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MEETING MINUTES & NOTES--CORRESPONDENCE  and MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)

ANSI N45.4 +  and ANSI N13.1 1 +

Boron +, Iodine +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Chlorine +, Chloride +, Aluminum +, Titanium +, Silver +  and Tin +

10 CFR 50 Appendix R +, 10 CFR 50.46 +  and 10 CFR 50.56 +

TXX-4904, Forwards Addl Info Re Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps, Per 860502 Request.Info Concerns Reactor Coolant Pump Trip Criteria,Potential Problems & Operator Training & Procedures +, TXX-6376, Forwards Comments on NUREG-0797,SSER 12,Section 9.5.1, Fire Protection. Technical Basis for Fire Protection Program Remains App a to Apcsb 9.5-1 & 10CFR50.48(a),Footnote 3 +, TXX-88467 +, TXX-1653 +, TXX-88096 +, TXX-6582, Forwards Table of Comments Not Included in Util 870815 Clarification of Fire Protection Program,Per Sser 12 (NUREG-0797).Fire Protection Program Review & Fire Hazards Analysis Incorporated Into Design Basis Documents.W/O Encl +, TXX-6236, Forwards Results of Review of NRC 860805 SER (NUREG-1216) Re Tdi Emergency Diesel Generator Operability/Reliability. Response Categories Include Generic Phase I issues,plant- Specific Problems,Phase II Issues & Maint & Surveillance +, TXX-6157, Forwards Response to Request for Supplemental Info Re Coating Performance Program (Sser 9,NUREG-0797).Program Implemented on 850617 for in-process Coating Work Assures Integrity of Containment Coatings Throughout Life of Plant +, TXX-4653, Advises That Response to Findings Noted in Insp 50-445/85-11 Delayed Due to Planning & Participation in NRC Audits of Design Adequacy & Quality of Const Areas.Response Will Not Be Submitted Until 860115 +, TXX-4644, Forwards Rev B to LOCA & Seismic Analysis, in Response to 841109 Request for Addl Info Re Containment Purge & Vent Valve Operability.Addl Info,Including Table Re Valve Operator Torque Margins,Also Encl +, TXX-4641, Forwards Rev 4 to ODA-204, Preparation of Emergency Response Guidelines, Rev 0 to EOS-0.0, Rediagnosis & Rev 1 to Generic Plant Comparison, in Response to Preliminary License Condition Re Second Operating Cycle +, TXX-4613, Provides Results of Review of Coatings Nonconformance Repts Where use-as-is Was Disposition.Description of Program Providing in Situ Performance Evaluation for Containment Coatings Over Life of Plant & Related Info Encl +, TXX-4512, Advises That Util Power Corp Recommendation Incorporated Into Overall Turbine Generator Insp Plan.Requests That Licensing Condition Re Turbine Disk Insp Be Modified to Require Ultrasonic Insp Once Every 50,000 Operating Hours +, TXX-4491, Forwards Info Re Initiation of nonsafety-related Containment Coatings Program on 850610,per Sser 9.Program Will Be Fully Implemented by 850617.Addl Info Expected by 850801 +, TXX-4273, Advises of Adoption of Westinghouse Generic Core Damage Assessment Methodology,In Response to NUREG-0737,Item II.B.3, Post-Accident Sampling Capability +, TXX-4083, Forwards post-accident Sampling Sys Summary Procedure for Estimating Core Damage,Per NRC 830913 Request to Complete TMI Action Item II.B.3.Westinghouse Generic Procedure Scheduled for Completion by Feb 1984 +, TXX-4034, Forwards Supplemental Response to Items 1.b,4 & 6 of SER Suppl 2,Section II.B.3 Open Items Re post-accident Sampling Sys +  and TXX-3612, Forwards Comanche Peak Steam Electric Station Person-Motion Study of Post-Accident Sampling Activities to Demonstrate Compliance W/GDC-19 & NUREG-0737,Item II.B.3, Per SER Suppl 2 (NUREG-0797) +

05000445  +, 05000446  +, 00445  +  and 00446  +

Malloy M +  and NRC OFFICE OF SPECIAL PROJECTS +

GDC 61 +, GDC 63 +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +

ML20155C727 +, ML20155C727 +, ML20155C727 +, ML20155C727 +, ML20155C727 +, ML20155C727 +, ML20155C727 +, ML20155C727 +  and ML20155C727 +

8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

NUREG-1216, Safety Evaluation Supporting Amend 16 to License NPF-35 +, 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 +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

CP +  and OSP +

Regulatory Guide 1.137 +, Regulatory Guide 1.52 +, Regulatory Guide 1.143 +, Regulatory Guide 8.8 +, Regulatory Guide 1.23 +, Regulatory Guide 1.60 +, Regulatory Guide 1.32 +, Regulatory Guide 1.50 +, Regulatory Guide 1.140 +, Regulatory Guide 1.59 +, Regulatory Guide 1.145 +  and Regulatory Guide 1.95 +

Texas +, Pennsylvania +, Georgia +, Maryland +, Washington +, California +, New York +  and Wisconsin +

Steam Generator +, Feedwater +, Service water +, Auxiliary Feedwater +, HVAC +, Fuel Pool Cooling and Cleanup +, Circulating Water System +, Main Steam Safety Valve +, Decay Heat Removal +, Main Condenser +, Main Steam +, Containment Spray +  and Extraction steam +

TXX-4904, Forwards Addl Info Re Generic Ltr 85-12, Automatic Trip of Reactor Coolant Pumps, Per 860502 Request.Info Concerns Reactor Coolant Pump Trip Criteria,Potential Problems & Operator Training & Procedures +, TXX-6376, Forwards Comments on NUREG-0797,SSER 12,Section 9.5.1, Fire Protection. Technical Basis for Fire Protection Program Remains App a to Apcsb 9.5-1 & 10CFR50.48(a),Footnote 3 +, TXX-88467 +, TXX-1653 +, TXX-88096 +, TXX-6582, Forwards Table of Comments Not Included in Util 870815 Clarification of Fire Protection Program,Per Sser 12 (NUREG-0797).Fire Protection Program Review & Fire Hazards Analysis Incorporated Into Design Basis Documents.W/O Encl +, TXX-6236, Forwards Results of Review of NRC 860805 SER (NUREG-1216) Re Tdi Emergency Diesel Generator Operability/Reliability. Response Categories Include Generic Phase I issues,plant- Specific Problems,Phase II Issues & Maint & Surveillance +, TXX-6157, Forwards Response to Request for Supplemental Info Re Coating Performance Program (Sser 9,NUREG-0797).Program Implemented on 850617 for in-process Coating Work Assures Integrity of Containment Coatings Throughout Life of Plant +, TXX-4653, Advises That Response to Findings Noted in Insp 50-445/85-11 Delayed Due to Planning & Participation in NRC Audits of Design Adequacy & Quality of Const Areas.Response Will Not Be Submitted Until 860115 +, TXX-4644, Forwards Rev B to LOCA & Seismic Analysis, in Response to 841109 Request for Addl Info Re Containment Purge & Vent Valve Operability.Addl Info,Including Table Re Valve Operator Torque Margins,Also Encl +, TXX-4641, Forwards Rev 4 to ODA-204, Preparation of Emergency Response Guidelines, Rev 0 to EOS-0.0, Rediagnosis & Rev 1 to Generic Plant Comparison, in Response to Preliminary License Condition Re Second Operating Cycle +, TXX-4613, Provides Results of Review of Coatings Nonconformance Repts Where use-as-is Was Disposition.Description of Program Providing in Situ Performance Evaluation for Containment Coatings Over Life of Plant & Related Info Encl +, TXX-4512, Advises That Util Power Corp Recommendation Incorporated Into Overall Turbine Generator Insp Plan.Requests That Licensing Condition Re Turbine Disk Insp Be Modified to Require Ultrasonic Insp Once Every 50,000 Operating Hours +, TXX-4491, Forwards Info Re Initiation of nonsafety-related Containment Coatings Program on 850610,per Sser 9.Program Will Be Fully Implemented by 850617.Addl Info Expected by 850801 +, TXX-4273, Advises of Adoption of Westinghouse Generic Core Damage Assessment Methodology,In Response to NUREG-0737,Item II.B.3, Post-Accident Sampling Capability +, TXX-4083, Forwards post-accident Sampling Sys Summary Procedure for Estimating Core Damage,Per NRC 830913 Request to Complete TMI Action Item II.B.3.Westinghouse Generic Procedure Scheduled for Completion by Feb 1984 +, TXX-4034, Forwards Supplemental Response to Items 1.b,4 & 6 of SER Suppl 2,Section II.B.3 Open Items Re post-accident Sampling Sys +  and TXX-3612, Forwards Comanche Peak Steam Electric Station Person-Motion Study of Post-Accident Sampling Activities to Demonstrate Compliance W/GDC-19 & NUREG-0737,Item II.B.3, Per SER Suppl 2 (NUREG-0797) +

Safe Shutdown +, Coatings +, Met Tower +, Emergency Lighting +, Sewage Treatment Plant +, Loss of Offsite Power +, Exemption Request +, Turbine Missile +, Fire Protection Program +  and Water hammer +