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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- L-10-178, Reactor Pressure Vessel Head Commitment Letter + (Reactor Pressure Vessel Head Commitment Letter)
- 05000454/LER-2012-004, Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Repair Surface Indications + (Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzle Weld Repair Surface Indications)
- ML030280586 + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60 Day Response for Kewaunee Nuclear Plant, Request for Additional Information)
- NRC 2003-0006, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567) + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567))
- ML030280508 + (Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity, 60-Day Response for Point Beach Nuclear Plant, Request for Additional Information (TAC No.MB4566 & MB4567))
- ML053070495 + (Reactor Pressure Vessel Head Diagram)
- LIC-03-0163, Reactor Pressure Vessel Head Examination Report + (Reactor Pressure Vessel Head Examination Report)
- ML063620124 + (Reactor Pressure Vessel Head Inspection)
- NOC-AE-03001581, Reactor Pressure Vessel Head Inspection Results + (Reactor Pressure Vessel Head Inspection Results)
- ML032330260 + (Reactor Pressure Vessel Head Inspection Results)
- ML021420388 + (Reactor Pressure Vessel Head Inspection Results, Response to NRC Bulletin 2002-001, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity)
- ML023310018 + (Reactor Pressure Vessel Head Inspection, NRC Bulletin 2002-02 Supplemental Response)
- ML103470588 + (Reactor Pressure Vessel Head Leak-Off Line)
- 05000270/LER-2002-002, Reactor Pressure Vessel Head Leakage Due to Primary Water Stress Corrosion Cracking of Alloy 600 Control Rod Drive Nozzles + (Reactor Pressure Vessel Head Leakage Due to Primary Water Stress Corrosion Cracking of Alloy 600 Control Rod Drive Nozzles)
- 05000302/LER-2001-004 + (Reactor Pressure Vessel Head Leakage Due to Control Rod Drive Mechanism (CRDM) Nozzle Degradation)
- ML18218A112 + (Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1)
- EPID:L-2018-LRM-0045 + (Reactor Pressure Vessel Head Penetration Nozzle Post Peening Follow-up Inspection Relief Requests for Byron Unit 2 and Braidwood Unit 1)
- ML063060176 + (Reactor Pressure Vessel Head Replacement Project Deferment)
- ML030760715 + (Reactor Pressure Vessel Head Replacement Reconciliation Inspection)
- 05000348/LER-2003-002, Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met + (Reactor Pressure Vessel Head Set in Place with Technical Specification 3.4.12 Not Met)
- ML12138A135 + (Reactor Pressure Vessel Head Weld Flaw Evaluation - Response to NRC Request for Additional Information)
- ML12342A323 + (Reactor Pressure Vessel Head Weld Flaw Evaluation - Clarification Regarding Subsequent Examination of the Weld Flaw Indication)
- ML020700711 + (Reactor Pressure Vessel Head at Davis Besse Nuclear Power Station)
- ML22096A006 + (Reactor Pressure Vessel Inservice Inspection Requirements in the U.S)
- ML16274A227 + (Reactor Pressure Vessel Integrity)
- ML17138B779 + (Reactor Pressure Vessel Internals Vibration Test)
- ML040920397 + (Reactor Pressure Vessel Lower Head Penetration Inspection Results)
- RS-17-014, Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11 + (Reactor Pressure Vessel Penetration N-11B Repair Relief Request I5R-11)
- ML20092N287 + (Reactor Pressure Vessel Preservice Insp Program Plan)
- ML20197B424 + (Reactor Pressure Vessel Preservice Ultrasonic Exam Limitations at Sequoyah Nuclear Plant,Unit 1, Supplemental Rept)
- ML20197B430 + (Reactor Pressure Vessel Preservice Ultrasonic Exam Limitations at Sequoyah Nuclear Plant,Unit 2, Supplemental Rept)
- ML20262E108 + (Reactor Pressure Vessel Rollout Id)
- ML20262E114 + (Reactor Pressure Vessel Rollout Id. No Rev Date)
- BSEP 11-0037, Reactor Pressure Vessel Shell-to-Flange Weld Analytical Evaluation + (Reactor Pressure Vessel Shell-to-Flange Weld Analytical Evaluation)
- ML20149L826 + (Reactor Pressure Vessel Status Report)
- ML20079A134 + (Reactor Pressure Vessel Status Report)
- ML19330B488 + (Reactor Pressure Vessel Support Mod for Midland Nuclear Power Plant, Preliminary Rept 1)
- ML13032A251 + (Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment)
- ML20235H690 + (Reactor Pressure Vessel Surveillance Matls Testing & Fracture Toughness Analysis, Technical Rept)
- ML20062J404 + (Reactor Pressure Vessel Surveillance Program:Capsule Basket 2,Capsule Basket 3 & Neutron Dosimeter Monitor)
- ML20062J407 + (Reactor Pressure Vessel Surveillance Program:Capsule Basket 12 & Capsule Basket 13)
- L-89-098, Reactor Pressure Vessel Temp Limits Determination + (Reactor Pressure Vessel Temp Limits Determination)
- ML050140187 + (Reactor Pressure Vessel Upper and Lower Head Inspection Results)
- TSTF-542 + (Reactor Pressure Vessel Water Inventory Control)
- ML20093G910 + (Reactor Pressure Vessel Water Level Measurement Sys Evaluation Rept,Interim Closure Rept)
- ML20101E688 + (Reactor Pressure Vessel Water Level Measurement Sys Evaluation Rept)
- 05000335/FIN-2011005-01 + (Reactor Pressure Vessel supports not included in the St. Lucie ISI Program)
- ML20059J209 + (Reactor Primary Containment Bldg Ilrt,Byron Nuclear Station Unit 2,930909-10)
- ML20080L436 + (Reactor Primary Containment Bldg Integrated Leak Rate Test, 830629-0703)
- ML20064N280 + (Reactor Primary Containment Integrated Leak Rate Test LaSalle County Nuclear Power Station)
- ML19261A281 + (Reactor Primary Coolant Sys Pipe Rupture Study Method for Detection of Sensitization in Stainless Steel, Rept 43 Jan-Mar 1978)