L-2018-039, License Renewal Application - Supplement 1
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
L-11-317, Reply to Request for Additional Information for the Review of License Renewal Application (TAC No. ME4640) and Amendment No. 20
L-11-238, Reply to Request for Additional Information for the Review of License Renewal Application and License Renewal Application Amendment No. 13
L-11-203, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 9
L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4
L-2011-070, Request for Additional Information Regarding Extended Power Uprate License Amendment Request No. 205 and Piping and Non-Destructive Examination Issues
DCL-10-168, Response to NRC Letter Dated December 20, 2010, Request for Additional Information (Set 37) for License Renewal Application
RNP-RA/17-0063, 7 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
L-2018-082, Turkey Point, Units 3 and 4 - Enclosure 2 to L-2018-082, Applications for Withholding Proprietary Information from Public Disclosure Per 10 CFR 2.390 (Public Version)
L-2018-004, Enclosure 2 - Applications for Withholding Proprietary Information from Public Disclosure Pursuant to 10 CFR 2.390
NL-17-0534, Joseph M. Farley Nuclear Plant - Submittal of Updated Final Safety Analysis Report, 10 CFR 50.59 Report, Fire Hazard Analysis Changes, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and Revised NRC Commitme
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2 Decrease in Heat Removal by the Secondary System, Redacted
DCL-10-131, Response to NRC Letter Dated September 23, 2010, Request for Additional Information (Set 25) for the Diablo Canyon License Renewal Application
GO2-10-135, Response to Request for Additional Information, License Renewal Application
LR-N10-0346, Response to NRC Request for Additional Information Re CASS Materials & CASS Safety Injection Valves
LR-N10-0192, Response to NRC Request for Additional Information Dated May 14, 2010 Related to Aging Management Program B.2.1.6, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel
NRC 2010-0035, Response to Request for Additional Information on License Amendment 261 Extended Power Uprate
HNP-08-045, Second Ten-Year Interval Inservice Inspection Program-Final Documentation Including Requests for Relief in Accordance with 10 CFR 50.55a
PLA-6449, Request for Additional Information for the Review of License Renewal Application, Section B.2.1 - Questions and Responses
PLA-6391, Response to Request for Additional Information for the Review of License Renewal Application (Lra), Sections B.2.23, B.2.24, B.2.26, B.2.27, B.2.28, B.2.31
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis
NL-07-124, Supplement to License Renewal Application (LRA)
NL-07-069, Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval
WM 07-0049, License Renewal Application, Amendment 1
JAFP-07-0019, License Renewal Application, Amendment 9
NL-06-085, 2006 Summary Reports for In-Service Inspection and Repairs or Replacements
L-2018-193, Set 6 Responses to Request for Additional Information (RAI) on Subsequent License Renewal Application Safety Review
DCL-05-022, Inservice Inspection Report Twelfth Refueling Outage
DCL-04-111, Inservice Inspection Report for Diablo Canyon Unit 1 Twelfth Refueling Outage
NL-04-006, St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval
RNP-RA/03-0031, Response to Request for Additional Information Re Application for Renewal of Operating License, Attachment III, Pages 356 - 504
NRC 2021-0003, Refueling 39 (U1 R39) Reactor Coolant Pump Analytical Evaluation Report
1CAN039211, Provides Info to Change Util Commitment to Perform single-wall Radiography in Pump Casing & to Instead Conduct Reactor Coolant Pump Casing Structural Integrity Exams & Evaluations Using Methodology Contained in Listed ASME Case
L-96-028, TER on Third 10-Yr Interval Inservice Insp Program Plan: Consumers Power Co for Palisades Nuclear Plant
NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481
1CAN069207, Forwards Proprietary Pages to Summary Rept for Reactor Coolant Pumps Per Requirements of ASME Code Case N-481, Submitted by .Pages Withheld
1CAN089202, Requests 30-day Extension of Submittal Date for Inservice Insp Outage Summary Rept Due to Be Submitted on 920807. Extension Required Due to Heavy Workload Following Tenth Refueling Outage Which Ended on 920509
1CAN069201, Forwards Rev 0 to SIR-92-037, ASME Code Case N-481, Evaluation of Arkansas Nuclear One Unit 1 Reactor Coolant Pumps. Rept Provides Results of VT-2 Exam & ASME Code Case N-481 Evaluation
LIC-95-0120, Forwards Response to Anomalies Noted in SER for Third 10-yr Interval IST Program for Fcs,Ist Selection Philosophy & Rev 2 to ISI Program Plan for 1993-2003 Interval
LIC-95-0063, Provides Response to Request for Addl Info Re ISI Program Plan.Rev 2 to SEI-27, ISI & Test Program, Encl. W/Five Oversize Drawings
1CAN099302, Forwards Relief Request from Requirements of IWB-2420(b) of ASME Boiler & Pressure Vessel Code,Section XI,1980 Edition Re Successive Insps of RCP Weld Flaw Indications
1CAN049202, Forwards Scoping Evaluation for Arkansas Nuclear One,Unit 1 Reactor Coolant Pumps Per Requirments of ASME Code Case N-481, Consisting of 1986 & 88 Insp Results & 1986 & 88 Fracture Mechanics Evaluations.W/One Oversize Drawing
1CAN079304, Advises That NRC Review of Previously Submitted Code Case N-481 Evaluation Re Addl Exam of Reactor Coolant Pumps No Longer Required,Per NRC .Util Will Invoke Code Per Reactor Coolant Pump Insp Plan
L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004
RA-19-0131, 8 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
L-2018-166, WCAP-15355-NP, Revision 0, a Demonstration of Applicability of ASME Code Case N-481 to the Primary Loop Pump Casings
L-2018-151, Subsequent License Renewal Application Owners Group Topical Reports - Equivalency of Revision 0 and Revision 1 Documents
LR-N18-0053, 0 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement
LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
L-92-320, Advises That Util Intends to Invoke ASME Boiler & Pressure Vessel Code Case N-481, Alternative Exam Requirements for Cast Austenitic Pump Casing in Place of Relief Request 7 in Second 10 Yr Insp Plan
LR-N17-0034, 9 to Updated Final Safety Analysis Report, Appendix B, License Renewal Final Safety Analysis Report Supplement
3F0909-04, Response to Requests for Additional Information for the Review of the License Renewal Application and Amendment 3
L-2008-158, Submittal of In-Service Inspection Program Third Interval - Third Period Owners Activity Report for SL1-20 and SL1-21 Outages
L-2000-179, In-Service-Inspection Program, Third Interval Second Period, Owners Activity Reports for Refueling Outages SL1-18 and SL1-19
RNP-RA/03-0057, Submittal of Proprietary Documents in Support of License Renewal Application
PLA-6401, Response to Request for Additional Information for the Review of License Renewal Application (LRA) Sections 3.1, 3.2, 3.3, and 3.4
NRC 2005-0024, Response to Request for Additional Information Regarding the License Renewal Application
RS-03-181, Stations - Additional Information for the Review of the License Renewal Application
LIC-93-0071, Requests Interim Relief from Performing RCP Casing Volumetric Weld & Internal Surface Visual Exams & Provides Info Requested on 930122 by SD Bloom Re Levels of Personnel Radiation Exposure During Performance of RCP Exam