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    "query_string": "[[Category:SAFETY EVALUATION REPORT--LICENSING &amp; RELATED ISSUES]] [[Site::Byron||Braidwood]]",
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	Issue date	Title	Topic
IR 05000456/1984044	25 February 1986	Supplemental SER Re Electrical Separation Deficiencies Revealed During Const Appraisal Team Insps 50-456/84-44 & 50-457/84-40
ML20056D492	27 July 1993	Safety Evaluation Re Fuel Reconstitution
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
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
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
ML20127N185	25 January 1993	Safety Evaluation Accepting Inservice Testing Program for Valves,Relief Request VR-4
ML20127N991	15 May 1985	SER Re Util 831105 Response to Generic Ltr 83-28,Item 1.1., Post-Trip Review. Program & Procedures Inadequate
ML20128M939	17 May 1985	SER Based on Util 831105 Response to Generic Ltr 83-28, Item 1.1 Re post-trip Review Program Description & Procedure
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
ML20129H907	11 July 1985	SER Accepting 850605 Submittal Re Generic Ltr 83-28,Item 1.1 on post-trip Review Program & Procedures
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
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
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
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
ML20140H887	8 May 1997	Safety Evaluation Supporting Request for Relief from ASME Code Repair Requirements for ASME Code Class 3 Piping Ceco
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
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
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
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
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
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
ML20197B753	4 March 1998	SER Accepting License Request for Relief from Immediate Implementation of Amended Requirements of 10CFR50.55a for Plant,Units 1 & 2
ML20197D566	5 May 1986	SER Accepting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review - Data & Info Capabilities
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
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
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
ML20198H327	21 May 1986	Sser Re Automatic Sys to Prevent Charging Pump Deadheading. Design Mod Acceptable.Ser Confirmatory Item 16 Considered Closed
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
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
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
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
ML20199K402	25 June 1986	Safety Evaluation of Applicant 831105 & 840601 Responses to 830708 Generic Ltr 83-28,Item 2.1 (Part 1),requiring Identification of Reactor Trip Sys Components as safety- Related.Licensee Program Approved
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
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
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
ML20206R052	25 June 1986	Safety Evaluation Supporting Util 840229 & 860421 Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2 Re post-maint Testing (All Other safety-related Components)
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
ML20207Q221	16 January 1987	SER Accepting Util 861117 Submittal on Utilization of Charcoal Absorber Matl in Safety & nonsafety-grade Air Filtration Units
ML20209C357	23 January 1987	SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing
ML20209G638	17 September 1985	SER Supporting Util 831105 & 850215 Responses to Generic Ltr 83-28,Items 3.1.1 & 3.1.2, Post-Maint Testing Verification... & 4.1 & 4.5.1, Reactor Trip Sys Reliability.... Proposed Programs Meet Requirements
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
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
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
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
ML20211J714	5 November 1986	Reevaluation & Affirmation of No Significant Change Finding Pursuant to Braidwood Station Unit 1 OL Antitrust Review

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