LR-N17-0087, 2016 Annual Radioactive Effluent Release Report
LR-N16-0232, Response to Prelim White Finding in Integrated Inspection Report 05000354/2016003
NL-16-1390, License Amendment Request to Revise Technical Specification Section 5.5.12 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Correction to Attachment 3
LR-N18-0021, Supplemental Information to License Amendment Request for Implementation of WCAP-14333 and WCAP-15376, Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation Test Times and Completion Times
LR-N15-0078, Annual Radioactive Effluent Release Report
NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project
NL-14-106, 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project Indian Point Nuclear Generating Unit Nos. 2 & 3
NRC 2014-0054, Response (90 Day) to Request for Additional Information License Amendment Request Associated with NFPA 805
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
LR-N13-0093, 2012 Annual Radioactive Effluent Release Report, for the Period of January 1, 2012, to December 31, 2012
NRC 2013-0021, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping in Accordance with 10 CFR 50.55a(a)(3)(i)
NG-13-0102, Response to Request for Additional Information, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants
ULNRC-05908, Responses to Requests for Additional Information (RAI) for Severe Accident Mitigation Alternatives
NG-12-0177, Response to Request for Additional Information, License Amendment Request to Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Generational Plants
SBK-L-11197, Request for Alternative to Use ASME Code Case N-716 to Implement Risk-Informed Inservice Inspection Program
NL-10-2355, Request for Approval of Risk-Informed/Safety Based Inservice Inspection Alternative for Class 1 and 2 Piping FNP-ISI-AL T-12, Version 2.0
NRC 2018-0018, License Amendment Request 288, Request to Extend Containment Leakage Rate Test Frequency
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, List of Effective Pages
L-2016-198, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report, Chapter 5, Structures
DCL-15-027, Diablo Canyon Power Plant Er Changes Reflected in the Environmental Report Update Amendment 2. Part 5 of 9
LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
LR-N14-0084, Hope Creek and Salem, Units 1 and 2, 2013 Annual Radioactive Effluent Release Report
NL-14-106, 10CFR50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project, Indian Point Nuclear Generating Station, Unit Nos. 2 & 3
NG-17-0235, Duane Arnold Energy Center, Calc No. NEE-323-CALC-005, Revised Gaseous Radiological EALs Per NEI 99-01 Rev. 06
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
RNP-RA/10-0108, H. B. Robinson,Response to Request for Additional Information Regarding Changes to Technical Specification Section 3.3.2, Engineered Safety Feature Actuation System Instrumentation, and Section 3.3.6, Containment Ventilation Isolation
L-2010-212, Turkey Point, Units 3 & 4, Updated Final Safety Analysis Report - Unit 4 Cycle 24 Update, Chapter 5, Structures
LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
RNP-RA/10-0019, Supplemental Information for Request for Technical Specifications Change Regarding Steam Generator Alternate Repair Criteria
TSTF-09-15, Transmittal of TSTF-517, Revision 0, Allowance for Non-TS Cooling / Ventilation Systems Degradation on Support System Operability and Associated Implementation Guidance
L-2009-209, Response to Request for Additional Information Re License Amendment Request for H*: Alternate Repair Criteria for Steam Generator Tubesheet Expansion Region
CP-200901226, Response to Request for Additional Information Regarding License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria
NL-09-1375, Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.10
RS-09-117, Additional Information Supporting License Amendment Request to Revise Technical Specifications (TS) for Steam Generator Permanent Alternate Repair Criteria
LR-N09-0099, Hope Creek, and Salem, Units 1 and 2, 2008 Annual Radioactive Effluent Release Report, Cover Through Page 180
LR-N08-0096, 2007 Radioactive Effluent Release Report for January 1, 2007 to December 31, 2007
NRC 2013-0028, Point Beach Nuclear Plant, Units 1 and 2: License Amendment Request 271 - Transition to 10 CFR 50.48(c) - NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2
TSTF-06-05, TSTF-427, Revision 1, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability
NOC-AE-07002127, Request for License Amendment Related to Application of the Alternate Source Term
SVPLTR 06-0017, Response to Preliminary White Finding- HPCI Flooding - Exelon Nuclear
LR-N19-0042, 2018 Annual Radioactive Effluent Release Report (ARERR)
AEP-NRC-5691-04, Core Operating Limits Report
ET 09-0023, Response to Request for Additional Information Related to License Amendment Request for a Permanent Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator Program
3F0705-09, Response to Request for Additional Information Regarding Third 10-Year Inservice Inspection Program - Risk-Informed Inservice Inspection Program for Class 1, ASME Code, Category B-J and B-F Piping Welds - Question 1
LR-N04-0117, Stations, Radioactive Effluent Release Report
GO2-02-136, License Amendment Request - Alternative Source Term Response to Request for Additional Information
LR-N20-0025, 2019 Annual Radioactive Effluent Release Report (Rerr)
CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)
NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NSD-NRC-96-4895, Forwards W Responses to NRC RAI Re AP600 PRA & Assessment of Potential Impact of Diffusion Flames on AP600 Containment Wall & Pentrations, for Review
NSD-NRC-97-4994, Submits W Responses to NRC RAIs Re AP600 Internal Fire SD Analysis Documented in Chapter 57 of AP600 Probabilistic Risk Assessment Rept
RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds
B14572, Application for Amend to License DPR-61,proposing Interim Changes for Incorporation of Addl LCO for TS Requiring That 480 Volt Ac MCC 5 & Abt Scheme Be Operable During Modes 1,2, 3 & 4.Permanent Changes Will Be Proposed Later Half of 1994
GO2-85-105, Semiannual Effluent Rept,Jul-Dec 1984
RS-10-172, Additional Information Supporting the Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System
CPSES-200701127, Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times
NUREG/CR-6410, USEC - Staff Pre-filed Exhibit 25, NUREG/CR-6410, Nuclear Fuel Cycle Facility Accident Analysis Handbook
DCL-07-018, Request for Extension of Completion Date for Unit 1 Corrective Actions and Modifications Required by Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at
TSTF-06-07, TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability