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

IWB-3514 +, IWB-2500 +, IWC-2520 +, IWC-2600 +  and IWC-1230 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Lead +, Silver +  and Tin +

10 CFR 50.72 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 73 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 73.21 +, 10 CFR 73.55 +, 10 CFR 73 Appendix C +, 10 CFR 2.790 +, 10 CFR 50.49#b3 +, 10 CFR 50.49#i +, 10 CFR 50.54#f +, 10 CFR 50.34#b6iii +, 10 CFR 50.55a#g +, 10 CFR 50.55a#b +, 10 CFR 50.55a#g2 +, 10 CFR 50.55a#a2 +, 10 CFR 73.55#f +, 10 CFR 73.55#e +, 10 CFR 73.55#b +, 10 CFR 73.55#a +, 10 CFR 73.55#d +, 10 CFR 73.55#g +, 10 CFR 73.55#c +, 10 CFR 73.2#f1 +, 10 CFR 50.55a#a2i +...

ASME Code Case N-253-2 +  and ASME Code Case N-253 +

Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +

Physical Protection +  and Emergency Preparedness +

00387  +, 00388  +, 05000387  +  and 05000388  +

GDC 44 +, GDC 31 +, GDC 32 +, GDC 36 +, 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 83-41, Fast Cold Starts of Diesel Generators +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-24, TMI Task Action Plan Item I.G.1, "Special Low Power Testing and Training," Recommendations for BWRS +, NRC Generic Letter 83-20, Integrated Scheduling for Implementation of Plant Modifications +, NRC Generic Letter 83-19, New Procedures for Providing Public Notice Concerning Issuance of Amendments To Operating Licenses +, NRC Generic Letter 83-18, NRC Staff Review of the BWR Owners' Group (BWROG) Control Room Survey Program +, NRC Generic Letter 83-17, Integrity of Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses +, NRC Generic Letter 83-16, Transmittal of NUREG-0977 Relative to the ATWS Events at Salem Generating Station, Unit NO. 1 +, 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 83-01, Operator Licensing Examination Site Visit +  and NRC Generic Letter 84-01, NRC Use Of The Terms "Important To Safety" and "Safety Related" +

ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +, ML17139C297 +...

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 6.481481e-4 d (0.0156 hours, 9.259259e-5 weeks, 2.1308e-5 months)  +

PLA-1716, Responds to Ser,Suppl 5,Item 3.11.1(1)(a) Re nonsafety- Related Electrical Equipment.Failure of nonsafety-related Equipment Unlikely Due to Classification Under Qualification Program +, ML18031A388 +, ML031080565 +, 05000387/LER-1982-018, Forwards LER 82-018/03L-0 +, 05000387/LER-1982-032, Forwards LER 82-032/01T-0 +, ML20087J852 +, ML20082C348 +, 05000387/LER-1983-082, Requests Clerical Correction Be Made to Transmittal Ltr for LER 83-082/01T-0.Correct Ltr Number Is PLA-1741 +, 05000387/LER-1983-048, Forwards LER 83-048/03L-0 +, 05000387/LER-1983-139-01, Alternate Power Supply Breaker Removed & Bus 1A203 Did Not Have Two Independent Offsite Sources of Power.Caused by Personnel Error.Proper Interpretation of Tech Specs Provided +, 05000387/LER-1983-144-01, /01T-0:on 831105,while Operating at Less than 2% Power,Failure to Locate Partially Obscured Deuterium Analyzer Return Valves Made Analyzer Channels Inoperable. Caused by Location of Analyzer Return Valves +, 05000387/LER-1983-083-03, /03L-0:on 830520,during Review of Draft Procedures,Alarm Check Required by Tech Spec Not Included in Chemistry Surveillance Procedures.Change Made to Surveillance Procedures to Include Alarm Check +, 05000387/LER-1983-075-01, /01P-0:on 830515,interactions of Chlorine Detector in Control Room Emergency Outside Air Supply Sys Noted Following Loss of Power.Procedure Changes Instituted to Provide Operators W/Appropriate Corrective Actions +, ML18040B016 +, ML17138B850 +  and ML17053C239 +

Valcor +, General Electric +  and Target Rock +

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-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, 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-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-776 +, NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +, NUREG-0776, Safety Evaluation on Followup Allegation Re Chugging Loads at Facility,Per Sser 3 (NUREG-0776) +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

RT +  and EP-IP-030 +

Regulatory Guide 1.97 +, Regulatory Guide 1.27 +, Regulatory Guide 1.75 +, Regulatory Guide 1.70 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.29 +

NEDO-22209 +  and NEDE-22178 +

2P-202A +, 07-79-01B +, 2P-206-A +, 2E-205-A +, 2P-202-A +, 2P-206A +, 2E-205 +, 2P-206B +, 2P-206A-359-2 +  and D8B-221 +

Pennsylvania +, Maryland +, Washington +  and Idaho +

Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Recirculation Pump +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Remote shutdown +, Residual Heat Removal Service Water +, Spray Pond +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Main Steam +

Safe Shutdown +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Hydrostatic +, Probabilistic Risk Assessment +, Nondestructive Examination +, Incorporated by reference +, High Energy Line Break +, Scram Discharge Volume +, Loss of Offsite Power +, Integrated leak rate test +, Safeguards Contingency Plan +, Exemption Request +, Control of Heavy Loads +, Liquid penetrant +  and Fire Protection Program +