L-MT-17-010, License Amendment Request: Revision to Emergency Plan Staff Augmentation Response Times
L-MT-17-029, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
NL-17-1155, NFPA-805 Transition Due Date Extension
2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications
1CAN051602, Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-805
NL-15-2310, Supplemental License Amendment Request to Revise Existing Facility Operating License Commitments Regarding NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plant
W3F1-2016-0003, Revised Licensing Actions and Implementation Items Regarding Adoption of National Fire Protection Association Standard NFPA 805 License Amendment Request (LAR)
AEP-NRC-2017-10, Request for Deviation from National Fire Protection Association (NFPA) 805 Requirements
CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants
CNL-15-074, Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants
GNRO-2015/00028, Submittal of 2014 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
GNRO-2011/00030, Annual Radioactive Effluent Release Report (ARERR)
L-PI-18-005, License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805
AEP-NRC-2018-39, Supplement to Request for Deviation from National Fire Protection (NFPA) Standard 805 Requirements
L-MT-18-024, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 11, Radioactive Waste Management
LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 11, Waste Disposal and Radiation Protection System
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report,(Ufsar), Revision 25, Chapter 11, Waste Disposal and Rad Protection System
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 11, Waste Disposal and Radiation Protection System
NG-17-0037, Duane Arnold Energy Center - Evaluation of Proposed Amendment for License Amendment Request (TSCR-165) for Revision to Emergency Planning Zone in the Duane Arnold Energy Center Emergency Plan
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems
LR-N12-0121, Salem and Hope Creek - 2011 Annual Radioactive Effluent Release Report
AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009
RC-18-0091, License Amendment Request - LAR-16-01490 National Fire Protection Association Standard 805 Program Revisions
L-2018-170, License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals
L-MT-18-044, Changes to the Monticello Nuclear Generating Plant (MNGP) Emergency Plan
L-2018-219, Supplement to License Amendment Request 265, Revise NFPA 805 License Condition for Reactor Coolant Pump Seals
3F0419-03, 2018 Annual Radioactive Effluent Release Report
3F0406-05, Off-Site Dose Calculation Manual, Revision 27
PLA-5662, Proposed Third Ten-Year Inservice Inspection, Interval Inservice Inspection Program Plan
DCL-03-049, 2002 Annual Radioactive Effluent Release Report
SVP-03-052, Radioactive Effluent Report for January Through December 2002, Chapters 10 and 12, Appendix a - F
3F0420-01, 2019 Annual Radioactive Effluent Release Report
NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
RS-20-131, Part II: Planning Standards and Criteria
3F0421-01, 2020 Annual Radioactive Effluent Release Report
DCL-21-019, Supplement to License Amendment Request 20-03 Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition
GO2-21-133, License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
U-602574, Annual Radioactive Effluent Release Rept Jan-Dec 1995
3F0495-20, Radioactive Effluent Release Rept 1994 Crystal River Unit 3
U-602444, Annual Radioactive Effluent Release Rept Jan-Dec 1994
Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
3F0423-02, 2022 Annual Radioactive Effluent Release Report
U-601799, Semiannual Radioactive Effluent Release Rept Jul-Dec 1990
L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project
PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments
L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut
L-2024-032, Emergency License Amendment Request- One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions
L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project
NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5
W3F1-2020-0032, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 28, 2020
05000271/LER-1976-022-01, /1T:on 760718-20,approx 82,800 Gallons Low Level Radioactive Water Inadvertently Released from Overflow Line on Condensate Storage Tank Through Storm Drains to Connecticut River.Caused by Tank Moat Leaks
NL-19-1475, Response to Request for Additional Information Regarding the License Amendment Request to Transition to 10 CFR 50.48(c)- NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants
L-MT-22-026, Changes to the Emergency Plan
NUREG-2254, Summary of the Uncertainty Analyses for the State-of-the-Art Reactor Consequence Analyses Project
RA-18-0226, Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System
NL-17-1962, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
NUREG/CR-7288 Volume 2, Evaluation of In-Service Radon Barriers Over Uranium Mill Tailings Disposal Facilities - Appendices
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative
NG-21-0008, Attachment 3: Defueled Offsite Dose Assessment Manual (Dodam)
L-2021-040, Radiological Emergency Plan, Revision 67
DCL-24-111, License Amendment Request 24-05 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b for TS 3.3.1 and 3.3.2
BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material
CNL-21-017, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis, (L-2020-LLA-0099)
L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project
L-2024-038, To Seabrook Emergency License Amendment Request - One Time Extension to Technical Specifications (TS) 3/4.8.1 Action a.3 Allowed Outage Time for an Inoperable Offsite Source
NUREG-2244, Habit 2.2 Description of Models and Methods
NUREG-1343, Forwards NUREG-1353, Regulatory Analysis for Resolution of Generic Issue 82, Beyond Design Basis Accidents in Spent Fuel Pools. No Actions Should Be Required of Licensees
3F0425-02, 2024 Annual Radioactive Effluent Release Report
VPN-021-98, Trojan Nuclear Plant Annual Radiological Environ Monitoring Rept for 970101-1231