Browse wiki

Letter  and Inspection Report

ASME Section XI +  and ASME Section III +

Boron +, Iron +, Nitrogen +  and Lead +

10 CFR 21 +, 10 CFR 20 +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 2.390 +, 10 CFR 20.1201 +, 10 CFR 20.1501 +, 10 CFR 50.65 +, 10 CFR 61.55 +, 10 CFR 61.56 +, 10 CFR 20.1101 +, 10 CFR 50 Appendix B Criterion V +, 10 CFR 50 Appendix B Criterion XVI +, 10 CFR 50.65#b +, 10 CFR 50.65#a1 +  and 10 CFR 50.65#a4 +

H. Berrick +, D. Labott +, Gray M, RI/DRP/Br3 610-337-5209 +, C. Fricker +, G. Sosson +, R. Gary +, T. Joyce +, S. Mannon +, S. Robitzski +, T. Gierich +, R. Kalman +, S. Gurnam +, B. McTigue +  and Andrea Johnson +

Barrier Integrity +, Initiating Events +, Mitigating Systems +, Occupational Radiation Safety +  and Public Radiation Safety +

05000272  +, 05000311  +, 00311  +  and 00272  +

05000272/FIN-2005007-01 +, 05000272/FIN-2005005-01 +, 05000311/FIN-2005005-03 +, 05000272/FIN-2005005-04 +, 05000272/FIN-2005005-05 +, 05000311/FIN-2005005-07 +, 05000272/FIN-2005005-08 +, 05000272/FIN-2005003-05 +, 05000311/FIN-2005005-09 +, 05000272/FIN-2005005-06 +, 05000272/FIN-2005004-00 +  and 05000272/FIN-2004005-01 +

Mel Gray +  and Reactor Projects Region 1 Branch 3 +

IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +, IR 05000272/2005005 +...

0.00153 d (0.0367 hours, 2.18254e-4 weeks, 5.0226e-5 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 3.009259e-4 d (0.00722 hours, 4.298942e-5 weeks, 9.893e-6 months)  +, 5.555556e-4 d (0.0133 hours, 7.936508e-5 weeks, 1.8264e-5 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +  and 2.546296e-4 d (0.00611 hours, 3.637566e-5 weeks, 8.371e-6 months)  +

TI 2515/160 +  and TI 2515/161 +

IP 71111.12 +, IP 71111.01 +, IP 71111.04 +, IP 71111.06 +, IP 71111.22 +, IP 71111.05 +, IP 71111.13 +, IP 71111.08 +, 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 71111.23 +, IP 71111.14 +, IP 05000 +, IP 92709 +, IP 71007 +, IP 71111.16 +, IP 20260 +, IP 20261 +, IP 20245 +, IP 70051 +, IP 41521 +, IP 71111.20, Refueling and Other Outage Activities +  and IP 71152, Problem Identification and Resolution (PI&R) +

NRC Inspection Manual 0609 +, NRC Inspection Manual 0308 +, NRC Inspection Manual 0609, Appendix H +, NRC Inspection Manual 0609 Appendix H +, NRC Inspection Manual 0609, Appendix G +, NRC Inspection Manual 0609 Appendix K +, NRC Inspection Manual 0609/Appendix A, The Significance Determination Process (SDP) for Findings At-Power +, NRC Inspection Manual 0609/Appendix C, Occupational Radiation Safety Significance Determination Process +  and NRC Inspection Manual 0612, Power Reactor Inspection Reports +

IP 71122.02 +, IP 71121.02 +, IP 71121.01 +, IP 92709 +, IP 71007 +, IP 71121.03 +  and IP 71152, Problem Identification and Resolution (PI&R) +

I-131 +  and H-3 +

05000272/LER-2005-004, Containment Sump As-found Condition Not in Accordance with Design Documents +  and 05000272/LER-2004-005, ECCS Leakage Outside Containment Exceeds Dose Analysis Limits (11 RHR Heat Exchanger) +

NUREG-1649, G20070409/LTR-07-0404 - Cross Reference Between the Mya ISA and the ROP +  and NUREG/CR-5496, Issues Final Rept,Evaluation of Loss of Offsite Power Events at Nuclear Power Plants 1980-1996,NUREG/CR-5496.Observations & Findings of Study Listed.Without Encl +

1E-5 +, 1E-4 +, 1PS-59 +, S1CBV-1VC3 +  and 2SC-177 +

Washington +  and New Jersey +

Steam Generator +, Reactor Coolant System +, Service water +, Emergency Diesel Generator +, Auxiliary Feedwater +, Shutdown Cooling +, Residual Heat Removal +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Containment Spray +

TS-3.4.3 +, TS-3.4.10.3 +  and TS-6.12 +

PSEG +  and Levis W +

Boric Acid +, High winds +, Packing leak +, High Radiation Area +, Stroke time +, Time to boil +, Internal Flooding +, Past operability +, Probabilistic Risk Assessment +, Nondestructive Examination +, Temporary Modification +, VT-2 +, Significance Determination Process +, Foreign Material Exclusion +, Process Control Program +, Large early release frequency +, Stress corrosion cracking +, Loss of Offsite Power +, Operability Determination +, Safeguards Contingency Plan +, Code Reconciliation +, Liquid penetrant +, Dissimilar Metal Weld +, Substantial potential for overexposure +, Substantial potential for an overexposure +, Unidentified leakage +  and Overexposure +

WO 60050614 +, WO 30105497 +, WO 30078649 +, WO 30105879 +, WO 30112336 +, WO 30079193 +, WO 50075622 +, WO 50075529 +, WO 50089617 +, WO 60042708 +, WO 60042739 +, WO 80077710 +  and WO 50076195 +