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List of results

• 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)
• ML17346A602  + (ML17346A602)
• ML17346A613  + (ML17346A613)
• ML17346A614  + (ML17346A614)
• ML17346A615  + (ML17346A615)
• ML17346A616  + (ML17346A616)
• ML17346A618  + (ML17346A618)
• L-84-316, Forwards Response to 840702 Generic Ltr 84-15 Re Improving & Maintaining Diesel Generator Reliability.Program Developed to Reduce Rapid Start Testing of Emergency Diesel Generators.Reliability of Each Diesel Generator Reported  + (ML17346A619)
• ML17346A622  + (ML17346A622)
• L-84-324, Forwards Correction to Author Forwarding Offsite Dose Calculation Manual.Ltr Number Should Be L-84-188 Instead of L-84-128  + (ML17346A624)