CAC:MF8061# QUERY99897de55ebe2def0c2380c9bffbdb55
CAC:MF8061 Request
CAC:MF8061 Acceptance Review
CAC:MF8061 +
CAC:MF8061# QUERYc15a1fb92e2ab651551072d600bddaae
CAC:MF8061 Supplement
CAC:MF8061 Withholding Request
CAC:MF8061 Meeting
CAC:MF8061 RAI
CAC:MF8061 Response to RAI
CAC:MF8061 Approval
CAC:MF8061 Withdrawal
CAC:MF8061 Other
Vogtle Open
Vogtle Closed
Farley Open
CAC:MF8061# QUERY78e8ac68bc96f42ff16ba93aa32ada52
Farley Closed
NL-16-2513, Response to Follow-up Request for Information Regarding Reactor Pressure Vessel Threads-in-Flange Examination Requirement
NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0
NL-16-0723, Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 1.0
NL-16-0724, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 1.0
RA-17-0016, Duke Energy - Proposed Alternative in Accordance with 10 CFR 50.55(z)(1) for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange (17-GO-001)
RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)
RS-18-030, Relief Requests Associated with the Fourth Inservice Inspection Interval
NRC-19-0016, Submittal of the Inservice Inspection / Nondestructive Examination Program Relief Requests for the Fourth Ten-year Interval
L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange
NL-20-1011, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-04-04 Version 2.0
RA-19-0352, Duke Energy Carolinas, LLC - Relief Request for Alternative for Reactor Vessel Closure Stud Examinations
NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections
NMP1L3226, Submittal of Relief Requests Associated with the Fifth and Fourth Inservice Inspection Intervals
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative