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 Issue dateTitleTopic
ML20212F56423 September 1999SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity LimitsFire Barrier
ML20196K4981 July 1999Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI AcceptableHigh Radiation Area
Stroke time
Incorporated by reference
Foreign Material Exclusion
Power-Operated Valves
Scaffolding
ML20195C4846 November 1998SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA ProgramTemporary Modification
Process Control Program
ML20217Q6706 May 1998SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating CyclesIncorporated by reference
ML20217P8287 April 1998Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i)Incorporated by reference
ML20217P0386 April 1998Safety Evaluation Supporting Amend 135 to License NPF-29Exemption Request
ML20216J42118 March 1998SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear StationIncorporated by reference
ML20199H37119 November 1997SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50Nondestructive Examination
VT-2
Incorporated by reference
ML20199F34318 November 1997SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1Condition Adverse to Quality
ML20216E9924 September 1997Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed PlantsHydrostatic
VT-2
Incorporated by reference
Pressure boundary leak
ML20134C56730 January 1997SER Denying Request for Exemption from 10CFR50.55a Entergy Operating,Inc Et Al,Grand Gulf Nuclear Station,Unit 1
ML20149M42212 December 1996Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept EnclNon-Destructive Examination
Hydrostatic
Nondestructive Examination
VT-2
Incorporated by reference
Liquid penetrant
ML20138B56811 December 1996Safety Evaluation Re Emergency Plan Change 28.001-95 to Entergy Operations,Inc,Grand Gulf Nuclear Station
ML20134K53218 November 1996Safety Evaluation Supporting Request for Relief Re 10CFR50.55a Inservice Testing of Main Steam Safety/Relief Valves for License NPF-29Stroke time
ML20129D04422 October 1996Safety Evaluation Supporting Request for Relief I-00014Hydrostatic
VT-2
Incorporated by reference
ML20129B87518 October 1996Safety Evaluation Accepting First 10-year Interval ISI Program Plan Addl Request for ReliefHydrostatic
Incorporated by reference
Dissimilar Metal Weld
ML20128H2497 October 1996Safety Evaluation Authorizing Licensee Proposed Alternative to Use ASME Code Case N-508-1 for Rotation of Serviced Snubbers & Pressure Relief Valves for Sole Purpose of Testing in Lieu of ASME Requirements
ML20107F56117 April 1996Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives RequestIncorporated by reference
Backfit
ML20128N13817 February 1993Safety Evaluation Accepting Proposal to Raise Design Ground Water Level from 109 Ft Above Msl to 114.5 Ft Above MslHydrostatic
ML20058B44125 October 1990Safety Evaluation Granting 900709 Request for Relief from Requirements for Leakage Testing of RCS in ASME Code,Section XI
ML20062A19416 October 1990Safety Evaluation Granting Relief Request from Inservice Insp RequirementsHydrostatic
Liquid penetrant
ML20059N4971 October 1990Safety Evaluation Accepting Util Response to Generic Ltr 88-01,w/listed ExceptionsPressure Boundary Leakage
ML20058N3946 August 1990Generic SER Re Mark III Containment Hydrogen Control, Concluding That HGN-112-NP, Generic Hydrogen Control Info for BWR-6 Mark III Containments Provides Acceptable Basis for Technical Resolution of Degraded Core Hydrogen IssueSafe Shutdown
Probabilistic Risk Assessment
Coatings
Fuel cladding
Scaffolding
ML20055G52718 July 1990Safety Evaluation Re Facility Procedures Generation Package. Util Needs to Revise Package to Address Programmatic Improvements IdentifiedExclusive Use
ML20055G03416 July 1990Safety Evaluation Re Boraflex Gaps in Spent Fuel Racks. Storage Racks Can Safely Accomodate Max Reactivity of Unit 1 Cycle 1 Through Cycle 4 Fuel.Storage Rack Surveillance Program Acceptable for long-term Storage of Spent FuelUnanalyzed Condition
Shutdown Margin
Operating Basis Earthquake
Earthquake
ML20055F90816 July 1990Safety Evaluation Accepting Criticality Analysis for Cycle 5 Fuel in Spent Fuel Storage Racks
ML20246D80221 August 1989Safety Evaluation Granting 880524 Requests for Relief from Certain Requirements of ASME Code,Section XIHydrostatic
Liquid penetrant
ML20246B63117 August 1989Safety Evaluation Supporting Amend 25 to License NPF-62
ML20247G70421 July 1989SER Accepting Licensee Commitment to Install ex-core Neutron Flux Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97,Rev 2,prior to Restart Following Fourth Refueling Outage
ML20245A82517 April 1989SER Re Proposed Changes to Administrative Controls Section of Tech Specs Concerning Min Shift Crew Composition,Unit Staff Qualifications,Training,Plant Safety Review Committee & Safety Review Committee Composition.Changes Unacceptable
ML20244D52914 April 1989Safety Evaluation Supporting Util Actions in Response to Generic Ltr 83-28,Position 4.5.2, Testing of Reactor Trip Sys. Justification for Not Testing Reactor Mode Switch or Backup Scram Valves Provided
ML20248J9005 April 1989Safety Evaluation Accepting Licensee Statements Confirming That Vendor Interface Program Exists W/Nsss Vendor for Components Required for Performance of Reactor Trip Function
ML20151P0295 August 1988Safety Evaluation Supporting Generic Ltr 83-28,Position 4.5.1 Re on-line Testing of Reactor Trip Sys
ML20234D90230 December 1987Safety Evaluation Supporting 870612,0814,1026 & 1119 Relief Requests from First 10-yr Interval Inservice Insp Program Requirements of Section XI of ASME CodeHydrostatic
VT-2
Incorporated by reference
ML20149E70930 December 1987Safety Evaluation Supporting Amend 41 to License NPF-29Hydrostatic
ML20234C76723 December 1987Safety Evaluation Granting 870612,0814,1026 & 1119 Requests for Relief from Certain Section XI ASME Code Requirements Re First 10-yr Interval Inservice Insp ProgramHydrostatic
VT-2
Incorporated by reference
ML20236B10215 October 1987Safety Evaluation of 870630 Submittal Supplemented on 870821 & 0911 Re Deferral of Certain Insps of Tdi Div II Emergency Diesel Generators.Deferral of Certain Design Review & Quality Revalidation Baseline Insps Approved
ML20235V1707 October 1987Safety Evaluation Re 861022 Rev 2 to Process Control Program (PCP) for Processing & Packaging of Wet Radwastes.Pcp AcceptableProcess Control Program
ML20234A9474 September 1987Safety Evaluation Re Util 870702 Submittal Re Containment Isolation for Various Instrument Lines.Util Proposed Alternate Basis to Meet GDC 55 to 10CFR50 App a Acceptable
ML20237H17121 August 1987Safety Evaluation Supporting Util 851014,870403 & 870622 Submittals Providing Info Re ATWS-related Design Features, Alternate Rod Injection,Standby Liquid Control Sys & Recirculation Pump Trip
ML20236M38431 July 1987Safety Evaluation on Generic Ltr 83-28,Items 3.1.1,3.1.2, 3.2.1 & 3.2.2 Re post-maint Testing.Licensee Programmatic Controls & Procedures for post-maint Testing of Components in Reactor Trip & safety-related Sys Acceptable
ML20215J1354 May 1987Safety Evaluation Re Spill of Sulphuric Acid at Plant on 860322.Licensee Monitoring & Recovery Sys Adequate to Contain & Eliminate Existing Acid Plume.No Addl Measures Recommended
ML20210C33930 April 1987Safety Evaluation Accepting Licensee 870129 Proposed Solution to Concern Re Control of Activities within Exclusion Areas
ML20204J14523 March 1987SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment DesignReactor Vessel Water Level
Hydrostatic
Earthquake
ML20207R1055 March 1987Safety Evaluation Supporting Util 861125 Rept on Conformance to Reg Guide 1.133,Rev 1, Loose-Part Detection Program for ...Sys of Light Water Cooled Reactors. License Condition 2.C(14) Adequately Addressed
ML20212M3864 March 1987Safety Evaluation Accepting Util 861223 Response to IE Bulletin 79-26, Boron Loss from BWR Control Blades, Per License Condition 2.C.(12)Shutdown Margin
ML20207N27612 January 1987SER Supporting License Condition 2.C.(17) Which Replaces Check Valve Disc in Train B Feedwater Line Into Which Cold Water from Condensate Storage Tank Injected by RCIC
ML20212G34212 January 1987Safety Evaluation Accepting Util 850228 & 860214 Submittals on Conformance to Reg Guide 1.97,Rev 2
ML20211P39012 December 1986SER Supporting Util 860825 Request for Rev to Relief Request I-00007 Seeking Relief from Surface Exam for Welds within Flued Heads & Guard PipesLiquid penetrant
Dissimilar Metal Weld
ML20214W8168 December 1986Safety Evaluation Granting Util 861015 Request for Release from Commitment to Compare Performance of on-line Instrumentation Vs Grab Sampling TechniquesGrab sample