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List of results

• IR 05000219/1993008  + (Engineering Insp Rept 50-219/93-08 on 930503-07.No Violation Noted.Major Areas Inspected:Design Mod,Corporate & Site Activities & Overall Communications Between Corporate & Site Engineering)
• IR 05000387/1990024  + (Engineering Insp Repts 50-387/90-24 & 50-388/90-24 on 901105-16.No Violations Noted.Major Areas Inspected:Control of Design,Design Changes,Mods & Temporary Mods,Staffing, Organization,Communication Between Depts & QA)
• ML22265A176  + (Engineering Inspection Presentation Slides for ROP Public Meeting)
• ML18057A215  + (Engineering Inspection Review Public Presentation (2-21-18))
• ML21291A189  + (Engineering Inspections Going forward-ROP Monthly Oct 2021)
• ML23005A282  + (Engineering Inspections Update Presentation- ROP Public Meeting January 2023)
• ML20215G712  + (Engineering Instruction SP-52-166, Ultrasonic Insp Procedure for Forgings,Bars,Plates,Bolting,Pipe,Tubing & Fittings - in Accordance W/Asme Code for Pumps & Valves for Nuclear Power. Related Info Encl)
• 05000390/FIN-2012005-01  + (Engineering Justification for Design of Control Building Watertight Hatches)
• 05000390/FIN-2012005-03  + (Engineering Justification for Modifications to NON-CONFORMING Ice Baskets)
• ML20205Q241  + (Engineering Operating Procedure EOP 25-4.00, Work Authorization)
• ML20205N878  + (Engineering Operating Procedure EOP 30-4.00, Engineering Info Sys. W/761015 Ref Page)
• ML20205P068  + (Engineering Operating Procedure EOP 40-5.00, Engineering Document Release)
• ML20205P316  + (Engineering Operating Procedure EOP 40-6.00, Independent Design Verification. W/770331 Temporary Procedure & Ref Page)
• ML20205Q182  + (Engineering Operating Procedure EOP 75-5.00, QA Training Program)
• ML20259E328  + (Engineering P&I Diagram:Service 402 HVAC-Control Building)
• ML20259E301  + (Engineering P&I Diagram:Sys 107 Feed Water Sys)
• ML20259E307  + (Engineering P&I Diagram:Sys 204 Residual Heat Removal-LPCI)
• ML20259E312  + (Engineering P&I Diagram:System 118 Service Water Normal)
• ML20259E333  + (Engineering P&I Diagram:System 204 Residual Heat Removal-LPCI)
• ML20259E325  + (Engineering P&I Diagram:System 205 Low Pressure Core Spray)
• ML20259E320  + (Engineering P&I Diagram:System 208 MSIV Positive Leakage Control)
• ML20259E341  + (Engineering P&I Diagram:System 209 Reactor Core Isolation Cooling)
• ML20259E337  + (Engineering P&I Diagram:System 256 Service Water - Standby)
• ML20265B062  + (Engineering P&ID Diagram System 051 Nuclear Boiler Instrumentation)
• ML20205P521  + (Engineering Practices & Procedures Manual Number 5.38, Design Verification)

• ML18018A823  + (Engineering Procedure 3.2, Design Change Control)

• ML20005F098  + (Engineering Procedure HEP-183, 10CFR21 Evaluation/Reporting Procedure, Rev 0)
• ML20148Q771  + (Engineering Procedure S-V-2.12, Inservice Insp Class 2 Components)
• ML20148Q693  + (Engineering Procedure S-V-2.13, Inservice Insp Class 3 Components)
• ML20148Q736  + (Engineering Procedure S-V-2.14, Inservice Testing of Pumps)
• ML20148Q742  + (Engineering Procedure S-V-2.15, Inservice Testing of Valves)
• ML20260K032  + (Engineering Production Schedule:Tectonic Province Acceleration)
• ML20260K027  + (Engineering Production Schedule:Tectonic Province Acceleration)
• ML20072B203  + (Engineering Program Plan,Project Instruction PI-3201-009, Midland Independent Design & Const Verification Program, Project 3201. Corrected Pages Encl)
• ENS 52707  + (Engineering Re-Evaluation of Tornado Impacts)
• PLA-6510, Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension  + (Engineering Report 0000-0101-0766-NP-R0, Main Steam Line Limit Curve Adjustment During Power Ascension)
• ML14260A439  + (Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2)
• NOC-AE-14003161, Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.  + (Engineering Report 1060, Rev. 1, Meter Factor Calculation & Accuracy Assessment for South Texas Project Units 1 & 2.)
• ONS-2015-058, Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc  + (Engineering Report 555, Oconee, Units 1, 2, and 3 - Ul 1569 Impact and Crush Tests on Keowee Underground Trench Power Cables for Duke Energy Carolinas, Llc)
• 1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 560  + (Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 560)
• ML12342A220  + (Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331)
• 1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331  + (Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331)
• LIC-13-0070, Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 1 of 2  + (Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 1 of 2)
• ML13193A237  + (Engineering Report EA12-021, Revision 1, Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Force Recommendation 2.3: Seismic. Part 2 of 2)
• ML040340118  + (Engineering Report ER-03-005, Revision 0, Sgla Characterization (1) Characterization of D.C. Cook Unit 1 Steam Generator Lower Assemblies)
• ML14260A438  + (Engineering Report ER-1059, Rev. 1, Bounding Uncertainty Analysis for Thermal Power Determination at South Texas Project Units 1 & 2 Using LEFM System)
• ML031080495  + (Engineering Report ER-290N, Bounding Uncertainty Analysis for Thermal Power Determination at Indian Point Unit 2 Nuclear Power Station Using LEFM System. Nonproprietary Version)
• 3F1207-03, Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station  + (Engineering Report ER-608NP, Revision 2, LEFM + Meter Factor Calculation and Accuracy Assessment for Crystal River Unit 3 Nuclear Power Station)
• ML093080009  + (Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 49)
• ML093080005  + (Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B)
• CP-200901403, Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45  + (Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45)