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List of results

• ML022470409  + (Relief, Use of ASME Code Case N-532-1, Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission, MB6089)
• ML050250415  + (Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2)
• ML030310256  + (Relief, Use of Code Case N-532-1 for Fourth 10-Year Interval Inservice Inspection Program)
• ML030620328  + (Relief, Use of Code Case N-600 for the Fourth 10-Year Interval, MB5403 and MB5404)
• ML031130039  + (Relief, Visual Test Requirements for Insulated Pressure-retaining Bolted Connections, MB7315)
• ML030090647  + (Relief, Volumetric Examination for Reactor Vessel Head-to-Flange Weld, MB5693)
• ML060830291  + (Relief, Volumetric Examination of Essentially 100 Percent of the Volume as Required by the ASME, Boiler and Pressure Vessel Code, Section XI, for Class 1 and 2 Welds)
• ML031070510  + (Relief, from ASME Code Operations and Maintenance Code Istb 4.3(e)(1) Ten-Year Interval Inservice Test for Containment Spray Pumps CBS-P9A and CBS-P9B (Tac No. MB6676))
• ML041190330  + (Relief, from the Requirements of the ASME Boiler and Pressure Vessel Code, Section XI Concerning Check Valve Inservice Testing Program, MC1032)
• ML092180954  + (Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155)
• ML022460046  + (Relief, the Third 10-Year Interval Inservice Inspection Program Plan, MB1607)
• ML13051A266  + (Reliefs from the Requirements of the ASME Boiler and Pressure Vessel Code for the Fourth 10-Year Inservice Inspection Interval)
• ML16340A922  + (Relieving Watch (Shift Turnover), Revision 3)
• ML102240343  + (Reload 16 Cycle 17 Supplemental Reload Licensing Report - License Amendment Request (H09-01) Supporting Use of Co-60 Isotope Test Assemblies)
• NLS2013027, Reload 27, Cycle 28 Startup Report  + (Reload 27, Cycle 28 Startup Report)
• ML20043H105  + (Reload 9/Cycle 10 Core Operating Limits Rept)
• ML17304A977  + (Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 1 Cycle 3)
• ML17300A956  + (Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 1 Cycle 2)
• ML17305B376  + (Reload Analysis Rept for Palo Verde Nuclear Generating Station,Unit 3,Cycle 3)
• ML17303A722  + (Reload Analysis Rept for Palo Verde Nuclear Generating Station Unit 2,Cycle 2)
• ML20135B459  + (Reload Analysis Rept for San Onofre Nuclear Generating Station 2,Cycle 3)
• ML20095H935  + (Reload Analysis Rept for Waterford 3 Cycle 6)
• ML20078D948  + (Reload Core Analysis Methodology Overview)
• ML20070P372  + (Reload Core Analysis Methodology Overview)
• ML20098F120  + (Reload Design Methodology)

• ML20207M754  + (Reload Design Methodology II)

• ML19354E695  + (Reload Evaluation Rept for Fort Calhoun Station Unit 1, Cycle 13)
• ML19305E312  + (Reload Fuel Application)
• ML20155D031  + (Reload Info & SAR for Oyster Creek Cycle 12 Reload)
• ML20095G859  + (Reload Licensing Rept for Browns Ferry Unit 2,Cycle 6. Determination of No Significant Hazards Encl)
• ML18026A849  + (Reload Licensing Rept,Unit 3, Cycle 6)
• ML18139B401  + (Reload Nuclear Design Methodology)
• ML18153B385  + (Reload Nuclear Design Methodology)
• ML20066E070  + (Reload Rept Catawba Unit 1,Cycle 6)
• ML20065D047  + (Reload Rept Catawba Unit 2 Cycle 7)
• ML20095B024  + (Reload Rept,Catawba Unit 1 Cycle 7. TS & Bases Included in Section 8.1)
• ML20126F014  + (Reload Rept,Catawba Unit 2,Cycle 6)
• ML20073M245  + (Reload Safety Analysis)
• ML19323H680  + (Reload Safety Analysis)
• ML20082U930  + (Reload Safety Evaluation)
• ML111820358  + (Reload Safety Evaluation)
• ML17325A428  + (Reload Safety Evaluation DC Cook Nuclear Plant Unit 1 Cycle 10)
• ML20096C393  + (Reload Safety Evaluation Methods for Application to Monticello Nuclear Generating Plant)
• ML20041B179  + (Reload Safety Evaluation Methods for Application to Prairie Island Units)
• ML17261A870  + (Reload Safety Evaluation Re Ginna Nuclear Plant Cycle 19)
• ML20247L406  + (Reload Safety Evaluation Sequoyah Unit 2,Cycle 4)
• ML20238F235  + (Reload Safety Evaluation for Millstone Unit 3 Cycle 2)
• ML20247L401  + (Reload Safety Evaluation for Redesign of Sequoyah Unit 2 Cycle 4)
• ML18139C308  + (Reload Safety Evaluation for Surry 1 Cycle 7 Redesigned Core (Part 2))
• ML20098E922  + (Reload Safety Evaluation,Beaver Valley Nuclear Plant Unit 1 Cycle 5)
• ML20236R863  + (Reload Safety Evaluation,Beaver Valley Nuclear Plant Unit 1 Cycle 7)