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List of results

• ML20205G200  + (Safety Evaluation Supporting Results of near-term Insp of Thermal Shield & Thermal Shield Support Sys,Contained in Util 860425 Final Core Support Barrel Insp Rept (post-Cycle 6))
• ML17059B542  + (Safety Evaluation Supporting Results of Reinsp of Util Core Shroud for Plant,Unit 1)
• ML20027C438  + (Safety Evaluation Supporting Resumption of Power Operations Following once-through Steam Generator Repair & Emergency Feedwater Sys Mods)
• ML20042G888  + (Safety Evaluation Supporting Rev 0 to Certificate of Compliance 9790,Model A1W-3 Holddown/Support Barrel & Shroud Disposal Container)
• ML20197E936  + (Safety Evaluation Supporting Rev 1 to Core Stratification Sample Acquisition Program)
• ML20155D394  + (Safety 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 NRC)
• ML20150D705  + (Safety Evaluation Supporting Rev 10 to Emergency Plan)
• ML20134F519  + (Safety Evaluation Supporting Rev 12 to Facility Site Addendum Re Removal of 345 Kv Offsite Transmission Line to West Gardner Switching Station from Design)
• ML20034B773  + (Safety Evaluation Supporting Rev 13 to Util First 10-yr Interval Inservice Insp Program)
• ML20059J006  + (Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant)
• ML20235G737  + (Safety Evaluation Supporting Rev 2 to Inservice Testing Program,Providing Cold Shutdown Valve Testing Justifications & Addl Relief Requests)
• ML20127B705  + (Safety Evaluation Supporting Rev 4 to First 10-yr Interval Inservice Insp Program for Facility)
• ML20133G496  + (Safety Evaluation Supporting Rev 4 to First 10-yr Inservice Insp Program & Granting Relief from Hydrostatic Testing Requirements of ASME Code)
• ML20127B690  + (Safety Evaluation Supporting Rev 5 to First 10-yr Interval Inservice Insp Program for Facility)
• ML20155D108  + (Safety Evaluation Supporting Rev 6 to Offsite Dose Calculation Manual as Acceptable Ref for Use W/Tech Specs)
• ML20151N470  + (Safety Evaluation Supporting Rev to Position Re Nuclear Sys Protection Sys self-test Sys Failure Detection & Indication for Facility)
• ML18106A213  + (Safety Evaluation Supporting Rev to TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing)
• ML20024H343  + (Safety Evaluation Supporting Rev to Test Frequency for Cable Megger Testing to License NPF-86)
• ML20137N479  + (Safety Evaluation Supporting Review of Response to IE Bulletin 80-11, Masonry Wall Design)
• ML19309B073  + (Safety Evaluation Supporting Revised ECCS Evaluation Model)
• ML19312C665  + (Safety Evaluation Supporting Revised ECCS Evaluation Model)
• ML13330B232  + (Safety Evaluation Supporting Revised Feedwater Line Break Analysis.Criteria W/Regard to Sys Pressure,Core Coolability & Radiological Consequence Met & Modeling Error of Previous Analysis Properly Addressed)
• ML19332B101  + (Safety Evaluation Supporting Revised License SNM-1227)
• ML18046B095  + (Safety Evaluation Supporting Revised Operating Allowance for Steam Generator B.Evaluation Based on Findings of Sept- Oct 1981 Insp of Eddy Current Testing,Data Evaluation & Tube Plugging)
• ML20155B835  + (Safety Evaluation Supporting Revised Procedure OP-3140, Providing Technically Acceptable Actions During Degraded Grid Voltage Conditions W/O LOCA to Assure Protection of Class 1E Electrical Sys & Equipment)

• ML19323G752  + (Safety Evaluation Supporting Revised QA Program)

• ML20136E584  + (Safety Evaluation Supporting Revised TSs 3.6.6.1 Sbvs. Proposed Changes Are Administrative in Nature & Provides Clearer & More Concise Direction to FPL Operators)
• ML16342D988  + (Safety Evaluation Supporting Revised Withdrawal Schedule)
• ML19319B945  + (Safety Evaluation Supporting Revision of Tech Spec 3.4.2 to Commit to Operability Decay Heat Removal Sys Pressure Relief Valve DH-4849 & to Remove Control Power from DH-11 & DH-12 When Open to Assure Overpressure Protection of RCS)
• ML19319B950  + (Safety Evaluation Supporting Revision of Tech Spec 4.5.2 Assuring Proper ECCS Flows During LOCA)
• ML19329B055  + (Safety Evaluation Supporting Revision of Tech Spec Table 3.2-1, DNB Margin Reactor Coolant Flow Rates to Accommodate DNBR Penalty Per OL Condition)
• ML19275A417  + (Safety Evaluation Supporting Revocation of Show Cause Order for Suspension of Facility Operation)
• ML20126L820  + (Safety Evaluation Supporting Revs 1 & 3 to 10-yr Inservice Insp Program & Request for Relief from Hydrostatic Testing Requirements)
• ML20246L422  + (Safety Evaluation Supporting Revs 15 & 6 to Pump & Valve Inservice Testing Program & Relief Requests)
• ML15244A119  + (Safety Evaluation Supporting Revs to Solid Waste Process Control Programs)
• ML20137T887  + (Safety Evaluation Supporting SPDS as Interim Implementation Until Open Issues Resolved.Issues Include Hot Leg Temp,Rhr Flow Rate,Stack Monitor,Steam Generator Radiation & Containment Isolation)
• ML20028D438  + (Safety Evaluation Supporting Safe Shutdown Capability in Event of Fire Per 10CFR50 App R,Sections III.G.3 & Iii.L)
• ML19225A399  + (Safety Evaluation Supporting Safety Injection Sys Actuation Tech Spec Change Request)
• ML20238C116  + (Safety Evaluation Supporting Schedular Exemption from GDC 54 & 55 Re MSIV Operability to Permit Fuel Load.Salp Input Also Encl)
• ML17059A001  + (Safety Evaluation Supporting Schedular Exemption from App J Interval for Type B Leak Rate Testing of Four Containment Penetrations)
• ML20195D204  + (Safety Evaluation Supporting Schedular Exemption from 10CFR50.46(a)(1)(i))
• ML20141C903  + (Safety Evaluation Supporting Second 10 Yr Interval ISI Program Plan Requests for Relief ISI-10 & ISI-11)
• ML17222A742  + (Safety Evaluation Supporting Second 10-Yr Interval Inservice Insp Program Plan)
• ML18037A520  + (Safety Evaluation Supporting Second 10-yr Interval Inservice Insp Program Plan for Unit 2)
• ML20136D672  + (Safety Evaluation Supporting Second 10-yr Interval Inservice Insp Program Plan)
• ML20128P170  + (Safety Evaluation Supporting Second 10-year Interval Inservice Insp Program Plan Requests for Relief NDE-23 Through NDE-30 for Plant Unit 2)
• ML20211F880  + (Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1)
• ML20041D124  + (Safety Evaluation Supporting Seismic Qualification of Auxiliary Feedwater Sys)
• ML19329C504  + (Safety Evaluation Supporting Selection of Matls for Reactor Vessel Internals & Reactor Coolant Pressure Boundary.Also Approves Controls to Prevent Hot Cracking of Austenitic Stainless Steel Welds)
• ML20209C314  + (Safety Evaluation Supporting Shroud Head Connection Replacement at Facility,Per Util 860107 Submittal)
• ML20091K761  + (Safety Evaluation Supporting Single Loop Operation Up to 50%)