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List of results
- ML23305A041 + (Updated Steam Generator Tube Inspection Report)
- ML23305A042 + (Updated Steam Generator Tube Inspection Report)
- LR-N21-0076, Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements + (Updated Steam Generator Tube Inspection Report - Twenty-second Refueling Outage (2R22) to Reflect TSTF-577 Reporting Requirements)
- ML19351F074 + (Updated Stipulations Re Intervenors Pl Hourihan,K Dahl & C Shuey Contentions.Parties Agreed to Language in Accepted Contentions 1,5,7 & 8 & Disputed Contentions 6A,6B,14,17,18, 23A,23B & 28)
- L-13-312, Updated Submittal of FENOC Response to NRC Request for Information Pursuant to 10CFR50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident + (Updated Submittal of FENOC Response to NRC Request for Information Pursuant to 10CFR50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident)
- JAFP-04-0173, Updated Submittal of Security Plan + (Updated Submittal of Security Plan)
- JAFP-04-0168, Updated Submittal of Security Plan + (Updated Submittal of Security Plan)
- BVY 04-104, Updated Submittal of Security Plan + (Updated Submittal of Security Plan)
- PLA-5815, Updated Submittal of the PPL Susquehanna, LLC Physical Security Plan Revision 0, PLA-5815 + (Updated Submittal of the PPL Susquehanna, LLC Physical Security Plan Revision 0, PLA-5815)
- PLA-5798, Updated Submittal of the Plant Physical Security Plan Revision 0 PLA-5798 + (Updated Submittal of the Plant Physical Security Plan Revision 0 PLA-5798)
- GNRO-2004/00055, Updated Submittal to Security Plan, T&Q Plan and Safeguards Contingency Plan Incorporating RAI Responses + (Updated Submittal to Security Plan, T&Q Plan and Safeguards Contingency Plan Incorporating RAI Responses)
- ML20213D531 + (Updated Summary of Clinical Evaluation Study)
- ML20003H778 + (Updated Summary of Intervenor B Bursey Standing Contentions)
- ML21089A218 + (Updated Supplemental Guidance Regarding IMC 2515 Appendix E Application to Radiation Safety Inspections)
- NL-09-138, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.)
- L-2008-160, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.)
- ML090641038 + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML090641018 + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML111180686 + (Updated Supplemental Response to NRC Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- L-2009-179, Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors + (Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML092170370 + (Updated Supplemental Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- LR-N09-0072, Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML091000557 + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML093290316 + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- ML082380244 + (Updated Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors)
- RS-14-133, Updated Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident + (Updated Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
- ML20039D753 + (Updated Supplemental Testimony on Seismicity.Overall Seismic Design Appropriately Conservative to Provide Reasonable Assurance Plant Can Be Operated W/O Undue Risk to Public. Prof Qualifications Encl)
- ML14351A428 + (Updated TIP Comparisons for Current Operating Conditions, GE-PPO- 1GYEF-KG1-742, Enclosure 2)
- ML033350032 + (Updated TS Bases Pages B 2-6, B 3/4 7-2, B 3/4 7-2a, B 3/4 7-2b)
- ML20216E184 + (Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry)
- ML14215A002 + (Updated TSTF Membership and Distribution)
- TSTF-18-08, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-14-07, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-13-06, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-12-16, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-11-01, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-24-05, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-24-05, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-23-01, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- TSTF-21-05, Updated TSTF Membership and Distribution + (Updated TSTF Membership and Distribution)
- ML20203M057 + (Updated TVA Non-Proprietary Slides for Open Session of July 16, 2020, Partially Closed Public Meeting to Discuss Sequoyah License Amendment Request)
- ML20042F017 + (Updated Table 3A for Effluent & Waste Disposal Semiannual Rept for Second Half of 1988 Re Solid Waste & Irradiated Fuel Shipments)
- ML20042F021 + (Updated Table 3A, Solid Waste & Irradiated Fuel Shipments to Effluent & Waste Disposal Semiannual Rept for First Half of 1989)
- ML20002E105 + (Updated Table II to Electrical Equipment Environ Qualification Rept)
- ML23121A075 + (Updated Table of 2023 Estimates for Fuel Facility Licensing and Inspection Costs)
- ML19169A012 + (Updated Table of NRC ASME B&PV Code)
- ML18031A824 + (Updated Table of NRC Representatives on ASME B&PV Code, Section III, Division 1 and Division 5 Committees)
- ML20100K346 + (Updated Tables 1A,1C & 2B to Effluent & Waste Disposal Semiannual Rept, for Jan-June 1984)
- ML20077G990 + (Updated Tables 1A,1C,2A & 2B Re Gaseous & Liquid Effluents to Semiannual Effluent Release Rept for Second Half 1990)
- ML20235J158 + (Updated Tables 1A,1C,2A & 2B of Calvert Cliffs Nuclear Power Plant Effluent & Waste Disposal Semiannual Rept:First Half 1987)
- ML20214W527 + (Updated Tables 1A,1C,2A & 2B to Semiannual Effluent Release Rept for Second Half 1985)
- ML20058B907 + (Updated Tables 1C,2A,2B & Page 4 to Semiannual Effluent Release Rept for First Half 1990)
- ML20042F012 + (Updated Tables 1C,2A,2B,3A & Page 7 of Semiannual Effluent Release Release Rept for Second Half of 1989)
- PLA-7309, Updated Talen Energy Corp. Director Information Application for Approval of Indirect Transfer of Control + (Updated Talen Energy Corp. Director Information Application for Approval of Indirect Transfer of Control)
- PLA-7316, Updated Talen Energy Corporation Officer Information Application for Approval of Indirect Transfer of Control + (Updated Talen Energy Corporation Officer Information Application for Approval of Indirect Transfer of Control)
- ML14191B148 + (Updated Talking Points for July 17th Meeting with Exelon Regarding Braidwood and Byron AFW Cross-tie Amendment)
- ML19344E374 + (Updated Tech Spec Change Request 91,replacing 800814 Submittal.Consists of Proposed Revision to Tech Specs, Section 6 of App a & Section 5 of App B Re New Mgt Organization)
- ML18153C398 + (Updated Tech Spec Page 6.1-2 to Be Inserted in Place of Previously Submitted Page)
- ML091170368 + (Updated Tech Spec Pages, from Licensee, License Amendment Request Lic 08-0078, Administrative Revisions to the Technical Specifications to Correct Typographical Errors and Provide Clarification)
- ML20058N173 + (Updated Tech Specs Permitting Removal of Rod Sequence Control Sys & Reducing Rod Worth Minimizer Cutoff Setpoints to 10%-rated Thermal Power)