PNP 2017-009, Transmittal of 2016 Annual Radioactive Effluent Release and Waste Disposal Report
W3F1-2016-0064, Mitigating Strategies Assessment (MSA) Report for Flooding Hazard
RNP-RA/16-0029, 2015 Annual Radioactive Effluent Release Report
Information Notice 1993-79, Core Shroud Cracking at Beltline Region Welds in Boiling-Water Reactors
RS-17-162, Radiological Emergency Plan Addendum Revision
LIC-15-0102, Response to NRC Request for Additional Information Re License Amendment Request to Adopt Emergency Action Level Scheme Per NEI 99-01, Rev. 6
GNRO-2015/00058, Response to License Renewal Application (LRA) Request for Additional Information (RAI) Set 47, Question 4.2.1-2c (5) (a) I
W3F1-2015-0042, Attachment 2 to WF3-CS-15-00010, Rev. 0, Document 51-9227040-000, Fukushima Flood Hazard Reevaluation Report, Pp. 3-147 Through the End
L-15-010, Offsite Dose Calculation Manual, Revision 29
NL-15-061, Submittal of 2014 Annual Radiological Environmental Operating Report
NRC 2015-0024, 2014 Annual Monitoring Report for the Period January 1 Through December 31, 2014
TMI-14-046, Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End
NL-14-068, 2013 Annual Radiological Environmental Operating Report
L-14-135, Offsite Dose Calculation Model, Revision 27
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
NL-13-027, Submittal of 2012 Annual Radiological Environmental Operating Report
AEP-NRC-2013-25, Annual Radioactive Effluent Release Report
NRC 2013-0038, Submittal of 2012 Annual Monitoring Report
L-12-152, Offsite Dose Calculation Manual, Revision 26
GNRO-2012/00056, Response to Request for Additional Information (RAI) Set 13 Dated May 9, 2012
NRC-2010-0029, Comment (73) of Nina Bell, on Behalf of Northwest Environmental Advocates, on Draft Supplemental Environmental Impact Statement for Renewed Operating License NPF-21, for Columbia Generating Station; NUREG-1437, Supplement 47
NRC 2011-0039, Redacted - Point Beach, Units 1 and 2, Submittal of 2010 Annual Monitoring Report
L-11-150, Offsite Dose Calculation Manual, Rev. 24
PNP 2018-020, Offsite Dose Calculation Manual and Big Rock Point ISFSI - Attachment 2, 2017 Radioactive Effluent Release Report
AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual
TMI-15-034, Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station
RA-15-019, Attachment 9 - EP-AA-1007, Revised Radiological Emergency Plan Annex Information for Peach Bottom Atomic Power Station
RA-15-019, Attachment 7 - EP-AA-1008, Revised Radiological Emergency Plan Annex Information for Limerick Generating Station
RA-15-019, Attachment 6 - EP-AA-1005, Revised Radiological Emergency Plan Annex Information for LaSalle County Station
RA-15-019, Attachment 5 - EP-AA-1004, Revised Radiological Emergency Plan Annex Information for Dresden Station
RA-15-019, Attachment 4 - EP-AA-1003, Revised Radiological Emergency Plan Annex Information for Clinton Power Station
RA-15-019, Attachment 3 - EP-AA-1002, Revised Radiological Emergency Plan Annex Information for Byron Station
RA-15-019, Attachment 1 - Response to the Request for Additional Information - License Amendment Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
RA-14-032, Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Page PBAPS 3-77 Through End
RA-14-032, Attachment 8: Discussion of Revision to the Radiological Emergency Plan Annex for Oyster Creek Nuclear Generating Station, Page Ocgs 3-76 Through End
RA-14-032, Attachment 7: Discussion of Revision to the Radiological Emergency Plan Annex for Limerick Generating Station. LGS 3-70 Page LGS 3-155
RA-14-032, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
RA-14-032, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
RA-14-032, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
RA-14-032, Attachment 11: Discussion of Revision to the Radiological Emergency Plan Annex for Three Mile Island Nuclear Station, Page TMI 3-80 Through End
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 3 - Design of Structures, Components, Equipment, and Systems
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
LR-N10-0140, Hope Creek - Attachment 1, Offsite Dose Calculation Manual Revision, 23
NG-10-0265, Duane Arnold, 2009 Annual Radiological Material Release Report
L-2010-033, St. Lucie, Units 1 and 2, Offsite Dose Calculation Manual, Chemistry Operating Procedure C-200, Rev 32.
NRC-2009-0046, Annual Monitoring Report, Cover Letter Through Part D, Groundwater Monitoring
NG-09-0308, Duane Arnold - 2008 Annual Radiological Material Release Report
NEI 99-01, Dresden, Units 2 & 3, Attachment 5, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1004, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 5B and 5C, Dr 3-77 - Dr 3-160
NEI 99-01, Clinton, Unit 1, Attachment 4, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1003, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosure 4B and 4C, Cl 3-74 - Cl 3-151
NEI 99-01, Byron, Units 1 and 2, Attachment 3, Discussion of Revision to the Radiological Emergency Plan Annex, EP-AA-1002, NEI 99-01, Rev. 6, Development of Emergency Action Levels for Non-Passive Reactors, Enclosures 3B, 3C, by 3-75 - by 3-157
CY-06-063, 2005 Annual Radiological Environmental Operating Report
CY-05-116, Annual Radiological Environmental Operating Report for 2004
CY-01-084, Response to the Request for Additional Information (RAI) Regarding the Haddam Neck Plant License Termination Plan
HBL-19-005, Annual Radioactive Effluent Release Report for 2018
RA-19-0135, Annual Radioactive Effluent Release Report
ULNRC-04932, NPDES Permit Proposed Change Concerning the Schedule of Compliance for Groundwater Monitoring
HBL-03-003, Annual Radioactive Effluent Release Report for 2002
NRC-94-4194, Forwards Responses to NRC Requests for Addl Info Re AP600
IA-99-111, Partially Deleted Final Response to Request Re Current Public Exposure Stds Approved by DOE for Amount of Radioactivity in Metal & Pending Decisions to Lower Exposure Stds to 10 Mrems Per Year.Responsive Documentation Encl
HBL-21-004, Annual Radioactive Effluent Release Report for 2020
B12443, Application for Amend to License NPF-49,changing Tech Spec 3.6.1.4 to Allow Plant Operation Above Limit of Figure 3.6-1 for Containment Sys Air Partial Pressure.Safety Evaluation Encl.Fee Paid
TSTF-22-07, Transmittal of TSTF-592, Revision 0, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
B11777, Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity
HL-4781, Submits Addl Info Requested by NRC Re Recent Core Shroud Mod on Plant Unit 1
GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
W3P87-1770, Responds to NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants, Which Requested Info Re Licensee Programs for Monitoring Thickness of Pipe Walls in High Energy Single Phase & two-phase Carbon Steel Piping Sys
05000352/LER-1987-052, :on 870922,unplanned Isolation of RWCU Sys Occurred Due to Signal from Steam Leak Detection Sys.Caused by Defective Riley Co Differential Temp Switch 86VTFF.Temp Switch Replaced
05000354/LER-1986-083, :on 861101,inadvertent Actuation of Channel D LOCA Logic Occurred from Invalid Reactor Water Level Signal. Caused by Equipment Failure in That Inboard 1 Isolation Valve Leaked Through.Valve Will Be Repaired
05000269/LER-1987-002-04, :During Wk of 870127,determined That Operators May Not Be Able to Isolate Particular Letdown Flow Path. Caused by Design Deficiency.Power Removed from Breakers for Valves LP-1 & HP-2 on 870129
05000272/LER-1986-002, :on 860131,failure to Implement Portions of Inservice Testing Program Discovered.Caused by Inadequate Mgt Attention to Program Requirements.Required Testing of Valves in ASME Sections 1-10 Performed
05000219/LER-1988-015, :on 880805,reactor Isolation Signal Inadvertently Initiated During Intermediate Range Neutron Monitor Front Panel Surveillance.Caused by Circuit Not Configured to Facilitate Testing.Fuse Replaced
05000213/LER-1988-003, :on 880204,electric Fire Pump Declared Inoperable Due to High Amperage.Caused by Physical Damage to Stuffing Box Brass Bushing in Electric Driven Fire Pump. Repairs Initiated on Pump
05000336/LER-1985-009-01, :on 851106,during Routine Testing on Unit Simulator,Design Discrepancy Noted in Charging Pump B Circuitry.Caused by Design Error Which Inhibits Pump Operation.Mod to Circuit Implemented
05000260/LER-1985-018-03, :on 851106,potential Created to Violate Secondary Containment.Caused by Failure to Provide Positive Control of Containment During Mod of Carbon Steel Piping in Emergency Equipment Cooling Water Sys
05000341/LER-1985-048, :on 850724,reactor Bldg HVAC Failed to Start After Planned Trip.Hvac Exhaust Isolation Damper Reopened When Isolation Signal Reset Despite Exhaust Fan Trip. Response Procedure Revised
05000322/LER-1985-032, :on 850822,HPCI Turbine Exhaust Diaphragm High Pressure Side B Signal Initiated Causing HPCI Sys Isolation. Caused by Leak in Diaphragm W/Buildup of Water in Sensing Lines.Rupture Disk Replaced
05000286/LER-1984-014-01, :on 841013,trip Signal Received While Unit Subcritical.Caused by Blown Control Power Fuse on Channel 35 Intermediate Range Monitor.Fuse Replaced
05000373/LER-1985-013-01, :on 850212,while Finishing Precoating of Filter Demineralizer,Reactor Water Cleanup Sys Isolated on High Differential Flow.Caused by Internal Accumulated Sys Leakage & Flow Perturbations
05000352/LER-1992-005-01, :on 920415,security System Experienced Unscheduled Outage & Firewatch Insp Not Performed.Caused by Cognitive Personnel Error in Security.Security Shift Sergeant Counseled
05000397/LER-1984-068, :on 840628,control Room Emergency Filtration Unit Automatically Actuated Due to Spike on Corresponding Control Room Outside Air Radiation Monitor.Caused by RCIC Valve Closing During Testing.Alarm Reset
05000318/LER-1984-002-01, :on 840313 & 22,condenser off-gas Radiation Monitor 2-RI-1752 Declared Inoperable & Grab Sample Not Taken During Period.Caused by Disconnected Connector Due to Improperly Functioning Bayonet Clasps
NG-93-2104, Application for Amend to License DPR-49,consisting of Request for TS Change (RTS-197A),correcting Errors & Improving Consistency of Rewrite of TS Section 3.6, Primary Sys Boundary
05000369/LER-1990-006-02, :on 900226,discovered Abnormal Degradation on Steel Containment Vessel.Corrosion Caused by Design Deficiency Caused by Unanticipated Environ Interaction. Detailed Insps Conducted
ST-HL-AE-4021, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991
PNP 2024-008, Annual Radioactive Effluent Release Report
RS-22-069, Constellation Nuclear Radiological Emergency Plan Addendum Revision. Includes EP-AA-1006, Addendum 3, Revision 10, Emergency Action Levels for Quad Cities Station
RAIO-0319-64959, LLC Supplemental Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
RAIO-0918-61868, LLC Supplemental Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
L-96-111, Forwards Response to NRC Request for Addl Info Re Proposed License Amends Relocation of Radiological Effluent Ts,Using Guidance of GL 89-01
GO2-90-144, Washington Nuclear Plant 2 Semiannual Effluent Release Rept,Jan-June 1990
L-82-459, Forwards Final Response to NRC Question 220.37 Re Masonry Walls.W/Two Oversize Drawings Encl.Aperture Cards Are Available in PDR
RAIO-0818-61468, LLC Response to NRC Request for Additional Information No. 356 (Erai No. 9253) on the NuScale Design Certification Application
HBL-13-004, ODCM, Revision 22, Volume 4, Safstor/Decommissioning Offsite Dose Calculation Manual
AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009
L-2008-170, Re-Submittal of the 2007 Annual Radiological Environmental Operating Report, Required by Technical Specification 6.9.1.3
L-2008-115, 2007 Annual Radiological Environmental Operating Report
CY-04-131, Estimates for Release of Radionuclides from Potentially Contaminated Concrete at the Haddam Neck Nuclear Plant
BW040050, 2003 Annual Radiological Environmental Operating Report
E910-02-025, Summary of Information Provided to NRC in 04/08/2002 & 05/08/2002 Meetings Re Saxton Nuclear Experimental (SNEC) License Termination Plan, Dose Modeling & Characterization Issues Addressed in NRC RAIs
ET 02-0012, Annual 10 CFR 50.59 Evaluation Report
RA-02-008, Transmittal of Special Report, Transuranic and Other Hard to Detect Radionuclides in Maine Yankee Sample Media
RS-22-057, Constellation Radiological Emergency Plan Addendum Revision
NRC 2022-0014, 2021 Annual Monitoring Report
RS-22-056, Constellation Radiological Emergency Plan Addendum Revision
NG-21-0008, Attachment 3: Defueled Offsite Dose Assessment Manual (Dodam)
PNP 2025-015, Annual Radioactive Effluent Release Report
AEP-NRC-2021-27, Annual Radioactive Effluent Release Report
JAFP-23-0060, Emergency Plan Document Revisions
TSTF-23-07, TSTF Response to NRC Request for Additional Information on TSTF-592, Revision 1, Revise Automatic Depressurization System (ADS) Instrumentation Requirements
TSTF-23-02, TSTF Response to Request for Additional Information on TSTF-592,Revise Automatic Depressurization System (ADS) Instrumentation Requirements and Submission of Revision 1