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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20206A656 | 21 April 1999 | Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code | Incorporated by reference |
| ML20202H985 | 29 January 1999 | Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 | Time of Discovery Nondestructive Examination Incorporated by reference Scaffolding Backfit |
| ML20198S178 | 31 December 1998 | SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 | Boric Acid Nondestructive Examination VT-2 Dissimilar Metal Weld |
| ML20217H718 | 1 April 1998 | Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl | |
| ML20217B883 | 24 March 1998 | SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan | Boric Acid Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Pressure boundary leak |
| ML20203H955 | 23 February 1998 | SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 | |
| ML20203C281 | 9 December 1997 | Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program | |
| ML20198T362 | 24 October 1997 | Safety Evaluation Authorizing Supporting Second 10-year Interval ISI Program Requests for Relief RR-17 & RR-25 as Submitted by Southern Nuclear Operating Co on 970529 | Boric Acid VT-2 Incorporated by reference Scaffolding |
| ML20210R207 | 27 August 1997 | Safety Evaluation Accepting Relief Requests for Pump & Valve Inservice Testing Program | Boric Acid Incorporated by reference Cold shutdown justification |
| ML20058A304 | 19 November 1993 | Safety Evaluation Re Accumulator Pressure & Vol Instrumentation of Reg Guide 1.97 Environ Qualification Requirements,Per Generic Ltr 82-33.Category 3 Qualification of Instrumentation Acceptable | |
| ML20062J864 | 10 November 1993 | Safety Evaluation Denying Licensee 920617 Request for Amends to License Changing TS 3/4.6.1.7 & 4.6.1.2f for Plant | |
| ML20059J006 | 3 November 1993 | Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant | Reactor Vessel Water Level |
| ML20057F829 | 12 October 1993 | Safety Evaluation Accepting Util Submittals of Rev 7 to IST Program for Unit 1 & Rev 4 to IST Program for Unit 2 | |
| ML20057E302 | 4 October 1993 | Safety Evaluation Accepting Proposed Changes to EAL in Rev 15 of Plant Emergency Plan | |
| ML20056H644 | 26 August 1993 | Safety Evaluation Denying TS Change for Surveillance of Emergency Core Cooling Sys | High Radiation Area |
| ML20127B705 | 6 January 1993 | Safety Evaluation Supporting Rev 4 to First 10-yr Interval Inservice Insp Program for Facility | Incorporated by reference |
| ML20127B690 | 6 January 1993 | Safety Evaluation Supporting Rev 5 to First 10-yr Interval Inservice Insp Program for Facility | Incorporated by reference |
| ML20126F333 | 23 December 1992 | Safety Evaluation Accepting Licensee Schedule for Completing MOV Testing Program in Response to GL 89-10 | |
| ML20059E917 | 31 August 1990 | SER Supporting Util 890928 Request for Exemption from 10CFR20,App a & Authorizing Use of Radioiodine Protection Factor for Sorbent Canisters | |
| ML20206L649 | 22 November 1988 | Supplemental Safety Evaluation Concluding That Commitment & Schedule Re 14 Open Items Concerning SPDS Acceptable. Commitment to Complete 1000 H Availability Test by 881231 Acceptable.Requirements of License Condition 2.C.7(b) Met | |
| ML20155C990 | 3 October 1988 | Safety Evaluation Concluding That ATWS Design Proposed by Util Meets 10CFR50.62 Requirements,Subj to Successful Completion of Certain Noted Human Factors Engineering Reviews | Anticipated operational occurrence |
| ML20151E042 | 18 July 1988 | Sser Supporting Electrical Cable & Raceway Configurations for Plant | |
| ML20236S525 | 20 November 1987 | Safety Evaluation Supporting Util 870121,0522,0720 & 0929 Submittals Re Seismic Adequacy for Spent Fuel Pool Racks | |
| ML20236D294 | 28 October 1987 | Safety Evaluation Supporting Fire Suppression Sys Changes for Facility | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
| ML20236A852 | 15 October 1987 | Safety Evaluation Concluding That Util 870713,0930 & 1015 Submittals in Support of License Condition 2.C(8) Provide Acceptable Justification That Inorganic Zinc Coating on Fuel Oil Storage Tanks Will Not Adversely Affect Generators | Coatings |
| ML20235S810 | 7 October 1987 | Safety Evaluation Supporting Proposed Redesign of Steam Generator Upper Support of Reactor Coolant Loop Sys for Unit 2 & Proposed Revised FSAR | Safe Shutdown Earthquake Operating Basis Earthquake Earthquake |
| ML20235G737 | 22 September 1987 | Safety Evaluation Supporting Rev 2 to Inservice Testing Program,Providing Cold Shutdown Valve Testing Justifications & Addl Relief Requests | Unanalyzed Condition Boric Acid Cold shutdown justification |
| ML20237H301 | 19 August 1987 | Safety Evaluation Accepting 870601 Proposed Deletion of Electrical Penetration Filter & Exhaust Sys | |
| NUREG-1137, Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification | 14 August 1987 | Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification | Safe Shutdown Earthquake |
| ML20236H115 | 30 July 1987 | Safety Evaluation Supporting Util long-term Proposal for Support of Cable in Vertical Cable Trays Through Use of Stainless Steel Cable Ties | |
| ML20236F359 | 29 July 1987 | Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 2.1 Re Identification of safety-related Reactor Trip Sys Components.Util Response Adequate | |
| ML20235J944 | 7 July 1987 | Safety Evaluation Supporting Supplemental Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 Per NUREG-1000 | |
| ML20212F538 | 8 January 1987 | Safety Evaluation of Water Hammer Events & Corrective Actions Taken to Ensure Nuclear Svc Water Cooling Water Sys Integrity & long-term Operability.Sys Functional Integrity & long-term Operability Capability Adequate | |
| ML20214P397 | 15 September 1986 | SER Supporting Environ Qualification of Asco Solenoid Valves | |
| ML20205F273 | 8 August 1986 | Safety Evaluation Re Operability & Reliability of Tdi Emergency Diesel Generators.Submittal Concludes Technical Resolution of Generic Tdi Generator Issues | Liquid penetrant |
| ML20215A752 | 7 July 1986 | SER Supporting Util 860523 Proposed Changes to Tech Specs Re Reactor Trip Sys Instrumentation & Surveillance in Response to Generic Ltr 85-09.SALP Input Also Encl | Coatings Process Control Program |
| ML20215A967 | 22 May 1986 | SER Re Util 851207 Proposed Changes to Tech Specs Pertaining to Reactor Trip Sys Instrumentation & Surveillance,Per Generic Ltr 85-09.Proposed Tech Specs Should Be Submitted for Review,Per Generic Ltr.Salp Input Also Encl | |
| ML20215A782 | 8 May 1986 | Sser Re Util Response to Generic Ltr 83-28,Item 4.3, Reactor Trip Breaker Automatic Shunt Trip. Licensee Should Submit Proposed Tech Specs Consistent W/Generic Ltr 85-09 Guidance for NRC Review.Salp Input Also Encl | |
| ML20215G113 | 11 April 1986 | SER Re Util 830414,850315,0620,0906 & 860121 Responses to Reg Guide 1.97.Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 2,w/exception of Containment Sump Water Temp | |
| ML20127G742 | 13 June 1985 | Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks in Feedwater Sys |