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ANSI/ANS 3.5-2009 +, ANSI/ANS 58.8-1994 +  and ANSI/ANS-3.5-2009 +

ASME Section III +, ASME Section I +  and ASME Section II +

Hydrogen +  and Lead +

10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 50 +, 10 CFR 52 +, 10 CFR 26.205 +, 10 CFR 50.47 +, 10 CFR 50.120 +, 10 CFR 50.150 +, 10 CFR 52.79 +, 10 CFR 50.54 +, 10 CFR 50.54#m2i +, 10 CFR 50.54#m2iv +, 10 CFR 50.54#k +, 10 CFR 50.54#m1 +, 10 CFR 50.54#m +, 10 CFR 50.34#f2iii +, 10 CFR 50.34#f2iv +, 10 CFR 50.54#m2iii +, 10 CFR 50.34#f2xi +, 10 CFR 50.34#f2xxvi +, 10 CFR 50.54#m2ii +, 10 CFR 50.34#f2xix +, 10 CFR 50.34#f2xviii +, 10 CFR 50.34#f2xii +, 10 CFR 50.34#f2xxi +, 10 CFR 50.34#f2xxiv +, 10 CFR 50.34#f2xvii +, 10 CFR 50.34#f3i +, 10 CFR 50.34#f2v +, 10 CFR 50.34#f2xxvii +...

Regulatory Guide 1.97 +, Regulatory Guide 1.47 +, ML021700373 +, ML12324A013 +, ML051390358 +, ML102560009 +, ML070720184 +, ML052770225 +, ML17249A979 +, ML17271A188 +, ML16123A404 +, ML18204A406 +, ML18086B746 +, ML18085B039 +, ML18212A336 +, ML18081A107 +, ML18178A202 +, ML17094A129 +, ML17094A153 +, ML063480112 +, ML102520360 +, ML071580631 +, ML090060858 +, ML15177A386 +, ML15177A387 +, ML15227A008 +, ML15234A008 +, ML15254A494 +, ML15293A581 +, ML15314A023 +...

Technical Support Center +  and Emergency Operations Facility +

Cayetano Santos +  and NRC/NRO/DLSE/LB2 +

ML18269A174 +, ML18269A174 +, ML18269A174 +, ML18269A174 +, ML18269A174 +, ML18269A174 +, ML18269A174 +, ML18269A174 +  and ML18269A174 +

NUREG-0835 +, NUREG-0711 +, NUREG/CR-6400 +, NUREG/CR-6753 +, NUREG/CR-3331 +, NUREG/IA-0137 +, NUREG-1122, Rev. 3 Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors +, NUREG-1462, Notification of 921209 Meeting w/ABB-C-E in Rockville,Md to Discuss Status of Closure of Open Items in Draft SER for Sys 80+ (NUREG-1462).Meeting Agenda Encl +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +  and NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +

AOP +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.47 +, Regulatory Guide 1.33 +  and Regulatory Guide 1.206 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, Safety Parameter Display System +, Remote shutdown +, Main Steam Line +, Safety Relief Valve +  and Control Rod +

Safe Shutdown +, Fitness for Duty +, Reactor Vessel Water Level +, Ultimate heat sink +, Probabilistic Risk Assessment +, Incorporated by reference +, Shift Technical Advisor +, Loss of Offsite Power +, Exemption Request +  and Manual Operator Action +