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Issue date | Title | Topic | |
---|---|---|---|
IR 05000341/1985050 | 16 January 1987 | Safety Evaluation Re Proposed Fire Protection Mod to Independent Alternative Safe Shutdown Capability to Satisfy Open Items in Insp 50-341/85-50 | Safe Shutdown Fire Barrier |
ML20059J459 | 25 January 1994 | Safety Evaluation Supporting Request for Relief from ASME Code Re Inservice Testing Requirements to Measure Vibration Amplitude Displacement | |
ML20125C804 | 8 December 1992 | Safety Evaluation Accepting Util 920729 Revised Feedwater Nozzle Analysis for Plant,Per Generic Ltr 81-11 | Nondestructive Examination Finite Element Analysis |
ML20133L737 | 2 January 1997 | Safety Evaluation Supporting Amend 11 to License DPR-9 | Coatings |
ML20138L796 | 19 February 1997 | SER Related to Inservice Testing Program Relief Request Detroit Edison Co,Fermi Unit 2 | Incorporated by reference |
ML20151X065 | 11 September 1998 | Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant | Stroke time Incorporated by reference Power-Operated Valves |
ML20153B881 | 18 September 1998 | Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference |
ML20154L103 | 14 October 1998 | Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode | Foreign Material Exclusion |
ML20154L426 | 18 April 1985 | Safety Evaluation Supporting 1983 ASME Code,Section XI, Paragraph IWV-3520 Requirement for Periodic Closure Verification Testing of Normally Closed Check Valves w/safety-related Functions | Stroke time Power Operated Valves |
ML20154R233 | 21 October 1998 | Safety Evaluation Supporting Amend 13 to License DPR-9 | |
ML20198L424 | 8 January 1998 | Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval | Stroke time Incorporated by reference |
ML20198S334 | 6 January 1999 | Safety Evaluation Supporting Amend 15 to License DPR-9 | |
ML20203L570 | 19 August 1986 | Safety Evaluation Supporting Proposed Tech Specs Re Alternative Shutdown Sys.Acceptability Based,In Part,On Performance of Tests in Accordance W/Reg Guide 1.68, Initial Test Programs for Water-Cooled Nuclear Plants | |
ML20204E037 | 17 March 1999 | Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period | Incorporated by reference |
ML20205Q714 | 15 April 1999 | Safety Evaluation Supporting Amend 16 to License DPR-9 | |
ML20206B537 | 7 April 1987 | Safety Evaluation Supporting Util Request to Amend License Condition 2.C(10), Emergency Diesel Generator Lube Oil Surveillance Program. NRC Does Not Agree Condition Should Be Revised by Substituting for Mar 1985 Ltr | |
ML20206G508 | 5 May 1999 | Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety | Incorporated by reference |
ML20206J930 | 10 May 1999 | SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves | Power-Operated Valves Backfit |
ML20207H555 | 16 July 1986 | SER Re Corrective Actions for Emergency Diesel Generators. Concurs W/Licensee Proposed Special Bearing Insp,Provided Envelope Provided by Demonstration Test Program Not Exceeded | Safe Shutdown |
ML20207R854 | 12 March 1987 | Safety Evaluation Re Facility Mark I Containment Vacuum Breaker Structural Integrity.Licensee Restored Safety Margins of Breakers by Replacing Critical Parts W/Adequate Matl.Corrective Action Acceptable | |
ML20210R050 | 22 August 1997 | Safety Evaluation Accepting Revised Fermi-2 Control Ctr HVAC Sys Design Criteria in Design Criteria Document Submitted by Detroit Edison | Safe Shutdown Earthquake Finite Element Analysis |
ML20212E316 | 27 February 1987 | Safety Evaluation Re Operation of Rockwood Stone,Inc Quarry Near Plant | Hydrostatic Operating Basis Earthquake Earthquake |
ML20212J842 | 26 February 1987 | Safety Evaluation Approving Individual to Serve as Shift Operations Advisor,Per Generic Ltr 84-16 | |
ML20215E006 | 12 December 1986 | Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components | |
ML20217E907 | 2 October 1997 | Safety Evaluation Accepting Licensee Request for Relief from Certain ISI Requirements of ASME Boiler & Pressure Vessel Code,Section XI for Plant,Unit 2 | VT-2 Incorporated by reference Pressure Boundary Leakage |
ML20217N438 | 25 October 1999 | Safety Evaluation Supporting Amend 17 to License DPR-9 | |
ML20235S873 | 6 October 1987 | Safety Evaluation Re First 10-yr Interval Inservice Insp Program.Relief Granted from Exam & Testing Requirements of ASME Code & Alternate Methods Imposed Through Document | Incorporated by reference |
ML20236A398 | 15 October 1987 | Safety Evaluation Re Potential Hazards Associated W/ Operation of & Potential Explosion Accidents at Rockwood Stone,Inc Quarry.Hazards Considered Insignificant,Based on Util Confirmatory Analysis & Independent NRC Evaluation | Safe Shutdown Earthquake Hydrostatic Earthquake |
ML20236D742 | 28 July 1987 | Safety Evaluation Re Main Steam Instrument Line Leaks. Licensee Satisfactorily Resolved Problems Re Main Steam Instrument Line Leaks Which Occurred in Jan 1987 & Recurred in Apr 1987 | Flow Induced Vibration |
ML20236K326 | 1 July 1998 | SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 | Finite Element Analysis |
ML20236L655 | 4 November 1987 | SER Re Generic Ltr 83-28,Item 2.2.1, Equipment Classification Programs for All Safety-Related Components. Util 831103 Response Acceptable | |
ML20236X861 | 5 August 1998 | SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 | Finite Element Analysis |
ML20237A697 | 10 December 1987 | Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 1 Requiring Confirmation That All Reactor Trip Sys Components Identified as safety-related.Response Acceptable | |
ML20237A705 | 10 December 1987 | Safety Evaluation Re Util Response to Generic Ltr 83-28, Item 2.1,Part 2 Requiring Confirmation That Interface Established W/Nsss or W/Vendors of Each Reactor Trip Sys Components.Response Acceptable | |
ML20237B409 | 8 December 1987 | SER Accepting Util Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing (Reactor Trip Sys Components, All Other safety-related Components) | |
ML20237E117 | 25 August 1998 | Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program | Hydrostatic Nondestructive Examination VT-2 Incorporated by reference Scaffolding |
ML20244B714 | 4 April 1989 | SER Accepting Util Responses to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability | |
ML20246B289 | 28 April 1989 | Safety Evaluation Supporting Amend 9 to License DPR-9 |