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Letter  and Inservice/Preservice Inspection and Test Report

IWB-2500 +, IWC-5220 +, IWC-2500 +, IWC-5222 +, IWB-5000 +, IWB-5222 +, IWB-2000 +, IWB-5220 +, IWB-1220 +, IWC-1220 +, IWB-3512 +, IWA-1400 +, IWA-2430 +, IWA-2314 +, IWA-4520 +, IWA-4521 +, IWA-2210 +, IWA-4660 +, IWA-1300 +  and IWA-24 +

ASME Section XI +, ASME Section III +  and ASME Section I +

Carbon +  and Hydrogen +

BWRVIP-75-A +, BWRVIP-75 +, BWRVIP-108 +, BWRVIP-05 +  and BWRVIP-241 +

10 CFR 50.55a +, 10 CFR 50.55a#g4iv +, 10 CFR 50.55a#g6iiA +, 10 CFR 50.55a#b2viiiE +, 10 CFR 50.55a#z2 +, 10 CFR 50.55a#b5 +, 10 CFR 50.55a#c2 +  and 10 CFR 50.55a#b5i +

ASME Code Case N-513-2 +, ASME Code Case N-513-3 +, ASME Code Case N-666 +, ASME Code Case N-638-4 +, ASME Code Case N-597-2 +, ASME Code Case N-661-2 +, ASME Code Case N-578-1 +, ASME Code Case N-702 +, ASME Code Case N-513-4 +, ASME Code Case N-789 +, ASME Code Case N-795 +, ASME Code Case N-648-1 +, ASME Code Case N-666-1 +, ASME Code Case N-508-4 +, ASME Code Case N-562-2 +, ASME Code Case N-639 +, ASME Code Case N-747 +, ASME Code Case N-552 +, ASME Code Case N-516-3 +, ASME Code Case N-552-1 +, ASME Code Case N-56 +, ASME Code Case N-606-1 +, ASME Code Case N-638-6 +, ASME Code Case N-751 +, ASME Code Case N-778 +, ASME Code Case N-799 +  and ASME Code Case N-613-2 +

RS-17-071, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 +, RS-16-215, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography +, RS-17 +  and L-2520 +

H.1(o) +, S.5(a) +, H.7(l) +  and H.1(l) +

05000373  +, 05000374  +, 00373  +  and 00374  +

RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography +, ML073600374 +, ML023330203 +, ML17171A320 +  and ML7150A091 +

ER-AA-330-001 +, ER-AA-330 +, ER-AA-330-002 +, ER-AA-330-007 +, ER-AA-330-003 +, ER-AA-330-005 +, ER-AA-330-006 +  and ER-AB-331 +

Exelon +, Trafton W +  and True North Consulting +

ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +, ML17314A008 +  and ML17314A008 +

NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AM +, ES +, SP +  and RT +

RS-17-071, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 +, RS-16-215, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography +  and RS-17 +

Regulatory Guide 1.147 +, Regulatory Guide 1.26 +  and Regulatory Guide 1.14 +

I4R-09 +, 14R-05 +, 14R-06 +, 14R-07 +, 14R-08 +, 14R-09 +, 14R-01 +, 14R-02 +, 14R-03 +, 14R-04 +, 202L-R2 +, I4R-02 +, 14R-1 +, 14T-03 +, 14T-04 +, 14T-02 +, 14T-05 +, I4T-02 +, L4R-03 +, 14R-O +, 43R06-04 +, 14R-0-t +, 14R-IO +, I4R-Ol +, 14T-OI +, 14T-Ol +, I4T-03 +, I4T-04 +, I4T-05 +, I4R-OI +...

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Emergency Core Cooling System +, Control Rod +, Main Steam +  and Extraction steam +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Non-Destructive Examination +, Weld Overlay +, Nondestructive Examination +, VT-2 +, Incorporated by reference +, High Energy Line Break +, Aging Management +, Flow Accelerated Corrosion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Integrated leak rate test +, License Renewal +, Liquid penetrant +, Through-Wall Leakage +, Dissimilar Metal Weld +, DM weld +  and Thermal fatigue +