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

ANSI N18.1976 +  and ANSI B31.1 +

IWB-3640 +  and IWB-2500 +

ASME Section XI +  and ASME Section III +

Boron +, Iodine +, Cesium +, Nitrogen +, Oxygen +, Hydrogen +, Lead +, Tin +  and Tungsten +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 2.206 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.62 +, 10 CFR 50.55a +, 10 CFR 50.49#b2 +, 10 CFR 50.49#b1 +, 10 CFR 50.49#b3 +, 10 CFR 50.55#e +  and 10 CFR 50.55#a +

RS-422 +  and L 18 +

00498  +, 00499  +, 05000498  +, 05000499  +, 00275  +  and 00323  +

51 FR 12502 +  and 51 FR 26393 +

GDC 57 +, GDC 15 +, GDC 16 +, GDC 55 +, GDC 56 +, GDC 14 +, GDC 21 +, GDC 24 +, GDC 30 +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 81-12, Fire Protection Rule (45 FR 76602, 11/19/80) +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  and NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps +

ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +, ML20237G463 +...

6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 7.75463e-4 d (0.0186 hours, 1.107804e-4 weeks, 2.54935e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 384 +, IEEE 323 +, IEEE 279 +, IEEE 500 +  and IEEE 472 +

Tritium +, Cs-137 +, Sr-90 +  and H-3 +

ML20091P945 +, ML20147C169 +, ML20138H998 +, IR 05000498/1983026 +, ML20199B534 +, IR 05000498/1987004 +, IR 05000498/1986033 +, ML20205D653 +, IR 05000498/1986014 +, ML20206P962 +, ML20206K292 +, IA-86-885, Final Response to FOIA Request.App C Documents Encl & Available in Pdr.App D Documents Partially Withheld (Ref FOIA Exemption 6).App E Documents Completely Withheld (Ref FOIA Exemption 7) +, IR 05000498/1986037 +, ML20207S303 +, ML20207Q050 +, IR 05000498/1987018 +, ML20214G489 +, ML20213G083 +, ML20213D679 +, IR 05000498/1986019 +, ML20265D953 +, ML20265D907 +, IR 05000498/1987029 +, ML20216D111 +, IA-88-107, Responds to Re Allegations W/Significant Bearing on Safety of Plant.Full Info Re Allegations Should Be Provided within 30 Days or Steps Will Be Taken to Acquire Info by Other Means +, ML20215M133 +, IR 05000498/1986038 +, ML20215A426 +, ML20214W612 +, ML20211G023 +...

Westinghouse +, Limitorque +  and Valcor +

NUREG/CR-0912 +, NUREG/CR-4572 +, NUREG/CR-4263 +, 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-0781, Summary of 890130-0201 Meeting W/Westinghouse,Houston Lighting & Power,Texas Utils,Bnl & EAS in Monroeville,Pa Re Overview of Status of Work on Bmi Thimble Tube Wear.Related Info Encl +, NUREG-781 +, 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-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +, NUREG-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +, NUREG-0531, Forwards NUREG-0531, Investigation & Evaluation of Stress Corrosion Cracking in Piping of LWR Plants & Notice of Issuance.W/O Rept.Fr Notice Encl +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

4kV +  and 600V +

AM +, ES +, SP +, RT +, EAP +, CP +  and CP-003 +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.143 +, Regulatory Guide 1.23 +, Regulatory Guide 1.99 +, Regulatory Guide 1.141 +  and Regulatory Guide 8.27 +

5R-20-9Z-42040 +, 5R-28-9Z-42079 +, 9E-EW05-01 +, 5R-13-9Z-4016 +  and E0Ps-that +

Texas +, Tennessee +, Connecticut +, Colorado +, Maryland +, North Carolina +, Washington +, California +, Massachusetts +, Idaho +, New York +  and Oregon +

Steam Generator +, Reactor Coolant System +, Feedwater +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Safety Parameter Display System +, HVAC +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Control Room Envelope +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Loop seal +, Mission time +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Internal Flooding +, Nondestructive Examination +, Emergency Lighting +, High Energy Line Break +, Notice of Violation +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Loss of Offsite Power +, Main Steam Line Radiation Monitor +, Safeguards Contingency Plan +, Exemption Request +, Earthquake +, Fuel cladding +, Fire Protection Program +, Core Exit Thermocouple +, Overspeed +, Thermal fatigue +, Water hammer +...

WCAP-10698 +, WCAP-8687 +, WCAP-8252 +, WCAP-11002 +, WCAP-11340 +, WCAP-10489 +, WCAP-11256 +, WCAP-10456 +, WCAP-11383 +, WCAP-11351 +  and WCAP-11348 +

WCAP-10698 +, WCAP-8687 +, WCAP-8252 +, WCAP-11002 +, WCAP-11340 +, WCAP-10489 +, WCAP-11256 +, WCAP-10456 +, WCAP-11383 +, WCAP-11351 +  and WCAP-11348 +