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ASME Section I +  and ASME Section III +

Boron +, Iodine +, Cesium +, Krypton +, Nitrogen +, Hydrogen +, Xenon +, Chloride +, Lead +, Helium +  and Silver +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.44 +  and 10 CFR 50#i +

GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +, GO2-85-758, Forwards Crdr & Emergency Procedure Functional Task Analysis Summary Rept & Emergency Operating Procedures, Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions +, GO2-91-198, Advises That Mods Necessary to Implement Listed Issues Re Excess Flow Check Valve Position Display & Annunicator Alarm Intensity Per Dcrdr Completed,Per Generic Ltr 88-20 +, GO2-84-272, Advises That Reactor Coolant Disolved Gas Grab Sampling Capability Installed,Tested & Operational,Per Condition of Amend 1 to License NPF-21.Procedures Prepared & Appropriate Personnel Trained +, GO2-84-617, Advises That Review of Reactor Vessel Water Level Instrumentation in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23 Completed.License Condition 9 Re Inadequate Core Cooling Instrumentation Analysis Satisfied +, GO2-88-074, Provides Status of Activites in Addressing Aspects of NRC Re Dcrdr.Supplementary Rept Will Be Submitted Upon Completion of Items Identified in Status Rept +, GO2-83-247, Forwards Plant Procedures 1.3.1,1.3.6,1.3.7,1.3.8,1.3.9 & 1.5.1 to Close Out SER (NUREG-0892) Confirmatory Issue 22, Assurance of ESF Functioning (II.K.1.5) & Safety-Related Sys Operability Status (II.K.1.10) +  and GO2-80-107 +

H.2(a) +  and H.2(n) +

EC-145 +  and EC-364 +

GO2-13-174, Final Safety Analysis Report, Amendment 62, Appendix J - Shielding Evaluation Report +, GO2-85-758, Forwards Crdr & Emergency Procedure Functional Task Analysis Summary Rept & Emergency Operating Procedures, Including Rev 1 to Procedure 5.0.0, Emergency Procedure General Precautions +, GO2-91-198, Advises That Mods Necessary to Implement Listed Issues Re Excess Flow Check Valve Position Display & Annunicator Alarm Intensity Per Dcrdr Completed,Per Generic Ltr 88-20 +, GO2-84-272, Advises That Reactor Coolant Disolved Gas Grab Sampling Capability Installed,Tested & Operational,Per Condition of Amend 1 to License NPF-21.Procedures Prepared & Appropriate Personnel Trained +, GO2-84-617, Advises That Review of Reactor Vessel Water Level Instrumentation in Response to NUREG-0737,Item II.F.2 & Generic Ltr 84-23 Completed.License Condition 9 Re Inadequate Core Cooling Instrumentation Analysis Satisfied +, GO2-88-074, Provides Status of Activites in Addressing Aspects of NRC Re Dcrdr.Supplementary Rept Will Be Submitted Upon Completion of Items Identified in Status Rept +, GO2-83-247, Forwards Plant Procedures 1.3.1,1.3.6,1.3.7,1.3.8,1.3.9 & 1.5.1 to Close Out SER (NUREG-0892) Confirmatory Issue 22, Assurance of ESF Functioning (II.K.1.5) & Safety-Related Sys Operability Status (II.K.1.10) +  and GO2-80-107 +

ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +, ML14010A315 +  and ML14010A315 +

IEEE 344-1975 +  and IEEE 279 +

NUREG/CR-158 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-0892, Forwards Suppl to SER Chapter 9 Conditionally Accepting Applicant 830719 Request to Delay Relocation of HPCS Diesel Generator Control Panel & Installation of Air Dryers in Emergency Diesel Generator Air Starting Sys +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-1580, Notice of Availability of Draft NUREG/CR-1580, Human Engineering Guide to Control Room Evaluation +, 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-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.3 +, Regulatory Guide 1.33 +, Regulatory Guide 1.70 +, Regulatory Guide 1.100 +  and Regulatory Guide 1.89 +

NEDO-24708A +  and NEDO-24708 +

07-79-06A +, 07-79-06B +, 07-01-009 +, 07-01-000 +  and 07-01-00A +

Tennessee +, Pennsylvania +, Georgia +, Illinois +, Washington +, New York +, Oklahoma +, Mississippi +, Nebraska +, Vermont +  and Iowa +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Automatic Depressurization System +, Remote shutdown +, Emergency Core Cooling System +, Main Steam Line +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Reactor Vessel Water Level +, Grab sample +, Anticipated operational occurrence +, Temporary Modification +, Feedwater Controller Failure +, Loss of Offsite Power +, Fuel cladding +  and Loss of condenser vacuum +