ASME Code Case N-2D588
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creation date: 2025-12-06T17:36:01-05:00
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ASME Code Case N-588
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ML110050298
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ML13325A023
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RIS 2004-04, Use of Code Cases N-588, N-640, and N-641 in Developing Pressure-Temperature Operating Limits
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2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits
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RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application
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CNL-14-144, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-494)
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L-14-289, Pressure and Temperature Limits Report. Revision 2
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CNL-14-065, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-491)
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BYRON 2014-0040, Pressure and Temperature Limits Report (PTLR) Revised for Negative Pressure Application During Reactor Coolant System Vacuum Fill
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NRC 2013-0022, Supplement to License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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L-12-324, Reply to Supplemental Request for Additional Information for the Review of License Renewal Application (TAC No.ME4640) and License Renewal Application Amendment No. 33
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page: https://kanterella.com/L-2D12-2D324-2C_Reply_to_Supplemental_Request_for_Additional_Information_for_the_Review_of_License_Renewal_Application_-28TAC_No.ME4640-29_and_License_Renewal_Application_Amendm…
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ML12194A280
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ML12193A535
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ML121070686
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L-11-319, Pressure and Temperature Limits Report
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L-11-116, Pressure and Temperature Limits Report
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L-2011-115, Response to NRC Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Reactor Materials Issues
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ML110840267
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L-11-085, Regarding the Submittal of the Unapproved Pressure and Temperature Limits Report
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ML18022A201
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RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
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RS-16-248, Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
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RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Technical Requirements Manual
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NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 4 - Reactor Coolant System
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NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)
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RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 05 - Reactor Coolant System and Connected Systems
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ML101110128
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L-09-225, Supplemental Information Related to a License Amendment Request to Incorporate the Use of Alternate Methodologies for the Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves, and Request for Exemption from
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L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr
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BYRON 2007-0051, Reactor Coolant System (RCS) Pressure and Temperature Limits Reports (PTLR)
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NRC-05-0011, Proposed License Amendment Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10
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NRC 2003-0018, Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves for Pbnp Units 1 & 2
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page: https://kanterella.com/NRC_2003-2D0018-2C_Request_for_Exemptions_to_10_CFR_50.61-2C_Appendices_G_and_H_to_10_CFR_50-2C_and_Approval_of_PTS_Application_for_Pbnp_Unit_2_and_Proposed_Heatup_and_Cooldown_…
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wiki page sort key: NRC 2003-0018, Request for Exemptions to 10 CFR 50.61, Appendices G and H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves for Pbnp Units 1 & 2

RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits
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RNP-RA/04-0098, Request for Technical Specifications Change to Reactor Coolant System Pressure and Temperature Limits
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W3F1-2003-0075, Ses, Unit 3, License Amendment Request NPF-38-250, Revision to Pressure/Temperature and Low Temperature Overpressure Protection Limits for 32 Effective Full Power Years
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2CAN040405, License Amendment Request Technical Specification Change Request for Modification of ANO-2 RCS
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LR-N04-0136, Request for Change to Technical Specifications Pressure/Temperature Limits
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LR-N02-0406, Request for Change to Reactor Material Surveillance Program Hope Creek Generating Station
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NL-02-006, Response to Request for Additional Information Indian Point 2 License Amendment Request for Reactor Coolant System Heatup and Cooldown Limitation Curves
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L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 4
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L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 5
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1CAN041502, Responses to Request for Additional Information Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
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RIS 2004-05, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
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GO2-04-107, License Amendment Request to Revise Technical Specification 3.4.11, Reactor Coolant System Pressure and Temperature Limits
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ML13058A059
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LR-N03-0173, Technical Specification Bases Change Re Reactor Coolant System Pressure and Temperature Limits
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RNP-RA/06-0033, Transmittal of Technical Specifications Bases Revisions
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L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits
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RIS 2004-09, Status on Deferral of Active Regulation of Ground-Water Protection at In Situ Leach Uranium Extraction Facilities
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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
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NRC-2009-0234, FRN: General Notice. Biweekly Notice. Application and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations. Sholly Report for Fr Publication on June 16, 2009
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RIS 2004-06, Independent Survey of Power Reactor Licensees
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RIS 2004-09, Status on Deferral of Active Regulation of Ground-Water Protection at in Situ Leach Uranium Extraction Facilities
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L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
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BW150112, Submittal of Pressure and Temperature Limits Reports (Ptlrs), Revision 8 and Braidwood, Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision 7
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BW140044, Pressure and Temperature Limits Reports (Ptlrs), Revision 7 and Braidwood Unit 2 - Pressure and Temperature Limits Reports (Ptlrs), Revision
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BW140001, Pressure and Temperature Limits Reports (Ptlrs)
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TMI-12-183, Revision to the Pressure and Temperature Limit Curves and the Low Temperature Overpressure Protection Limits, and 10 CFR 50.12 Exemption Request - Initial RT NDT Values for Linde 80 Welds
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ML092150447
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BW070019, Pressure and Temperature Limits Reports (Ptlrs), Revision 4
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NUREG-1916 Volume 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
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ML062910417
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L-96-003, License Amendment Request: Adoption of GL 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits and TSTF-419-A, Rev. 0, Revise PTLR Definition
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ML050250436
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NRC 2004-0111, License Renewal Application Response to Request for Additional Information
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NRC 2004-0085, License Renewal Application Revised Information
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