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 Issue dateTitleTopic
ML17006A10926 January 2017Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads Inflange InspectionIncorporated by reference
NL-16-1329, Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.04 August 2016Proposed Inservice Inspection Alternative VEGP-ISI-ALT-11, Version 2.0 and Proposed Inservice Inspection Alternative FNP-ISI-ALT-19, Version 2.0Finite Element Analysis
Stress corrosion cracking
Weak link
ML15226A22931 July 2015PWR Vessel Internals Program Plan for Aging Management of Reactor InternalsNondestructive Examination
Functionality Assessment
Aging Management
Stress corrosion cracking
License Renewal
EVT-1
Liquid penetrant
DM weld
Power Uprate
NL-15-1507, J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor Internals31 July 2015J.M. Farley Nuclear Plant, Unit 1, PWR Vessel Internals Program Plan for Aging Management of Reactor InternalsNondestructive Examination
Functionality Assessment
Aging Management
Stress corrosion cracking
License Renewal
EVT-1
Liquid penetrant
DM weld
Power Uprate
NL-11-0255, Outage Inservice Inspection Summary Report15 February 2011Outage Inservice Inspection Summary ReportHydrostatic
Nondestructive Examination
VT-2
FLEX
Flow Accelerated Corrosion
Dissimilar Metal Weld
ML10175040212 July 2010Relief Request for Extension of the Reactor Vessel Inservice Inspection (ISI) Date to the Year 2020 (Plus or Minus One Outage) (Tac No. ME3010)Incorporated by reference
ML1005603342 March 2010Safety Evaluation of Relief Request FNP-ISI-ALT-08 Version 1.0 for Reactor Vessel Nozzle to Safe-end Dissimilar Metal Weld and Adjacent Austenitic Safe-end Weld ExaminationsIncorporated by reference
Stress corrosion cracking
Dissimilar Metal Weld
NL-10-0266, Proposed Alternative FNP-ISI-ALT-0823 February 2010Proposed Alternative FNP-ISI-ALT-08Stress corrosion cracking
Dissimilar Metal Weld
NL-09-0410, Proposed Alternatives for the Fourth ISI Interval22 April 2009Proposed Alternatives for the Fourth ISI IntervalStress corrosion cracking
Dissimilar Metal Weld
ML06277035929 September 2006Evaluation of Relief Request ISI-GEN-ALT-06-02Incorporated by reference
Dissimilar Metal Weld
ML05116041419 May 2005Relief, RR-56, Examination of RPV Lower Shell to Bottom Head Circumferential Weld No. APRI-1-1100-8Incorporated by reference
NL-04-0237, ASME Section XI Request for Relief No. RR-56, Examination of Reactor Pressure Vessel Circumferential Weld31 March 2004ASME Section XI Request for Relief No. RR-56, Examination of Reactor Pressure Vessel Circumferential Weld
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on OperabilitySafe Shutdown
Unanalyzed Condition
Fitness for Duty
Probabilistic Risk Assessment
Condition Adverse to Quality
Missed surveillance
Operability Determination
Exemption Request
Pressure Boundary Leakage
Backfit
Operational leakage
ML20077M9562 August 1991Interval 2,Period 1,Outage 3 Inservice Insp Rept of Jm Farley Unit 1Hydrostatic
Nondestructive Examination
VT-2
Stress corrosion cracking
Eddy Current Testing
Liquid penetrant
Dissimilar Metal Weld
ML20154C96512 May 1988Safety Evaluation Re Flaw Indications in Reactor Pressure VesselAnticipated operational occurrence
Probabilistic Risk Assessment
Nondestructive Examination
ML20153D6475 May 1988Forwards Final Repts on Evaluation & Disposition of Indications Exceeding ASME Section XI Stds Found During Inservice Exam of Reactor vessel.WCAP-11763, Background & Technical Basis for Handbook on Flaw Evaluation..., EnclProbabilistic Risk Assessment