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

Boron +, Iodine +, Iron +, Oxygen +, Lead +, Sulfur +, Zinc +  and Tungsten +

10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.49 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 50.55a +, 10 CFR 50.34#b2 +, 10 CFR 50.55a#g6 +, 10 CFR 70.24#9 +  and 10 CFR 50.12#a1 +

Emergency Preparedness +  and Mitigating Systems +

00424  +, 00425  +, 05000424  +  and 05000425  +

FV-0611 +  and FV-0610 +

May 12, 1986  +  and November 27, 1987  +

GDC 16 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +  and GDC 4, Environmental and dynamic effects design bases +

NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-23, Safety Evaluation of "Emergency Procedure Guidelines" +, NRC Generic Letter 85-12, Implementation of TMI Action Item II.K.3.5, "Automatic Trip of Reactor Coolant Pumps +, NRC Generic Letter 87-14, Operator Licensing Examinations +, NRC Generic Letter 87-12, Loss of Residual Heat Removal While the Reactor Coolant System is Partially Filled +, NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +, NRC Generic Letter 87-09, Sections 3.0 and 4.0 of Standard Tech Specs on Limiting Conditions for Operation and Surveillance Requirements +, NRC Generic Letter 87-08, Implementation of 10 CFR 73.55 Miscellaneous Amendments and Search Requirements +  and NRC Generic Letter 87-06, Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves +

ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +, ML20149D628 +...

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)  +  and 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +

LBP-86-41 +  and LBP-86-28 +

Feedwater +, ML20100J625 +, IR 05000424/1987019 +, IR 05000424/1987022 +, ML20204B982 +, ML20203K037 +, ML20207K278 +, ML20207C643 +, IR 05000424/1986084 +, ML20207Q322 +, IR 05000424/1987027 +, ML20214M585 +, ML20214L047 +, IR 05000424/1986127 +, IR 05000424/1987011 +, IR 05000424/1987042 +, ML20236E988 +, IR 05000424/1987055 +, ML20235W021 +, ML20235S270 +, ML20235M077 +, ML20235K088 +, IR 05000424/1987054 +, ML20235E144 +, ML20235A334 +, IR 05000424/1986112 +, ML20214T559 +, ML20236F239 +, ML20209F570 +, 05000424/LER-1987-050, :on 870728,reactor Trip Occurred.Caused by Personnel Error. Baseline Secondary Performance Test Suspended Until Further Engineering Tests Performed, Personnel Disciplined & Shop Meetings Held +...

Target Rock +  and Westinghouse +

NFPA 13 +  and NFPA 24 +

NRC Bulletin 79-15 +, NRC Bulletin 80-06 +, NRC Bulletin 87-01 +  and NRC Bulletin 85-03 +

NUREG/CR-4572 +, NUREG/CR-3660 +, NUREG/CR-4263 +, NUREG-137 +, NUREG-1137, Safety Evaluation Supporting Util 870601 Proposal Re Pipe Break Criteria Used for Flooding Analyses & Addition of Moderate Energy non-seismic Category I Piping to Exceptions List.Nrc Does Not Entirely Agree W/Util Justification +, 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-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-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 +

ML20149D628 +  and ML20149D628 +

Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.140 +, Regulatory Guide 1.68 +, Regulatory Guide 1.94 +  and Regulatory Guide 1.148 +

9A-1 +, 9A-46 +, 1HV-8716A +, 07-06-001 +, 1HV-8809A +, 1HV-8 +, 1HV-8809 +  and 1HV-3258 +

Palisades +, NPF-68 +  and NPF-61 +

Texas +, Georgia +, Maryland +, Washington +, Idaho +, New York +  and Florida +

Steam Generator +, Reactor Coolant System +, Feedwater +, Emergency Diesel Generator +, Auxiliary Feedwater +, Safety Parameter Display System +, HVAC +, Residual Heat Removal +, Control Room Emergency Filtration System +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Control Room Envelope +  and Main Steam +

Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Shutdown Margin +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Safe Shutdown Earthquake +, Coatings +, Operating Basis Earthquake +, Emergency Lighting +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Cold shutdown justification +, Earthquake +, Through-Wall Leakage +, Core Exit Thermocouple +, Affidavit +, Thermal fatigue +, Spent fuel rack +, Leak-Before-Break +  and Leak Before Break +

WCAP-8252 +, WCAP-9401-P-A +, WCAP-10529 +, WCAP-10931 +, WCAP-10456 +, WCAP-10551 +, WCAP-11583 +, WCAP-11584 +, WCAP-11599 +, WCAP-11600 +, WCAP-10552 +  and WCAP-11531 +

WCAP-8252 +, WCAP-9401-P-A +, WCAP-10529 +, WCAP-10931 +, WCAP-10456 +, WCAP-10551 +, WCAP-11583 +, WCAP-11584 +, WCAP-11599 +, WCAP-11600 +, WCAP-10552 +  and WCAP-11531 +