Semantic search
Jump to navigation
Jump to search
Issue date | Title | Topic | |
---|---|---|---|
ML20217G996 | 14 October 1999 | SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & | VT-2 Incorporated by reference |
ML20212A744 | 10 September 1999 | Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety | Hydrostatic VT-2 Incorporated by reference Finite Element Analysis Liquid penetrant |
ML20210U811 | 4 August 1999 | SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a | |
ML20210K986 | 30 July 1999 | Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs | Stroke time |
ML20207B648 | 25 May 1999 | SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station | |
ML20205B509 | 26 March 1999 | SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 | Boric Acid VT-2 Incorporated by reference Scaffolding |
ML20205C510 | 21 March 1999 | Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections | Ultimate heat sink Offsite Circuit |
ML20204G383 | 19 March 1999 | Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 | Boric Acid VT-2 Incorporated by reference Scaffolding |
ML20155B671 | 26 October 1998 | Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan | Boric Acid High Radiation Area Non-Destructive Examination Hydrostatic Coatings Nondestructive Examination VT-2 Incorporated by reference Scaffolding |
ML20154D440 | 2 October 1998 | Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 | Boric Acid VT-2 Scaffolding |
ML20238F328 | 31 August 1998 | SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 | |
ML20238F655 | 28 August 1998 | SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams | VT-2 Incorporated by reference |
ML20217K633 | 20 April 1998 | Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code | |
ML20217K717 | 20 April 1998 | Safety Evaluation Accepting Requests for Relief NR-22,NR-23 & NR-24 for First 10-yr Insp Interval | VT-2 Incorporated by reference |
ML20216F492 | 11 March 1998 | Correction to Safety Evaluation Re Revised SG Tube Rapture Analysis | |
ML20212H185 | 6 March 1998 | SE Approving Temporary Use of Current Procedure for Containment Repair & Replacement Activities Instead of Requirements in Amended 10CFR50.55a Rule | |
ML20197B753 | 4 March 1998 | SER Accepting License Request for Relief from Immediate Implementation of Amended Requirements of 10CFR50.55a for Plant,Units 1 & 2 | |
ML20199G259 | 28 January 1998 | Safety Evaluation Rept Accepting Revised SG Tube Rupture Analysis | |
ML20199H003 | 21 January 1998 | SER Accepting Pressure Temp Limits Rept & Methodology for Relocation of Reactor Coolant Sys pressure-temp Limit Curves & Low Temp Overpressure Protection Sys Limits for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2 | |
ML20199C140 | 16 January 1998 | SER Accepting Request to Integrate Reactor Vessel Weld Metal Surveillance Program for Byron,Units 1 & 2 & Braidwood,Units 1 & 2 Per 10CFR50 | |
ML20199C123 | 13 January 1998 | Safety Evaluation Granting Second 10-yr Inservice Insp Program Plan Relief Request | Boric Acid Non-Destructive Examination Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Liquid penetrant Scaffolding |
ML20197G004 | 11 December 1997 | Safety Evaluation Accepting First 10-yr Interval Insp Program Plan,Rev 4 & Associated Requests for Relief for Plant | VT-2 Liquid penetrant Scaffolding |
ML20198H321 | 3 December 1997 | Safety Evaluation Re Licensee Submittal of IPE for Plant, Units 1 & 2,in Response to GL 88-02, IPE for Severe Accident Vulnerabilities | Boric Acid Loop seal Mission time Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
ML20198R306 | 27 October 1997 | Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Process Meets Intent of Subj GL | Boric Acid Loop seal Mission time Internal Flooding Probabilistic Risk Assessment Severe Accident Management Guideline |
ML20211L215 | 3 October 1997 | Safety Evaluation Supporting Licensee Relief Request,Per 10CFR50.55a(a)(3)(i) | Ultimate heat sink Design basis earthquake Earthquake |
ML20217C168 | 22 September 1997 | Safety Evaluation Accepting Request for Relief from ASME Code,Section Iii,Div 2 for Repair of Damaged Concrete Reinforcement Steel | |
NUREG-1335, Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 | 28 August 1997 | Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335 | Internal Flooding |
ML20141L932 | 29 May 1997 | Safety Evaluation Accepting Use of ASME Boiler & Pressure Vessel Code,Section Ix,Code Cases 2142-1 & 2143-1 for Reactor Coolant Sys for Plants | |
ML20141B555 | 13 May 1997 | SE Accepting First 10-yr Interval Inservice Insp Program Plan Request for Relief NR-29 for Braidwood Station,Units 1 & 2 | Incorporated by reference |
ML20140H887 | 8 May 1997 | Safety Evaluation Supporting Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping Ceco | |
ML20134L781 | 18 November 1996 | Safety Evaluation Granting Listed Relief Requests,Per 10CFR50.55a(f)(6)(i) Based on Impracticalities in Design of Valves That Limit IST in Traditional Manner Using Position Indicating Lights | Safe Shutdown Boric Acid Ultimate heat sink Stroke time Weld Overlay Probabilistic Risk Assessment Incorporated by reference Cold shutdown justification Power-Operated Valves Scaffolding |
ML20129F910 | 25 October 1996 | Safety Evaluation Accepting Request to Apply LBB Analyses to Eliminate Large Primary Loop Pipe Rupture from Structural Design Basis for Plant,Units 1 & 2 | Safe Shutdown Earthquake Earthquake |
ML20059E287 | 30 December 1993 | Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively | |
ML20056D492 | 27 July 1993 | Safety Evaluation Re Fuel Reconstitution | |
ML20127N185 | 25 January 1993 | Safety Evaluation Accepting Inservice Testing Program for Valves,Relief Request VR-4 | |
ML20059L337 | 14 September 1990 | SER Granting Interim Relief for 1 Yr or Until Next Refueling Outage to Continue Current Testing Methods While Licensee Investigates Feasibility of Acceptable Alternatives | |
ML20059L458 | 14 September 1990 | Sser Supporting Util Changes to Inservice Testing Program | Safe Shutdown Boric Acid Stroke time |
ML20058L996 | 6 August 1990 | Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SER | Safe Shutdown Emergency Lighting |
ML20058M000 | 6 August 1990 | Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SER | Safe Shutdown |
ML20248D591 | 7 August 1989 | SER Accepting Util 881130,890411,27 & 0523 Submittals Re Seismic Qualification of Byron Deep Wells | Safe Shutdown Ultimate heat sink Earthquake |
ML20247D147 | 18 July 1989 | SER Supporting Util Proposed Implementation of ATWS Design, Per 10CFR50.62 Requirements | Anticipated operational occurrence |
ML20244D819 | 13 June 1989 | SER Supporting Util ATWS Mitigating Sys Actuation Circuitry Designs | Anticipated operational occurrence |
ML20247B328 | 24 April 1989 | Safety Evaluation Re Mechanical Draft Cooling Tower Tests | Ultimate heat sink |
ML20244A722 | 11 April 1989 | Safety Evaluation Concluding That Rev 1 to First 10-yr Interval Inservice Insp Program Plan Constitutes Basis for Compliance w/10CFR50.55a & Tech Spec 4.0.5.Response to Items 2.2.2 & 2.2.3 of Inel Technical Evaluation Rept Requested | Incorporated by reference |
ML20155F159 | 6 October 1988 | Safety Evaluation Re Mixed Greases W/Greater than 5% Unqualified Contaminant in Limitorque Valve Operators. Insufficient Info Presented to Draw Conclusions | |
ML20236L200 | 30 October 1987 | Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 | |
ML20237G856 | 10 August 1987 | SER on Util 870303 & 0522 Ltr Re Optpipe Computer Code Used in Snubber Reduction Program.Code Acceptable for Piping Dynamic Analysis Using Both Uniform & Independent Support Motion Response Spectrum | |
ML20210R206 | 6 February 1987 | Safety Evaluation Supporting Util 850517,0802,0823,1211 & 860429 Submittals Re Environ Effects of High Energy Line Breaks in Auxiliary Steam or Steam Generator Blowdown Sys. Design of Blowdown Sys Acceptable | Boric Acid |
ML20210T257 | 6 February 1987 | SER Re Util 850802 Submittal Describing Design Details of Steam Generator Blowdown & Auxiliary Steam Sys to Detect & Isolate High Energy Line Breaks.Sys Design Acceptable, However,Two Deviations from IEEE-STD-297 Criteria Apparent | |
ML20209C357 | 23 January 1987 | SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing |