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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
ML20247K253	11 September 1989	Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively
ML20247E376	7 September 1989	Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively	Offsite Dose Calculation Manual Process Control Program
ML20248C073	3 August 1989	Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants
ML20246L257	26 June 1989	Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
ML20245J075	25 April 1989	Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
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
ML20205Q572	31 October 1988	SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security	Exemption Request
ML20205Q576	31 October 1988	SER 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 & Security	Exemption Request
ML20205M573	26 October 1988	Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively
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
ML20155G480	28 September 1988	Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively
ML20151E042	18 July 1988	Sser Supporting Electrical Cable & Raceway Configurations for Plant
ML20195G553	24 June 1988	Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC
ML20154H217	18 May 1988	Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program
ML20147D963	25 February 1988	Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90
ML20147E926	23 February 1988	Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively
ML20236S525	20 November 1987	Safety Evaluation Supporting Util 870121,0522,0720 & 0929 Submittals Re Seismic Adequacy for Spent Fuel Pool Racks
ML20236M963	6 November 1987	Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue	Anticipated operational occurrence
ML20236L200	30 October 1987	Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72
ML20236D294	28 October 1987	Safety Evaluation Supporting Fire Suppression Sys Changes for Facility	Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Earthquake
ML20195G550	28 October 1987	Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex	Systematic Assessment of Licensee Performance
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
ML20235A733	18 September 1987	Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable
ML20195G546	21 August 1987	Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235
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
ML20236Y022	8 July 1987	Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant	Boric Acid

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