Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
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CNL-19-007, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus
NL-17-0643, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request
RNP-RA/16-0057, License Amendment Request to Modify the Licensing Basis Alternate Source Term
CNS-15-058, Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits
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
RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 4, Reactor
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
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
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15.4-1 - 15A-6
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
RS-11-159, Quad Cities, Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 11, Chapter 15 - Accident and Transient Analyses
JAFP-09-0070, Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time
Press Release-02-077, NRC Seeks Comments on Proposed Agenda for Annual Nuclear Safety Research Conference in October
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
CPSES-200701126, Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits
CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report
DCL-03-069, License Amendment Request 03-09, Revision of TS 3.1.7, Rod Position Indication 3.2.1, Heat Flux Hot Channel Factor, 3.2.4, Quadrant Power Tilt Ratio, & 3.3.1, Reactor Trip System Instrumentation for Beacon Implementation
GO2-19-119, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific
GO2-04-177, License Amendment Request: Control Rod Drop Accident Analysis
NOC-AE-040016, Broad-Scope Risk-Informed Technical Specification Amendment Request
NOC-AE-03001458, Letter of Intent to Submit a Broad-Scope Risk-Informed Technical Specification Amendment Request
CNRO-2004-00055, (GGNS) - Early Site Permit Application, Part 3 - Environmental Report
W3F1-2002-0013, Supplement to Amendment Request NPF-38-234 Replacement of Part-Length Control Element Assemblies
L-20-151, License Amendment Request to Correct Non-conservative Technical Specifications 3.2 .1, Heat Flux Hot Channel Factor Fa(Z) and 5.6.3, Core Operating Limits Report (COLR)
NSD-NRC-97-5501, Forwards W Responses to FSER Open Items on AP600.Summary of Responses Provided in Table 1,including FSER Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column
B210059, Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents
LIC-98-0005, Provides Submittal as Suppl to Ltr Re SAR Update & 10CFR50.59 Rept for Fort Calhoun Station.Attachment a Describes Procedure Change & Summarizes Safety Analysis
NOC-AE-0140, Application for Amend to Licenses NPF-76 & NPF-80, Incorporating Revised Radiological Aspects of Operation at Reduced Feedwater Temp & Operation with Replacement SGs Into Encl Pages of STP Usfar
B11292, Forwards Responses to SER Confirmatory Items 29,32,33,35 & 38.FSAR Pages Addressed in Responses Provided in 840724 Amend 9 to Fsar.Items Considered Resolved
CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications
2CAN099004, Forwards Response to 900809 Telcon Questions on CEN-386-P Re Extended Burnup,Including Criteria,Methods & Analysis
LD-84-069, Forwards marked-up CESSAR FSAR Pages Reflecting Review of Tech Specs Re First Sys 80 Plant.Rev Involves Interface Requirements for MSIV & Main Feedwater Isolation Valve Closure Time
TXX-9223, Forwards line-by-line Descriptions of Changes in Amend 85 to FSAR
LD-83-019, Forwards Amended CESSAR-F Section 15.3.3, Single Reactor Coolant Pump Rotor Seizure W/Loss of Offsite Power, in Response to NRC 820115 Request & SER Comfirmatory Item 16
LD-94-036, Forwards Comments of Chapter 4 of Sys 80+ Final SER, NUREG-1462 for Technical Accuracy & Consistency w/CESSAR-DC
LD-82-003, Forwards Responses to Fuel Performance Analyses Identified in CESSAR SER Confirmatory Item 3.Encl Transmitted for NRC Review of FSAR
LD-81-088, Forwards Draft Input for CESSAR-F to Be Submitted as App C Re Description of Reactor Operation at Reduced Power Level W/Operation of Two Reactor Coolant Pumps Diametrically Opposed.Includes Info Provided in 811002 Submittal
RAIO-0719-66284, LLC Response to NRC Request for Additional Information No. 516 (Erai No. 9647) on the NuScale Design Certification Application
BSEP 18-0027, ANP-3655NP, Revision 0, Brunswick Mellla+ CRDA Assessment with Draft Criteria
DCL-15-047, License Amendment Request 15-02 Revision of Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and Technical Specification 5.6.5. Core Operating Limits Report (Colr), For.
CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (MUR) Power Uprate
DCL-12-002, Revision to the Updated Final Safety Analysis Report Section 4.3.2.2, Power Distribution; and Technical Specification Bases 3.1.7, Rod Position Indication; 3.2.1, Heat Flux Hot Channel Factor (Fo(Z)),3.2.2,.
RS-10-015, 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
BSEP 07-0053, Areva Np, Inc., Topical Report, ANP-2637, Revision 1, Boiling Water Reactor Licensing Methodology Compendium
RS-06-019, Response to NRC Request for Additional Information with Respect to Request for License Amendment Related to Application of Alternative Radiological Source Term
GO2-20-052, Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems
TXX-9400, Proposed Tech Specs Replacing Existing Spec & Bases Re QPTR W/Spec & Bases Consistent W/Improved Stds TS for Westinghouse Plants (NUREG-1431)
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)