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Issue date | Title | Topic | |
---|---|---|---|
ML20211C331 | 30 April 1999 | Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood | Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent |
ML20202G936 | 30 January 1999 | Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program B.5.b Mitigating Strategies Deep Dose Equivalent Power change |
ML20217Q852 | 1 May 1998 | Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments | Nuclear Accident Reporting System |
ML20199J758 | 31 December 1997 | Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 | Boric Acid Ultimate heat sink Stroke time Weld Overlay Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding |
ML20198M262 | 31 October 1997 | Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 | Offsite Dose Calculation Manual |
ML20216H824 | 31 October 1997 | Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Power change |
ML20137B922 | 28 February 1997 | Revs 1.3 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.4 to Chapter 11, Radiological Environ Monitoring Program & 1.4 to Chapter 12, Radioactive Effluent Technical Standards, Odcm,Byron Annex | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Power change |
ML20116L469 | 12 August 1996 | Rev 1 to 1595-00305.30000, Byron Station Units 1 & 2 Second Interval Inservice Insp Program Plan-NRC Submittal | Boric Acid High Radiation Area Non-Destructive Examination Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Scaffolding |
ML20100Q176 | 31 March 1996 | Rev 1.3 to Odcm | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Power change |
ML20134N305 | 25 March 1996 | Rev 1 to 10CFR50.59 Se | Boric Acid Turbine Missile |
ML20095J613 | 31 December 1995 | Rev 0 of IST Plan Pumps & Valves Byron Nuclear Generating Station Units 1 & 2 | Boric Acid Ultimate heat sink Stroke time Weld Overlay Probabilistic Risk Assessment Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding |
ML20129B705 | 22 September 1995 | Rev 0 to Byron/Braidwood Units 1 & 2 SG Eddy Current Analysis Guidelines | |
ML20092B105 | 2 September 1995 | Rev 0 to SG Structural Insp Plan in Support of Braidwood 1 & Byron 1 3.0 Volt Ipc | Scaffolding |
ML20091M864 | 25 August 1995 | Verification Analysis for Computer Program | |
ML20072R411 | 9 September 1994 | Rev 13 to IST Program Plan for Pumps & Valves | Boric Acid Stroke time Cold shutdown justification Power-Operated Valves Power Operated Valves Scaffolding |
ML20076L746 | 31 August 1994 | Rev 1.2 to Odcm,Chapters 10,11,12 & App F | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Deep Dose Equivalent Power change |
ML20072Q197 | 29 August 1994 | Proposed Rev 0a to Section 7 of ISI Program Plan for Pressure Testing | Non-Destructive Examination Hydrostatic VT-2 |
ML20083N870 | 31 July 1994 | Rev 7 to Byron & Braidwood Stations Units 1 & 2 Eddy Current Analyis Guidelines | |
ML20064H910 | 11 March 1994 | Rev 12 to Section 4.0 of IST Program Plan for Valves | Boric Acid Stroke time Power-Operated Valves Power Operated Valves |
ML20064H901 | 11 March 1994 | Rev 10 to Section 3.0 of IST Program Plan for Pumps | Boric Acid |
ML20063F872 | 31 January 1994 | Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Byron Station | Grab sample Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program Power change |
ML20064N328 | 20 December 1993 | Rev 0 to Operating Parameter Uncertainties for Byron/ Braidwood Revised Thermal Design Procedure | |
ML20127D069 | 30 December 1992 | Corporate Emergency Response Organization Required Reading Package 92-11 | |
ML20058E868 | 29 September 1992 | Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1 | |
ML20101B030 | 21 April 1992 | Corrected Rev 0.F to Page 11-19 of Chapter 11 of ODCM | |
ML20090A854 | 27 February 1992 | Rev 11 to Section 4.0 of Inservice Testing Program Plan for Valves | Boric Acid Stroke time Power-Operated Valves Power Operated Valves |
ML20090H765 | 27 February 1992 | Rev 0.D to Odcm | |
ML20024H404 | 23 May 1991 | Rev 9 to Inservice Testing Program Plan for Valves. | Boric Acid Stroke time Probabilistic Risk Assessment Power-Operated Valves Power Operated Valves |
ML20024H403 | 23 May 1991 | Rev 8 to Inservice Testing Program Plan for Pumps. | Boric Acid |
ML20065Q160 | 7 December 1990 | Rev 9 to Inservice Testing Program Plan for Valves | Boric Acid Stroke time Power-Operated Valves Power Operated Valves |
ML20065Q158 | 7 December 1990 | Rev 8 to Inservice Testing Program Plan for Pumps | |
ML20073C138 | 4 December 1990 | Inservice Insp Program Plan for Pressure Testing, Section 7 | Hydrostatic Nondestructive Examination VT-2 |
ML20059J017 | 31 August 1990 | Errata to Rev 0.A to ODCM Figure 11-4, Ingestion & Waterborne Exposure Pathway Sample Locations | |
ML20058E860 | 30 April 1990 | Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1 | |
ML20006C057 | 18 January 1990 | Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. | |
ML16152A895 | 2 January 1990 | Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. | |
ML15264A157 | 2 January 1990 | Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 | Health Physics Network |
ML20012A380 | 1 January 1990 | Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. | Offsite Dose Calculation Manual |
ML20012A379 | 1 January 1990 | Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. | Offsite Dose Calculation Manual |
ML20012A377 | 1 January 1990 | Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. | Boric Acid Offsite Dose Calculation Manual |
ML20012A375 | 1 January 1990 | Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. | Offsite Dose Calculation Manual |
ML20012A369 | 5 December 1989 | Rev 8 to, Process Control Program,Mcguire Nuclear Station. | Process Control Program |
ML20011D244 | 1 December 1989 | Crisis Mgt Implementing Procedures. | |
ML20012A372 | 27 November 1989 | Rev 4 to, Process Control Program,Cawtaba Nuclear Station. | Boric Acid Process Control Program |
ML20012A373 | 15 November 1989 | Rev 4 to, Process Control Program Oconee Nuclear Station. | Process Control Program |
ML19332C845 | 1 November 1989 | Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 | Health Physics Network |
ML19325F193 | 1 November 1989 | Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. | Safe Shutdown |
ML19354D439 | 25 October 1989 | Revised Procedures,Including Rev 11 to Bzp 200-A1, Pwr... Action Levels (Eals) & Rev 2 to Bzp 210-A1, PWR Emergency Action Level (EAL) Philosophy. | Health Physics Network High winds Shutdown Margin Grab sample Safe Shutdown Earthquake Operating Basis Earthquake Nuclear Accident Reporting System Earthquake Fuel cladding Power change |
ML20247H337 | 15 September 1989 | Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. | Boric Acid Earthquake Fatality |
ML20245L765 | 7 August 1989 | Rev 0 to Offsite Dose Calculation Manual | Offsite Dose Calculation Manual |