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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-84-233, Forwards Fees for 840521 Amends to Licenses DPR-31 & DPR-41, Revising & Expanding Table 3.13-1 Re safety-related Snubbers + (ML17346A504)
- L-84-228, Forwards Inservice Insp Rept for 840306-0631 + (ML17346A509)
- ML17346A510 + (ML17346A510)
- ML17346A511 + (ML17346A511)
- ML17346A513 + (ML17346A513)
- RAIO-1217-57618, LLC Response to NRC Request for Additional Information No. 251 (Erai No. 9188) on the NuScale Design Certification Application + (ML17346A519)
- L-84-231, Provides Addl Info Re 840822 Commitment to Calculate Dose Rate from Spent Fuel Assembly w/9 Ft of Water Shielding Above Top of Fuel Rods.Analysis Performed for Fuel Assembly W/Initial Enrichment of 4.5 W/O & Burnup of 50,000 Mwd/Mtu + (ML17346A520)
- L-84-232, Informs That Response to NRC 840813 Request for Addl Info Re Proposed Spent Fuel Pool Expansion Will Be Delayed Until 840917,because All Info Requested from Bechtel/Westinghouse Has Not Been Received/Reviewed + (ML17346A523)
- ML17346A531 + (ML17346A531)
- L-84-250, Requests Withdrawal of Tech Specs for Reactor Vessel Level Monitoring Sys from Table 3.5.5 Re Accident Monitoring Instrumentation,Contained in 840615 Application to Amend Licenses DPR-31 & 41,per NUREG-0737.Revised Pages Encl + (ML17346A536)
- L-84-252, Forwards Emergency Plan Implementing Procedures 1107, Duties of Emergency Planning Supervisor,Offsite Emergency Organization & 1211, Activation & Use of Emergency News Ctr (Turkey Point),Offsite Emergency Organization + (ML17346A537)
- ML17346A538 + (ML17346A538)
- ML17346A539 + (ML17346A539)
- ML17346A540 + (ML17346A540)
- ML17346A542 + (ML17346A542)
- L-84-253, Requests Extension Until 841019 to Provide Addl Info Re 10-yr Inservice Insp Summary Plan.Extension Due to Difficulties of Researching Large Amount of Info & Inservice Insp Manual Preparation + (ML17346A544)
- L-84-254, Advises That Addl Info Re Proposed Amend to Spent Fuel Storage Facility Expansion Will Be Further Delayed Until 840925 Due to 840910 Identification of Requirement + (ML17346A547)
- L-84-239, Responds to 840814 Draft Safety Evaluation of Inadequate Core Cooling Instrumentation Sys,Per NUREG-0737,Item II.F.2.Addl Info,Implementation Milestones & Implementation Rept for Reactor Vessel Level Monitoring Sys Encl + (ML17346A548)
- L-84-226, Forwards Radioactive Effluent Release Data Rept & Radiological Environ Monitoring Rept for Jan-June 1984 & Suppl to Radiological Environ Monitoring Rept for Jul-Dec 1983 + (ML17346A553)
- ML17346A555 + (ML17346A555)
- ML17346A556 + (ML17346A556)
- ML17346A557 + (ML17346A557)
- ML17346A558 + (ML17346A558)
- L-84-263, Forwards Response to 840813 Request for Addl Info Re Proposed Amend to Spent Fuel Facility Expansion + (ML17346A560)
- RC-17-0182, (VCSNS) - Anchor Darling Double Disc Gate Valve Information and Status + (ML17346A561)
- L-84-270, Revised Emergency Operating Procedures,Including O-ADM-110 Re Verification Guideline for Emergency Operating procedures,O-ADM-111 Re Emergency Procedure Validation Plan & Procedures Generation Package + (ML17346A562)
- L-84-268, Informs of Inability to Respond to Generic Ltr 84-15 Re Diesel Generator Reliability by 841001.Responses to Items 1 & 3 Will Be Provided for St Lucie Units 1 & 2 by 850131. Response to Item 2 Will Be Provided by 841023 + (ML17346A563)
- ML17346A565 + (ML17346A565)
- ML17346A567 + (ML17346A567)
- ML17346A568 + (ML17346A568)
- L-84-264, Forwards Response to NRC 840906 Request for Addl Info Re Proposed Amend to Expand Spent Fuel Storage Facility.Decay Heat Load Analysis Revised Based on Listed Assumptions & Bases + (ML17346A569)
- ML17346A570 + (ML17346A570)
- ML17346A571 + (ML17346A571)
- L-84-276, Forwards Response to NRC 840815 Request for Addl Info Re Facility Safety Parameter Display Sys Implementation Plan,In Accordance W/Generic Ltr 82-33 + (ML17346A572)
- ML17346A573 + (ML17346A573)
- RC-17-0169, Notification of an Intended Change of a Commitment Date for Open Phase Condition Made in RC-14-0019 + (ML17346A577)
- L-84-278, Responds to Questions 5a,b & C in NRC 840813 Request for Addl Info Re Application for Amend to Licenses DPR-31 & DPR-41,changing Structural Design of Spent Fuel Pit & New Storage Racks + (ML17346A579)
- RAIO-1217-57617, LLC Response to NRC Request for Additional Information No. 261 (Erai No. 9063) on the NuScale Design Certification Application + (ML17346A580)
- ML17346A581 + (ML17346A581)
- ML17346A582 + (ML17346A582)
- ML17346A583 + (ML17346A583)
- L-84-284, Forwards Suppl to Util 840928 Response to NRC 840813 Request for Addl Info Re Proposed Amend to Spent Fuel Storage Facility Expansion.Changes Involve Item 1.3 on Region 2 Racks,Summary of Design Stresses & Min Margins of Safety + (ML17346A585)
- ML17346A587 + (ML17346A587)
- L-84-290, Advises That Administrative Procedure 0103.38 Re Control & Use of Vendor Technical Manuals Issued to Assure Proper Use in Nuclear safety-related Sys,Per Generic Ltr 83-28 + (ML17346A589)
- L-84-292, Forwards Response to 840926 Request for Addl Info Re Offsite Dose Calculation Manual Review + (ML17346A590)
- L-84-238, Forwads List of Addl Components to Be Added to Pump & Valve Test Program.Implementation Date for Spent Fuel Pit Cooling Pump Set for 860101 to Allow Completion of Mods Required for Testing + (ML17346A595)
- ML17346A596 + (ML17346A596)
- L-84-286, Ack Receipt of 840817 Request for Addl Info Re Second 10-yr Inservice Insp Summary Plan.Requested Info Will Be Submitted by 841119 + (ML17346A597)
- L-84-303, Advises That 841005 Commitment to Use Discharge of High Head Safety Injection Pump as Seismic Category 1 Source of Makeup Water for Spent Fuel Pit Inappropriate for Pit Cooling.Pit Cooling Loop Will Be Upgraded as Alternative + (ML17346A599)
- ML17346A600 + (ML17346A600)
- ML17346A601 + (ML17346A601)