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SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES  and TEXT-SAFETY REPORT

ASME Section VIII +  and ASME Section XI +

Hydrogen +  and Nitrogen +

10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix H +, 10 CFR 51.21 +, 10 CFR 50.55a +, 10 CFR 50.51 +  and 10 CFR 50.55a#g6ii +

05000219  +  and 00219  +

50 FR 32133 +  and 58 FR 6814 +

NRC Generic Letter 84-11, Inspections of BWR Stainless Steel Piping +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +, ML20035D347 +...

ML070290668 +, ML072850101 +, ML060550285 +, ML20058N078 +, ML20067B975 +, ML20085G025 +, IR 05000219/1988022 +, ML20207N233 +, 05000219/LER-1988-023, :on 880927,drywell Airlock Door Leak Rate Not Tested at Frequency or Test Pressure Required by 10CFR50, App J.Caused by Insufficient Administrative Controls.Tech Spec Change Under Review +, 05000219/LER-1992-010, :on 920824,high Steam Flow Occurred During Warmup of Main Turbine That Resulted in Reactor Low Water Level Scram.Caused by Drift in Adjustment of Sv.Threads on Restoring Arm Will Be Repaired +, 05000219/LER-1992-004, :on 920424,discovered That Testing Methodology for Flow Converter Units for RPS Resulted in Loss of High Recirculation Flow Scram Protection.Caused by Procedural Inadequacy.Surveillance Procedure Revised +, 05000219/LER-1991-007, :on 911102,discovered That Offgas Sys Isolation Function Exceeded 15-minute Delay Limit in Ts. Caused by Inadequate Technical Evaluation of Replacement Time Delay.Surveillance Procedures Revised +, ML20053B321 +, ML20043B394 +, ML20035A703 +, ML17202V098 +, ML19318C297 +, ML19305D596 +  and ML20079M963 +

NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +  and NUREG-1382, Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review +

Regulatory Guide 1.99 +  and Regulatory Guide 1.78 +

Pennsylvania +, Washington +  and New Jersey +

Reactor Coolant System +, High Pressure Coolant Injection +, Reactor Core Isolation Cooling +, Reactor Pressure Vessel +, Core Spray +  and Emergency Core Cooling System +

TS-4.3 +, TS-3.10 +, TS-3.3.A +, TS-5.2.5 +, TS-3.4.A +  and TS-4.5.P +

Intergranular Stress Corrosion Cracking +  and Hardened vent +