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 Issue dateTitleTopic
ML20217G99614 October 1999SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 &VT-2
Incorporated by reference
ML20212A74410 September 1999Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & SafetyHydrostatic
VT-2
Incorporated by reference
Finite Element Analysis
Liquid penetrant
ML20210U8114 August 1999SER 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
ML20210K98630 July 1999Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related MovsStroke time
ML20207B64825 May 1999SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station
ML20205B50926 March 1999SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2Boric Acid
VT-2
Incorporated by reference
Scaffolding
ML20205C51021 March 1999Revised 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 CorrectionsUltimate heat sink
Offsite Circuit
ML20204G38319 March 1999Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11Boric Acid
VT-2
Incorporated by reference
Scaffolding
ML20155B67126 October 1998Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program PlanBoric Acid
High Radiation Area
Non-Destructive Examination
Hydrostatic
Coatings
Nondestructive Examination
VT-2
Incorporated by reference
Scaffolding
ML20154D4402 October 1998Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2Boric Acid
VT-2
Scaffolding
ML20238F32831 August 1998SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2
ML20238F65528 August 1998SE 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 ExamsVT-2
Incorporated by reference
ML20217K63320 April 1998Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code
ML20217K71720 April 1998Safety Evaluation Accepting Requests for Relief NR-22,NR-23 & NR-24 for First 10-yr Insp IntervalVT-2
Incorporated by reference
ML20216F49211 March 1998Correction to Safety Evaluation Re Revised SG Tube Rapture Analysis
ML20212H1856 March 1998SE Approving Temporary Use of Current Procedure for Containment Repair & Replacement Activities Instead of Requirements in Amended 10CFR50.55a Rule
ML20197B7534 March 1998SER Accepting License Request for Relief from Immediate Implementation of Amended Requirements of 10CFR50.55a for Plant,Units 1 & 2
ML20199G25928 January 1998Safety Evaluation Rept Accepting Revised SG Tube Rupture Analysis
ML20199H00321 January 1998SER 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
ML20199C14016 January 1998SER Accepting Request to Integrate Reactor Vessel Weld Metal Surveillance Program for Byron,Units 1 & 2 & Braidwood,Units 1 & 2 Per 10CFR50
ML20199C12313 January 1998Safety Evaluation Granting Second 10-yr Inservice Insp Program Plan Relief RequestBoric Acid
Non-Destructive Examination
Hydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
Liquid penetrant
Scaffolding
ML20197G00411 December 1997Safety Evaluation Accepting First 10-yr Interval Insp Program Plan,Rev 4 & Associated Requests for Relief for PlantVT-2
Liquid penetrant
Scaffolding
ML20198H3213 December 1997Safety Evaluation Re Licensee Submittal of IPE for Plant, Units 1 & 2,in Response to GL 88-02, IPE for Severe Accident VulnerabilitiesBoric Acid
Loop seal
Mission time
Internal Flooding
Probabilistic Risk Assessment
Severe Accident Management Guideline
ML20198R30627 October 1997Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Process Meets Intent of Subj GLBoric Acid
Loop seal
Mission time
Internal Flooding
Probabilistic Risk Assessment
Severe Accident Management Guideline
ML20211L2153 October 1997Safety Evaluation Supporting Licensee Relief Request,Per 10CFR50.55a(a)(3)(i)Ultimate heat sink
Design basis earthquake
Earthquake
ML20217C16822 September 1997Safety 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-133528 August 1997Staff Evaluation Rept Concluding That Licensee IPE Complete Wrt Info Requested by GL 88-20 & Associated Guidance, NUREG-1335Internal Flooding
ML20141L93229 May 1997Safety Evaluation Accepting Use of ASME Boiler & Pressure Vessel Code,Section Ix,Code Cases 2142-1 & 2143-1 for Reactor Coolant Sys for Plants
ML20141B55513 May 1997SE Accepting First 10-yr Interval Inservice Insp Program Plan Request for Relief NR-29 for Braidwood Station,Units 1 & 2Incorporated by reference
ML20140H8878 May 1997Safety Evaluation Supporting Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping Ceco
ML20134L78118 November 1996Safety 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 LightsSafe Shutdown
Boric Acid
Ultimate heat sink
Stroke time
Weld Overlay
Probabilistic Risk Assessment
Incorporated by reference
Cold shutdown justification
Power-Operated Valves
Scaffolding
ML20129F91025 October 1996Safety Evaluation Accepting Request to Apply LBB Analyses to Eliminate Large Primary Loop Pipe Rupture from Structural Design Basis for Plant,Units 1 & 2Safe Shutdown Earthquake
Earthquake
ML20059E28730 December 1993Safety 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
ML20056D49227 July 1993Safety Evaluation Re Fuel Reconstitution
ML20127N18525 January 1993Safety Evaluation Accepting Inservice Testing Program for Valves,Relief Request VR-4
ML20059L45814 September 1990Sser Supporting Util Changes to Inservice Testing ProgramSafe Shutdown
Boric Acid
Stroke time
ML20059L33714 September 1990SER Granting Interim Relief for 1 Yr or Until Next Refueling Outage to Continue Current Testing Methods While Licensee Investigates Feasibility of Acceptable Alternatives
ML20058L9966 August 1990Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SERSafe Shutdown
Emergency Lighting
ML20058M0006 August 1990Safety Evaluation Denying Licensee Response to Station Blackout Rule.Staff Recommends That Licensee Reevaluate Areas of Concern Identified in SERSafe Shutdown
ML20247K25311 September 1989Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E3767 September 1989Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectivelyOffsite Dose Calculation Manual
Process Control Program
ML20248D5917 August 1989SER Accepting Util 881130,890411,27 & 0523 Submittals Re Seismic Qualification of Byron Deep WellsSafe Shutdown
Ultimate heat sink
Earthquake
ML20248C0733 August 1989Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20247D14718 July 1989SER Supporting Util Proposed Implementation of ATWS Design, Per 10CFR50.62 RequirementsAnticipated operational occurrence
ML20246L25726 June 1989Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20244D81913 June 1989SER Supporting Util ATWS Mitigating Sys Actuation Circuitry DesignsAnticipated operational occurrence
ML20245J07525 April 1989Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20247B32824 April 1989Safety Evaluation Re Mechanical Draft Cooling Tower TestsUltimate heat sink
ML20244A72211 April 1989Safety 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 RequestedIncorporated by reference
ML20205Q57631 October 1988SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & SecurityExemption Request