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INTERNAL OR EXTERNAL MEMORANDUM  and MEMORANDUMS-CORRESPONDENCE

ANSI N14.6-1978 +, ANSI N14.6 +, ANSI B30.2-1976 +, ANSI B30.9-1971 +, ANSI B30.2 +, ANSI B30.9 +  and ANSI N18.1976 +

Boron +, Iodine +, Cesium +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Chloride +  and Lead +

10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50 Appendix E +, 10 CFR 73.21 +, 10 CFR 2.790 +, 10 CFR 20.408 +, 10 CFR 50.49#b2 +, 10 CFR 50.49#b3 +  and 10 CFR 50.47#b +

ASME Code Case N-411 +, ASME Code Case N-397 +, ASME Code Case N-413 +  and ASME Code Case N-71-13 +

05000461  +  and 00461  +

Office of Nuclear Reactor Regulation +  and Siegel B +

GDC 15 +, GDC 14 +, GDC 30 +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 84-24, Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants +, NRC Generic Letter 84-16, Adequacy of On-Shift Operating Experience for Near Term Operating License Applicants +, NRC Generic Letter 85-08, 10 CFR 20.408 Termination Reports - Format +, NRC Generic Letter 85-07, Implementation of Integrated Schedules for Plant Modifications +  and NRC Generic Letter 85-06, Quality Assurance Guidance for ATWS Equipment That is Not Safety-Related +

ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +, ML20134K583 +...

9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +, 0.00667 d (0.16 hours, 9.523809e-4 weeks, 2.19168e-4 months)  +, 0.0926 d (2.222 hours, 0.0132 weeks, 0.00304 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

IEEE 323 +  and IEEE 384 +

ML20052H438 +, ML20082E876 +, ML20077N428 +, ML20101J966 +, ML20100N186 +, ML20099M430 +, ML20099M129 +, ML20099F428 +, ML20093K183 +, ML20137M193 +, ML20128Q772 +, ML20128P740 +, ML20128G541 +, ML20128G066 +, ML20128E802 +, ML20127K189 +, ML20127A760 +, ML20127A561 +, IA-84-940, Notification of 841218 Meeting W/Hydrogen Control Owners Group in Norwood,Ma,To Review & Inspect Installation of Test Equipment in 1/4 Scale Test Facility +, ML20262G398 +, U-600032, Affirms That Util Will Implement Reg Guide 1.33, Surveillance Requirements, Prior to Fuel Load.Epri Affiliation Will Be Contained to Monitor Progress of Cable Study Being Performed by Univ of Connecticut +, ML20054F596 +, ML20263C459 +, ML20011B249 +, ML19340D287 +  and ML19209A274 +

Westinghouse +, Limitorque +  and General Electric +

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

NUREG-0512 +, NUREG/CR-2136 +, NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads, +, NUREG-0462 +, NUREG-0887, Forwards Approved Changes to Tech Specs for Full Power License,Per 860618,0718 & 30 Requests.Certification That Changes Consistent W/Fsar,Ser & as-built Plant Requested by 860908 +, NUREG-0853, Forwards Suppl 6 to NUREG-0853, SER Re Operation of Clinton Power Station,Unit 1 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, 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-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-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-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +  and NUREG-1000 +

SP +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.75 +, Regulatory Guide 1.9 +, Regulatory Guide 1.108 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.64 +  and Regulatory Guide 1.44 +

07-47-470 +  and 4e-be +

Connecticut +, Illinois +, Washington +, California +, Alabama +  and Idaho +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Main Steam +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Reactor Vessel Water Level +, Ultimate heat sink +, Grab sample +, Offsite Dose Calculation Manual +, Anticipated operational occurrence +, Hydrostatic +, Operating Basis Earthquake +, Squib +, Emergency Lighting +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Control of Heavy Loads +, Fuel cladding +, Affidavit +, Thermal fatigue +, Water hammer +  and Control Room Habitability +