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Matthew Mitchell
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NRC Headquarters
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NRC-17-0062, Submittal of Revised Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval
NLS2015075, Deviation from BWRVIP-18 and BWRVIP-41 Inspection Requirements Cooper Nuclear Station
NLS2011035, Deviation from BWRVIP-25 Inspection Requirements
BVY 11-024, Deviation from BWRVIP-25 Inspection Requirements
PMNS20191185, Presubmittal Meeting with Duke Energy to Discuss a Proposed Relief Request to Extend the Interval Between Reactor Vessel Closure Stud Examinations from 10 Years to a Maximum of 30 Years for Duke Energy Operating Reactor Facilities
CP-202000311, Notification of Deviation from Electric Power Research Institute MRP 2018-027, NEI 03-08 Needed Inspection Guidance for PWR CRDM Thermal Sleeve Wear, Superseded by PWROG-16003-P, Evaluation of .
PMNS20200439, Discussion of 10CFR50.55a(b)(2)(xxvi) Condition for Pressure Testing of Mechanical Joints
CP-202000578, (CPNPP) - Notification of Deviation from OG-20-113, PWR Owners Group NEI 03-08 Needed and Good Practice Guidance: Thermal Sleeve Cross-Sectional Failure - Westinghouse Nuclear Safety Advisory Letter NSAL-20-1 Dated.
PMNS20211337, Closed Webinar with NextEra Energy to Discuss Issues Related to the Unit 3 Intake Cooling Water Discharge Line
PMNS20220020, NRC Public Meeting to Discuss Draft Regulatory Issue Summary (RIS) on Operational Leakage
NPL-98-0777, Forwards Addl Info Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Rev 0 to Calculation 98-0132, Evaluation of 23.6 EFPY P-T Limit & LTOP Applicability Date & Pressurized Thermal Shock at 32 EFPY, Encl
PMNS20230313, Use of Probabilistic Fracture Mechanics (Pfm) and Performance Monitoring Public Meeting (Hybrid)
SECY-23-0061, Clarification of the Staff’S Position on Certain American Society of Mechanical Engineers Code Alternatives for More than One 10-Year Inservice Inspection Interval Under Title 10 of the Code of Federal Regulations 50.55a
PMNS20240525, Sufficiency Gaps Identified in EPRI Report 3002025288 on Enhanced Risk-Informed Categorization Methodology for Pressure Boundary Components
PMNS20220445, Meeting for Electric Power Research Institute (EPRI) to Present Anticipated ASME Code Case N-729 Visual Exam Updates to the U.S. Nuclear Regulatory Commission (NRC)
PNO-III-97-006, on 970129,inspector Learned That 12 Muzzle Reference Sensors Were Missing from Shipment of Refurbished Devices & Licensee Did Not Make Rept to Nrc.Licensee Search & Investigation for Sensors Continuing
PNO-III-97-002, on 970108,package Was Received from Syncor Intl Nuclear Pharmacy Which Exceeded DOT Regulatory Limits. Licensee Decontaminated Container & Used It for Return Shipment to Syncor Intl on 970109
PNO-III-98-024, on 970714,apparent Misadministration Occurred During Intrabronchial Brachytherapy Cancer treatment.Ir-192 Catheter Removed from Intended Site by Patient
PNO-III-98-026, on 970106,patient Prescribed 2,000 Rad Dose of Ir-192 & Received 108 Rads.Patient Removed Bronchial Catheter from Location.Nurse Recovered Catheter & Placed in Shielding Provided in Patient Room
PNO-III-97-083, on 971009,Midwest Iron & Metal,Reported Gauge Found in Scrap Matl Which Appeared to Contain Radiation Source.Gauge Placed in Secured Area,Pending Further Action. Current Ownership of Gauge Unknown