, Revision 2, Using the Consolidated Line Item Improvement Process (CLIIP)
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
L-15-026, License Amendment Request to Steam Generator Technical Specifications
L-PI-15-004, Supplement to License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System)- Shutdown
ULNRC-06145, Pressure and Temperature Limits Report, Revision 6
L-PI-14-085, 10CFR 50.55a Requests Associated with the Fifth Ten-Year Interval for the Inservice Inspection Program
L-2014-029, St, Lucie Nuclear Plant, Units 1 and 2, License Amendment Request, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler -523, Generic Letter 2008-01, Managing Gas Accumulation, Using
L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report
WO 14-0024, Changes to Technical Specification Bases - Revisions 57 Through 60
MNS-14-003, License Amendment Request for Technical Specification (TS) 3.4.12, Low Temperature Overpressure Protection (LTOP) System
ULNRC-05975, Revision to TS LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4, 5 and 6 License Amendment Request LDCN 13-0003
L-13-360, Pressure and Temperature Limits Report Revision
W3F1-2013-0040, Technical Specification Index and Bases Update to the NRC for the Period May 1, 2012 Through June 30, 2013
L-PI-13-017, License Amendment Request (LAR) to Revise Technical Specification (TS) 3.5.3, ECCS (Emergency Core Cooling System) - Shutdown
NL-13-001, Proposed Changes to Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements
L-MT-12-077, License Amendment Request: Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities
W3F1-2012-0095, Response to a Request for Additional Information Regarding License Amendment Request to Relocate Technical Specifications to the Technical Requirements Manual
L-12-077, Pressure and Temperature Limits Report Revision
W3F1-2011-0018, License Amendment Request to Relocate Technical Specifications to the Technical Requirements Manual
PLA-6695, Amend. Request No. 308 to License NPF-14 & Amend. Request No. 279 to License NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-514, Rev. 3, Revise BWR Operability Requirements & Actions RCS Leakage Instrumentation
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 14.0 - Initial Test Program
NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 4 of 6
NL-15-1898, Enclosure 4: EAL Verification and Validation Documents - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 6
NL-15-1898, Enclosure 3: Hatch EAL Calculations - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 1 of 3
NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76
NL-16-109, Indian Point 2 Technical Requirements Manual
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 5 of 9
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, Technical Requirements Manual
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
TSTF-11-13, Transmittal of TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition
TSTF-10-14, Submittal of TSTF-513, Revision 3 and TSTF-514, Revision 2
NL-09-1676, Request to Revise Technical Specification 3.7.8, Service Water System (Sws)
NL-09-1644, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (SWS)
RS-09-121, License Amendment Request for a One-Time Extension of the Essential Service Water Train Completion Time
ULNRC-05566, Amplification for Amendment, Revision of Technical Specification 3.3.2 and 3.7.2 and Addition of New Technical Specification 3.7.19 (License Amendment Request OL-1277 Revised)
TSTF-09-03, Transmittal of TSTF-513, Revision 1, Revise PWR Operability Requirements and Actions for RCS Leakage Instrumentation and TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
L-08-327, Pressure and Temperature Limits Report, Revision 3
NRC 2008-0075, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
L-PI-08-046, Application for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater (AFW) Pump Inoperable Using Consolidated Line Item Improvement Process
BSEP 08-0083, License Amendment Request for Adoption of TSTF-484, Revision 0 - Use of TS 3.10.1 for Scram Time Testing Activities
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5A and 5B, Cover - Dr 3-76
JAFP-18-0068, Response to Request for Additional Information: License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ULNRC-05445, One-Time Completion Time Extension for Essential Service Water (ESW) System
RNP-RA/07-0108, Transmittal of Technical Specifications Bases Revisions
L-07-087, Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report
NLS2007036, Technical Specification Bases Changes
JAFP-07-0023, Application for Amendment to Technical Specifications 3.10.1. Re Inservice Leak and Hydrostatic Testing Operation, Consistent with TSTF-484
CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating
ULNRC-05356, Figure 14.9, Pressure and Temperature Limits Report
NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report
DCL-06-130, Response to NRC Request for Additional Information Regarding License Amendment Request 06-04, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity (TSTF-449)
L-06-149, Improved Technical Specification (ITS) Conversion License Amendment Request
NL-06-1637, Request to Implement an Alternative Source Term
L-06-132, Supplement to License Amendment Request No. 183 - Submittal of Final Proposed Technical Specification Changes
NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1
L-MT-06-054, Supplemental Submittal Regarding Full Scope Application of an Alternative Source Term (AST)
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
RS-06-079, Request for Technical Specification Change to Revise Surveillance Requirement Note
CPSES-200601056, Response to Request for Additional Information Related to License Amendment Request (LAR) 2004-010 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
NLS2006042, License Amendment Request for Revision of Technical Specification 3.10.1, Inservice Leak and Hydrostatic Testing Operation
LR-N06-0055, Request for Change to Technical Specifications to Add Requirements for Steam Generator Tube Integrity, Steam Generator Program and Steam Generator Tube Inspection Report and to Revise Reactor Coolant System Operational Leakage Requiremen
2CAN050601, Response to NRC Request for Additional Information on ANO-2 Steam Generator Tube Inservice Inspection Program
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)
SBK-L-06064, License Amendment Request 06-02, Application for Technical Specification Improvement Regarding Steam Generator Integrity Using the Consolidated Line Item Improvement Process
NG-06-0250, Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.1
W3F1-2006-0007, Supplement to Amendment Request NPF-38-262, Steam Generator Tube Inservice Inspection Program
NL-04-1408, Request for Technical Specifications Change Steam Generator Program - Revision I
RA-18-0198, (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
NRC-2015-0170, FRN Re. Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing
CNL-19-014, Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)
RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
L-19-102, Submittal of Pressure and Temperature Limits Report Revision
NL-19-0221, Risk-Informed Technical Specifications Initiative 4b, Risk-Managed Technical Specifications, SNC Response to NRC Request for Additional Information (RAI)
NL-19-0635, End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications
RA-18-0282, Technical Specification Bases Changes
L-PI-19-038, Submittal of Revised Pressure and Temperature Limits Report
NL-19-1183, Response to Request for Additional Information Regarding End State Revision from Hot Shutdown to Cold Shutdown
1CAN060502, Arkansas, Unit 1 - License Amendment Request Response to NRC Request for Additional Information on ANO-1 Proposed Technical Specification Change to Steam Generator Tube Inservice Inspection Program
JAFP-05-0084, Application for Technical Specifications (TS) Change Regarding Mode Change Limitations (TSTF-359) Using the Consolidated Line Item Improvement Process (CLIIP)
CNL-19-124, Response to Request for Additional Information to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (W
RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ET 14-0034, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process
RAIO-0719-66473, LLC Supplemental Response to NRC Request for Additional Information No. 197 (Erai No. 9051) on the NuScale Design Certification Application
RAIO-0219-64635, LLC Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
ND-18-0610, Supplement to Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004S1)
ND-18-0053, Request for License Amendment: Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability (LAR-18-004)
NL-04-1537, Response to Request for Additional Information Regarding Technical Specification Revision Request, DC Sources and TSTF-360, Revision 1
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project
NOC-AE-04001794, License Amendment Request Revision to Proposed Amendment to Technical Specifications for Steam Generators
NOC-AE-04001765, License Amendment Request - Proposed Amendment to Technical Specifications for Steam Generators
HNP-04-097, Day Response to NRC Bulletin 2004-01 for the Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-water Reactors
NL-04-0134, Request to Revise Technical Specifications to Relocate the Cold Overpressure Protection System Arming Temperature
NRC-04-0005, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
WO 04-0003, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
L-PI-03-089, License Amendment Request (LAR) Dated 10/31/03, Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with Unit 1 Replacement Steam Generators
NRC 2003-0091, Request for Withdrawal, and Resubmittal, of Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, Approval of PTS Application for Pbnp Unit 2 and Withdrawal of Associated License Amendment Request (LAR) 235 and Submi
NRC 2003-0058, License Amendment Request 235, TS LCO 5.6.5 Reactor Coolant System Pressure & Temperature Limits Report
NRC 2003-0033, Technical Specification Bases Revisions
L-2003-007, NRC Bulletin 2002-01, Request for Additional Information Response
HNP-02-164, Letter from James Scarola, Harris Nuclear Plant - - Request for Additional Information, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
NRC 2002-0030, License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate
NLS2002094, Response to Revised DBA Methodology-Request for Cooper Nuclear Station
HNP-02-118, 30-Day Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head & Vessel Head Penetration Nozzle Inspection Programs
ULNRC-04721, Technical Specification Bases Revision 3
RC-02-0123, Application for Renewed Operating License, Appendix F Severe Accident Mitigation Alternatives
DCL-02-079, Units, 1 and 2, License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report
HNP-02-063, 60-Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
HNP-02-052, Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
WO 02-0004, Revision to Technical Specifications Re Suspension of Positive Reactivity Additions
L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13
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
AEP-NRC-2020-09, Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable
AEP-NRC-2020-61, Unit 2, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable
CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)
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
BSEP-88-1162, Supplemental Response to Violations Noted in Insp Repts 50-324/88-14 & 50-325/88-14.Corrective Actions:Requirements Established to Monitor Reactor Vessel Temp on 30-minute Periodicity When in Shutdown Cooling
B17416, Forwards Response to RAI Re Licensee 980806 Proposed Amend to License NPF-49,allowing One Time Extension to SG Insp Interval Defined in TS 3.4.5.List of Commitments Made in Ltr,Provided in Attachment 1
NRC-99-0032, Forwards Rev 4 to Fermi 2 Its,Per Submittal .Rev Provides Responses to NRC RAI Re ITS Sections 3.4 & 3.9 Contained in Ltr
BSEP-88-0534, Responds to Violations Noted in Insp Repts 50-324/88-14 & 50-325/88-14.Corrective Actions:Engineering Evaluation Err 88-0167 Written Documenting Basis for Continued Operation of Plant & Personnel Will Be Briefed on Event
ULNRC-06702, Enclosureplacement Version of Attachment 3 to ULNRC-06688, Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505
2CAN099503, Application for Amend to License NPF-6,adding Repair Limit Specifically for Circumferential Cracks in Expansion Transition Region of ANO-2 SGs
RBG-42193, Rev to Application for Amend to License NPF-29 & Proposed Amend to License NPF-47,revising TS 3/4.6.2.2, Drywell Bypass Leakage
L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions
TXX-4182, Forwards Description & Summary Evaluation of Proposed Deferred Preoperational Testing of Safety Injection Sys Check Valve Leakage & Containment Cooling Sys for Review
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
RNP-RA/06-0028, Request for Technical Specifications Change Regarding Steam Generator Tube Integrity Using the Consolidated Line Item Improvement Process
NL-15-177, Watts Bar, Unit 2, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Ma
NRC-2011-0230, FRN: General Notice. Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
LR-N07-0039, Response to RAI 2 on LCR S06-01, Request for Change to Technical Specifications to Add Steam Generator Tube Integrity Program
CNL-21-062, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019)
CNL-19-106, Supplement to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)
RAIO-0119-64178, LLC - Response to NRC Request for Additional Information No. 512 (Erai No. 9634) on the NuScale Design Certification Application
L-HU-04-033, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process
NRC-19-0054, DTE Energy Company - License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
CNL-16-086, Response to Request for Additional Information Technical Specifications 3.7.8 Change - Essential Raw Cooling Water System
CP-202000575, (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,
NG-97-1598, Provides Partial Response to 970818 RAI Re DAEC Request to Convert TSs to Improved TS
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
CNL-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.
DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)
CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F
CNS-15-098, Technical Specification Bases Changes
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
ULNRC-05608, ULNRC-05608, Revision of Technical Specification 3.3.2 and 3.7.3 (License Amendment Request OL-1289)
L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report
CPSES-200203861, License Amendment Request (LAR) 02-09 Revision to Technical Specifications Regarding Suspension of Positive Reactivity Additions
LR-N16-0055, Response to Request for Additional Information Regarding Chilled Water System Modifications
1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
05000424/LER-1989-004, :on 890119,reactor Shutdown Initiated Due to RCPB Leakage from Rcs.Moisture Observed in Drain Valve for Pressurizer Safety Valve Loop Seal Line.Caused by Fatigue Failure Due to Vibration.Supports Added
DCL-20-068, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System
05000414/LER-1987-016-01, :on 870413,facility Shutdown Due to Unidentified Reactor Coolant Leakage Greater than 1.0 Gallon Per Minute.Caused by Nozzle & Disc of Valve 2NM434 Badly Pitted.Valve Repaired
TSTF-19-11, TSTF Response to NRC Questions on TSTF-554, Revise Reactor Coolant Leakage Requirements
05000413/LER-1985-060, :on 851010,both motor-driven Auxiliary Feedwater Pumps Automatically Started After Main Feedwater Pump Tripped on High Discharge Pressure.Caused by Unidentified Primary Coolant Sys Leak
TSTF-13-11, TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation Corrected Pages
05000266/LER-1997-039-01, :on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored
CNL-16-039, Application to Modify Technical Specifications Regarding Use of Component Cooling System (Ccs)Pump 2B-B to Support CCS Train B Operability (WBN-TS-14-004)
05000317/LER-1985-013, :on 851009,unidentified RCS Leakage Determined to Be Greater than 1.0 Gpm.Caused by Cracked Weld Between Reactor Coolant Pump Shaft Seal & Control Bleedoff Line.Line & Flanges Replaced.Design Mod Implemented
05000339/LER-1985-008-02, :on 850725,increased RCS Leakage Occurred. Caused by 2-inch Valve Packing Leak Off RCS Loop A.Maint Performed to Stop Leak
05000413/LER-1996-009-02, :on 960930,use of Inadequate Reactor Coolant Controlled Leakage Test Occurred.Caused by Omission of Relevant TS Bases Info.Revised Procedures for Performing Reactor Coolant Sys Controlled Leakage Test
NSD-NRC-97-5029, Forwards Response to NRC Re TS Comments
05000423/LER-1995-020, :on 951202,RCS Pressure Boundary Leak from Valve Bonnet Stem leak-off Pipe Occurred.Caused by Crack Near Toe of Fillet Weld Between Pipe & Valve Body.Removed Pipe & Valve Bonnet Weld
05000339/LER-1991-011-02, :on 911103,plant Shutdown Required by Technical Specifications Due to RHR Valve Packing Failure.Caused by Failure of Packing RHR Sys Inlet Isolation Motor Operated Valve.Valve Packing Repaired
05000361/LER-1995-006, :on 950406,RCS Dissolved Oxygen Found Out of Specification.Caused by Failure to Follow Procedure.Returned Oxygen Level to Below TS Steady State Limit by Addition of Hydrazine
05000369/LER-1990-025, :on 900827,shutdown Because of Unidentified RCS Leakage Greater than TS Limits Occurred Due to Equipment Failure
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
05000458/LER-1990-006, :on 900309,error in Calculations for Pressure Temp Limit Curves in Tech Specs 3.4.6.1-1 Discovered.Caused by Personnel Error.Tech Spec Pressure Temp Limit Curves to Be Revised,Per Generic Ltr 88-11
05000336/LER-1981-033-03, /03L-0:on 810928,leak in RCS Traced to Isolation Valve 2-RC-403,block Valve for Power Operated Pressurizer Relief Valve 2-RC-402.Cause Not Stated.Valve Isolated
05000369/LER-1990-025-01, :on 900827,Unit 1 Shut Down Because of Unidentified RCS Leakage Exceeding Tech Spec Limits.Caused by Equipment Failure.Procedure AP/1/A/5500/10 Implemented. Valve 1NC-33 Will Be Repacked at Next Outage
NL-17-0447, Response to Request for Additional Information on Technical Specifications Change to Adopt Risk Informed Completion Times
RS-08-045, LaSalle, Units 1 and 2, Technical Requirements Manual
LR-N17-0034, Salem Generating Station, Units 1 & 2, Submittal of Revision 29 to Updated Final Safety Analysis Report, and Technical Specification Bases Changes and Quality Assurance Topical Report, NO-AA-10, Rev. 85
RA-15-019, Attachment 9 - EP-AA-1007, Revised Radiological Emergency Plan Annex Information for Peach Bottom Atomic Power Station
NLS2003056, Emergency Plan Implementing Procedures for Cooper Nuclear Station
1CAN021101, Supplemental to License Amendment Request Related to Changes to Technical Specification – Completion Times for One Inoperable RCS Cooling Loop
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
LR-N22-0078, Submittal of Technical Specification Bases Changes, Amendment No. 215
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000388/LER-2019-002, Valid Actuation of the Primary Containment Isolation System Due to a Trip of Reactor Protection System Bus 2B
RAIO-0719-66472, LLC Supplemental Response to NRC Request for Additional Information No. 520 (Erai No. 9642) on the NuScale Design Certification Application
NLS2019011, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
NL-18-1302, License Amendment Request for Technical Specification Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line .
RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
05000316/LER-2076-053, Re Containment Air Particulate & Radio Gas Monitor (R-11 & R-12) Pump Failing to Run
05000316/LER-2076-027, Re Mode 1 Position, Containment Air Particulate Detector Pump Would Not Run
L-PI-18-031, License Amendment Request to Adopt TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco
05000272/LER-1980-050-03, /03L-0:on 800908 Discovered Failed Air Particulate Detector in Reactor Coolant Leak Detection Sys.Caused by Cracked Sodium Iodide Crystal.Detector Replaced & Satisfactorily Tested
RAIO-0318-59203, LLC Supplemental Response to NRC Request for Additional Information No. 157 (Erai No. 9033) on the NuScale Design Certification Application
05000400/LER-1987-051, :on 870831,main Feedwater Pump a Tripped Due to Feedwater Oscillation.Caused by Feedwater Sys Design Problems.Valve Stem Repaired & Feedwater Sys Changes to Improve Reliability Under Evaluation
05000400/LER-1997-023, :on 920721,RCS PIV Testing Deficiency Was Noted.Caused by Failure to Consider All Testing Variables During Initial Sp Development.Surveillance Tp OST-1506 Was Revised to Incorporate Correction Factor
05000250/LER-1993-002-01, :on 930115,small Steam Leak Discovered on Abandoned Pressurizer Spray Valve Bypass Line.Caused by Welders Failing to Ensure Adequate Pullback of Pipe Cap.New Pipe Cap Welded on & Faulted Line Removed
05000250/LER-1990-006, :on 900406,control Room Ventilation Sys for Common Control Room of Units Tripped While Performing Procedure TP-584.Caused by Personnel Error.Individual Counseled
GO2-96-116, Forwards Response to NRC Re Violations Noted in Insp Rept 50-397/96-03.Util Denies Violation a & No Corrective Actions Taken
L-95-228, Application for Amends to Licenses DPR-67 & NPF-16,amending TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation by Adapting STS for C-E Plants (NUREG-1432),Spec 3.4.15 for Facilities
AEP-NRC-2016-07, License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6
05000413/LER-2012-001-01, Regarding Automatic Reactor Trip Due to Faulted Reactor Coolant Pump Motor Cable Resulted in Zone G Relay Lockout and Subsequent Loss of Offsite Power and Emergency Diesel Generator Automatic Start for Both Units
WO 12-0066, License Amendment Request to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System
TSTF-12-14, Response to NRC Request for Supplemental Information and Withdrawal Regarding TSTF-534, Revision 0, Clarify Application of Pressure Boundary Leakage Definition
NRC 2013-0051, License Amendment Request 272, Exemption Request - Optimized ZIRLO Fuel Rod Cladding
NRC-11-0013, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
SBK-L-11066, License Amendment Request 11-01, Application to Revise the Technical Specifications for Reactor Coolant System Leakage Detection Instrumentation
1CAN111001, Supplement to License Amendment Request Related to Changes to Technical Specification – Completion Times for One Inoperable RCS Cooling Loop
TSTF-10-20, Response to NRC Request for Additional Information Regarding TSTF-432, Revision 0, Change in Technical Specifications End States (WCAP-16294)
TSTF-10-24, Submittal of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
TSTF-09-18, Response to June 11, 2009 Request for Additional Information Regarding TSTF-514, Revision 0, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
NL-09-1622, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws)
ET 08-0039, Revision to TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, TS 3.7.2, Main Steam Isolation Valves (Msivs), and Addition of New TS 3.7.19, Secondary System Isolation Valves
RS-08-087, License Amendment Request to Administratively Clarify the Operating Licenses and Technical Specifications
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
TSTF-07-05, TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
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)
05000361/LER-2006-001, Both Trains of Shutdown Cooling Declared Inoperable Due to the Discovery of a Through Wall Pipe Crack in Common Header
TSTF-06-01, TSTF-412, Revision 2, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable
WM 06-0033, Revision to Technical Specification (TS) 3.7.2, Main Steam Isolation Valves (Msivs), and TS 3.7.3, Main Feedwater Isolation Valves (Mfivs)
TXX-0518, License Amendment Request (LAR) 04-010, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
DCL-04-141, Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. Steam Generator (SG) Tube Surveillance Program. & 5.6.10
RS-04-188, Request for Amendment to Technical Specifications Associated with Direct Current Electrical Power
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
DCL-04-089, Response to June 14 and July 6, 2004, NRC Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Tube Surveillance Program, & 5.6.10
NRC-2004-0011, To License Amendment Request 236 Pressure Temperature Limits Report
NLS2003124, 1 to EPIP 5.7.1, Emergency Classification
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
NRC-2002-0094, Supplement to License Amendment Request 226, Measurement Uncertainty Recapture (MUR) Power Uprate
3F0502-06, Technical Specifications Bases Control Program
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
TSTF-04-13, TSTF-449, Revision 2, Steam Generator Tube Integrity
NL-13-078, Proposed License Amendment Regarding Technical Change Traveler TSTF-432-A Revision 1
3F0506-05, 2005 Technical Specifications Bases Control Program
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RNP-RA/03-0061, Transmittal of TS Bases Revisions
CNL-15-181, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 4
DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System
RS-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use of
DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys
DCL-16-104, Technical Specification Changes for License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1..
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision
DCL-20-066, License Amendment Request 20-01 Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System
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
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
RAIO-0319-64840, LLC Supplemental Response to NRC Request for Additional Information No. 157 (Erai No. 9033) on the NuScale Design Certification Application
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
CP-202100394, Supplement to License Amendment Request (LAR) 20-006
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
NRC-21-0001, License Amendment Request to Revise Technical Specifications to Remove Obsolete Information, Make Minor Corrections, and Make Miscellaneous Editorial Changes
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
1CAN081004, Changes to Technical Specification Related to Completion Times for One Inoperable RCS Cooling Loop
NL-19-0771, Risk Informed Technical Specification Information Only Bases Changes
RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T
L-06-137, Beaver, Units 1 & 2 - Partial Withdrawal of Beyond Scope Issue Bsi) -26 Contained in License Amendment Request Nos. 296 and 169, Improved Standard Technical Specification Conversion
PLA-5764, Proposed License Amendment Numbers 267 for Unit 1 and 232 for Unit 2 Mode Change Limitations Using the Consolidated Line Item Improvement (CLIIP) Process PLA-5764
ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)
DCL-86-238, Forwards Rev 4 to Diablo Canyon Unit 1 Inservice Insp & Testing Program Plan & Rev 1 to Diablo Canyon Unit 2 Inservice Insp & Testing Program Plan. Response to Sser 31 & Justification for Changes Also Encl
CNL-15-177, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Manual
L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States
L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ
RBG-27108, Forwards Suppl Rept of Safety Evaluations for Documents Only Changes Included in USAR for Mar 1986 - Feb 1987
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
ONS-2015-106, Technical Specification (TS) Bases Change
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-001, Primary Containment Radiation EAL Threshold Determination
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
TSTF-05-05, Letter Transmitting TSTF-449, Revision 4, Steam Generator Tube Integrity
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Page PBAPS 3-77 Through End
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Cover Through Page PBAPS 3-76
JAFP-23-0060, Emergency Plan Document Revisions
LR-N25-0073, Pressure and Temperature Limits Report (PTLR) Revision 2
TSTF-25-03, TSTF Response to NRC Second Request for Additional Information on TSTF-600, Revision 1, Revise the Reactor Coolant System (RCS) Pressure Isolation Valve (PIV) Leakage Testing Frequency
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual
L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change
NRC 2020-0001, Pressure Temperature Limits Report (PTLR)
ULNRC-05219, Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program