Browse wiki

Letter  and Response to Request for Additional Information (RAI)

Iodine +, Sodium +, Hydrogen +  and Lead +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.62 +, 10 CFR 50.90 +, 10 CFR 50.91 +, 10 CFR 50.92 +, 10 CFR 50.55a +, 10 CFR 50.36#c2i +, 10 CFR 50.36#c +  and 10 CFR 50.65#a4 +

05000352  +, 05000353  +, 00352  +  and 00353  +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, ML071200238 +, ML070810400 +, ML111960066 +, ML17062A466 +, ML18172A145 +, TSTF-18-07, TSTF Comments on Draft Safety Evaluation for Traveler TSTF-505, Provide Risk-Informed Extended Completion Times and Submittal of TSTF-505, Revision 2 +, ML18347B366 +, ML19045A011 +, ML19192A031 +, ML011550525 +, RS-14-069, Seismic Hazard and Screening Report (Central and Eastern United States (CEUS) Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near- +  and NEI 06-09, Risk-Managed Technical Specifications (RMTS) Guidelines +

Turbine Trip +  and Reactor Trip +

Exelon +  and David Gudger +

GDC 44 +, GDC 17, Electric power systems +  and GDC 19, Control room +

ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +, ML19224B705 +...

0 d (0 hours, 0 weeks, 0 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 2.083333e-4 d (0.005 hours, 2.97619e-5 weeks, 6.849e-6 months)  +

IR 05000352/2018011 +  and ML19045A011 +

NUREG/CR-5485 +, NUREG/CR-3539 +, NUREG/CR-5565 +, NUREG-1855, Summary of 7/18/19 Public Meeting with Nuclear Energy Institute to Discuss Application of NUREG-1855, Guidance on the Treatment of Uncertainties Associated with PRAs in Risk-Informed Decision Making +, NUREG/CR-3028, Forwards NUREG/CR-3028, Review of Limerick Generating Station PRA & Vols 1 & 2 to NUREG/CR-0027, Proceedings of Intl Meeting on Thermal Nuclear Reactor Safety. Advises That NUREG/CR-3300 Not Published.W/O Encls +, NUREG-0991, Advises That Rev 1 to Plant Preservice Insp Program for Reactor Coolant Pressure Boundary & for ASME Code Class 2 & 3 Sys & Components Acceptable & in Compliance W/ 10CFR50.55a(g)(2).Evaluation Included in NUREG-0991,Suppl 7 +, NUREG-1360, Forwards Tech Specs,NUREG-1360 & Sser 8 Re Application for OL for Unit 2.W/o Encl +, NUREG/CR-4461, Requests Assistance in Achieving Mod of Reg Guide 1.76 Re Tornado Design Criteria,Based on NRC Recommendation in NUREG/CR-4461 & Initial Response to EPRI Declining to Adopt ANSI/ANS-2.3-1980 Std +, NUREG/CR-3493 +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

James Barstow +  and None none +

CP +  and Emergency Operating Procedure +

TAC:ME3551 +, EPID:L-2018-LLA-0567 +  and TAC:76689 +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.117 +

NEDC-32170P +, NEDO-24708A +, NEDC-30936P +  and NEDC-30936 +

SR-4.8.1.1.2 +, SR-4.8.1.1.1 +, SR-4.0.3 +, SR-4.0.2 +, SR-4.8.l.l +  and SR-4.1.5 +

1E-6 +, 1E-5 +, 3E-6 +, 3E-7 +, 2E-7 +, 5E-7 +, 5E-6 +, 4E-5 +, 8E-7 +, 5E-02 +, 8x10-7 +, 1t-7 +, 4rM-ecl +, 77me-n +  and 1t1e-e +

Pennsylvania +, Washington +  and Idaho +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Standby Liquid Control +, Intermediate Range Monitor +, Residual Heat Removal Service Water +, Spray Pond +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +, Control Rod +, Containment Spray +, Low Pressure Coolant Injection +...

TS-3.6.4.1 +, TS-3.5.1 +, TS-3.8.1 +, TS-3.7 +, TS-3.3.3 +, TS-3.6.1.3 +, TS-3.8.1.1 +, TS-3.3.2 +, TS-3.3.5 +, TS-3.7.1.2 +, TS-3.3.1 +, TS-3.1.5 +, TS-3.6.2.2 +, TS-3.7.1.1 +, TS-3.6.5.3 +, TS-3.3.4.2 +, TS-3.6.2 +, TS-3.3.9 +, TS-3.3.4.1 +, TS-3.3 +, TS-3.6.3.a +, TS-6.8.4.m +, TS-3.5.1.d +, TS-3.1.5.1 +, TS-3.7.2.a +, TS-4.1.5.c +  and TS-3.7.1.l +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Hot Short +, Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Tornado Missile +, Internal Flooding +, Probabilistic Risk Assessment +, Multiple Spurious Operation +, High Energy Line Break +, Tornado Generated Missile +, Tornado Missile Protection +, Surveillance Frequency Control Program +, Scram Discharge Volume +, Large early release frequency +, Loss of Offsite Power +, Excess Flow Check Valve +, Fuel cladding +, Offsite Circuit +, Failure to Scram +, Loss of condenser vacuum +, Control Room Habitability +  and Gas accumulation +