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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
- ML17213B358 + (20:28:02, 8 January 2025)
- ML17213B357 + (20:28:03, 8 January 2025)
- ML17213B355 + (20:28:05, 8 January 2025)
- ML17213B354 + (20:28:06, 8 January 2025)
- ML17213B352 + (20:28:07, 8 January 2025)
- L-83-276, Advises That Vendor Safety Analysis to Support Installation of Mods to Auxiliary Sys,Per Util Re Main Steam Line Break W/Continued Feedwater Addition,Is Under Review. Response to Core Reactivity Question Expected by 830615 + (20:28:08, 8 January 2025)
- L-83-285, Forwards Info Justifying Continued Operation W/Electrical Equipment in Item 114 Per .All Other Items Listed in Category Ii.B of Franklin Research Ctr Technical Evaluation Rept Replaced W/Qualified Transmitters + (20:28:12, 8 January 2025)
- L-83-280, Advises That 10-yr pressure-temp Operating Limits (P-T) for Plant Recovery Program Reactor Vessel Internals & Thermal Shield Valid for Upcoming Cycle 6.P-T Limits Will Be Reviewed & Revised,If Necessary,Prior to Exceeding 7.4 EFPY + (20:28:14, 8 January 2025)
- ML17213B343 + (20:28:17, 8 January 2025)
- ML17213B340 + (20:28:18, 8 January 2025)
- ML17213B341 + (20:28:18, 8 January 2025)
- ML17213B339 + (20:28:19, 8 January 2025)
- ML17213B338 + (20:28:19, 8 January 2025)
- ML17213B337 + (20:28:20, 8 January 2025)
- L-83-227, Forwards Fire Hazard Analysis for Facility + (20:28:21, 8 January 2025)
- ML17213B336 + (20:28:21, 8 January 2025)
- ML17213B332 + (20:28:23, 8 January 2025)
- ML17213B331 + (20:28:24, 8 January 2025)
- ML17213B330 + (20:28:25, 8 January 2025)
- ML17213B328 + (20:28:26, 8 January 2025)
- ML17213B326 + (20:28:27, 8 January 2025)
- ML17213B324 + (20:28:30, 8 January 2025)
- ML17213B323 + (20:28:31, 8 January 2025)
- ML17213B321 + (20:28:35, 8 January 2025)
- ML17213B320 + (20:28:36, 8 January 2025)
- L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility + (20:28:37, 8 January 2025)
- L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations + (20:28:39, 8 January 2025)
- L-83-264, Forwards Plant Recovery Plan Presented at 830425 Meeting Re Reactor Vessel Internals & Thermal Shield,In Response to Item C of .Plan Will Be Revised Daily W/Updates Provided Upon Availability + (20:28:41, 8 January 2025)
- L-83-262, Withdraws 830405 Relief Request for Performing Inservice Insp.Relief Will Not Be Required + (20:28:43, 8 January 2025)
- L-83-254, Requests Relief from Tech Spec 4.4.10.1.a & 10CFR50.55a(g) Requirements Re Inservice Insp.Relief Requested Due to Problems W/Thermal Shield Which Necessitated Removal of Reactor Internals + (20:28:48, 8 January 2025)
- L-83-255, Advises of Changes That Should Be Made to to DG Eisenhut Re Reload Safety Analysis for Cycle 6.Ref 2 of XN-NF-83-81 Cycle 6 SAR Should Be Deleted & Ref 11 Should Be Changed to XN-NF-75-32(P),Suppls 1-4 + (20:28:50, 8 January 2025)
- L-83-257, Advises That First Reactor Vessel Matl Irradiation Surveillance Specimen Will Be Removed in Conjunction W/ Current Extended Outage to Remove Reactor Vessel Thermal Shield,Tentatively Scheduled for Completion in Dec 1984 + (20:28:51, 8 January 2025)
- L-83-261, Forwards Suppl 1 to 830412 Request for Exemption from Section III-0 of App R Requirements Re Reactor Coolant Pumps in Fire Protection Sys + (20:28:53, 8 January 2025)
- ML17213B303 + (20:28:56, 8 January 2025)
- ML17213B300 + (20:28:57, 8 January 2025)
- ML17213B299 + (20:28:58, 8 January 2025)
- ML17213B297 + (20:29:00, 8 January 2025)
- ML17213B296 + (20:29:01, 8 January 2025)
- ML17213B291 + (20:29:02, 8 January 2025)
- ML17213B294 + (20:29:02, 8 January 2025)
- L-83-247, Application for Amend to License NPF-16,modifying Surveillance Requirements of RCS Pressurizer to Comply w/NUREG-0737,Item II.B.3.1 Emergency Power Supply for Pressurizer Heaters + (20:29:03, 8 January 2025)
- ML17213B290 + (20:29:03, 8 January 2025)
- L-83-230, Lists Info Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program to Be Provided Prior to Startup,Per 830413 Telcon.Reactor Vessel Internals & Thermal Shield Insp Results Will Be Provided Prior to Startup + (20:29:05, 8 January 2025)
- L-83-238, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capabilities.Status & Implementation Schedule & List & Description of Reg Guide 1.97,Type a Variables Encl + (20:29:07, 8 January 2025)
- L-83-236, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capability (NUREG-0737,Suppl 1).Status & Proposed Implementing Schedule Submitted + (20:29:09, 8 January 2025)
- L-83-240, Responds to Generic Ltr 83-10b Re Resolution of TMI Action Plan Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Program to Close Out Item Under Development in Conjunction w/C-E Owners Group Program + (20:29:10, 8 January 2025)
- ML17213B269 + (20:29:13, 8 January 2025)
- ML17213B268 + (20:29:14, 8 January 2025)
- RAIO-0817-55190, LLC Response to NRC Request for Additional Information No. 76 (Erai No. 8792) on the NuScale Design Certification Application + (20:29:15, 8 January 2025)
- L-83-229, Forwards Rev 1 to Administrative Procedure 0520025, Process Control Program, Operating Procedure 0520023, Dewatering Radioactive Bead Resins, & Chem Nuclear Sys Test Procedure for Dewatering Conical Bottom Demineralizers & Resin Liners + (20:29:16, 8 January 2025)
- L-83-220, Discusses Two Concerns Re Continuous Containment Purge Sys in Event of Loca.Concerns Will Be Resolved Prior to Exceeding 5% Power + (20:29:19, 8 January 2025)