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Letter  and Emergency Preparedness-Emergency Plan

Boron +, Iodine +, Uranium +, Oxygen +, Hydrogen +  and Lead +

10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 50.47 +, 10 CFR 50.90 +, 10 CFR 50.92 +, 10 CFR 50 Appendix E +, 10 CFR 50.54#q +, 10 CFR 50.47#b4 +  and 10 CFR 50.92#c +

Emergency Preparedness +  and Barrier Integrity +

SECY 91-283 +  and L-16-277 +

H.2(a) +, S.4(n) +  and H.2(e) +

05000334  +, 05000412  +, 00334  +  and 00412  +

ML13091A209 +, ML12346A463 +, ML12313A340 +, RIS 2003-18, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, Dated January 2003 +, RIS 2005-02, Clarifying the Process for Making Emergency Plan Changes +, Information Notice 2013-01, Emergency Action Level Thresholds Outside the Range of Radiation Monitors +  and Information Notice 2005-19, Effect of Plant Configuration Changes on the Emergency Plan +

FirstEnergy +  and Richey M L +

ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +, ML16277A113 +  and ML16277A113 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 1.851852e-4 d (0.00444 hours, 2.645503e-5 weeks, 6.088e-6 months)  +, 0.00116 d (0.0278 hours, 1.653439e-4 weeks, 3.805e-5 months)  +  and 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +

NEI 03-12 +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

Information Notice 2005-19, Effect of Plant Configuration Changes on the Emergency Plan +  and Information Notice 2013-01, Emergency Action Level Thresholds Outside the Range of Radiation Monitors +

NUREG-1228 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, 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-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +  and NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +

None none +  and Mark Thaggard +

AOP +, ES +, Emergency Operating Procedure +, SP-1 +  and AM-RA +

Regulatory Guide 1.1 +, Regulatory Guide 1.3 +, Regulatory Guide 1.2 +  and Regulatory Guide 2.1 +

RIS 2003-18, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, Dated January 2003 +, RIS 2007-02, Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events +  and RIS 2005-02, Clarifying the Process for Making Emergency Plan Changes +

2C-1 +, 2H-1 +, 2H-2 +, 2C-2 +, 2FWE-TK210 +, 2SGC-RQ100 +, 2RMR-RQ206 +, 2HVS-RQ101 +, 1OM-10 +, 1OM-53C +, 20M-53A +, 20M-1 +, 20M-10 +, 2HVS-RQ101B +, 1WT-TK-10 +, 2DBD-39 +, 2F-2 +, 2F-1 +, 1C-3 +, 1H-1 +, 2S-2 +, 2C-3 +, 2C-5 +, 2C-4 +, 1H-2 +, 1VM-BAT-1 +, 1S-3 +, 1F-1 +, 1F-2 +, 10M-53A +...

Manual Scram +  and Automatic Scram +

Beaver Valley +  and NPF-73 +

Ohio +, Pennsylvania +, Washington +  and West Virginia +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Transformer +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Control Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.4.13 +, TS-3.8.7 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.4.16 +, TS-1.1 +, TS-3.8.8 +, TS-3.7.15 +, TS-3.9.6 +, TS-4.3.2 +, TS-5.4.2 +  and TS-3.4.16.A +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Time of Discovery +, High winds +, Shutdown Margin +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Time to boil +, Safe Shutdown Earthquake +, Internal Flooding +, Operating Basis Earthquake +, Operator Manual Action +, Loss of Offsite Power +, Spent Fuel Pool Instrumentation +, Containment high range radiation monitor +, Safeguards Contingency Plan +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Grace period +, Power change +, Core Exit Thermocouple +, Unidentified leakage +, Control Room Habitability +  and Spill +