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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-83-164, Forwards Suppl 1 to Analytical Justification of Seismic Test Adequacy of St Lucie,Unit 2 CPC & Ni Modules in Reactor Protection Sys Cabinet, Operability Rept + (ML17213B175)
- ML17213B176 + (ML17213B176)
- ML17213B177 + (ML17213B177)
- L-83-151, Forwards Revised Justification for Interim Operation,Prior to Installation of Containment Flame Impingement Shields, Highlighting Measures Taken to Provide Fire Protection in Affected Areas Above & Beyond Present NRC Requirements + (ML17213B178)
- L-83-158, Forwards Const/Startup Monthly Status Rept for Feb 1983. Current Target Fuel Load Date Is 830323 + (ML17213B179)
- ML17213B180 + (ML17213B180)
- ML17213B181 + (ML17213B181)
- L-83-171, Advises That Essential Apparatus Will Be Installed by End of First Refueling to Test 8-inch Minipurge Valves in Containment Ventilation Sys Every 92 Days,Per Tech Spec 4.6.1.7.4 + (ML17213B182)
- L-83-170, Forwards Proprietary Exxon Nuclear Analysis of Power Distribution Measurement Uncertainty for St Lucie,Unit 1. Responses Re Overpressure Mitigating Sys & Cycle 6 Reload Encl.Proprietary Rept Withheld (Ref 10CFR2.790) + (ML17213B183)
- ML17213B187 + (ML17213B187)
- L-83-172, Discusses Mods to Batch C & 16 Selected Batch B Fuel Assemblies Similar to Mods at AR Power & Light Unit 2.Shims Installed on Guide Tubes to Increase Shoulder Gap & Holddown & Flow Plates Machined in Thickness to Maintain Length + (ML17213B189)
- L-83-184, Forwards marked-up Table 3-1 of Radiological Emergency Plan. Changes Respond to Comments During 830322 Telcon & Will Be Incorporated Into Rev 13 by 840101 + (ML17213B190)
- L-83-181, Forwards P 25,corrective Action Plans,To Suppl a to Engineering Verification Program, Inadvertently Omitted from Util + (ML17213B191)
- ML17213B192 + (ML17213B192)
- ML17213B193 + (ML17213B193)
- L-83-185, Forwards Rev 2 to Offsite Dose Calculation Manual + (ML17213B194)
- ML17213B195 + (ML17213B195)
- ML17213B196 + (ML17213B196)
- L-83-183, Forwards Schedule Outlining Portions of Initial Test Program That May Be Incomplete by Core Load + (ML17213B197)
- ML17213B198 + (ML17213B198)
- L-83-187, Forwards Revised Radiological Effluent Tech Specs.Tech Spec Change Request Withdrawn + (ML17213B200)
- ML17213B201 + (ML17213B201)
- ML17213B202 + (ML17213B202)
- L-83-173, Requests OL Be Granted Based on Facility Readiness for Fuel Load by 830331.Plant Completion Status Will Not Have Adverse Impact on Plant Safety.Facility Designed,Constructed & Tested,Per FSAR & Licensing Commitments + (ML17213B203)
- ML17213B204 + (ML17213B204)
- ML17213B206 + (ML17213B206)
- ML17213B207 + (ML17213B207)
- L-83-199, Confirms Understanding of ESF Actuation Sys,(Esfas) Testing Per IEEE-338 & Reg Guide 1.22 Requirements,In Response to .All ESFAS Actuation Devices Tested During Shutdown Per FSAR & Tech Specs + (ML17213B208)
- L-83-193, Submits Interim Justification for Plant Operation Up to 5% Power.Request for Addl Info Re Environ Qualification of Electric Equipment Under Evaluation.Final Response Will Be Submitted Before Exceeding 5% Power + (ML17213B213)
- L-83-200, Revises Statement on Page 2 of Re Audit Findings A.8.7 & A.8.9 of App C to SER Suppl 1 Re LPSI & HPSI Sys + (ML17213B214)
- L-83-196, Advises That Baseline Leak Testing,Per NUREG-0737, Item III.D.1.1,will Be Component of Hot Ops II Testing After Core Load,Prior to Initial Criticality.No Fission Products Will Be Present in RCS During Test + (ML17213B215)
- L-83-197, Informs That Testing of Valves During Hot Ops II Justified,Per .Affected safety-related Sys Not Required Prior to Initial Criticality + (ML17213B216)
- L-83-198, Informs That Installation of TSI Shields in Cable Tray Racks Will Be Completed Prior to First Refueling,Per . Shields Can Be Installed During Power Operation.Detailed Schedule of Outages Not Required + (ML17213B217)
- L-83-205, Forwards Table Summarizing Fire Protection Tech Spec Commitments for Items Scheduled for Completion by 5% Power + (ML17213B218)
- L-83-207, Forwards List of Correspondence to NRC Affecting Plant Configuration as Described in Fsar,In Response to NRC Request.Ltrs Will Be Incorporated Into Upcoming Amend 14 to FSAR + (ML17213B219)
- L-83-192, Forwards Revised Page in Initial Test Program Schedule,Per NRC Request.Change Involved Completion Date for Preoperational Test 2-1730080 + (ML17213B223)
- L-83-201, Informs That Util Commits to Rearrange Instruments Described in to left-to-right,top-to-bottom Convention by End of First Refueling,Per Human Factors Engineering Branch Audit Findings + (ML17213B225)
- L-83-209, Responds to Questions Raised During NRC 830223-24 Site Visit Re Availability of Readout of Core Exit Thermocouples When Plant Computer Down & Procedure for Loss of All Ac Power. Computer Readout Always Available Through Redundant Sys + (ML17213B228)
- ML17213B231 + (ML17213B231)
- L-83-214, Forwards One Time Relief Request Re Tech Spec Requirements for Performing Inservice Insp Following Removal of Reactor Internals.License Amend Fee Not Required + (ML17213B244)
- L-83-203, Submits Interim Response to NRC Re Containment Purge Valve Operability.Henry Pratt Co Commissioned to Prepare Rept for Purge Valves Using Present Conservative Methodology.Rept Will Address out-of-plan Upstream Elbow + (ML17213B246)
- L-83-219, Forwards Responses to Reactor Sys Branch Questions Re Overpressure Mitigating Sys,In Response to NRC . Response to Reactor Physics Section Questions Re Cycle 6 Reload Provided in + (ML17213B250)
- L-83-218, Provides Assurances That Single Failure in Circuits Penetrating Containment Lacking Primary & Secondary Fault Protection Would Not Impair Integrity of Containment Electrical Penetration,Per Reg Guide 1.63 Commitment + (ML17213B251)
- L-83-220, Discusses Two Concerns Re Continuous Containment Purge Sys in Event of Loca.Concerns Will Be Resolved Prior to Exceeding 5% Power + (ML17213B252)
- ML17213B259 + (ML17213B259)
- 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 + (ML17213B265)
- ML17213B266 + (ML17213B266)
- RAIO-0817-55190, LLC Response to NRC Request for Additional Information No. 76 (Erai No. 8792) on the NuScale Design Certification Application + (ML17213B267)
- ML17213B268 + (ML17213B268)
- ML17213B269 + (ML17213B269)
- 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 + (ML17213B284)