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List of results

• ML20198J765  + (Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units)
• ML18038B516  + (Safety Evaluation Accepting 10CFR50,App R post-fire Safe Shutdown Program)
• ML20128D523  + (Safety Evaluation Accepting 120-day Response to Suppl 1 to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46,)
• ML20132A688  + (Safety Evaluation Accepting 1981 Version of Westinghouse Large Break ECCS Evaluation Model)
• ML17347B251  + (Safety Evaluation Accepting 30 Start & Load Acceptance Test in Lieu of 300 Start & Load Acceptance Test.Proposed Emergency Diesel Generators (Edgs) Similar to Previous type- Tested EDGs W/Stated Exceptions Raising Stress Concerns)
• ML20127J546  + (Safety Evaluation Accepting 731026 & 31 Proposed Changes to TS Re off-gas Holdup Sys)
• ML20127G621  + (Safety Evaluation Accepting 740123 Proposed Changes During Refueling Outage)
• ML18066A786  + (Safety Evaluation Accepting 8% Reduction in Calculated Fluence Due to Physical Changes in Plant & Denying Remaining 17% Due to Spectral Adjustments)
• ML20009B152  + (Safety Evaluation Accepting 810305 Proposed Alternative for Meeting NRC 791107 Recommendation GL-2 Which Requires Installation of Redundant Valve in Parallel W/Automatic Feedwater Sys Suction Valve)
• ML20134K735  + (Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing)
• ML14184A598  + (Safety Evaluation Accepting 840204 Submittal Outlining Intended Methods for Obtaining Scaling Factors for Waste Oil to Be Used in Implementing 10CFR61)
• ML20237H301  + (Safety Evaluation Accepting 870601 Proposed Deletion of Electrical Penetration Filter & Exhaust Sys)
• ML20236X649  + (Safety Evaluation Accepting 871006 Request for Reduced Duration Integrated Leak Rate Test at Facility,Based on Methodology in BN-TOP-1,Rev 1, Testing Criteria for Integrated Leak Rate Testing of Primary Containment..)
• ML20012A986  + (Safety Evaluation Accepting 880222 Inservice Insp Plan for First 10-yr Interval Inservice Insp & 890511 Requests for Relief from ASME Section XI Requirements for Pressurizer & Steam Generator)
• ML20033F445  + (Safety Evaluation Accepting 880630,0927 & 1019 Responses to Generic Ltr 88-01 Except as Noted & Concluding That Proposed IGSCC Insp & Mitigation Program Reasonably Assures Maint of long-term Structural Integrity of Austenitic Steel Piping)
• ML20059J238  + (Safety Evaluation Accepting 921125 TS Changes,Augmented by 930702 Response to NRC Rai,Allowing Use of Fixed Incore Detector Sys at Facility)
• ML17292A885  + (Safety Evaluation Accepting 951215 ISI Program Relief Request for RPV Alternative Exam for WPPSS WNP-2)
• ML17292B336  + (Safety Evaluation Accepting 970114 Submittal Which Requested Closure of Post TMI Commitment to Submit Safety Relief Valve in-service Performance Repts.Licensee Should Maintain Records at Plant Site for Future NRC Insps & Audits)
• ML20216E992  + (Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants)
• ML20199F675  + (Safety Evaluation Accepting 971209 Proposed Change to CPS USAR Which Will Impact Commitments Made in CPS QAP Description)
• ML20153F987  + (Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam)
• ML20249B628  + (Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower)
• ML20216F100  + (Safety Evaluation Accepting 980331 Licensee Proposal to Perform Alternative Testing for Containment Pressurization Test for Vynp)
• ML20236L182  + (Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3))
• ML20247K332  + (Safety Evaluation Accepting ATWS Mitigation Sys,Pending Tech Spec Issue Resolution)

• ML20058P433  + (Safety Evaluation Accepting ATWS Recirculation Pump Trip Sys Design Mod)

• ML18100B019  + (Safety Evaluation Accepting Actions Proposed & Taken by Licensee in Response to IEB-88-009, Thimble Tube Thinning in Westinghouse Reactors)
• ML18095A427  + (Safety Evaluation Accepting Actions Taken by Util to Fully Resolve Issues Identified in Bulletin 88-002 Re Rapidly Propagating Fatigue Cracks in Steam Generator Tubes)
• ML20055H915  + (Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes)
• ML18029A761  + (Safety Evaluation Accepting Adequacy of Electric Distribution Sys Voltages.Temp Rise on Induction Motors Will Decrease Due to Voltage Increase)
• NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31  + (Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31)
• ML15112A397  + (Safety Evaluation Accepting Alternative Proposed in Lieu of IWL-2421 of Subsection Iwl of Section XI of ASME Code)
• ML20125A434  + (Safety Evaluation Accepting Alternative Exam Methods Per 10CFR50.55a(a)(3)(i) & Addl Info Re Auxiliary Feedwater Sys Lube Oil Cooling,Per ISI Relief Requests B-7,B-8 & B-9 & Code Case N-481)
• ML17335A288  + (Safety Evaluation Accepting Alternative to 10CFR50.55a(g)(6) (Ii)(A),Augmented Reactor Pressure Vessel Exam Requirements for Donald C Cook Nuclear Plant,Unit 2)
• ML20203B424  + (Safety Evaluation Accepting Alternative to ASME Code Section XI Requirements to Use Code Case N-516-1 for Underwater Welding)
• ML20217E747  + (Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds)
• ML18065A793  + (Safety Evaluation Accepting Alternative Method to Inservice Exam Requirements of ASME Boiler & Pressure Vessel Code)
• ML17263A579  + (Safety Evaluation Accepting Alternative Proposed in 10-yr Inservice Insp Program Relief Requests 25 & 26,if Addl Surface Exam Performed on Root Pass of Weld)
• ML17191B410  + (Safety Evaluation Accepting Alternative to Licenses NPF-72, NPF-77,NPF-37,NPF-66,NPF-19,NPF-25,NPF-11,NPF-18,DPR-29 & DPR-30,respectively)
• ML20217A946  + (Safety Evaluation Accepting Amend 10 to License SNM-1227)
• ML20217Q955  + (Safety Evaluation Accepting Amend 12 to License SNM-1107)
• ML20127K414  + (Safety Evaluation Accepting Amend 12/change 20 to DPR-22 Changing Hydraulic Snubber TS)
• ML20094R302  + (Safety Evaluation Accepting Amend 174 to License DPR-46)
• ML20216G749  + (Safety Evaluation Accepting Amend 3 to License SNM-1097)
• ML20217P916  + (Safety Evaluation Accepting Amend 41 to License SNM-0696)
• ML20216G691  + (Safety Evaluation Accepting Amend 42 to License SNM-0696)
• ML20127J638  + (Safety Evaluation Accepting Amend 6 to DPR-22 Re Use of 250 Mci Kr-85)
• ML20078Q966  + (Safety Evaluation Accepting Amend 63 to License DPR-65)
• ML20127J513  + (Safety Evaluation Accepting Amend 7 (TS Change 16) to DPR-22 Re Reactor Vessel Matl Surveillance Program)
• ML20065N661  + (Safety Evaluation Accepting Amend 93 to License NPF-38)
• ML20059F972  + (Safety Evaluation Accepting Amend to License SNM-1865 Re Organizational Changes for Radiation Protection Functions)