Browse wiki

Report, Miscellaneous, Technical Specification, Bases Change  and Manual

Nitrogen +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 72.48 +  and 10 CFR 50.36#c2ii +

NRC-15-0101, Commitment to Maintain Severe Accident Management Guidelines +, NRC-90-0043, Responds to NRC Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202 +, NRC-06-0014 +, NRC-88-0155 +, NRC-89-0055 +, NRC-94-0064 +, NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991 +, NRC-90-0178, Forwards Rev 3 to Inservice Testing Program (Plan) for Pumps & Valves for Fermi 2 Power Plant +, NRC-87-0033, Forwards Supplemental Response to NRC Ltr Re Insp Rept 50-341/85-03.Corrective Actions:Surveillance Procedures Revised to Remove Conflicting Info Involving Valve Inoperability.Title Pages of All Affected Procedures Encl +, NRC-88-0255, Responds to NRC Re Violations Noted in Insp Rept 50-341/88-21.Corrective Actions taken:safety-related Sys & Sys Containing QA1 Components Reviewed & 3 Addl Valves Recommended for Inclusion Into Locked Valve Program +, NRC-91-0094, Responds to NRC Re Violations Noted in Insp Rept 50-341/91-02.Corrective Actions:Writers Guide Revised to Define Acceptance Criteria in Technical Surveillance Procedures & Onsite Radiation Protection Meetings Held +  and NRC-17-0057, 1 to Updated Final Safety Analysis Report, List of Effective Sections, Tables, and Figures +

05000341  +  and 07200021  +

NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +  and NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs +

ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +, ML17305A038 +  and ML17305A038 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

NEI 96-07 +, NEI 98-03, Submittal of Revision No. 19 to Updated Safety Analysis Report for Monticello +  and NEI 99-04, Guideline for Managing NRC Commitment Changes +

NRC-15-0101, Commitment to Maintain Severe Accident Management Guidelines +, NRC-90-0043, Responds to NRC Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202 +, NRC-06-0014 +, NRC-88-0155 +, NRC-89-0055 +, NRC-94-0064 +, NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991 +, NRC-90-0178, Forwards Rev 3 to Inservice Testing Program (Plan) for Pumps & Valves for Fermi 2 Power Plant +, NRC-87-0033, Forwards Supplemental Response to NRC Ltr Re Insp Rept 50-341/85-03.Corrective Actions:Surveillance Procedures Revised to Remove Conflicting Info Involving Valve Inoperability.Title Pages of All Affected Procedures Encl +, NRC-88-0255, Responds to NRC Re Violations Noted in Insp Rept 50-341/88-21.Corrective Actions taken:safety-related Sys & Sys Containing QA1 Components Reviewed & 3 Addl Valves Recommended for Inclusion Into Locked Valve Program +, NRC-91-0094, Responds to NRC Re Violations Noted in Insp Rept 50-341/91-02.Corrective Actions:Writers Guide Revised to Define Acceptance Criteria in Technical Surveillance Procedures & Onsite Radiation Protection Meetings Held +  and NRC-17-0057, 1 to Updated Final Safety Analysis Report, List of Effective Sections, Tables, and Figures +

Regulatory Guide 1.93 +  and Regulatory Guide 1.6 +

SR-3.5.1.4 +, SR-3.0.4 +, SR-3.5.3.1 +, SR-3.5.1.5 +, SR-3.4.9.1 +, SR-3.4.8.2 +, SR-3.4.9.2 +, SR-3.9.7.1 +, SR-3.6.2.4.1 +, SR-3.5 +, SR-3.6.2.4.2 +, SR-3.5.3.2 +, SR-3.6.2.3.2 +, SR-3.6.2.3.3 +, SR-3.9.7.2 +, SR-3.9.8.2 +  and SR-3.9.8.3 +

Fermi +  and 07200021 +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Automatic Depressurization System +, Emergency Equipment Cooling Water +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +  and Low Pressure Coolant Injection +

TS-3.7.2 +, TS-3.5.1 +, TS-3.5.2 +, TS-3.5.3 +, TS-3.0.4 +, TS-3.9.7 +, TS-3.8.8 +, TS-3.8 +, TS-3.0.4.a +, TS-3.0.4.b +  and TS-3.9.8 +

Office of Nuclear Material Safety and Safeguards +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Unanalyzed Condition +, Reactor Vessel Water Level +, Ultimate heat sink +, Stroke time +, Temporary Modification +, Incorporated by reference +, Test box +, Surveillance Frequency Control Program +, Loss of Offsite Power +, Fuel cladding +, Biofouling +, GOTHIC +, Water hammer +  and Gas accumulation +