Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence
Regulatory Guide 1.190# QUERYf733a35d2fd02122892359e8e0b1c94e
Regulatory Guide 1.190# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9
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Regulatory Guide 1.190# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
Regulatory Guide 1.190# ERR1dd423a8697e32d6813ecd1a7aae482c
L-16-227, ANP-3339, Rev. 0, Davis-Besse Unit 1 Reactor Vessel Material Surveillance Program: Analysis of Capsule TE1-C
GNRO-2014/00080, Affidavits for the Proprietary MP Machinery and Testing, LLC (Mpm) Reports Attached in Letters GNRO-2014/00080 and GNRO-2015/00011
GNRO-2015/00046, Provides Clarification to Fluence Methodology License Amendment Request Letter GNRO-2014/00080 Dated November 21, 2014 to Include Draft marked-up UFSAR Pages and a Regulatory Commitment to Revise the GGNS UFSAR Upon NRC Approval
GNRO-2015/00038, Response to Request for Additional Information Regarding Fluence License Amendment Request, Request for Commitment
GNRO-2015/00033, Docketed Letters Regarding Fluence Calculation Methodology Concerning License Renewal Amendment Request for Additional Information Set 47, Question 4.2.1-2c in Entergy Letter GNRO-2013/00069 Dated 9/23/13
GNRO-2015/00031, Response to Request for Additional Information Regarding Fluence License Amendment Request
GNRO-2015/00011, Supplement to License Amendment Request Application to Revise the Current Methodology from 0 EFPY Through the End of Extended Operations to a Single Fluence Method
NOC-AE-14003131, Request for Additional Information Reactor Vessel Radiation Surveillance Program, TAC MF0699
NRC 2013-0005, License Amendment Request 252, Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-2007-198, Proposed License Amendment Update PT Curve and LTOP for 55 EFPY
L-2019-048, Response to Request for Additional Information (Rai), Subsequent License Renewal Application Safety Review Revision 1, Second Submittal Set 8
PLA-7841, Thirty-Day Response to Request for Additional Information Regarding Proposed License Amendment Requesting Application of Advanced Framatome Methodologies
NL-20-0458, Response to Request for Additional Information Related to License Amendment Request for Measurement Uncertainty Recapture Power Uprate
L-2023-012, License Amendment Request 23-01, Remove Period of Applicability (Poa) from Pressure Temperature Limits (PTL) and Low Temperature Overpressure Protection (L Top) Curves
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
GNRO-2015/00021, Follow-up Response to U.S. Nuclear Regulatory Commission Letter, Updated Fluence Methodology License Amendment Request Unacceptable with Opportunity to Supplement, Dated February 18, 2015, to Provide
NUREG/CR-7281, Radiation Evaluation Methodology for Concrete Structures
L-2022-044, Subsequent License Renewal Application Revision 1, Supplement 2
W3F1-2017-0004, Responses to Request for Additional Information from Sets 4, 5 and 6 Regarding the License Renewal Application
ULNRC-06354, Results of Analysis of Ex-Vessel Neutron Dosimetry for Reactor Vessel Radiation Surveillance Program
LR-N17-0092, Supplemental Information to 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
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
W3F1-2017-0027, Responses to Request for Additional Information Set 16 Regarding the License Renewal Application
JAFP-17-0103, Pressure and Temperature Limits Report, Rev. 1 (40 Effective Full-Power Years)
CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations
W3F1-2016-0070, Responses to Request for Additional Information Set 3 Regarding the License Renewal Application
L-2016-227, License Amendment Request Change to P /T Limit Curve and LTOP Period of Applicability
CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates
NL-16-0172, Response to Request for Information Regarding Changes to Technical Specification Section 1.0, 3.4.9, and 5.0
W3F1-2017-0065, License Amendment Request for Use of RAPTOR-M3G Code for Neutron Fluence Calculations
2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits
DCL-15-121, Responds to NRC Letter Dated September 24, 2015, Request for Additional Information for the Review of the License Renewal Application - Set 38
AEP-NRC-2015-94, Response to License Condition Regarding Analysis of Pressure and Temperature Curves for Ferritic Reactor Vessel Materials
RS-15-232, Response to NRC Requests for Additional Information, Set 9, Dated August 18, 2015 Related to the License Renewal Application
GNRO-2015/00058, Response to License Renewal Application (LRA) Request for Additional Information (RAI) Set 47, Question 4.2.1-2c (5) (a) I
NLS2015073, Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 2
CNL-15-124, Submittal of Response to NRC Request for Additional Information on the Proposed License Amendment Request to Modify Browns Ferry Nuclear Plant, Unit 3 P/T Limits (BFN TS-494)
RS-15-165, Response to NRC Requests for Additional Information, Set 2, Dated May 29, 2015 Related to the License Renewal Application
NRC-2014-0137, Comment (17) of Kevin Kamps on Behalf of Beyond Nuclear on Draft Guidance Regarding the Alternate Pressurized Thermal Shock Rule
NRC-2015-0073, Comment (1) of Anonymous Individual Opposing on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
CNS-15-024, WCAP-17993-NP, Revision 0-B, Justification for the Use of RAPTOR-M3G for the Catawba, Unit 1, Measurement Uncertainty Recapture (MUR) Power Uprate Fluence Evaluations
L-15-023, Response to Request for Additional Information Regarding a Request to Amend Technical Specification 3.4.11, RCS Pressure and Temperature (Pit) Limits
CNL-14-144, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-494)
CNS-15-007, License Amendment Request (LAR) for Measurement Uncertainty Recapture (MUR) Power Uprate - Response to NRC Requests for Additional Information (Rals)
CNL-14-221, Response to NRC Request for Additional Information Regarding Review of License Renewal Application, Set 23, B.1.34-9.d (Follow Up)
CNL-14-181, Response to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, Set 22, B.1.34-9c
L-14-289, Pressure and Temperature Limits Report. Revision 2
RS-14-265, Response to Request for Additional Information Regarding Request for Withholding Information from Public Disclosure by Electric Power Research Institute, Inc
L-MT-14-046, Submittal of the Pressure and Temperature Limits Report (Ptlr), Revision 1
RS-14-225, Stations, Units 1 & 2 - Response to NRC Request for Additional Information, Set 37, Dated July 7, 2014, License Renewal Application
CNL-14-065, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-491)
RS-14-149, Responses to NRC Requests for Additional Information, Set 22, Dated April 24, 2014, Related to the Byron Station, Units 1 and 2, and Braidwood Station, Units 1, and 2, License Renewal Application
1CAN051401, Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 1
NRC 2014-0016, Submittal of License Amendment Request 252 Technical Specification 5.6.5, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)- Response to Request for Additional Information
RS-14-079, Units 1 and 2 - Response to NRC Requests for Additional Information, Set 11, Dated February 18,2014 Related to the License Renewal Application
RS-14-002, Response to NRC Requests for Additional Information, Set 4, Dated December 12, 2013, Related to the License Renewal Application
GNRO-2013/00069, Response to Requests for Additional Information (RAI) Set 47, Dated August 28,2013
NL-13-081, Response to Request for Additional Information Regarding License Amendment Request Concerning PT-Limits and LTOP Requirements
NRC-13-0026, Response to Request for Additional Info Re Proposed License Amendment to Relocate Pressure and Temperature Curves to Pressure & Temperature Limits Report
PNP 2013-046, Updated Palisades Nuclear Plant Reactor Vessel Fluence Evaluation
L-MT-13-036, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement for Application of License Amendment 172
GNRO-2013/00003, Response to Requests for Additional Information 4.2.1-2b and 4.7.3-1a
NRC-12-0037, Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report
DCL-12-124, 10 CFR 54.21 (B) Annual Update to the Diablo Canyon Power Plant License Renewal Application and License Renewal Application Amendment Number 46
GNRO-2012/00156, Response to Requests for Additional Information (RAI) Set 42 Dated November 20, 2012
SBK-L-12256, WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation
GNRO-2012/00121, Response to Requests for Additional Information (RAI) Set 36 Dated September 14,2012
RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests
ULNRC-05891, Enclosure 1: Callaway Plant Unit 1 License Renewal Application - Request for Additional Information Set 4 Responses
GNRO-2012/00085, Response to Request for Additional Information (RAI) Set 25 Dated June 27, 2012
NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station
NLS2012023, Response to Request for Additional Information License Amendment Request to Revise Technical Specification 3.4.9, RCS Pressure and Temperature (Pit) Limits
BVY 11-078, Response to Request for Additional Information for Core Plate Hold Down Bolt Inspection Plan and Analysis
SBK-L-11186, License Amendment Request 11-06, Application to Revise the Applicability of the Reactor Coolant System Pressure - Temperature Limits and the Cold Overpressure Protection Setpoints
L-11-319, Pressure and Temperature Limits Report
NLS2011015, License Amendment Request to Revise Technical Specification Pressure/Temperature Limit Curves and Surveillance Requirements
NG-11-0320, Fourth 10-Year Inservice Inspection Plan
NL-11-0242, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), HNP-ISI-ALT-11
HNP-11-001, Request for License Amendment, Measurement Uncertainty Recapture Power Uprate
L-11-116, Pressure and Temperature Limits Report
GO2-11-083, Response to Request for Additional Information License Renewal Application
LIC-11-0041, Transmittal of Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
DCL-11-020, CFR 54.21(b) Update to the DCPP License Renewal Application
BVY 11-021, NEDO-33618, Revision 0, Vermont Yankee Core Plate Bolt Stress Analysis Report, Attachment 2 to Bvy 11-021
L-11-085, Regarding the Submittal of the Unapproved Pressure and Temperature Limits Report
CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)
RBG-47824, License Amendment Request to Correct a Non-Conservative Technical Specification Figure 3.4.11-1 Minimum Temperature Required Vs. RCS Pressure by Replacing with 54 Effective Full Power Years (EFPY) Curves
BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
W3F1-2018-0020, Responses to Request for Additional Information Set 18 Regarding the License Renewal Application
BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations
RA-18-0024, Supplemental Information to Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
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
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 4, Reactor
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
L-2016-198, Redacted Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 18.0 - Response to NUREG-0737 Clarification of TMI Action Plan Requirements
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor
L-2015-160, WCAP-17939-NP, Revision 0, Analysis of Capsule 97 Degrees from the Florida Power & Light Company St. Lucie, Unit 2, Reactor Vessel Radiation Surveillance Program, Part 2 of 3
L-2015-160, WCAP-17939-NP, Revision 0, Analysis of Capsule 97 Degrees from the Florida Power & Light Company St. Lucie, Unit 2, Reactor Vessel Radiation Surveillance Program, Part 1 of 3
RS-14-338, Byron/Braidwood Nuclear Stations, Updated Final Safety Analysis Report (Ufsar), Revision 15, Chapter 5 Reactor Coolant System and Connected Systems
RS-14-054, LaSalle, Unit 1, Supplemental Information Supporting License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature (Pit) Curves
RS-13-266, LaSalle County Station, Unit 1, License Amendment Request to Revise Reactor Coolant System (RCS) Pressure and Temperature Curves
NL-13-148, Browns Ferry, Unit 1, Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature Limits (BFN TS 484)
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
NRC-12-0037, Fermi 2, Proposed License Amendment to Relocate Pressure and Temperature Curves to a Pressure Temperature Limits Report
RA-18-072, Pressure and Temperature Limit Report Revision 1
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
RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 5.0, Reactor Coolant System and Connected Systems
NL-11-0387, WCAP-17343-NP, Rev 0, Analysis of Capsule Z from the Southern Nuclear Operating Company Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program, Enclosure 2 to NL-11-0387
BVY 10-071, Technical Specifications Proposed Change No. 293 Revised Reactor Vessel Pressure-Temperature Limitation Curves
L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 1; Descriptions and Technical Justifications for the Renewed Facility Operating License, Technical Specifications, and Licensing Basis Changes
GO2-10-169, Response to Request for Additional Information License Renewal Application
L-MT-10-054, Response to Requests for Additional Information Concerning Extension of Permanent Relief from Inspection Requirements of 10 CFR 50.55a(g) for Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the Renewed O
GO2-10-135, Response to Request for Additional Information, License Renewal Application
L-2010-078, Attachment 1, St. Lucie License Amendment Request Extended Power Uprate, Description and Technical Justifications for the Renewed Facility Operating License, Technical Specifications, and Licensing Basis Changes
L-PI-10-035, Supplement to License Amendment Request for Measurement Uncertainty Recapture - Power Uprate, Withdrawal of Proposed Change to Analysis Methodology for Pressure Temperature Limits Report
L-2009-222, Response to Request for Additional Information (RAI) Regarding Update to NRC Reactor Vessel Integrity Database and Exemption Request for Alternate Material Properties Bases Per 10 CFR 50.12 and 10 CFR 50.60 (B)
JAFP-09-0060, Summary of Commitment Changes for 2007 and 2008
NL-09-0464, Supplement to the Proposed License Amendment Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements (ME0788)
L-09-058, Comments on Safety Evaluation Report with Open Item Related to the License Renewal
NL-08-1758, Submittal of Revision 4 of the Pressure Temperature Limits Report
NL-08-143, Additional Information Regarding License Renewal Application - Reactor Vessel Fluence Clarification
NL-08-1385, Submittal of Revision 4 of the Pressure Temperature Limits Report
LIC-08-0071, Transmittal of Fort Calhoun, Unit 1, Reactor Coolant System Pressure and Temperature Limits Report, Revision 4
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 4.0 - Reactor
JAFP-08-0034, Application for Amendment to Technical Specifications Regarding Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) Consistent with TSTF-419-A
NL-08-0448, Unit 1, Submittal of Revision 3 of the Pressure Temperature Limits Report
RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR)
NL-08-0275, Response to 01/28/2008 Request for Additional Information
LIC-08-0013, Transmittal of Editorial Corrections to the Pressure Temperature Limits Report (PTLR)
L-08-060, License Renewal Application Amendment 1: Revision to Reactor Vessel Integrity Aging Management Program Information and Details of Reactor Vessel Surveillance Capsule Withdrawal Schedule Information
1CAN111401, Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
1CAN081403, Arkansas Nuclear One, Unit 1 - License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
NL-07-140, Reply to Request for Additional Information Regarding License Renewal Application
NRC 2007-0049, Supplement to License Amendment Request 251; Technical Specification 5.6.5., Reactor Coolant System Pressure and Temperature Limits Report
GNRO-2007/00034, Report of 10 CFR50.59 Safety Evaluations and Commitment Changes - April 1, 2006 Through March 31, 2007
PLA-6163, Proposed License Amendment Re Constant Pressure Power Uprate - Supplement
NL-07-0270, Proposed Alternative for RPV Circumferential Weld Examinations
NRC 2006-0090, License Amendment Request 251; Technical Specification 5.6.5, Reactor Coolant System Pressure and Temperature Limits Report
LIC-06-0138, Transmittal of Revision 3 of Fort Calhoun Station, Unit No. 1 (Fcs), Pressure Temperature Limits Report (PTLR)
NL-06-2262, Unit 2, Submittal of Revision 3 of the Pressure Temperature Limits Report
ULNRC-05315, Application for License Amendment to Revise Technical Specification 5.6.6; Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-2006-037, Reactor Vessel Surveillance Capsule, Proposed Change in Withdrawal Schedule
L-MT-06-060, License Renewal Application Update
NG-06-0439, Fourth 10-Year Inservice Inspection Plan
L-MT-06-049, (Mngp), Comments Regarding the Safety Evaluation Report for MNGP License Renewal Application
L-MT-06-029, Supplemental Information Regarding Monticello Nuclear Generating Plant License Renewal Application
BSEP 06-0026, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power
CNRO-2006-00010, Revised Request for Alternative to 10 CFR 50.55a Examination Requirements of Category B1.11 Reactor Pressure Vessel Welds
JAFP-06-0016, Proposed License Amendment: Changes to the Reactor Vessel Material Surveillance Program
NG-05-2208, License Amendment Request Pursuant to 10 CFR 50.90: Revision to the Plant Reactor Pressure Vessel Material Surveillance Program (TSCR-081)
CPSES-200502416, Revision to Technical Specification 5.6.6; Reactor Coolant System Pressure and Temperature Limits Report
L-2018-175, Subsequent License Renewal Application, Safety Review Requests for Additional Information (RAI) Set 5 Responses
L-2018-187, Subsequent License Renewal Application Revision to SLRA Section 3.5.2.2.2.6, Reduction of Strength and Mechanical, Properties of Concrete Due to Irradiation
RA-18-0163, Response to Request for Additional Information - Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report
RAIO-0418-59445, LLC Response to NRC Request for Additional Information No. 234 (Erai No. 9118) on the NuScale Design Certification Application. (Non-Proprietary)
L-2019-037, Subsequent License Renewal Application Safety Review Requests for Additional Information (RAI) Set 9 Responses
RA-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits
RA-19-0338, Pressure and Temperature Limits Report for Unit Nos. 1 and 2
CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)
NLS2019040, 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)
RA-19-0403, Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z
LIC-05-0081, Transmittal of Revision 1 of Fort Calhoun Station, Unit, Pressure Temperature Limits Report (PTLR)
NLS2005090, Calculation No. Nedc 05-019, Rev 0, Reactor Pressure Vessel Fluence Evaluation
NRC-05-0011, Proposed License Amendment Request to Revise the Reactor Coolant System Pressure and Temperature Limit Curves in Technical Specification 3.4.10
M190008, GE-Hitachi Nuclear Energy Americas, LLC - Peak Cladding Temperature/10 CFR 50.46 for Advanced Boiling Water Reactor (ABWR) Design Certification Renewal Application, Supplemental Information
ET 08-0043, Submittal of Supplemental Information on Proposed Changes to Technical Specifications
ET 08-0038, Application to Revise Technical Specification 5.6.6., Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr)
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
L-2004-244, Proposed License Amendment Extension of the Reactor Coolant System Pressure/Temperature Curve Limits and LTOP to 35 EFPY
RBG-46368, Additional Information Regarding River Bend Station Fluence Calculations
RS-04-133, Request for Changes Related to Technical Specifications Section 3.4.9, Reactor Coolant System Pressure-and Temperature (Pit) Limits
GO2-04-164, License Amendment Request to Revise the Reactor Pressure Vessel Material Surveillance Program
PLA-5811, Proposed Amendment No. 235 to License NFP-22: Changes to Reactor Pressure Vessel Pressure-temperature (P-T) Limits PLA-5811
RNP-RA/04-0098, Request for Technical Specifications Change to Reactor Coolant System Pressure and Temperature Limits
NL-04-1123, Request to Revise Reg Guide 1.190 Implementation Date
NL-04-0992, Response to Request for Additional Information Regarding Request to Revise Technical Specifications and Pressure and Temperature Limits Report
GO2-04-107, License Amendment Request to Revise Technical Specification 3.4.11, Reactor Coolant System Pressure and Temperature Limits
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
W3F1-2004-0047, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
NL-04-042, Reactor Vessel Material Surveillance Program: Preliminary Analysis Results for Capsule X
NLS2004043, Supplement to License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves, Figures 3.4.9-1, 3.4.9-2, & 3.4.9-3
LR-N04-0136, Request for Change to Technical Specifications Pressure/Temperature Limits
NLS2004042, Confirmation of Commitments Discussed in 03/05/04 Teleconference
GO2-04-032, Schedule for Requesting Revision of Technical Specification P/T Curves and Adoption of the BWRVIP Integrated Surveillance Program
NL-03-2177, Request to Revise Technical Specifications and Pressure and Temperature Limits Report
RS-04-032, Extension of Relief for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Additional License Operating Period
NG-04-0103, Request to Implement NDE-R047 Addressing Boiling Water Reactor Shell Weld Inspection Recommendations of the Boiling Water Reactor Vessel & Internals Project (BWRVIP) Report BWRVIP-05
NL-04-0073, Fluence Calculations and Methodology for the Unit I Updated Analysis of Core Shroud Vertical Welds
NLS2004005, License Amendment Request to Revise Technical Specification 3.4.9 Pressure Temperature (P/T) Curves Figures 3.4.9-1, 3.4.9-2, and 3.4.9-3
NLS2004004, Revision to Commitment Referenced to Amendment 201 Safety Evaluation
L-14-163, Response to Request for Additional Information on Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules
LIC-03-0124, Transmittal of Fort Calhoun Station (FCS) Pressure Temperature Limits Report (Ptlr), Revision 0
NG-03-0608, Revised Non-Proprietary GE Report GE-NE-A22-00100-08-01a-R2, Pressure-Temperature Curves for Duane Arnold Energy Center
RS-03-131, Additional Information Supporting Relief Request for Alternative Reactor Pressure Vessel Circumferential Weld Examinations for Fourth Interval Inservice Inspection Program
NRC 2003-0051, Response to Request for Additional Information (RAI) Regarding Request for Exemptions to 10 CFR 50.61, Appendices G & H to 10 CFR 50, and Approval of PTS Application for Pbnp Unit 2 and Proposed Heatup and Cooldown Limit Curves
RS-03-113, Reactor Coolant System Pressure & Temperature Limits
BSEP 03-0062, Request for License Amendments Re Implementation of the Boiling Water Reactor Vessel and Internals Project Reactor Pressure Vessel Integrated Surveillance Program to Address the Requirements of Appendix H to 10 CFR Part 50
NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years
NOC-AE-03001506, CFR 50.59 Summary Report
LIC-03-0052, Response to Request for Additional for Information, Pressure-Temperature Limits Report Amendment Request
GNRO-2003/00021, License Amendment Request to Revise Section 5.3 of UFSAR to Change Reactor Vessel Material Surveillance Program
NL-03-0704, Measurement Uncertainty Recapture Power Uprate Request for Additional Information Response
NG-03-0123, Technical Specification Change Request (TSCR-059): Adoption of Generic Letter 96-03: 'Relocation of Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits.'
L-MT-03-016, Response to Request for Additional Information Regarding Integrated Vessel Surveillance Program
RS-03-010, Supporting Documentation for Amendment to Technical Specifications Section 3.4.11, RCS Pressure and Temperature (P/T) Limits. Attachment 4, Table of Contents - Appendix F
NLS2002104, License Amendment Request, Adopt Integrated Reactor Vessel Material Surveillance Program
LR-N02-0406, Request for Change to Reactor Material Surveillance Program Hope Creek Generating Station
BSEP 02-0186, Response to Request for Additional Information, Proposed License Amendment to Revise Pressure - Temperature Curve Limits
PLA-5528, Supplement No. 1 to Proposed Amendment No. 247 to Unit 1 License No. NPF-14 and Proposed Amendment No. 212 to Unit 2 License No. NPF-22: Revision to the RPV Material Surveillance Program PLA-5528
L-2002-199, Reactor Vessel Surveillance Capsule Report of Test Results
DCL-03-052, Rev 0 to WCAP-15958, Analysis of Capsule V from Pacific Gas & Electric Co Diablo Canyon Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix a Through E
RNP-RA/02-0133, Response to Request for Additional Information on Amendment Request to Increase Authorized Reactor Power Level
NRC 2002-0075, Responses to Request for Additional Information License Amendment Request 226, Measurement Uncertainty Recapture Power Uprate
RBG-45990, License Amendment Request 2002-23 Re Request for a Change to the Reactor Vessel Material Surveillance Program from River Bend Station, Unit 1
NRC-02-0062, Proposed License Amendment for Participation in the BWRVIP ISP Plan for RPV Material Surveillance
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
PLA-5498, Proposed License Amendment Re Revision to the RPV Material Surveillance Program PLA-5498 for Susquehanna Steam Electric Station
RNP-RA/02-0104, License No. DPR-23, Response to Requests for Additional Information on Amendment Request to Increase Authorized Reactor Power Level
RNP-RA/02-0033, Part 1 of 2, H.B. Robinson Steam Electric Plant, Unit No. 2, Report of Analysis of Surveillance Capsule X for Reactor Vessel Radiation Surveillance Program
LR-N02-0039, Request for Change to Technical Specifications, Extended Use of Pressure - Temperature Limit Curves
NOC-AE-02001249, Additional Information to Support the Request for Approval of Power Uprate and a Revision to the Technical Specifications
GNRO-2020/00020, Core Operating Limits Report (COLR) Cycle 23, and Pressure and Temperature Limits Report (PTLR) Update for Grand Gulf Nuclear Station, Unit 1 (GGNS)
LR-N20-0033, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
NRC-20-0009, DTE Energy Company Transmittal of Revision to the Pressure and Temperature Limits Report (PTLR)
RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System
L-20-274, Amendment Request to Update Analytical Methods Used to Develop Reactor Coolant System Pressure and Temperature Limits
W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years
GO2-21-016, License Amendment Request to Change Technical Specification 3.4.11 Reactor Coolant System Pressure and Temperature Limits
CNL-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28)
WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 4
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 5
L-MT-22-021, 0 to Updated Safety Analysis Report, Appendix K, Revision 37, Renewed Operating License-USAR Supplement
RA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule
L-MT-23-030, Subsequent License Renewal Application Supplement 3
RA-21-0307, Subsequent License Renewal Application Response to NRC Requests for Confirmation of Information - Set 1
JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 23
L-24-189, License Renewal Application for Revision O - Supplement 1
NL-08-014, Clarifications to Reactor Vessel Surveillance Program and Neutron Embrittlement Time-Limited Aging Analyses and Audit Item 105; and Revision to License Renewal Regulatory Commitment List
DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1
NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant
RS-23-006, Supplemental Information Regarding License Amendment Request – Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report
L-MT-23-035, Subsequent License Renewal Application Supplement 5
CNL-24-011, Application for Subsequent Renewed Operating Licenses, Supplemental Information - Neutron Fluence Analyses Methodology
CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application – Sets 2 and 3
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
L-18-030, WCAP-18102-NP, Rev 1, Beaver Valley Unit 1 Heatup and Cooldown Limit Curves for Normal Operation
RAIO-0318-59069, LLC Response to NRC Request for Additional Information No. 107 (Erai No. 8984) on the NuScale Design Certification Application
RAIO-0518-59989, LLC Response to NRC Request for Additional Information No. 404 (Erai No. 9436) on the NuScale Design Certification Application
L-MT-17-075, 5 to Updated Safety Analysis Report, Appendix K, Introduction
L-17-292, Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule
JAFP-16-0172, Response to Request for Additional Information Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1 Implementation of BWRVIP-05
CNS-15-078, WCAP-18060-NP, Revision 1, Response to RAIs Concerning the Use of RAPTOR-M3G for the Catawba Unit 1 Measurement Uncertainty Recapture (MUR) Power Uprate Fluence Evaluations
CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (MUR) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations
PNP 2014-049, License Amendment Request to Implement 10 CFR 50.61 a, Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
NRC-15-0010, Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 16
CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (MUR) Power Uprate
NRC-15-0011, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 17
SBK-L-18151, 1 - Additional Changes to the NextEra Energy Seabrook License Renewal Application
ET 07-0014, Response to NRC Requests for Additional Information Related to Wolf Creek Generating Station License Renewal Application
NUREG-1916 Volume 2, Safety Evaluation Report - Related to the License Renewal of Shearon Harris Nuclear Power Plant, Unit 1
BVY 06-083, License Renewal Application, Amendment 12
BVY-06-083, License Renewal Application, Amendment 12
L-MT-05-111, Response to Requests for Additional Information Regarding the Plant License Renewal Application
PLA-5933, Proposed Amendment No. 280 to Unit 1, and Proposed Amendment No. 249 to Unit 2, Revise Technical Specification 3.4.10, RCS Pressure and Temperature (P/T) Limits
L-MT-05-052, Monticello. Response to Request for Additional Information and Submittal of Additional Information in Support of the Plant License Renewal Application
NRC 2004-0111, License Renewal Application Response to Request for Additional Information
NRC 2004-0085, License Renewal Application Revised Information
NL-04-0933, Application for License Renewal - Supplemental Information
RS-02-196, Revised Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits
RS-02-167, Request for Amendment to Technical Specifications Justification for the Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure and Temperature (P/T) Limits
RS-02-122, Justification for Continued Use of Technical Specifications, Section 3.4.11, RCS Pressure & Temperature (P/T) Limits
NG-03-0474, Revised Pages for General Electric Co. Report, GE-NE-A22-00100-08-01-R1, Pressure-Temperature Curves for Alliant Energy Duane Arnold Energy Center
RS-05-092, Response to Request for Additional Information - Pressure and Temperature Limits Curves for 54 Effective Full Power Years
RS-12-151, Fifth Interval Inservice Inspection Program Plan and Relief Requests
RBG-47835, Submittal of Response to License Renewal Application NRC Request for Additional Information Set 10
RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits
RA-21-0288, Subsequent License Renewal Application Supplement 2
LR-N21-0079, Submittal of Hope Creek Generating Station Technical Specification Bases Changes
L-MT-25-012, Pressure Temperature Limits Report for the Monticello Nuclear Generating Plant, Revision 2
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
L-2021-098, Update to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
JAFP-07-0125, ENT-FLU-002-R-005, Rev 0, James A. FitzPatrick, License Renewal Application - Amendment 14, Fluence Calculation, Non-Proprietary Version
LR-N07-0035, Response to Request for Additional Information Request for License Amendment - Extended Power Uprate
TMI-13-020, Supplemental Information - 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
LR-N25-0073, Pressure and Temperature Limits Report (PTLR) Revision 2