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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20155E115 | 7 April 1986 | Safety Evaluation Supporting Implementation of post-warranty Run Operational Readiness | |
| ML20155E986 | 19 December 1973 | Draft Safety Evaluation Detailing Items Requiring Resolution Expected to Occur Prior to Issuance of Const Permit | Ultimate heat sink Fuel cladding |
| ML20155F910 | 10 April 1986 | Safety Evaluation Supporting Util Request for Relief from ASME Boiler & Pressure Vessel Code Requirements | |
| ML20155H349 | 3 November 1998 | Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 | Hydrostatic VT-2 Incorporated by reference |
| ML20195C484 | 6 November 1998 | SER 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 Program | Temporary Modification Process Control Program |
| ML20195G886 | 18 November 1988 | SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Reactor Trip Sys Components | |
| ML20195H151 | 23 November 1988 | Safety Evaluation Accepting Responses Re Item 4.5.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability on-line Testing | |
| ML20195J895 | 17 June 1999 | Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii) | Incorporated by reference |
| ML20196A661 | 18 November 1988 | SER Accepting Util Response to Generic Ltr 83-28,Item 2.1, Part 2 Re Vendor Interface Programs for Reactor Trip Sys Components | |
| ML20196F491 | 1 December 1998 | SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 | Boric Acid High Radiation Area VT-2 Incorporated by reference Scaffolding |
| ML20196K498 | 1 July 1999 | Safety 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 Acceptable | High Radiation Area Stroke time Incorporated by reference Foreign Material Exclusion Power-Operated Valves Scaffolding |
| ML20197B515 | 23 October 1986 | Safety Evaluation Accepting,In Part & Denying,In Part,Util 860522 Request for Tech Spec Changes Re Diesel Generator Testing,Per Generic Ltr 84-15 | Offsite Circuit |
| ML20197E365 | 6 May 1986 | Safety Evaluation Supporting Util Large Break LOCA ECCS Analysis | |
| ML20198C554 | 15 May 1986 | Safety Evaluation Accepting Util Response to Items 3.1.3 & 3.2.3 of Generic Ltr 83-28 Requiring Licensee Review of Existing Tech Specs for post-maint Testing Requirements That May Degrade Safety.Items Closed | |
| ML20198M784 | 29 December 1998 | SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 | Probabilistic Risk Assessment Nondestructive Examination Large early release frequency Dissimilar Metal Weld |
| ML20199F343 | 18 November 1997 | SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 | Condition Adverse to Quality |
| ML20199H371 | 19 November 1997 | SER 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 10CFR50 | Nondestructive Examination VT-2 Incorporated by reference |
| ML20199H626 | 21 January 1999 | Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change | Hydrostatic |
| ML20199L624 | 26 June 1986 | SER Re Operability/Reliability of Tdi Emergency Diesel generator.Three-phase Plan for Assuring Generator Reliability Discussed.Sample License Conditions Encl | Liquid penetrant |
| ML20202F019 | 28 November 1997 | Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 | |
| ML20202G842 | 9 July 1986 | SER Accepting Util 831104,841119 & 850826 Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Signal Components | |
| ML20203E937 | 9 December 1997 | Safety Evaluation Granting Relief Request,Per 10CFR50.55a(g) (I) | Incorporated by reference |
| ML20203G436 | 22 July 1986 | Safety Evaluation Re Inservice Insp Program & Requests for Relief from Certain Inservice Insp Requirements.Inservice Insp Plan Acceptable for Implementation | |
| ML20203H859 | 17 February 1999 | Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3 | Boric Acid VT-2 Incorporated by reference |
| ML20203N706 | 9 October 1986 | Safety Evaluation Supporting Amend 2 to License NPF-47 | Packing leak |
| ML20203Q093 | 22 April 1986 | Safety Evaluation Supporting Util 850613 & 860311 Responses Re Confirmatory Tests of Auxiliary Pressurizer Spray Sys. Design Satisfies Requirements of BTP Rsb 5-1 W/Single Failure of Charging Loop Isolation Value | |
| ML20204B186 | 15 March 1999 | Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) | VT-2 Incorporated by reference |
| ML20204F891 | 25 July 1986 | Safety Evaluation Supporting Type a Containment Leakage Test Results,As Modified & Stated in 860228 Summary Technical Rept & 860228 Proposal to Use Current Schedule for Subsequent Type a Testing | |
| ML20204J145 | 23 March 1987 | SER Supporting Licensee Responses to Humphrey Concerns on Safety of Mark III Containment Design | Reactor Vessel Water Level Hydrostatic Earthquake |
| ML20205A633 | 25 March 1999 | SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3 | Hydrostatic Incorporated by reference |
| ML20205C604 | 19 March 1987 | Safety Evaluation Supporting Util 831105 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing | |
| ML20205D471 | 26 March 1999 | SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 | |
| ML20205D548 | 26 March 1999 | SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) | Incorporated by reference |
| ML20205D606 | 31 March 1999 | Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel | Time of Discovery Nondestructive Examination Through-Wall Leak |
| ML20205H875 | 25 October 1988 | Safety Evaluation Supporting Util 861124 & 880603 Responses to Generic Ltr 86-06,TMI Action Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps | Anticipated operational occurrence |
| ML20205M369 | 26 March 1987 | Sser Re Mark III Containment Related Issues | |
| ML20205M694 | 12 April 1999 | Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 | VT-2 Incorporated by reference Dissimilar Metal Weld |
| ML20205S215 | 27 May 1986 | Safety Evaluation Supporting Util 860110 Proposal to Remove Four Peak Recording Accelerographs Mounted on Reactor Piping | |
| ML20206A211 | 21 April 1999 | Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 | Stroke time Incorporated by reference Power-Operated Valves |
| ML20206F069 | 29 April 1999 | Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 | Boric Acid Nondestructive Examination VT-2 Incorporated by reference |
| ML20206F502 | 15 November 1988 | Safety Evaluation Supporting Transfer of Operating Responsibility to Sys Energy Resources,Inc | |
| ML20206H434 | 20 May 1986 | Safety Evaluation Supporting Amend 98 to License DPR-51 & Approval to Use B&W Integrated Reactor Vessel Matl Surveillance Program | |
| ML20206H789 | 5 June 1986 | Safety Evaluation Supporting Util Reactor Internals Vibration Assessment | Flow Induced Vibration |
| ML20206M771 | 11 May 1999 | SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 | |
| ML20206Q257 | 29 August 1986 | Sser Supporting 860607 & 0813 Proposed Limited Deferrel of Div II Emergency Diesel Generator Design/Quality Review Insps,Based on Favorable Implementation of Insp Program Outlined in Proposal | |
| ML20207E723 | 2 June 1999 | Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect | |
| ML20207E863 | 3 June 1999 | Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3 | |
| ML20207F339 | 9 August 1988 | Safety Evaluation Supporting Proposed Rev to Tech Spec Bases B 3/4.7.6, Control Room Air Conditioning Sys | Ultimate heat sink |
| ML20207H415 | 16 July 1986 | Safety Evaluation Supporting Technical Solution to Address Operability & Reliability of Tdi Emergency Diesel Generators | Liquid penetrant |
| ML20207K072 | 7 January 1987 | Safety Evaluation Re Reactor Coolant Pump Shaft Integrity Issue at Facility.Licensee Adequately Informed & Trained Operators as to Symptons & Actions to Be Taken Re Reactor Coolant Pump Sheared Shaft Event.Responses Acceptable |