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NUREG REPORTS, SAFETY EVALUATION REPORT--FACILITY  and TEXT-SAFETY REPORT

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

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50 Appendix B Criterion II +  and 10 CFR 50.34#e +

00471  +  and 05000471  +

Technical Support Center +  and Emergency Operations Facility +

GDC 19, Control room +  and GDC 54 +

ML20005A908 +, ML20005A908 +, ML20005A908 +, ML20005A908 +, ML20005A908 +, ML20005A908 +, ML20005A908 +, ML20005A908 +  and ML20005A908 +

1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +

Westinghouse +  and General Electric +

NUREG-22 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0659, Forwards IEEE Comments on NUREG-0659.Response to Comments Should Be Received by 810421 +, NUREG-0731, Summary of 860314 Meeting W/Util in Bethesda,Md Re Qualifications of Radiation Protection Manager as Compared to Qualifications Outlined in 1975 Rev 1 to Reg Guide 1.8, Personnel Selection & Training. Viewgraphs Encl +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0718, Forwards Final Rule on Licensing Requirements for Pending CP & Mfg License Applications & NUREG-0718,Revision 2.SER Comparison to New Requirements Revealed Util Commitments & CP Conditions Conform to Nureg.W/O NUREG +, NUREG-06968 +, NUREG-0737.22 +, NUREG-0718.2 +, NUREG-0635.28 +, NUREG-06969 +, NUREG-0696.9 +, NUREG-0022, Forwards Suppl 4 to SER (NUREG-75/054) Re Application for Const Permits +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

AM +, ST +  and CP +

Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.78 +, Regulatory Guide 1.47 +, Regulatory Guide 1.149 +, Regulatory Guide 1.26 +, Regulatory Guide 1.58 +, Regulatory Guide 1.29 +, Regulatory Guide 1.41 +, Regulatory Guide 1.146 +, Regulatory Guide 1.95 +, Regulatory Guide 1.4.23 +  and Regulatory Guide 1.97.31 +

1C-6 +, 1C-54 +  and 50L-471 +

Massachusetts +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Containment Spray +  and Emergency Feedwater System +

Safe Shutdown +, Reactor Vessel Water Level +, Probabilistic Risk Assessment +, Design basis earthquake +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Core Exit Thermocouple +  and Control Room Habitability +