DCL-16-117, Reactor Coolant System Pressure and Temperature Limits Report, Revision 15
DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information
1CAN041502, Responses to Request for Additional Information Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits
DCL-14-021, Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 2
DCL-14-011, Reactor Coolant System Pressure and Temperature Limits Report
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
DCL-13-023, Reactor Coolant System Pressure and Temperature Limits Report
NOC-AE-11002742, Response to Requests for Additional Information for the License Renewal Application
DCL-11-021, Comments on the Safety Evaluation Report with Open Items Related to License Renewal
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 5, Reactor Coolant System
DCL-10-131, Response to NRC Letter Dated September 23, 2010, Request for Additional Information (Set 25) for the Diablo Canyon License Renewal Application
DCL-09-075, Pressure and Temperature Limits Report, Revision 10
L-PI-09-086, NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses
DCL-08-030, Transmittal of Pressure and Temperature Limits Report, Revision 9
DCL-07-103, Pressure and Temperature Limits Report, Revision 8, Effective October 25, 2007
DCL-07-061, Pressure and Temperature Limits Report, Revision 7
WM 07-0049, License Renewal Application, Amendment 1
L-HU-06-026, Supplement to Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity
05000272/LER-1994-017, :on 941117,determined That Margin for Pressurizer Overpressure Protection During Low Temp Conditions Inadequate.Caused by Design Deficiency.Procedure & Program Commitment & Compliance Reemphasized
L-92-095, Pressure-Temp Curves & LTOP Setpoint Curve for Max Reactor Vessel Fluence of 2.192 X 10^19 Neutrons/cm^2
ULNRC-05219, Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program
DCL-05-093, Pressure and Temperature Limits Report. Revision 6
DCL-05-047, Pressure and Temperature Limits Report (PTLR-1), Revision 5
DCL-05-016, Pressure and Temperature Limits Report (PTLR-1), Revision 4
DCL-05-001, Pressure and Temperature Limits Report (Ptlr). Revision 3
ET 09-0010, Pressure and Temperature Limits Report, Revision 1
L-2004-244, Proposed License Amendment Extension of the Reactor Coolant System Pressure/Temperature Curve Limits and LTOP to 35 EFPY
NL-04-0548, Request to Revise Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
NL-04-0134, Request to Revise Technical Specifications to Relocate the Cold Overpressure Protection System Arming Temperature
NL-03-093, Proposed Changes to Technical Specifications: Pressure-Temperature and Overpressure Protection System Limits for Up to 20 Effective Full Power Years
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
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
2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12
ULNRC-03823, Informs Commission of Implementation of Amend 124 to License NPF-30.Amend Modifies Plant Heatup & Cooldown Curves & Max Allowable PORV Setpoints for Cold Overpressure Protection
ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits
3F0997-11, Forwards Response to 970812 RAI Re Proposed License Amend for low-temp Overpressure Protection
3F1097-12, Provides Rev to LTOP Sys TS Change Request Notice 213, Including PORV Lift Setpoint TS Limit,Revised for Instrument Uncertainty.Calculation Encl
LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable
ULNRC-03638, Requests Exemption from 10CFR50.60 in Order to Apply Guidance in ASME Code Case N-514, Ltop. Exemption Supports Amend to Ts,Revising Heatup,Cooldown & Cold Overpressure Mitigating Sys Curves
3F1197-39, Informs NRC That FPC Is Changing Commitments Re LTOP as Stated in .Ltop Features as Proposed by TS Change Request Notice 213,rev 1,under Administrative Controls,Will Be Used.List of Commitments Attached
3F0797-10, TS Change Request Notice 213,rev 0 to License DPR-72, Establishing Requirements for Low Temperature Overpressure Protection Sys
3F1098-04, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) Sections 5.6.2.19,ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits
3F0697-23, Confirms That FPC Has Implemented Administrative Controls, Revised PORV Setpoint & Revises Commitment to Submit TS Change Request for LTOP Features at Plant
3F0497-05, Submits Info Re Revised LTOP in Response to . Exemption to Use ASME Code Case N-514 Requested
1CAN119608, Forwards Proposed ANO-1 TS Amend Request That Revises Svc Period & Associated Figures IAW TS 3.1.2.7,3.1.2.8 & 10CFR50,App G,For Review & Approval
WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)
NOC-AE-000521, Revised Application for Amends to Licenses NPF-76 & NPF-80,to Incorporate Administrative Word Change,Add Two Surveillances to Cold Overpressure Mitigation Sys (COMS) TS & Incorporate Two Functions Into Methodology
NOC-AE-000516, Forwards Response to NRC 990322 RAI Re Proposed Amend to TS 3.4.9.3 to Reflect Revised Cold Overpressure Mitigation Curve Associated with Replacement SG
NOC-AE-000436, Requests Exemption to 10CFR50.60, Acceptance Criteria for Fracture Prevention for Lightwater Nuclear Power Reactors for Normal Operation, to Apply ASME Code Case N-514 Guidance, Ltop
2CAN069602, Forwards Revised Spec 3/4.4.12,including New 24 H Action Statement for Single Inoperable LTOP Relief Valve in Modes 5 & 6,per Discussion W/Nrc Re 960411 Proposed TS Change on LTOP as Requested by GL 90-06
2CAN049601, Application for Amend to License NPF-6,revising TS Re LTOP & Request for Exemption to 10CFR50.60 for ASME Code Case N-514
2CAN129504, Discusses Info Re Schedule for GL 90-06 Resolution
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
3F0209-05, License Amendment Request 307, Revision 0, Methodology for Rod Ejection Accident Analysis Under Extended Power Uprate Conditions
05000327/LER-1993-010, :on 930430,Westinghouse Identified Error in Development of Calculations for Cold Overpressure Mitigation Sys Setpoints.Caused by Vendor Failure to Consider Elevation Difference.Engineering Evaluation Performed
05000266/LER-1993-003, :on 930319,discovered That Setpoints for Low Temp Overpressure Sys Nonconservative.Caused by Failure to Recognize RCS Pressure Transmitters in Subj Sys Development Analysis.Operations Special Order Issued
L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
05000272/LER-1994-017-01, :on 941117,listed Assumptions Could Place Unit 1 Outside Design/Licensing Basis for Pops Analysis.Pdp Operation Not Considered in Any Design Basis Pressure Limit of 450 Psig
L-93-290, Annual 10CFR50.59 Rept on Changes Test & Experiments for 920701-930601
05000250/LER-1993-005-01, :on 930325,discovered That Setpoint for Overpressure Mitigating Sys Outside Limiting Design & Licensing Bases When RCS Is Water Solid.Caused by Erroneous Pressure Differential.Controls Instituted
L-93-093, Requests Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Light Water Nuclear Power Reactors for Normal Operation
L-95-139, Application for Amend to License DPR-67,extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation
PNP 2011-016, License Amendment Request for Primary Coolant System Pressure-Temperature Limits
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
RS-05-103, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limits Report and Request for Exemption from 10 CFR 50 .60, Acceptance Criteria for Fracture Prevention Measures for
BW050010, Pressure and Temperature Limits Reports (Ptlrs), Revision 3
BW050018, Corrected Pressure and Temperature Limits Reports (Ptlrs), Revision 3, Braidwood Station, Units 1 and 2
DCL-03-177, Response to NRC RAI Regarding License Amendment Request 02-04, Revision of Technical Specification 5.6.6 - Reactor Coolant System Pressure and Temperature Limits Report
BW020110, Pressure & Temperature Limits Reports (Ptlrs), Revision 2, Braidwood Station, Units 1 & 2
BW020086, Response to U. S. NRC Request for Additional Information Regarding the Braidwood Station Pressure-Temperature Limits Reports
DCL-24-118, License Amendment Request 24-06, Revision to Technical Specification 1.1 and Addition of 5.5.21 to Use Online Monitoring Methodology
L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes
DCL-23-117, Reactor Coolant System Pressure and Temperature Limits Report
WBL-25-032, Unit 2 - Revised Pressure and Temperature Limits Reports (PTLR)