Browse wiki

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

Boron +, Oxygen +, Hydrogen +, Chloride +  and Lead +

10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 2 +, 10 CFR 73 +  and 10 CFR 73.55#g1 +

00416  +, 00417  +, 05000416  +  and 05000417  +

GDC 10 +, GDC 55 +  and GDC 19, Control room +

ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +, ML20039F023 +  and ML20039F023 +

AECM-81-400, Forwards Summary Results of Odyn Model Analyses for Certain Transient Events in Response to Question 211.145 in FSAR Chapter 15 & Outstanding Issue in SER Section 1.9(7). Completed Analyses Will Be Incorporated Into FSAR +  and AECM-81-256, Forwards Responses to NRC Questions Re Fire Protection. Electrical Isolation Will Be Provided Between Control Room & Remote Shutdown Panel.All Responses Will Be Incorporated Into FSAR Amend +

General Electric +  and Westinghouse +

NUREG-831 +, 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/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0831, Forwards Suppl 1 to SER (NUREG-0831) Prepared in Connection W/Application for Ols.W/O Encl +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

SAP +, SP +  and CP +

Regulatory Guide 1.97 +, Regulatory Guide 1.3 +, Regulatory Guide 1.127 +  and Regulatory Guide 1.61 +

NEDO-24708 +  and NEDO-20430 +

Illinois +, Washington +, Idaho +, Louisiana +  and Mississippi +

Reactor Coolant System +, Feedwater +, Secondary containment +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Remote shutdown +, Decay Heat Removal +, Safety Relief Valve +, Control Rod +  and Containment Spray +

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Feedwater Controller Failure +, Loss of Offsite Power +, Safeguards Contingency Plan +, Control of Heavy Loads +, Affidavit +  and Spill +