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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

IWB-2500 +  and IWC-2500 +

Boron +, Iodine +, Cesium +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 73 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.55a#g +, 10 CFR 50.55a#g5iii +, 10 CFR 50.55a#a3 +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g3 +, 10 CFR 73.55#f +, 10 CFR 73.55#e +, 10 CFR 73.55#b +, 10 CFR 73.55#d +, 10 CFR 73.55#h +, 10 CFR 73.55#c +, 10 CFR 73.2#f1 +, 10 CFR 50.55#g5iii +, 10 CFR 50.55a#g3iv +  and 10 CFR 50#i +

Emergency Preparedness +  and Physical Protection +

ANPP-33282 +, ANPP-34124 +, ANPP-33713 +, ANPP-34127 +, ANPP-34174 +, ANPP-33771 +, ANPP-33905 +, ANPP-34103 +, ANPP-33487 +, ANPP-31264 +  and ANPP-43103 +

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

Turbine Trip +  and Reactor Trip +

GDC 31 +, GDC 32 +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-15, Implement. of Reg. Guide 1.150, "Ultrasonic Testing of RX Vessel Welds During Preservice & Inservice Examinations, REV.1 +, NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +, NRC Generic Letter 85-16, High Boron Concentrations +  and NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +

ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +, ML17299A908 +...

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

ML17299A783 +, ML17299A672 +, ML17299A655 +, IR 05000529/1985011 +, ML17299A546 +, ML17299A543 +, ML17298B129 +, 05000528/LER-1985-068, Corrected LER 85-068-00:on 851020,discovered That Four Valves Not Tested within Required Quarterly Surveillance Interval by 851018.Caused by Ineffective Communication Between Nonlicensed Personnel +, IA-85-696, Further Response to FOIA Request for All Records Re loss-of-load Test Incident at Facility as Discussed in NRC 851002 Ltr to Util.App D Documents Available in Pdr. Search for Addl Documentation Continuing +, IR 05000924/2010003 +, 05000528/LER-1985-071, :on 851024,reactor Tripped Following Manual Turbine Trip Due to Low Steam Generator Level.Caused by High Pressure Pulse Due to Rapid Closure of Throttle Valves.Time Delay Increased for Low Level Trip Bistable +, 05000528/LER-1985-063, :on 850912,when Main Generator Breaker Opened, Reactor Tripped Due to Core Protection Calculators Sensing Loss of Forced Coolant Circulation.Reactor Trip Caused Turbine Trip.Cause Not Stated +, 05000528/LER-1985-064, :on 850826,actuation of Control Room Essential Filtration Actuation Signal Occurred.Caused by High Radiation Alarm Set Off by Ground Design Mod of Radiation Monitoring Sys.Esf Maint Procedures Revised +, 05000528/LER-1985-029, :on 850526,surveillance Procedure for Insp of Fire Door Performed 30 H & 22 Minutes After Previous Insp Rather than at Required 24 H Interval.Caused by Inability of Fire Watch to Gain Access to Doors +  and ML17298B898 +

NUREG-857 +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, 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-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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, 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-0857, Supplement No. 8 Safety Evaluate on Report Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2, and 3 +  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 +

RT +, CH-240 +, CH-501 +, CH-524 +, CH-536 +, CH-239 +  and CH-532 +

NPF-34 +  and Palo Verde +

Arizona +, Washington +, California +, Idaho +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Auxiliary Feedwater +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Residual Heat Removal +, Reactor Water Cleanup +, Spray Pond +, Emergency Core Cooling System +  and Main Steam Line +

Safe Shutdown +, Boric Acid +, Shutdown Margin +, Grab sample +, Offsite Dose Calculation Manual +, Hydrostatic +, Nondestructive Examination +, Emergency Lighting +, Incorporated by reference +, Loss of Offsite Power +, Safeguards Contingency Plan +, Control of Heavy Loads +, Liquid penetrant +  and Core Exit Thermocouple +