Browse wiki

Letter  and Inspection Report

10 CFR 50.72 +, 10 CFR 20 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 50.62 +, 10 CFR 55.46 +, 10 CFR 55.53 +, 10 CFR 55.59 +, 10 CFR 50 Appendix B Criterion V +  and 10 CFR 50 Appendix B Criterion XVI +

BELLAMY RR +, R. Peak +, S. Dupont +, J. Kandasamy +, M. Massaro +, J. Barstow +, D. Dicello +, P. Orphanos +, T. Keenan +, H. Ray +, J. Renda +, M. McKenna +, J. Dostal +, J. Kerr +, R. Wiebenga +, R. Reiner +, D. Peiffer +, J. Vaccaro +, S. Quick +  and R. Penny +

Barrier Integrity +, Initiating Events +  and Mitigating Systems +

H.7 +, H.11 +, P.2 +, H.2(b) +, P.1(a) +, P.2(a) +  and P.2(b) +

05000219  +  and 00219  +

ML052720204 +, ML091320652 +, ML091530199 +  and MN 09-020, Meeting Notice, Annual Assessment Meeting with Exelon Management to Discuss NRCs Assessment of the Safety Performance of the Oyster Creek Generating Station for Calendar Year 2008 +

ENS 44993 +  and ENS 45021 +

HU-AA-1211 +, CC-AA-102 +, LS-AA-115 +, MA-AA-716-010 +, LS-AA-125 +, ER-AA-2003 +, MA-AA-716-003 +, AD-AA-101 +, OP-AA-108-114 +, ER-AA-3003 +  and OP-AA-106-101-1001 +

05000219/FIN-2009003-01 +, 05000219/FIN-2009003-02 +, 05000219/FIN-2009003-03 +, 05000219/FIN-2009003-04 +, 05000219/FIN-2009003-05 +, 05000219/FIN-2009003-06 +  and 05000219/FIN-2009003-07 +

NRC/RGN-I/DRP/PB6 +  and Ronald Bellamy +

NRC Generic Letter 07-01 +  and NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +

IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +, IR 05000219/2009003 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 7.175926e-4 d (0.0172 hours, 1.025132e-4 weeks, 2.3591e-5 months)  +  and 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +

IP 71111.18 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.19 +, IP 71151 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71153, Event Followup +, IP 71111.11, Licensed Operator Requalification Program and Licensed Operator Performance +, IP 71111.07, Heat Sink Performance +, IP 71111.12Q +, IP 90128 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0612 Appendix B +, NRC Inspection Manual 0609.04 +, NRC Inspection Manual 0609, Appendix I +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, IMC 0305, Operating Reactor Assessment Program +  and NRC Inspection Manual 0612 Appendix E, Examples of Minor Issues +

IP 71111.11B +, IP 71003 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 71111.11Q +, IP 71111.04S +, IP 71111.05Q +, IP 71111.07T +, IP 71111.04Q +  and IP 71111.07A +

IR 05000219/2009008 +, IR 05000219/2009003 +  and IR 05000219/2008009 +

05000219/LER-2009-003, Regarding Manual Reactor Shutdown Caused by Loss of Cooling to the Main Transformer +  and 05000219/LER-2009-002, Failure to Take the Appropriate Tech Spec Action When Primary Containment Isolation Valve Became Inoperable +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +

Washington +  and New Jersey +

Feedwater +, Secondary containment +, Service water +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary containment +, Main Transformer +, Shutdown Cooling +, Reactor Recirculation Pump +, Core Spray +, Reactor Building Ventilation +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Steam Jet Air Ejector +, Decay Heat Removal +, Main Condenser +, Control Rod +, Main Steam +  and Containment Spray +

TS-3.5.A +  and TS-6.8.1 +

Pardee C +  and Exelon +

Safe Shutdown +, Ultimate heat sink +, Fire Barrier +, Internal Flooding +, Temporary Modification +, Condition Adverse to Quality +, Significance Determination Process +, Job Performance Measure +, Large early release frequency +, License Renewal +, Maintenance Rule Program +, Power change +, Downpower +, Unidentified leakage +  and Appropriate work instructions +