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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
- ULNRC-06449, Supplement to Owners Activity Report (OAR-1 Form) for Cycle/Refuel 22 + (Supplement to Owners Activity Report (OAR-1 Form) for Cycle/Refuel 22)
- NRC 2004-0012, Supplement to Owners Inservice Inspection Summary Report Submitted for Refueling Outage U1R27 + (Supplement to Owners Inservice Inspection Summary Report Submitted for Refueling Outage U1R27)
- NRC 2004-0087, Supplement to Owners Inservice Inspection Summary Report Submitted for Point Beach Nuclear Plant Unit 1 Refueling Outage U1R27 + (Supplement to Owners Inservice Inspection Summary Report Submitted for Point Beach Nuclear Plant Unit 1 Refueling Outage U1R27)
- ML033570561 + (Supplement to Oyster Creek Implementation of Emergency Action Levels Developed from NUMARC/NESP-007 Methodology)
- ML041130416 + (Supplement to Oyster Creek License Amendment Request No. 306-DC Electrical Power Sources Based on TSTF-360)
- ML043010274 + (Supplement to Oyster Creek License Amendment Request No. 326 - Clarification of Control Rod Operability Requirements)
- ML042300425 + (Supplement to Oyster Creek Technical Specification Change Request No. 323 - Relocation of Stability Protection Settings to the Core Operating Limits Report)
- DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater (AFW) System, TS 3.8.1, Ac... + (Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater (AFW) System, TS 3.8.1, Ac...)
- DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 + (Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1)
- LR-N10-0291, Supplement to PSEG Response to RAIs B.2.1.28-01, B.2.1.37-01 & B.2.1.37-02 Associated with Renewal Application + (Supplement to PSEG Response to RAIs B.2.1.28-01, B.2.1.37-01 & B.2.1.37-02 Associated with Renewal Application)
- ML17156A000 + (Supplement to Palisades Nuclear Plant Site Emergency Plan Revision Submittal)
- ML030700534 + (Supplement to Palisades Risk-Informed Inservice Inspection Piping Program)
- ML030770410 + (Supplement to Pbnp Record, RCE 01-069-01)
- ML20153D045 + (Supplement to Petition & Statement of Contentions of Commonwealth of Pa.* Requests That Board Grant Petition to Intervene & Request for Hearing on Contentions.Certificate of Svc Encl)
- ML062140418 + (Supplement to Petition to Add a New Contention)
- ML20065H545 + (Supplement to Petition to Intervene,Consisting of Contentions & Bases for Contentions)
- ML13134A372 + (Supplement to Petition to Revoke Mark I & II Operating License / Columbia Station)
- ML25216A030 + (Supplement to Petitioners Motion for Procedural Relief Pursuant to 10 CFR 2.323 (Clarification and Revision of Requested Action Regarding Fuel Loading))
- ML12045A369 + (Supplement to Pilgrim Watch Petitions for Review of LBP-12-01, LBP-11-23)
- TMI-17-051, Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013 + (Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013)
- ML17142A031 + (Supplement to Plant-Specific Path and Schedule for Resolution of Generic Letter 2004-02, Dated May 16, 2013)
- ML063380408 + (Supplement to Post Maintenance/Modification Surveillance Requirements License Amendment Request)
- L-PI-13-045, Supplement to Prairie Island Nuclear Generating Plant (PINGP) Aging Management Program Submittals + (Supplement to Prairie Island Nuclear Generating Plant (PINGP) Aging Management Program Submittals)
- ML21279A285 + (Supplement to Presentation Information for Second Pre-Application Meeting Re Use of Framatome Fuel at Plant)
- ML21279A286 + (Supplement to Presentation Information for Second Pre-Application Meeting Re Use of Framatome Fuel at Plant)
- 05000498/LER-2023-001-01, Supplement to Pressurizer Power Operated Valve Failed to Open + (Supplement to Pressurizer Power Operated Valve Failed to Open)
- ML23068A364 + (Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06))
- ML23229A499 + (Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06))
- NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) + (Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06))
- AEP-NRC-2018-73, Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination + (Supplement to Proposed Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination)
- ML21062A259 + (Supplement to Proposed Alternative Request to Utilize Code Case N-885)
- RA-20-0247, Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1) + (Supplement to Proposed Alternative for RPV Nozzle-to-Vessel Weld and Inner Radii Examination Requirements in Accordance with 10 CFR 50.55a(z)(1))
- 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) + (Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2))
- BSEP 18-0047, Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test + (Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test)
- ML062780203 + (Supplement to Proposed Alternative to ASME Code, Section XI, Repair Requirements)
- NOC-AE-20003755, Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) + (Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24))
- ML20212L568 + (Supplement to Proposed Alternative to ASME Section XI Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24))
- L-07-073, Supplement to Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements (Request No. BV1-PZR-01, Revision 1) + (Supplement to Proposed Alternative to American Society of Mechanical Engineers Code Section XI Repair Requirements (Request No. BV1-PZR-01, Revision 1))
- RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant + (Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant)
- ML25267A244 + (Supplement to Proposed Alternative to Use American Society of Mechanical Engineers (ASME) Code Case N-752)
- ML062630142 + (Supplement to Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI, Repair Requirements)
- ML062720122 + (Supplement to Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements)
- PLA-5430, Supplement to Proposed Amendment 244 to License NPF-14 and Proposed Amendment 208 to License NPF-22, Revising Main Steam Relief Valve Steam Setpoint Tolerance and Request for Relief from IST & ASME Code Requirements + (Supplement to Proposed Amendment 244 to License NPF-14 and Proposed Amendment 208 to License NPF-22, Revising Main Steam Relief Valve Steam Setpoint Tolerance and Request for Relief from IST & ASME Code Requirements)
- PLA-5520, Supplement to Proposed Amendment No. 211 to Unit 2 License NFP-22: MCPR Safety Limits and Reference Changes + (Supplement to Proposed Amendment No. 211 to Unit 2 License NFP-22: MCPR Safety Limits and Reference Changes)
- PLA-6120, Supplement to Proposed Amendment No. 281 to License NPF-14 and Proposed Amendment No. 251 to License NPF-22 for Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10CFR50.67 + (Supplement to Proposed Amendment No. 281 to License NPF-14 and Proposed Amendment No. 251 to License NPF-22 for Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10CFR50.67)
- PLA-6145, Supplement to Proposed Amendment No. 281 to License NPF-14 and Proposed Amendment No. 251 to License NPF-022: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative. + (Supplement to Proposed Amendment No. 281 to License NPF-14 and Proposed Amendment No. 251 to License NPF-022: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative.)
- PLA-6105, Supplement to Proposed Amendment Nos. 269, and 236: DC Electrical Power Systems Technical Specifications Rewrite + (Supplement to Proposed Amendment Nos. 269, and 236: DC Electrical Power Systems Technical Specifications Rewrite)
- PLA-6139, Supplement to Proposed Amendment Nos. 281, and 251: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67 + (Supplement to Proposed Amendment Nos. 281, and 251: Application for License Amendment and Related Technical Specification Changes to Implement Full-Scope Alternative Source Term in Accordance with 10 CFR 50.67)
- NOC-AE-08002363, Supplement to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation + (Supplement to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation)
- ML083370306 + (Supplement to Proposed Amendment to Technical Specification 3.3.1 Required Action for Inoperable Extended Range Neutron Flux Instrumentation)
- RNP-RA/16-0065, Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test + (Supplement to Proposed Amendment to Technical Specification 5.5.16 for the Adoption of Option B of 10 CFR 50, Appendix J for Type B and Type C Testing and the Permanent Change in 10 CFR 50, Appendix J, Integrated Leak Rate Test)