BSEP 16-0031, Annual Radioactive Effluent Release Report for 2015
RNP-RA/16-0029, 2015 Annual Radioactive Effluent Release Report
CNL-15-093, Response to NRC Request to Supplement Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Radiological Protection and Radiological Consequences
L-15-010, Offsite Dose Calculation Manual, Revision 29
MNS-15-028, Offsite Dose Calculation Manual (Odcm), Revision 55
BVY 15-037, Submittal of 2014 Radioactive Effluent Release Report
NL-15-048, 2014 Annual Radioactive Effluent Release Report
ONS-2014-044, 4 to the Offsite Dose Calculation Manual (OCDM)
BVY 14-038, Radioactive Effluent Release Report for 2013 Including Annual Radiological Impact on Man
L-14-135, Offsite Dose Calculation Model, Revision 27
LR-N14-0084, Offsite Dose Calculation Manual, Revision 27
NRC 2013-0038, Submittal of 2012 Annual Monitoring Report
L-12-152, Offsite Dose Calculation Manual, Revision 26
L-11-150, Offsite Dose Calculation Manual, Rev. 24
L-2015-048, to FPL-072-PR-002, Flooding Hazards Reevaluation Report for St. Lucie Nuclear Power Plant Units 1 & 2. Table 2-1 Through Figure 4-9
LR-N14-0084, Salem, Units 1 and 2, Offsite Dose Calculation Manual, Revision 27
RC-14-0032, Virgil C. Summer Unit 1, License Amendment Request LAR-14-02392, Request for NRC Approval of Proposed Changes to Emergency Action Levels. Attachments Iii, Iv, V & Vi: Technical Bases for Proposed EALs (Clean Copy), NEI 99-01 Revision 6 EA
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
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 23
LR-N10-0140, Salem - Attachment 1, Offsite Dose Calculation Manual, Revision 22
L-2010-033, St. Lucie, Units 1 and 2, Offsite Dose Calculation Manual, Chemistry Operating Procedure C-200, Rev 32.
NRC-09-0080, Engineering Calculation No. ENG-003, Revision 0, Calculation of EF1 Building Surface Dcgls.
NL-09-045, Indian Point, Units 1, 2, & 3, Offsite Dose Calculation Manual Changes and Justification Packages for 2008
NL-08-068, Indian Point, Units 1, 2 and 3 - 2007 Annual Radioactive Effluent Release Report
NL-06-056, Offsite Dose Calculation Manual (ODCM)
CY-06-063, 2005 Annual Radiological Environmental Operating Report
CY-05-116, Annual Radiological Environmental Operating Report for 2004
RA-19-0130, Submittal of Annual Radioactive Effluent Release Report 2018
RA-19-0135, Annual Radioactive Effluent Release Report
NL-05-054, Radioactive Effluent Release Report
PLA-5748, Annual Radiological Environmental Operating Report
NLS2004048, 2003 Annual Radiological Environmental Operating Report
L-2003-033, 2002 Annual Radioactive Effluent Release Report, Section 2.0, Appendix A-D
L-2002-045, Part 2 of 2, St. Lucie, Units 1 & 2, 2001 Annual Radioactive Effluent Release Report, St. Lucie Plant, Chemistry Operating Procedure C-200, Revision 23A
IA-84-299, Responds to FOIA Request for Info Re D Eisenhut 840402 Ltr to Jm Cain.Info Completely Withheld Because of Ongoing Ofc of Investigation Investigations.Related Info Released Under Separate FOIA Requests Available in PDR
IA-92-416, List of Records Re Cleveland Clinic Foundation Produced by NRC Nudocs for NRC
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
SECY-22-0028, Enclosure 5 - NRC Response to Public Comments on Appendices F-I for NUREG-BR-0058
HL-4868, Forwards Response to NRC 950606 RAI Re Core Shroud Mod Installed at Facility,To Clarify Methodology in Suppl a to Rev 1 to GENE-771-34-0794.GE Proprietary Rept, Finite Element Analysis... Also Encl.Ge Proprietary Rept Withheld
NG-95-0286, Application for Amend to License DPR-49,consisting of Proposed Change RTS-279 to TS to Remove Redundant LCOs & SRs for Containment Hydrogen & Oxygen Monitors in TS
BVY 20-017, 2019 Radiological Effluent Release Report
RS-24-047, 2023 Annual Radioactive Effluent Release Report
ULNRC-06011, Responses to RAI Set 3 Regarding Adoption of National Fire Protection Association Standard NFPA 805
BVY 24-018, 2023 Radiological Effluent Release Report
HBL-21-004, Annual Radioactive Effluent Release Report for 2020
05000302/LER-1989-014, :on 890413,alarm/automatic Actuation Setpoint for Operating Range Improperly Set High.Caused by Personnel Error.Monitor Setpoints Immediately Reset & Check Made of Other Monitor Setpoints & Verified
B12211, Forwards Summaries of Preoperational & Startup Testing,Maint & Operation of Deep Draft Pumps,In Response to IE Bulletin 79-15
05000277/LER-1986-010-02, :on 860413,containment Isolations Occurred When Startup Source 3 Deenergized.Caused by Transformer 1 Failure,Rupture & Subsequent Fire.Fire Extinguished.Startup Source Restored.Transformer Repaired
AECM-88-0052, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987
VPN-027-97, Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY96
05000382/LER-1996-010-01, :on 960807,discovered COLSS Not Monitoring Aztilt Due to Constants Not Being Loaded.Default Value for COLSS-CPS Tilt Limit Will Be Changed from 0.03 to 0.00
B11449, Forwards Response to 840802 SER Open Items Re Seismic & Dynamic Qualification Program
AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
05000316/LER-1983-120-03, /03L-0:on 831206,chart Paper for Containment Sump Flow Monitoring Recorder 2-CS-001 Would Not Advance.Cause Not Stated.Recorder Repaired.Design Change Submitted
05000416/LER-1983-162-01, /01T-0:on 831031,review of Operating Data from 830926-1030 Revealed That Drywell Pressure Instrumentation Readings Occasionally Exceeded Allowable Values.Cause Not Stated.Instrument Setpoints Will Be Lowered
SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment
GO2-94-053, WNP-2 Annual Operating Rept 1993
05000324/LER-1982-049-03, /03L-0:on 820325,during Channel Calibr & Functional Test of ECCS Shroud Level Instrumentation,Level Switch Actuated Out of Tech Spec Tolerances.Caused by Drift of Instrument Mechanism.Instrument Recalibr
05000352/LER-1987-028-01, :on 870610,hourly Fire Watch Required by TS 3.7.7 Not Performed Due to Personnel Error.Plant Security Organization Accepted Responsibility for Hourly Firewatch Patrol Required by Ts,Effective 930104
05000261/LER-1981-026-01, /01T-0:on 811120,primary to Secondary Leak of Approx 1.5 Gpm Found in Steam Generator A.Caused by Leaking Explosive Plug.Plant Shut Down,Plug Removed & Weld Repaired on 811127
05000413/LER-1990-021, :on 900212,fire Doors Declared Inoperable to Permit Routing of Hose to Drain Component Cooling Sys Equipment & Surveillance Intervals Exceeded 1 H.Caused by Mgt Deficiency.Notice Re Fire Watch Issued
U-600211, Requests NRC Concurrence to Terminate Overinsp Program for HVAC Duct & Duct Supports.Technical Justification & Util Answers to NRC Questions & Comments Per Encl
05000409/LER-1979-004-01, /01T-0 on 790119:indicated Leak Rate for Demineralized Water Isolation Valve Was 0.597 Std Cubic Ft/H.Caused by Normal Surface Wear.Valve Repaired & Now Complies W/Type C Test Criteria
HBL-19-005, Annual Radioactive Effluent Release Report for 2018
L-93-216, Combined Semiannual Radioactive Release Rept for Jan-June 1993 for St Lucie Plant,Units 1 & 2
GO2-81-561, Forwards Responses to Hydrologic Engineering Section Safety Questions 371.015,371.016,371.017 & 371.018 Contained in NRC .Other Responses Will Be Submitted by 820115.Ten Oversize Drawings Encl.Aperture Cards Are in PDR
L-79-248, Requests That 790412 Proposed Amend to License DPR-67 Be Modified to Include ETS 4.2, Min Effective Chlorine Usage. Mod Eliminates Overlapping Regulatory Requirements
BW170050, 2016 Radioactive Effluent Release Report
BW170041, Transmittal of 2016 Radioactive Effluent Release Report
BSEP 17-0037, Submittal of Annual Radioactive Effluent Release Report for 2016
PLA-7318, Submittal of Unit 2 Cycle 18 Core Operating Limits Report (COLR) PLA-7318
NL-19-0486, Enclosure 8: Vogtle Electric Generating Plant, Units 1 & 2 - Offsite Dose Calculation Manual - Version 32
HBL-13-004, ODCM, Revision 22, Volume 4, Safstor/Decommissioning Offsite Dose Calculation Manual
NL-17-047, Submittal of 2016 Annual Radioactive Effluent Release Report
ULNRC-05743, Offsite Dose Calculation Manual Revision 17
ULNRC-05621, 2008 Annual Radioactive Effluent Release Report
HBL-03-003, Annual Radioactive Effluent Release Report for 2002
E910-02-005, Supplemental Response to RAI 2 Questions
NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report
U-602635, Rev 2 to Vol D to Calculations for Functional Requirements for 1st & 2nd Level Undervoltage Relays at 4 Kv 1A1,1B1 & 1C1
05000295/LER-1988-017-02, :on 880723,reactor Trip Occurred When Power Increased to power-range Permissive P-10 Setpoint.Caused by Personnel Error & Procedural Deficiency.General Operating Procedure GOP 4 Will Be Changed to Add Step
BVY 25-014, 2024 Radiological Effluent Release Report