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Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

Iron +, Copper +, Nitrogen +, Carbon +, Chlorine +, Molybdenum +, Chloride +, Lead +, Aluminum +, Calcium +  and Zinc +

BWRVIP-183 +, BWRVIP-38 +, BWRVIP-76 +, BWRVIP-139 +, BWRVIP-47A +, BWRVIP-18A +, BWRVIP-104 +  and BWRVIP-58-A +

10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50.55a +, 10 CFR 54.4#a2 +, 10 CFR 50.55a#a3 +  and 10 CFR 50.55a#g6i +

Louise Lund +, Jeffrey Kulp +, J. Hufnagel +, M. Gallagher +, B. Harris +, P. Marcus +, P. Tamburro +, P. Orphanos +, T. Trettel +, M. Hand +, G. Harttraft +, A. Sparks +, R. Pinney +, Marc Ferdas +, R. Zak +, M. Dragoo +, D. Hinchliffe +, S. Bee Kok +, F. Ku +, J. O'Rourke +, D. Olszewski +, F. Polaski +, R. Pruthi +, S. Tang +, H. Asher +, M. Fallin +, R. Leski +, Andrew Prinaris +, Allen Hiser +, Lisa Regner +...

RA-08-030, Technical Specifications Section 5.6.6, Post Accident Monitoring Instrumentation Report +  and PM 187715 +

05000219  +  and 00219  +

ML070890637 +, ML090980328 +, ML090210106 +, ML091310413 +, ML080230078 +, ML080950235 +, ML090570036 +, ML082390685 +, ML073130188 +, ML060830567 +, ML070100234 +, ML090270872 +, RA-09-015, Proposed Relief Request to the Requirements of 10 CFR 50.55a Concerning Reactor Pressure Vessel Circumferential Shell Welds +, RA-08-004, Technical Specification Change Request No. 348 - Relocation of Pressure and Temperature (P-T) Curves to the Pressure and Temperature Limits Report (PTLR) +  and RA-09-010, Report No.: 0006004.404, Rev. 0, Oyster Creek Drywell Sandbed Region Wall Thinning Sensitivity Analyses Summary Report +

LS-AA-120 +, MA-AA-723-500 +, ER-AA-470 +  and LS-MA-1253 +

FOIA/PA-2010-0209 +  and FOIA/PA-2009-0214 +

Darrell Roberts +  and Division of Reactor Safety I +

IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +, IR 05000219/2009006 +...

IR 05000219/2009008 +, IR 05000219/2009003 +, IR 05000219/2009006 +, IR 05000219/2008007 +, IR 05000219/2007005 +  and IR 05000219/2006007 +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-1875, Supp 1, Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +  and NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +

AM +  and CH-5 +

Regulatory Guide 1.155 +, Regulatory Guide 1.127 +  and Regulatory Guide 1.190 +

Feedwater +, Service water +, Emergency Diesel Generator +, Primary containment +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Standby Liquid Control +, Intermediate Range Monitor +, Control rod blade +, Main Condenser +, Control Rod +  and Main Steam +

TS-6.8.1.c +  and TS-4.3.B +

Exelon +  and Pardee C +

High winds +, Non-Destructive Examination +, Coatings +, Met Tower +, Finite Element Analysis +, Aging Management +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, License Renewal +, EVT-1 +, Through-Wall Leak +  and Pressure Temperature Limits Report +