9, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
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Information Notice 1995-09, Use of Inappropriate Guidelines and Criteria for Nuclear Piping and Pipe Support Evaluation and Design
NUREG-0823, Supplement No. 1, Integrated Plant Safety Assessment, Systematic Evaluation Program
CNS-14-125, Request for Relief Number 14-CN-002 Continued Use of High Density Polyethylene (Hdpe) Material in Nuclear Safety Related Piping Application
CNS-14-097, Request for Relief Number 14-CN-002, Continued Use of High Density Polyethylene (Hdpe) Material in Nuclear Safety Related Piping Application
RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests
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 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
RS-16-248, Byron/Braidwood Nuclear Stations, Revision 16 to Updated Final Safety Analysis Report, Appendix a - Application of NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Figures 3.7.B.2-27 Through 3D-17
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.8.5-1 - 3.12-6
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3.6-1 - 3.7-223
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3-i - 3.5A-4
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
L-MT-10-023, CFR 50.55a Request No. 18: Alternative to Apply ASME Code Case N-705 to the Standby Liquid Control System Tank
PLA-6550, Comment (19) of T. S. Rausch on Behalf of PPL Susquehanna, LLC Re Draft Regulatory Guides; DG-1191, DG-1192 and DG-1193
NOC-AE-08002311, Withdrawal of Relief Request (RR-ENG-2-50)
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 5.0 - Reactor Coolant System and Connected Systems
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
PLA-6149, Comment (9) of B. T. Mckinney on Behalf of PPL Susquehanna, LLC on Draft Regulatory Guides DG-1133 and DG-1134
NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants
NMP2L2711, Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879
ND-19-0666, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report
ET 11-0003, Correction to 10 CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1
LR-N04-0310, Response to Request for Additional Information Regarding Request for Change to Technical Specifications to Support Removal of the Reactor Vessel Head Spray Piping Hope Creek Generating Station
DCL-04-016, Inservice Inspection Relief Request for ASME Code Case N-579
NL-03-2552, Relief Request RR-53, Use of Alternate Code Case for New Construction of Replacement Reactor Vessel Head Adaptors
M200041, GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 05 - Reactor Coolant System and Connected Systems
RS-20-142, Proposed Alternative to Utilize Code Case N-893
IA-86-669, Partial Response to FOIA Request for Info Re Generic Safety Issues & Gimcs.Forwards App C Document.App B & C Documents Available in PDR
A05975, Requests NRC Confirmation of Util Interpretation of Reg Guide 1.84 Applicability to plant-specific Use of ASME Code Case N-4111, Alternate Damping Values for Seismic Analysis of Class 1,2 & 3 Piping Sections,Section Iii,Div I
AECM-86-0233, Informs That 860513 Request for NRC Review Re Approval of Use of ASME Code Case N-411 Unnecessary Due to Issuance of Rev 24 to Reg Guide 1.84
NSD-NRC-97-5124, Forwards Draft SSAR Markups Re Structural Related Issues. Changes Will Be Included in Rev 13 of SSAR
3F0497-05, Submits Info Re Revised LTOP in Response to . Exemption to Use ASME Code Case N-514 Requested
AECM-87-0019, Forwards Summary Rept of Safety Evaluations Conducted as Result of Updated FSAR Change Notice Review Program,Per Util 860410 Response to Violation 50-416/86-02-01
ST-HL-AE-1839, Discusses Seismic Analysis Performed Using Code Case N-411 Damping Values.Listed Study Calculation Program & Methodology Meets Criteria Set Forth in
ST-HL-AE-2093, Forwards Revised FSAR Section 3.12, Conformance W/Nrc Reg Guides. Section Updated to Reflect Util Position on All Applicable Reg Guides
SECY-22-0075, Staff Requirements-SECY-21-0029 Inservice Testing and Inservice Inspection Program Rulemakings Update (NRC-2018-0291/3150-AK23)
NSD-NRC-96-4745, Provides Info Required for Closure Re Status of Dser Open Items Re Piping Analysis
NSD-NRC-96-4759, Responds to NRC Position on Damping Values to Be Used in Piping Analyses When Sys Model Includes Flexible Equipment. Requests NRC Reaffirm Position in Subsection 3.12.5.19 of Dser That Use of 5% Damping,Acceptable for Piping Sys
NRC-95-4555, Requests Approval of Use of ASME B&PV Code Case N-284,Rev 1 for Const of Components in Nuclear Power Facility
NRC-94-4184, Forwards Responses to NRC RAIs on AP600 from NRC 940316, 0419,29,0502,11,12,23 & 26 Ltrs.Revs of Responses Previously Submitted Also Provided,Completing Responses for NRC
RC-94-0232, Forwards Eleventh Annual 10CFR50.59 Rept for VC Summer Nuclear Station.Rept Contains Brief Description of Changes & Mods Made to Facility or QA Program,As Described in FSAR & Fire Protection Evaluation Rept
TXX-6912, Forwards Description of Amend 65 to Fsar.Amend,Transmitted Under Separate Cover,Includes Listed Revs,Including Fire Protection,Electrical Separation,Power Sys,Testing,Util Organization & Electrical Grounding
TXX-5003, Amends 860826 Request for NRC Approval to Use ASME Code Case N-253-4,changing Code Case to N-253-2
TXX-6086, Forwards FSAR Revs Reflecting Mods to Design Basis in Response to Modified GDC 4.Revs Will Be Documented in Future FSAR Amend.Cp Amend Not Required
LD-92-123, Forwards Section 17.3, Design Reliability Assurance Program Plan for Sys 80+ Standard Design, Rev 1 & Responses to 79 Issues Identified in Dser for Sys 80+
LD-92-091, Forwards Responses to 920409 Request for Addl Info Re Sys 80+ Severe Accident Design Features
PY-CEI-NRR-1499, Suppls Re Snubber Optimization of Feedwater Sys. Results of post-mechanical Stress Improvement Program Revealed No Significant Change in Size of Existing Indications
PY-CEI-NRR-1491, Forwards Rev 0 to Evaluation of Flaw Indication(S) in Perry Feedwater Nozzle to Safe-End Welds, Summary Technical Rept,Per Generic Ltr 88-01
LD-92-063, Forwards Info to Supplement 920325 Responses to NRC Request for Addl Info Re Analysis of Ruptured Reactor Coolant Pump Seal Cooler Tube & Single Failure Assumptions for Analysis of moderate-energy-line Break
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
RC-93-0234, Forwards Tenth Annual 10CFR50.59 Rept for VC Summer Nuclear Station
SECY-24-0040, Weekly Information Report Week Ending May 10, 2024
PMNS20240515, Meeting on Code Case N-883, Construction of Items Prior to the Establishment of a Section III, Division 1 Owner, Section III, Division 1
NRC-24-0027, Partial Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance
PMNS20240683, Continuation of the May 8th Public Comment Gathering Meeting on Code Case N-883, Construction of Items Prior to the Establishment of a Section III, Division 1 Owner, Section III, Division 1
RS-12-070, Response to Follow-up RAI Questions Related to Exelon Response to RAI Question 7
PMNS20240420, Meeting on Code Case N-883, Construction of Items Prior to the Establishment of a Section III, Division 1 Owner, Section III, Division 1
NRC-24-0064, Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance
LD-92-007, Forwards Response to Matls & Chemical Engineering Branch 910808,Structural & Geosciences Branch 910926 & Plant Sys Branch 911010 Requests for Addl Info Re SSAR - Design Certification
L-87-435, Informs of Util Intent to Use ASME Boiler & Pressure Vessel Code Case N-237-2, Hydrostatic Testing of Internal Piping, Section Iii,Div I,Classes 2 & 3 for Second 10-yr Insp Intervals,Per Reg Guide 1.84
GO2-87-142, Responds to 870209 Telcon Re Util 870121 Request to Implement ASME Code Case N411 in Piping Design.Staff Agreed That Code Case N411 May Be Implemented If Compliance W/ Analysis Stipulations of Reg Guide 1.84 Satisfied
GO2-87-026, Requests Approval to Apply ASME Code Case N411 on Facility, to Enhance Sys Reliability & Personnel Safety Through Optimization of Snubber Installations.Fee Paid
GO2-84-467, Requests Approval to Apply ASME Section III Code Case N-341 to ASME Section XI Certification activities.Five-yr Certification Provision Incorporated Into Section XI 1983 Edition But Not Yet Approved
GO2-84-071, Requests Authorization to Use ASME Code Case N-362 for Pressure Testing of Containment Items,Per 840210 Telcon
SRM-COMSECY-17-0041, NUREG-1100, Vol. 34, Congressional Budget Justification Fiscal Year 2019
ET 14-0039, CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1
RAIO-1217-57599, LLC Response to NRC Request for Additional Information No. 253 (Erai No. 9184) on the NuScale Design Certification Application
ET 10-0019, CFR 50.55a Request for Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division 1
CLI-09-07, Staff Assessment of the Oyster Creek 3-D Finite Element Analysis of the Drywell Shell
Press Release-98-202, Nuclear Regulatory Commission Has Received Seven Reports from Advisory Committee on Reactor Safeguards Following Committees Meeting on September 2-4 and September 30-October 2
RS-12-151, Fifth Interval Inservice Inspection Program Plan and Relief Requests
ET-NRC-92-3777, Forwards Westinghouse Responses to NRC Requests for Addl Info on AP600 from 920923 & 1001 Ltrs.Transmittal Partial Response to Ltrs.Listing of NRC Requests for Addl Info Responded to in Ltr Contained in Attachment a
TXX-4610, Discusses Implementation of NRC 850605 Conditions for Use of ASME Code Case N-397 Re Alternative Method for Spectral Broadening & N-411 Re Alternative Damping Factors. Expeditious Approval for Use of Code Cases Requested
PY-CEI-NRR-0265, Notifies & Requests Approval of Use & Implementation of ASME Code Case N-393,per Reg Guide 1.84 & 10CFR50.55(a)(3).Code Case Applied to Repair Welds on Carbon Steel W/Gas Tungsten Arc Process
LD-95-011, Forwards Rev Pages for Sys 80+ Design Control Document. Margin Bar Adjacent to Change & Rev Date Will Be Added to Revised DCD Page
RA-23-0310, Proposed Alternative for Continued Service of High-Density Polyethylene (Hdpe) Material in Class 3 Buried Piping
L-PI-25-041, CFR 50.55a Request Nos. 1-RR-5-16 and 2-RR-5-16, Proposed Alternative to Conditions for Applying Code Case N-513-5, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping and Gate