Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML20212E634 | 23 September 1999 | Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension | |
| ML20212D383 | 20 September 1999 | Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV | |
| ML20210N122 | 2 August 1999 | Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 | Nondestructive Examination Incorporated by reference |
| ML20209J077 | 16 July 1999 | Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist | Fire Barrier |
| ML20196F881 | 23 June 1999 | Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves | Backfit |
| ML20205F934 | 1 April 1999 | Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 | |
| ML20153H314 | 28 September 1998 | SE Accepting Util Proposed Alternatives as Contained in Relief Requests 3-SPT-3 & 3-SPT-4 for Second Interval & Code Case N-546 | Nondestructive Examination VT-2 |
| ML20247M190 | 20 May 1998 | Safety Evaluation Related to Browns Ferry,Unit 3 Nuclear Power Plant Individual Plant Exam | |
| ML20217E543 | 22 September 1997 | Safety Evaluation Re Flaw Evaluation of Core Spray Internal Piping for Plant,Unit 3 | Earthquake EVT-1 Flow Induced Vibration |
| ML20217C219 | 11 September 1997 | Safety Evaluation Supporting Amend 249 to License DPR-52 | Shutdown Margin Half scram Anticipated operational occurrence Fuel cladding |
| ML20149L230 | 28 July 1997 | Safety Evaluation Accepting License Relief Request from Certain ASME Code Requirements Delineated in Change to 10CFR50.55a for Plant,Units 1,2 & 3 | |
| ML20148U329 | 8 July 1997 | Safety Evaluation Denying Relief Request 3-ISI-1.Based on Review,Nrc Concludes That Licensee Does Not Have Sufficient Basis for Relief from Code Required Successive Exam | Incorporated by reference |
| ML20136D783 | 10 March 1997 | Safety Evaluation Authorizing Use of ASME Code Case N-416-1 | Non-Destructive Examination Hydrostatic VT-2 Incorporated by reference Pressure boundary leak Through-Wall Leakage |
| ML20132B270 | 11 December 1996 | Safety Evaluation Accepting Licensee Emi/Rfi site-survey Consistent W/Industry Stds & Practice | |
| ML20058K241 | 7 December 1993 | Supplemental Safety Evaluation Supporting Structural Steel Thermal Growth Design Critera at Plant | |
| ML20058J109 | 3 December 1993 | Safety Evaluation Accepting Licensee 921228 Submittal of Suppl Response to GL 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping | Non-Destructive Examination Weld Overlay Nondestructive Examination |
| ML20059C245 | 22 October 1993 | Safety Evaluation Accepting IST Program Requests for Relief | Stroke time Incorporated by reference Power-Operated Valves |
| ML20246M389 | 9 May 1989 | Safety Evaluation Supporting Util 890317 Proposed long-term Solution to Correct Rust Problems in Containment Spray Headers | |
| ML20245H337 | 1 May 1989 | Safety Evaluation Re Generic Ltr 83-28,Item 2.1 (Part 2) About Vendor Interface Program | |
| ML20245D571 | 19 April 1989 | Safety Evaluation Re Rust in Lower Containment Spray Header Due to Leaking Isolation Valves | |
| ML20247K556 | 23 September 1988 | Safety Evaluation Supporting Amends 155,151 & 126 to Licenses DPR-33,DPR-52 & DPR-68,respectively | |
| ML20154H272 | 19 April 1988 | Safety Evaluation Describing Relationship of Util Nuclear Performance Plan,Vol 3,Part Ii,Section 2.6, QA to TVA-TR75-1A, QA Program Description for Design,Const... W/Proper Implementation,Qa Program Description Acceptable | Systematic Assessment of Licensee Performance |
| ML20148K905 | 23 March 1988 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2, Post-Maint Testing of Reactor Trip Sys & All Other Safety-Related Components | |
| ML20246M234 | 29 February 1988 | Safety Evaluation Supporting Amends 145,141 & 116 to Licenses DPR-33,DPR-52 & DPR-68,respectively | |
| ML20214H909 | 13 May 1987 | Safety Evaluation Supporting Amends 133,129 & 104 to Licenses DPR-33,DPR-52 & DPR-68,respectively | |
| ML20206L982 | 20 June 1986 | Safety Evaluation Supporting Requests for Establishment of Common Date to Implement Inservice Insp Program Requirements.Start Date of 880301 Accepted for Second 10-yr Insp Interval | |
| ML20127D664 | 17 June 1985 | Safety Evaluation Re Licensee Response to Item 1.1 of Generic Ltr 83-28 on post-trip Review Program & Procedures. Post-trip Review Program & Procedures Acceptable | |
| ML18029A538 | 6 May 1985 | Safety Evaluation Re Mark I Containment long-term Program Pool Dynamic Loads Review for Plant.Pool Dynamic Loads Meet Acceptance Criteria of NUREG-0661 or Alternative Criteria Acceptable | |
| ML18029A540 | 6 May 1985 | Safety Evaluation Re Mark I Containment long-term Program Structural Review for Plant.Mods Follow NUREG-0661 Guidelines & Acceptable.Analyses Verified & Approved | |
| ML20148T781 | 1 December 1980 | Generic Safety Evaluation Re BWR Scram Discharge Sys | |
| ML20062A422 | 29 September 1978 | Safety Evaluation Rept Supporting Amend 43 to Lic DPR-33 Covering Pump Seizure Accident,Inadvertent Cold Loop Startup Transient & Monitoring of Safety Margins for 1 Loop Oper | |
| ML20247C172 | 23 February 1976 | Safety Evaluation Supporting Operation of Plant After Restoration & Mods of Facilities Following 750322 Fire |