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ASME Section XI +, ASME Section III +  and ASME Section II +

Arizona Radiation Regulatory Agency +  and Federal Emergency Management Agency +

Boron +, Iodine +, Cesium +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Tungsten +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.49 +, 10 CFR 50.49#i +, 10 CFR 50.47#b +  and 10 CFR 50.55#e +

CR-JAF-1981-00035 +  and CR-JAF-1981-00055 +

NRC-2017-000292 +, ANPP-29066 +, ANPP-29422 +, ANPP-29252 +, LD-84-061 +, LD-84-069, Forwards marked-up CESSAR FSAR Pages Reflecting Review of Tech Specs Re First Sys 80 Plant.Rev Involves Interface Requirements for MSIV & Main Feedwater Isolation Valve Closure Time +, LD-84-070, Forwards Proposed Changes to CESSAR Re Startup Testing for Review.Changes Currently in FSAR Change Process & Will Be Incorporated in CESSAR Amend 10 +  and LD-84-071, Forwards CESSAR Changes Re Reduced HPSI Pump Flow.Reanalysis of Most Limiting Small Break LOCA Demonstrates That Sys Performance Is within Acceptance Criteria of 10CFR50.46 +

CR-JAF-1981-00035 +  and CR-JAF-1981-00055 +

05000528  +, 05000529  +, 05000530  +, 00528  +, 00529  +  and 00530  +

Technical Support Center +  and Emergency Operations Facility +

GDC 21 +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-21, Long Term Low Power Operation in Pressurized Water Reactors +  and NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +

ML091330140 +, ML091330140 +, ML091330140 +, ML091330140 +, ML091330140 +, ML091330140 +, ML091330140 +  and ML091330140 +

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +, 5.902778e-4 d (0.0142 hours, 8.43254e-5 weeks, 1.94055e-5 months)  +, 4.282407e-4 d (0.0103 hours, 6.117725e-5 weeks, 1.40785e-5 months)  +, 7.638889e-4 d (0.0183 hours, 1.09127e-4 weeks, 2.5113e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 0.0081 d (0.194 hours, 0.00116 weeks, 2.6635e-4 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 5.787037e-4 d (0.0139 hours, 8.267196e-5 weeks, 1.9025e-5 months)  +, 0.00174 d (0.0417 hours, 2.480159e-4 weeks, 5.7075e-5 months)  +  and 0.00853 d (0.205 hours, 0.00122 weeks, 2.804285e-4 months)  +

IEEE 384 +, IEEE 383 +  and IEEE 279 +

LD-84-061 +, LD-84-069, Forwards marked-up CESSAR FSAR Pages Reflecting Review of Tech Specs Re First Sys 80 Plant.Rev Involves Interface Requirements for MSIV & Main Feedwater Isolation Valve Closure Time +, LD-84-070, Forwards Proposed Changes to CESSAR Re Startup Testing for Review.Changes Currently in FSAR Change Process & Will Be Incorporated in CESSAR Amend 10 +  and LD-84-071, Forwards CESSAR Changes Re Reduced HPSI Pump Flow.Reanalysis of Most Limiting Small Break LOCA Demonstrates That Sys Performance Is within Acceptance Criteria of 10CFR50.46 +

Westinghouse +, Foxboro +, Limitorque +, Valcor +  and Target Rock +

Information Notice 83-72 +  and Information Notice 79-22 +

NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs 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-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, 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-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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 +  and NUREG-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.52 +, Regulatory Guide 1.33 +, Regulatory Guide 1.143 +, Regulatory Guide 1.101 +, Regulatory Guide 1.58 +, Regulatory Guide 1.68 +, Regulatory Guide 1.80 +, Regulatory Guide 1.83 +  and Regulatory Guide 1.68.3 +

Connecticut +, Arizona +, Maryland +, Washington +, California +, New York +, Oklahoma +, New Hampshire +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Core Spray +, Residual Heat Removal +, Steam Bypass Control System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam +  and Containment Spray +

Hot Short +, Safe Shutdown +, Health Physics Network +, Non-Destructive Examination +, Grab sample +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Post Accident Monitoring +, Hydrostatic +, Probabilistic Risk Assessment +, Anchor Darling +, Nondestructive Examination +, High Energy Line Break +, Local Leak Rate Testing +, Shift Technical Advisor +, Stress corrosion cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Open House +, Exemption Request +, Earthquake +, Control of Heavy Loads +, Fire Protection Program +, Fire Watch +, Hourly Fire Watch +, Core Exit Thermocouple +, Siren +, Water hammer +...

J-SGA-UV-175 +, J-SGB-UV-135 +, J-SGB-HV-178 +, J-SGA-UV-172 +, J-SGB-UV-130 +, J-SGB-HV-184 +, J-SGB-HV-185 +, J-ECA-XCV-15A +, J-ECA-XCV-15B +, J-ECB-XCV-16A +, J-ECB-XCV-16B +, J-EWB-XCV-90A +, J-HFA-TE-73A +, J-HFA-TE-73B +, J-SGB-HV-179 +, J-EWA-XCV-89A +, J-EWA-XCV-89B +, J-EWB-XCV-90B +, J-HFA-TE-74A +, J-HFA-TE-74B +  and J-SIN-TE-712 +