Regulatory Guide 1.49# QUERYe1e9adc87da505ec9d1a0726a7a7b74a
Regulatory Guide 1.49# QUERY6e8e6098e14870e6e2c4dfebdb64e5a9
Regulatory Guide 1.49# QUERY1ad19f68f89bb9fba6e8320e6349fce3
Regulatory Guide 1.49# QUERY2f424dc36dc53148ebe16fe2b866f7dd

Regulatory Guide 1.49# QUERY63d5ea34e6aa3a2e0bea4e8bf23559a9
Regulatory Guide 1.49# ERR1dd423a8697e32d6813ecd1a7aae482c
RS-16-019, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation
RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation
RC-14-0179, Calculation - DC00040-123 - Rod Ejection Accident - TSC
L-MT-12-027, License Amendment Request: Provide Restoration Period Before Declaring Average Power Range Monitors Inoperable When Surveillance Requirement 3.3.1.1.2 Not Met
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 15, Accident and Transient Analysis
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
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
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, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 15
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
NL-15-169, NEDO-33824, Revision 0, Engineering Report, Browns Ferry Replacement Steam Dryer Stress Analysis.
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 15 - Accident Analysis
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NL-11-1812, Edwin I. Hatch, Unit 2 - 2011 Updated Final Safety Analysis Report, Revision 29, Chapter 6, Engineered Safety Features Through Chapter 7, Instrumentation and Control
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses
RS-10-001, LaSalle, Units 1 and 2, Attachment 8 - NEDO-33485, Rev. 0, Safety Analysis Report for LaSalle County Station Units 1 and 2, Thermal Power Optimization.
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
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
LR-N07-0084, Supplement to License Amendment Request for Extended Power Uprate, Revised No Significant Hazards Consideration
L-07-042, Supplemental Information, Steam Generator Tube Rupture Analysis Update
L-05-204, Additional Information Regarding Dose Consequence Analysis in Support of License Amendment Request Nos. 302 and 173
RS-05-111, Additional Information Supporting the Request for License Amendment Related to Application of Alternative Source Term
W3F1-2005-0032, License Amendment Request NPF-38-249-1 Extended Power Uprate (Amendment 199) License Condition Regarding Instrument Uncertainty
RNP-RA/04-0017, Supplement to Amendment Request Regarding Deletion of Additional Condition Related to Cycle Length
NRC-03-0007, Proposed License Amendment for Implementation of Alternative Radiological Source Term Methodology
CNRO-2002-00055, Rev to Tsar in Support of Appendix K Measurement Uncertainty Recovery Power Uprate Request
LIC-02-0109, Low Temperature Overpressure Protection Final Report, Revision 1, Table of Contents - Attachment a
RS-02-174, Co., Llc. (EGC) Application for Amendment to Licenses DPR-19, DPR-25, DPR-29 & DPR-30, Related to Application of Alternative Source Term, Attachments a - E-1
B210059, Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents
A04048, Rev 1 to Fuel Handling Accident During Reconstitution
NUREG-0491, Notice of Issuance of SER NUREG-0491 & Preliminary Design PDA-13 for Nuc Steam Supply Sys Portion of Nuc Pwr Plant as Described in Westinghouse Rept RESAR-414. W/O NUREG-0491
ST-HL-AE-5523, Forwards Rev 5 to Updated Fsar.New Updated FSAR Section 1.3.1 Has Been Added to Delineate Info Included in UFSAR Not Considered to Be Design or Licensing Basis Info
RC-95-0236, Comment Opposing Draft RG DG-1043,Proposed Rev 2 to RG 1.49, NPP Simulation Facilities for Use in Operator Exams
LD-95-013, Transmits Supplementary Revs for Incorporation Into DCD & Affidavit.Changes Resolve Inconsistencies Identified by NRC & by ABB-CE
JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis
L-95-252, Comment Supporting RG DG-1043,Rev 2 to RG 1.49, NPP Simulation Facilities for Use in Operator License Exams
PLA-6112, Revision to Proposed Amendment Nos. 281 and 251, Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67
BVY 04-081, Technical Specification Proposed Change No. 263 - Supplement No. 11 Extended Power Uprate - Response to Request for Additional Information
05000458/LER-2003-005, Operation Greater than Maximum Licensed Power Due to Erroneous Feedwater Flow Measurement
HL-6328, Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6
BSEP 02-0169, GE Nuclear Energy Report NEDO-33063, Safety Analysis Report for Brunswick Steam Electric Plant, Units 1 and 2, Maximum Extended Load Line Limit Analysis Plus
JPN-98-033, Forwards Response to NRC RAI Re Proposed TS Change Request for Plant.Proprietary Response to RAI Re Spent Pool Storage Capacity Increase & Calculation,Encl.W/Two Oversize Drawings.Proprietary Response Withheld,Per 10CFR2.790(a)(4)