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

Atomic Energy Act of 1954 +  and Energy Reorganization Act of 1974 +

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Zirconium +, Chloride +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 2 +, 10 CFR 140 +, 10 CFR 50.54 +, 10 CFR 50.55a +, 10 CFR 50.55a#g +, 10 CFR 50.48#c5 +  and 10 CFR 100#ii +

Emergency Preparedness +  and Initiating Events +

SECY-82-465 +, SECY-76-545 +, SECY-77-561 +, NRC 760 +  and NRC 245 +

00244  +  and 05000244  +

Turbine Trip +  and Reactor Trip +

47 FR 13750 +, 46 FR 62281 +, 45 FR 65474 +, 45 FR 73080 +  and 45 FR 73000 +

GDC 44 +, GDC 10 +, GDC 60 +, GDC 21 +, GDC 13 +, GDC 45 +, GDC 25 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 82-10, Post-TMI Requirements +, NRC Generic Letter 81-01, Qualification of Inspection, Examination, Testing and Audit Personnel +, 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 82-12, Nuclear Power Plant Staff Working Hours +, NRC Generic Letter 82-05, Post-TMI Requirements +  and NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +

ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +, ML17255A483 +...

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 2.314815e-4 d (0.00556 hours, 3.306878e-5 weeks, 7.61e-6 months)  +

IEEE 279-1971 +  and IEEE 308-1974 +

ML17309A110 +, ML17261A317 +, ML17258B162 +, ML17258A977 +, ML17258A899 +, ML17258A774 +, ML17258A479 +, ML17258A417 +, ML17258A174 +, ML17256A880 +, ML17256A704 +, ML17256A700 +, ML17256A399 +, ML17255A347 +, ML17255A346 +, ML17250A681 +, ML17249A731 +, ML17249A358 +, ML17244A465 +, ML17244A375 +, ML18143A416 +, L-76-006, R. E. Ginna - Letter Regarding IE Bulletin No. 76-06: Diagram Failures in Air Operated Auxiliary Actuators for Safety/Relief Valves +, ML18143B182 +, ML18186A129 +, ML20072N589 +, 05000244/LER-1983-019-03, /03L-0:on 830613,while Changing from Cold to Hot Shutdown,Containment Spray Pumps Found in pull-stop Position at 207 F.Caused by Changes in Tech Spec Interpretation. Pumps Placed in Auto +, 05000244/LER-1981-011, Forwards LER 81-011/03L-0 +, IR 05000244/1981018 +, ML17258A291 +, IR 05000244/1981008 +...

NRC 760 +  and NRC 245 +

NRC Bulletin 79-27 +, NRC Bulletin 79-14 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-0452 +, NUREG/CR-2792 +, NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG-0623 +, NUREG-0705 +, NUREG/CR-2569 +, NUREG/CR-3394 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG/CR-2403 +, NUREG/CR-1717 +, NUREG-0886, Responds to Expressing Concern Re Manner in Which NRC Deals W/Problem of Steam Generator Tube Integrity.Nrc Is Adequately Addressing Problem.Steam Generator Insp History,Abstract of NUREG-0886 & NRR Budget Analysis Encl +, NUREG-0516 +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG-0500, Informs Comm of Comments Received Re NRC Survey Rept on Differing Prof opinions(NUREG-0500)& Staff Plans to Dev NRC Proposed Policy & Procedures.Provides Sched for Completion of Response Actions +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0050, Forwards Documents Re 1975 Fire at Plant.Documents Provide Overview of Experience W/Significant Fire That Resulted in Spurious Component Operation,Loss of Control Functions & Erroneous Control Room Instrumentation Readings.W/O Encls +, NUREG-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, 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-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-944 +, 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-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, 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-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0138, Exemption from GDC 17 Requirements Re LPCI Swing Bus Design +...

Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.45 +, Regulatory Guide 1.3 +, Regulatory Guide 1.76 +, Regulatory Guide 1.33 +, Regulatory Guide 1.7 +, Regulatory Guide 1.82 +, Regulatory Guide 1.53 +, Regulatory Guide 1.26 +, Regulatory Guide 1.58 +, Regulatory Guide 8.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.61 +, Regulatory Guide 1.91 +, Regulatory Guide 1.83 +  and Regulatory Guide 1.35 +

SECY-82-465 +, SECY-76-545 +  and SECY-77-561 +

SER 10-1 +, SER 15-1 +, SER 18-1 +, SER 14-1 +, SER 15-2 +, SER 10-2 +, SER 10-3 +, SER 10-4 +, SER 16-1 +, SER 17-1 +, SER 19-1 +, SER 15-3 +, SER 17-2 +, SER 20-1 +, SER 21-1 +  and SER 22-1 +

07-95-209 +, 07-83-10d +  and 1arge-break +

Manual Scram +  and Automatic Scram +

Washington +, Virginia +  and New York +

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 +, Reactor Pressure Vessel +, Residual Heat Removal +, Circulating Water System +, Main Steam Safety Valve +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, High winds +, Shutdown Margin +, Reactor Vessel Water Level +, Loop seal +, Ultimate heat sink +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Coatings +, High Energy Line Break +, Feedwater Heater +, Shift Technical Advisor +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Eddy Current Testing +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Fuel cladding +, Pressure Boundary Leakage +, Generic Issues Program +, Fire Protection Program +, Backfit +, Core Exit Thermocouple +, Overspeed +, Eddy Current Test +, Water hammer +...