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IR 05000213/1997011
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ML20203K320
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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
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ML20206G228
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ML20235C382
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SECY-22-0028, Enclosure 5 - NRC Response to Public Comments on Appendices F-I for NUREG-BR-0058
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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
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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
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BVY 20-017, 2019 Radiological Effluent Release Report
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RS-24-047, 2023 Annual Radioactive Effluent Release Report
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ULNRC-06011, Responses to RAI Set 3 Regarding Adoption of National Fire Protection Association Standard NFPA 805
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BVY 24-018, 2023 Radiological Effluent Release Report
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HBL-21-004, Annual Radioactive Effluent Release Report for 2020
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automatic Actuation Setpoint for Operating Range Improperly Set High.Caused by Personnel Error.Monitor Setpoints Immediately Reset & Check Made of Other Monitor Setpoints & Verified
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B12211, Forwards Summaries of Preoperational & Startup Testing,Maint & Operation of Deep Draft Pumps,In Response to IE Bulletin 79-15
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ML20205G918
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ML20206R257
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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
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label: 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
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AECM-88-0052, Semiannual Radioactive Effluent Release Rept,Jul-Dec 1987
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VPN-027-97, Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY96
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ML20137J060
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ML20140G233
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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
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ML20138H465
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B11449, Forwards Response to 840802 SER Open Items Re Seismic & Dynamic Qualification Program
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ML20132C739
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AECM-84-0438, Semiannual Radioactive Effluent Release Rept, Jan-June 1984
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ML20108E371
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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
type: Subject
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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
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ML20081C014
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SNRC-1429, Semiannual Radioactive Effluent Release Rept for Third & Fourth Quarters,1987,Meteorological Summary & Offsite Dose Assessment
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ML20073P288
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ML20073G514
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GO2-94-053, WNP-2 Annual Operating Rept 1993
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IR 05000002/1993005
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ML20056G094
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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
type: Subject
label: 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
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ML20049J907
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ML20137Y341
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ML20082F566
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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
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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
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U-600211, Requests NRC Concurrence to Terminate Overinsp Program for HVAC Duct & Duct Supports.Technical Justification & Util Answers to NRC Questions & Comments Per Encl
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Type C Test Criteria
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HBL-19-005, Annual Radioactive Effluent Release Report for 2018
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L-93-216, Combined Semiannual Radioactive Release Rept for Jan-June 1993 for St Lucie Plant,Units 1 & 2
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BW170050, 2016 Radioactive Effluent Release Report
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BW170041, Transmittal of 2016 Radioactive Effluent Release Report
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PLA-7318, Submittal of Unit 2 Cycle 18 Core Operating Limits Report (COLR) PLA-7318
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NL-19-0486, Enclosure 8: Vogtle Electric Generating Plant, Units 1 & 2 - Offsite Dose Calculation Manual - Version 32
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HBL-13-004, ODCM, Revision 22, Volume 4, Safstor/Decommissioning Offsite Dose Calculation Manual
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NL-17-047, Submittal of 2016 Annual Radioactive Effluent Release Report
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ULNRC-05743, Offsite Dose Calculation Manual Revision 17
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ULNRC-05621, 2008 Annual Radioactive Effluent Release Report
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HBL-03-003, Annual Radioactive Effluent Release Report for 2002
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E910-02-005, Supplemental Response to RAI 2 Questions
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