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 Issue dateTitleTopic
ML20133G2023 October 1985SER Re Generic Ltr 83-28,Item 1.1,concerning post-trip Review.Criteria for Determining Acceptability of Restart Insufficient.Analysis of Sys Important to Reactor Safety Should Be Conducted Prior to Restart
ML20133P99223 October 1985Safety Evaluation Re Final Rept Concerning Primary Reactor Containment Structural Integrity Test.Test Acceptable
ML20134A9117 August 1985Safety Evaluation Supporting Licensee 831105 & 850708 Responses to Generic Ltr 83-28,Item 1.1 Re post-trip Review Program Description & Procedure
ML20134C56730 January 1997SER Denying Request for Exemption from 10CFR50.55a Entergy Operating,Inc Et Al,Grand Gulf Nuclear Station,Unit 1
ML20134E06614 August 1985Safety Evaluation Re Review of 841214 & s Concerning Insp Program for once-through Steam Generator Sleeved Tubes for Plant.Licensee Program for Eddy Current Insp of Tubes Acceptable
ML20134K46923 August 1985Safety Evaluation Re Review of in Situ Operational Test Rept on HPCS Svc Water Pump.Vibration Levels of Pump Small & within Acceptable LimitsFlow Induced Vibration
ML20134K53218 November 1996Safety Evaluation Supporting Request for Relief Re 10CFR50.55a Inservice Testing of Main Steam Safety/Relief Valves for License NPF-29Stroke time
ML20134P84125 November 1996Safety Evaluation Denying Request for Relief 96-001 Re Second 10-yr Interval ISI Program Plan,Due to Failure to Provide Basis for ImpracticalityVT-2
Incorporated by reference
ML20137B57827 December 1985Safety Evaluation Re Reactor Trip Sys Reliability (vendor- Related Mods),Item 4.1 of Generic Ltr 83-28.Licensee Response to Vendor Recommended Mods for Reactor Trip Sys Acceptable
ML20137G04819 August 1985Safety Evaluation Concluding That Delay Allowable for Up to 5 Yrs,But No Later than Dec 1990,for Final Resolution of High Groundwater Issue at Dewatering Well 8Met Tower
ML20137P94821 January 1986Safety Evaluation on Licensee 831105 & 850423 Responses to Generic Ltr 83-28,Item 4.1, Reactor Trip Sys Reliability (Vendor - Related Mods). Responses Acceptable
ML20137Q89722 November 1985Safety Evaluation Re Low Pressure ECCS Sys Pressure Permissive Interlocks.Exceeding ASME Code Allowable Design Pressure for Interlocks Unacceptable
ML20137Z1642 December 1985Safety Evaluation Supporting Release of Shift Advisors from Advisory Duties
ML20138B56811 December 1996Safety Evaluation Re Emergency Plan Change 28.001-95 to Entergy Operations,Inc,Grand Gulf Nuclear Station
ML20138C85028 April 1997Safety Evaluation Authorizing Proposed Alternative to Vibration Measurement Requirements of OM-6,paragraph 4.6.4 (B),For Standby Svc Water Pumps & Diesel Fuel Oil Transfer Pumps,Per 10CFR50.55a(a)(3)(ii)Incorporated by reference
ML20138E62316 October 1985Safety Evaluation Re Relief Requests from Preservice Insp Requirements.Asme Code Section XI Preservice Exams Impractical.Relief GrantedHydrostatic
Nondestructive Examination
VT-2
Liquid penetrant
ML20138F48616 October 1985SER Re Allowable Control Room Inleakage to Meet Habitability Requirements.Reduction in Allowable Control Room Inleakage for Completed Control Room to 590 Cfm Recommended
ML20138K0565 May 1997SER Approving Licensees IPE Process Capable of Identifying Severe Accidents & Severe Accident Vulnerabilities,For Plant,Unit 2Internal Flooding
ML20138K25222 October 1985SER Supporting Util post-trip Review Data & Info Capabilities,Per Item 1.2 of Generic Ltr 83-28
ML20138Q7056 December 1985SER Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1 & 3.2.3,re post-maint Testing
ML20138R03917 December 1985SER Accepting Util 831104 & 850527 Responses to Generic Ltr 83-28,Item 3.1 Re post-maint Testing Verification of Reactor Trip Sys Components
ML20138R20517 December 1985Safety Evaluation Conditionally Accepting Util Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Periodic Maint Program & Parameter Trending,Respectively
ML20140C76713 January 1986SER Supporting Listed Requests for Relief from ASME Code Section XI Re Inservice Insp Plan RequirementsVT-2
ML20141E87312 August 1982Supplemental Safety Evaluation Rept Accepting Licensee Response to NRC Bulletin 80-06, Engineered Safety Features Reset Controls
ML20141F38830 June 1997Safety Evaluation Authorizing Licensee Request for Extension of First ISI Interval to 970924Hydrostatic
Incorporated by reference
ML20141H84130 July 1997Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code
ML20147H43731 March 1997Safety Evaluation Accepting Proposed P-T Limits for Heatup, Cooldown,Inservice Leak & Hydrostatic Testing & Core CriticalityHydrostatic
ML20148C61027 October 1978SER Re Potentially Serious Degradation of Offsite Power Sys. Licensee Mod Would Change Loads from Being block-started to Being sequentially-started.Mod Acceptable
ML20148D43914 January 1988Safety Evaluation Supporting Util 870731 & 1030 Submittals on Facility Compliance Re Alternate Rod Injection & Recirculation Pump Trip Sys,Per ATWS Rule 10CFR50.62
ML20148H1275 June 1997Supplemental Safety Evaluation Re Conformance to Reg Guide 1.97,Entergy Operations,Inc,Waterford Steam Electric Station Unit 3
ML20149E70930 December 1987Safety Evaluation Supporting Amend 41 to License NPF-29Hydrostatic
ML20149E8832 August 1994Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water SysIncorporated by reference
Missed surveillance
ML20149K94516 February 1996Safety Evaluation Authorizing Relief Request for Second 10-yr Interval IST Program Plan for Pumps & Valves at FacilitySafe Shutdown
Incorporated by reference
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
ML20150F95012 July 1988Safety Evaluation Supporting Util 840803 & 870922 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing of All safety-related Components
ML20151B56930 March 1988SER Accepting Util Proposal Re Item 2.2.1 of Generic Ltr 83-28 Concerning Equipment Classification Programs for All safety-related Components
ML20151D41312 July 1988Safety Evaluation Supporting Util 831105 Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability Online Testing
ML20151M52821 July 1988Safety Evaluation Re Control Sys Single Failure Study
ML20151P0295 August 1988Safety Evaluation Supporting Generic Ltr 83-28,Position 4.5.1 Re on-line Testing of Reactor Trip Sys
ML20151Q4701 August 1988Supplemental Safety Evaluation Re First 10-yr Inservice Insp Program.Nrc Concurs W/Determination Made by Licensee That Section XI of ASME Code Exam Requirements for Category B-A Welds in Reactor Pressure Vessel Are Impractical to Perform
ML20151R22316 January 1986Safety Evaluation Re Licensee 831105 & 850726 Responses to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Re Testing (Reactor Trip Sys Components).Responses Acceptable
ML20151S5423 September 1998Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site InspFire Barrier
ML20154A9635 May 1988Safety Evaluation Accepting Util 880303 Request for Partial Exemption from 10CFR50,App J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. Util May Continue Type a Testing When Excessive Leakage Identified
ML20154J2479 October 1998SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1
ML20154M65622 September 1988Safety Evaluation Supporting Licensee post-trip Review Program & Procedures Per Generic Ltr 83-28,Item 1.1 Re Generic Implications for Salem ATWS Events
ML20154N70722 September 1988Safety Evaluation Accepting Util Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Test Program for safety-related Components
ML20154R73028 September 1988Safety Evaluation Supporting Util 840206 Response to Generic Ltr 83-28,Item 4.5.1, Reactor Trip Sys Reliability (Sys Functional Testing)
ML20155D1082 April 1986Safety Evaluation Supporting Rev 6 to Offsite Dose Calculation Manual as Acceptable Ref for Use W/Tech SpecsOffsite Dose Calculation Manual
ML20155D3948 April 1986Safety Evaluation Supporting Rev 1 to Process Control Program on Interim Basis.Future Rev Should Address Full Compliance w/10CFR61 When Revised Guidance Becomes Available from NRCProcess Control Program
ML20155D62327 May 1988Safety Evaluation Supporting Conditional Approval of Fracture Mechanics Analysis of Reactor Vessel Flaw Indications in Hot Leg Nozzle to Shell Weld for UtilAnticipated operational occurrence
Probabilistic Risk Assessment
Nondestructive Examination
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