Search by property

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• L-83-187, Forwards Revised Radiological Effluent Tech Specs.Tech Spec Change Request Withdrawn  + (ML17213B200)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)
• L-83-236, Responds to Generic Ltr 82-33 Re Requirements for Emergency Response Capability (NUREG-0737,Suppl 1).Status & Proposed Implementing Schedule Submitted  + (ML17213B285)
• 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  + (ML17213B286)
• 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  + (ML17213B287)
• 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  + (ML17213B288)
• ML17213B289  + (ML17213B289)
• ML17213B290  + (ML17213B290)
• ML17213B291  + (ML17213B291)
• ML17213B292  + (ML17213B292)
• ML17213B294  + (ML17213B294)
• ML17213B296  + (ML17213B296)
• ML17213B297  + (ML17213B297)
• ML17213B299  + (ML17213B299)
• ML17213B300  + (ML17213B300)
• ML17213B303  + (ML17213B303)
• 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  + (ML17213B305)
• 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  + (ML17213B306)
• 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  + (ML17213B309)
• 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  + (ML17213B310)
• L-83-262, Withdraws 830405 Relief Request for Performing Inservice Insp.Relief Will Not Be Required  + (ML17213B311)
• 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  + (ML17213B312)