AEP-NRC-2020-65, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-04
AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06
AEP-NRC-2009-58, Notification of MRP-139 Deviation
AEP-NRC-2021-35, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-05
AEP-NRC-2009-70, Revised Technical Justification for Deviation from EPRI MRP-139 Inspection Requirements for Reactor Vessel Alloy 600/82/182 Welds at DC Cook Nuclear Plant
AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07
1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035
CPSES-200700169, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
1CAN031003, Deviation from NEI Guideline - RCS Leakage Action Levels
HNP-07-015, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds
L-2009-128, Deviation from EPRI MRP-146 Ultrasonic Examination Schedule - NEI 03-08 Needed Work Product Element
L-20-115, CFR 50.55a Request Number 2-TYP-4-RV-07 for Bottom Mounted Instrumentation Penetration Examinations
L-20-117, 10 CFR 50.55a Request Number 2-TYP-4-RV-06, Hardship for Hot Leg Nozzle Inspections
L-2021-184, Relief Request Number 19 - Request for an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85
L-2022-015, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld - RAI
L-2013-314, Deviation from EPRI MRP-146 Revision I Inspection Schedule - NEI 03-08 Needed Work Product Element - for Information Only
L-PI-10-094, Supplement to License Amendment Request to Exclude the Dynamic Effects Associated with Certain Postulated Pipe Ruptures from the Licensing Basis Based Upon Application of Leak-Before-Break Methodology - Response to RAI
L-2022-011, Relief Request Number 20 - Request for an Alternative to the Requirements of the ASME Code for Examination of Reactor Vessel Closure Head Control Element Drive Mechanism (CEDM) Housing 27 Canopy Seal Weld
L-2021-231, Relief Request Number 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety
PNP 2012-035, Relief Request - Proposed Alternative - Use of Alternate ASME Code Case N-770-1 Baseline Examination
W3F1-2012-0085, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request
RS-21-008, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)
RA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)
NRC 2010-0050, Refueling 32 Analytical Evaluation Report for the Reactor Vessel
W3F1-2012-0099, Request for Alternative W3-1SI-021, ASME Code Case N-770-1 Baseline Examination Request for Alternative
RS-20-080, Request for Alternative: One-Time Deferral of Follow-Up Inspection for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surfaces in Accordance with 10 CFR 50.55a(z)(2)
ULNRC-06690, Enclosure 5: Callaway, Unit 1, LAR Supplement to Address Audit Discussion Points Summarized in NRC Letter Dated September 14, 2021 (ML21238A138)
RA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)
L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02
RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75
RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative
PNP 2025-002, License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis
NL-25-0152, Propoosed Inservice Alternative FNP-ISI-ALT-05-13 for Reactor Vessel Bottom Head Inspection