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| Issue date | Title | Topic | |
|---|---|---|---|
| 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 |
| 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 |
| 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 | |
| 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 |
| 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 |
| 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 | |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 | |
| 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 | |
| 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 |
| ML20209C357 | 23 January 1987 | SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing | |
| ML20214R548 | 26 November 1986 | Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against PTS Events | |
| ML20215D734 | 1 October 1986 | Safety Evaluation Re Util 860623 Request That One Startup Test Be Modified & Five Startup Tests Be Eliminated.Mod to Rod Drop Measurement Test & Elimination of Certain Other Startup Tests Acceptable | |
| ML20214N720 | 9 September 1986 | Safety Evaluation Conditionally Supporting Rod Swap Technique & Util Nuclear Analysis Methods for Control Rod Worth Measurements | |
| ML20198H327 | 21 May 1986 | Sser Re Automatic Sys to Prevent Charging Pump Deadheading. Design Mod Acceptable.Ser Confirmatory Item 16 Considered Closed | |
| ML20197H226 | 5 May 1986 | SER Re Util 831105,840229 & 860404 Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review Data & Info Capabilities. Responses Acceptable | |
| ML20203N533 | 28 April 1986 | SER Finding Util 831105 & 850806 Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability Acceptable | |
| ML20154C364 | 25 February 1986 | Suppl to Safety Evaluation Supporting Results of Tests Conducted by Wyle Labs Contained in Test Rept 17769-01 to Justify Less Separation Between Class 1E & non-Class 1E Cables than Required by Reg Guide 1.75 | |
| ML20236A785 | 15 January 1986 | Safety Evaluation Providing Risk Perspective of Util May 1983 Proposal to Change Tech Specs Re Allowed Outage Times from 3 to 7 Days for Nine Safety Sys,Including Charging, Safety Injection & RHR Pumps & Emergency Diesel Generators | Probabilistic Risk Assessment |
| ML20209J109 | 5 November 1985 | SER Supporting Licensee Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Test Requirements That May Degrade Rather than Enhance Safety | |
| ML20138A871 | 7 October 1985 | Sser Supporting Util 850725 Proposed FSAR Change, Incorporating Nuclear Const Issues Group Rev 2 to Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants Into FSAR Table 3.8-2 & Section 3.10.3.2.2 | |
| ML20137S724 | 26 September 1985 | Safety Evaluation Supporting Licensee Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 Re post-maint Testing & Reactor Trip Sys Reliability | |
| ML20132B369 | 24 September 1985 | SER Granting Licensee 850831 Request to Defer Preservice Insp of Safety Injection Sys Class 2 Welds Until First Outage of at Least 10 Days Duration | Incorporated by reference |
| ML20129H907 | 11 July 1985 | SER Accepting 850605 Submittal Re Generic Ltr 83-28,Item 1.1 on post-trip Review Program & Procedures | |
| ML20127N991 | 15 May 1985 | SER Re Util 831105 Response to Generic Ltr 83-28,Item 1.1., Post-Trip Review. Program & Procedures Inadequate |