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Category:Graphics incl Charts and Tables
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Pages in category "Graphics incl Charts and Tables"
The following 200 pages are in this category, out of 2,915 total.
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- 2CAN011502, Response to Request for Additional Information Concerning the Spring 2014 Steam Generator Inspections
- 2CAN012401, U.S. Additional Protocol
- 2CAN070807, Transmittal of Request for Alternative ANO2-PT-001 Visual Examination of Extended Reactor Coolant Pressure Boundary Piping During System Leakage Tests
A
- AEP-NRC-2008-56, Groundwater Permit Renewal Application
- AEP-NRC-2012-78, Final Report Kld TR-488, Revision 1, Development of Evacuation Time Estimates, Table K-1. Evacuation Roadway Network Characteristics
- AEP-NRC-2013-82, Revision to Regulatory Commitment Associated with Application for Renewed Operating License
- AEP-NRC-2014-16, Six Month Status Report in Response to March 12, 2012, Commission Order Modifying Licensees with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
- AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report
- AEP-NRC-2022-62, 1 to Updated Final Safety Analysis Report, Chapter 14.3, Reactor Coolant System Pipe Rupture (Loss of Coolant Accident) (Unit 1)
B
- BSEP 13-0071, Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Supplement to Walkdown Report
- BVY 10-069, License Renewal Application Annual Update Information
- BVY 13-037, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
- BVY 13-054, Response to Request for Additional Information Regarding Relief Request Nos. ISI-01 and ISI-03
- BVY 13-065, Response to Request for Additional Information Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)
- BYRON 2006-0007, Steam Generator Eddy Current Inspection Report, Cycle 12 Refueling Outage. Attachment B - Attachment B.5, Pages 17 Through 22
- BYRON 2022-0045, Day Inservice Inspection Report for Interval 4, Period 2, (B2R23)
C
- CNL-13-105, Response to NRC Request for Additional Information Regarding Review of the License Renewal Application, Sets 10 (3.0.3-1, Requests 3, 4, 6), 12 (B.1.6-1b, B.1.6-2b), 16 (4.3.1-8a)
- CNL-14-036, Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, Flooding, Of.....
- CNL-14-118, Confirmatory Action Letter Tier 2 Commitments Related to Integrated Improvement Plan
- CNL-15-213, Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License
- CNL-17-141, Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status
- CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)
- CNL-20-076, Response to Request for Additional Information Re Application to Revise Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency (SQN-TS-20-01)
- CNL-24-041, Enclosure 6: SQN Hourly Met 2004-2013
- CNRO-2005-00023, Response to Request for Additional Information Supporting Request for Alternative W3-R&R-003 Proposed Alternative to ASME Requirements for Weld Repairs
- CNRO-2018-00011, Submittal of Joint Plant Access Shared Information Table
- CNS-14-100, Relief Request Serial Number 14-CN-001, Relief Request for Limited Volumetric Examination of Class 1 Welds
- CP-200900283, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request
- CP-201300788, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), Response to Request for Additional Information
- CP-201900070, Commitment to Maintain Severe Accident Management Guidelines
- CPSES-200601160, Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.
- CY-02-012, Project Response to AIF Generator Survey
- CY-05-002, Letter to NRC Document Control Desk from G. Bouchard, Connecticut Yankee Atomic Power Company, Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002
- CY-05-018, Connecticut Yankee Atomic Power Company, 10 CFR 20 Appendix G Investigation
- CY-05-022, License Termination Plan Supplemental Information - Survey Areas Potentially Affected by Groundwater Contamination and Capture Zone Analysis
- CY-05-057, Supplemental Information Regarding the Request or Approval of Proposed Procedures, in Accordance with 10 CFR 20.2002
- CY-05-061, Supplemental Information Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002
- CY-05-090, Additional Information Regarding Request for Approval of Proposed Procedures in Accordance with 10 CFR 20.2002
- CY-05-117, Annual Radioactive Effluent Release Report
- CY-05-246, Revision to the Connecticut Yankee Quality Assurance Program (Cyqap)
- CY-06-070, 10 CFR 20, Appendix G Investigation
D
- DCL-06-080, PG&E Response to NRC Request for Additional Information Regarding, Special Report 06-01 - Results of Steam Generator (SG) Tube Inspections for Diablo Canyon, Unit 1 Thirteenth Refueling Outage
- DCL-08-021, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule
- DCL-10-083, Water Supplier Table
- DCL-11-023, Response to Summary of Telephone Conference Call Held on 02/28/2011, Between U.S. Nuclear Regulatory Commission & PG&E Co. Concerning Responses to Requests for Additional Info. for Renewal Application
- DCL-12-041, 2011 Annual Radiological Environmental Operating Report. Part 4 of 5
- DCL-14-081, Diablo Canyon Units 1 and 2, Central Coastal California Seismic Imaging Project (Cccsip) Chapter 2, GEO.DCPP.TR.12.01 R1 Figures 09-02-14
- DCL-14-081, Diablo Canyon Units 1 and 2, Central Coastal California Seismic Imaging Project (Cccsip) Chapter 5, GEO.DCPP.TR.14.04 R0 App A-G Figures 08-06-14
- DCL-14-110, One-Hundred-Twenty-Day Response to NRC Request for Additional Information - National Fire Protection Association Standard 805, Part 1 of 2
- DCL-15-131, Pressurizer Spray Line Pipe Weld Flaw Evaluation, Calculation Package, Part 2
- DCL-22-039, Irradiated Fuel Management Plan, Revision 1
E
- ENOC-07-00036, Entergy Operations, Inc. - Supplemental Information in Support of Application for Order Approving Indirect Transfer of Control of Licenses
- ENOC-08-00040, Commitment Update Relating to Application for Order Approving Indirect Transfer of Control of Licenses
- ET 09-0026, Notification of Deviation from EPRI Pressurized Water Reactor Secondary Water Chemistry Guidelines
- ET 09-0031, Supplemental Information Regarding NRC Request for Additional Information for Responses to Generic Letter (GL) 2004-02
- ET 14-0011, Second Six-Month Status Report for the Implementation of Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
- ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components
G
- GNRO-2012/00107, Vibration Data Report and Commitment Change
- GNRO-2014/00010, Draft Plant-Specific Supplement 50 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants
- GNRO-2015/00031, Response to Request for Additional Information Regarding Fluence License Amendment Request
- GO2-15-043, Response to Request for Additional Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423, Revision 1
H
- HBL-10-005, Revision 8 to the Defueled Safety Analysis Report, Revision 26 to the Quality Assurance Plan, and Revision 3 to the Technical Specifications Bases
- HBL-20-013, Final Status Survey Report for the Humboldt Bay Power Plant (Office Annex, Security Building, Intake Structure, Count Room Building, and Waste Management Facility)
- HNP-15-043, Response to Request for Additional Information 4 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints
I
J
- JAFP-04-0190, In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)
- JAFP-05-0179, Enclosure 13, Calculation JAF-CALC-ELEC-02610 125VDC B Station Battery Sizing & Voltage Drop Revision 2, Appendix 4, Page 2 of 2, SBO
- JAFP-10-0088, Submittal of Corrections to the 2004, 2005, 2006, 2007, and 2008 Annual Radioactive Effluent Release Reports
- JAFP-14-0145, Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
- JAFP-15-0017, J.A. Fitzpatrick - Response to Regulatory Issue Summary 2014-13
- JAFP-16-0060, James a Fitzpatrick - Extension to Commitments Made in Response to March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3, Emergency Communication and Staffing Assessments
- JAFP-16-0110, Correction to 2014 Annual Radioactive Effluent Release Report
L
- L-04-057, Units I and 2 - Annual Radioactive Effluent Release Report for 2003, and Annual Radiological Environmental Operating Report for 2003
- L-05-006, Response to Request for Additional Information in Support of License Amendment Requests Nos. 317 and 190
- L-05-066, Annual Environmental Report, Non-Radiological
- L-05-130, Responses to a Request for Additional Information (RAI Dated June 30, 2005) in Support of License Amendment Request Nos. 302 and 173
- L-08-094, Response to Request for Additional Information Regarding Measurement Uncertainty Recapture Power Uprate Amendment Application
- L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45)
- L-14-064, Supplemental Information Regarding Application for License Amendment to Adopt NFPA 805, Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
- L-17-085, Supplemental Information Regarding Pending Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments (CAC MF78066): Exhibit G, Pro Forma Income Statements
- L-20-191, Energy Harbor - Enclosed May 2020 NPDES Discharge Monitoring Report, Beaver Valley Power Station & Supplemental Monitoring Data for Outfall 001 (Dissolved Oxygen)
- L-20-276, Response to Request for Additional Information Regarding Steam Generator Inspection Report
- L-2004-293, Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information
- L-2005-141, 10 CFR 50.55a Request for Mechanical Clamping Device Used as Piping Pressure Boundary
- L-2008-002, Corporate Merger of Decommissioning Trustee
- L-2008-018, Transmittal of Pressurized Butt Weld Alloy Report, and Mitigation Status and Swol Inspection Results
- L-2008-178, Fourth Ten-Year Interval In-Service-Test Program Submittal RAI Reply to Relief Request PR-04
- L-2008-236, Extended Power Uprate, Data for NRC Confirmatory EPU Analyses
- L-2009-078, Extended Power Uprate Data for NRC Confirmatory EPU Analyses
- L-2010-096, Extended Power Uprate Data for NRC Confirmatory EPU Analyses
- L-2013-067, Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2012
- L-2014-340, RAI Reply - Fourth Ten-Year Interval Unit 2 Relief Request No. 4
- L-2015-093, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 50.46 Annual Report
- L-2016-109, Official Service List Changes and Distribution for Safeguards Information and Official Use Only-Security-Related Information
- L-2018-067, Units 1 and 2 - Submittal of Joint Plant Access Shared Information Table
- L-2019-020, Subsequent License Renewal Application Environmental Report Environmental Authorizations Updated Information
- L-2021-137, GL 2004-02 Debris Transport Calculation Non-Conservatism
- L-2021-138, GL 2004-02 Debris Transport Calculation Non-Conservatism
- L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications
- L-21-201, Acceptance Review Supplemental Information for Emergency Plan Amendment Request
- L-22-159, Supplement to a License Amendment Request Revising Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start and Bus Separation Instrumentation
- L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models
- L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
- L-75-161, Letter Regarding Atwt Analysis and Enclosing Loss of Load And/Or Turbine Trip Atwt Analysis for St. Lucie Unit 1.
- L-75-246, Responding to Letter of 5/15/75, Letter Furnishing Analyses & Other Relevant Info to Determine Potential for Occurrence & Potential Consequences of Secondary System Fluid Flow Instability (Water Hammer)
- L-76-199, Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Changes in Response to 04/14/1975 Letter from George Lear Which Requested That Heatup & Cooldown Rates in Technical Specifications ...
- L-76-201, Letter Submits Proposed Amendment to Facility Operating License with Supplemental Information Submitted as Appendix B of Spent Fuel Storage Facility Modification Safety Analysis Report
- L-76-221, Letter Regarding Condition E.3 to the Operating License and Attaching the Westinghouse Review of the Design of the Fan Cooler Motors and a Table Comparing the WCAP-7829 Test Machine Motors
- L-76-225, Letter Submits Proposed Amendment to Facility Operating License to Amend Appendix a Tech Spec, Concerning Cask Handling
- L-76-438, Letter Transmitting Supplemental Information Regarding ECCS Reevaluation After re-calculation Using Tech Spec Rated Power Level of 2200 Mwt
- L-77-106, 04/04/1977 Letter Proposed Amendment to Facility Operating Licenses DPR-31 & DPR-41 Options Available for Offsetting an Increased Rod Bow Penalty
- L-77-381, Letter Transmitting Revision 1 to Steam Generator Repair Report Which Was Forwarded on 9/20/1977
- L-77-434, Answers to Question Nos. 2 and 7 and Revised Answers to Questions 8 and 9 Pertaining to the Steam Generators Tube Integrity Supplemental Information
- L-78-217, 06/22/1978 Letter Proposed Modifications to Technical Specification Figure 2.1-1, Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation
- L-78-264, 08/09/1978 Letter Order for Amendment to Facility Operating Licenses DPR-31 & DPR-41
- L-78-271, 08/16/1978 Letter Thermal & Hydraulic Safety Limits
- L-78-297, Supplemental Information on Request to Amend Facility Operating Licenses Additional Information
- L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel
- L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End
- L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
- L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
- L-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
- L-PI-04-001, 1997 Met Files
- L-PI-06-031, Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time
- L-PI-12-078, PWR (Pressurized Water Reactor) Vessel Internals Program for Fulfillment of License Renewal Commitment 25
- L-PI-15-003, Notification of Change in Commitment Made in Letter Dated November 26, 2012 in Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)
- L-PI-22-005, WCAP-18660-NP, Revision 0, Analysis of Capsule N from the Xcel Energy Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Appendix C, Part 5 Through Appendix D
- LIC-05-0040, Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- LIC-06-0116, Spreadsheet File of Instructions, Time Temp Ph Input, Material Input, Materials Conversions, Results Tables
- LIC-07-0073, Closure of NRC TAC Issues
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 51 Through 90
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System, Attachment 2, Pages 91 Through End
- LIC-08-0037, Calculation FC05694, Calculation of Minimum Reactor Coolant Time Using Shutdown Cooling System.
- LIC-11-0041, Transmittal of Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)
- LIC-22-0001, Well Water Results with River Stage
- LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-0095
- LR-N04-0591, Response to Request for Additional Information Regarding Relief Requests S1-RR-04-V01 and V02
- LR-N06-0046, PSEG Metrics for Improving Work Environment, Salem and Hope Creek, Quarterly Report
- LR-N07-0150, Unit 2, Re-Submittal of Inservice Inspection Program Relief Requests S2-I2-RR-B01 and S2-I2-RR-C01
- LR-N09-0103, Submittal of 2008 Summary of Revised Regulatory Commitments
- LR-N12-0027, Submittal of RCS Dei Graphs Report
- LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149
- LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal
- LR-N16-0161, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3.8-1 Through 3.8-11
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 3A-1 (Deleted)
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Table 4.1-1 Through 4.1-3
- LR-N23-0050, Attachment 5: Hope Creek Pavan Output File
- LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
M
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