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MONTHYEARML20039F1501981-12-10010 December 1981 Requests Listed Info Be Provided Re Fuel Failures & Iodine Spiking,Prior to Start of Cycle 5 Operation.Info Relates to Investigation Into Cause of Previous Fuel Failures,Proposed Remedy & Notification If Addl Fuel Failures Occur Project stage: Other ML20064N3021983-02-0707 February 1983 Confirms Discussions W/Nrc Re Starting Date & Expected Duration for Refuel 4 & Establishes Schedule for Refuel 5. Refuel 4 Scheduled for 830319.Planned Mods Require 16 Wks. Cycle 5 Begins Approx 830709 Project stage: Other ML20073F5301983-03-31031 March 1983 Proposed Tech Specs Re Cycle 5 Operation W/Reactor Coolant Pump Power Monitors & 2-yr Cycle Impact Project stage: Other ML20073F5111983-03-31031 March 1983 Application for Amend to License DPR-72,consisting of Tech Spec Change Request 82 Re Cycle 5 Operation W/Reactor Coolant Pump Power Monitors (BAW-1767) & 2-yr Cycle Impact. Certificate of Svc Encl Project stage: Request ML20073F5751983-03-31031 March 1983 3,Cycle 5 Reload Rept Project stage: Other ML20072D9801983-06-17017 June 1983 Submits Addl Info Supporting 830331 Tech Spec Change Request 82 Re Cycle 5 Operation W/Reactor Coolant Pump Power Monitors.Response Time for Pump Status Based on Reactor Coolant Power Pump Monitor Trip Should Be 1.44 Project stage: Other ML20099B4181983-06-22022 June 1983 Application for Tech Spec Change Request 82 to License DPR-72,amending Shutdown Margin.Attachments C & E Encl,Per 830331 Submittal.W/Certificate of Svc Project stage: Request ML20099B4241983-06-22022 June 1983 Proposed Tech Spec Changes Re Shutdown Margin Project stage: Other ML20024B8181983-07-0606 July 1983 Forwards Addl Info in Support of Tech Spec Change Request 82 Re Cycle 5 Operation W/Reactor Coolant Pump Power Monitors (Rcppm) Per 830701 Request.Testing of All Rcppm Strings Prior to Startup Will Consist of Checking Time Delays Project stage: Other ML20076M4991983-07-12012 July 1983 Safety Evaluation Supporting Amend 64 to License DPR-72 Project stage: Approval ML20076M4921983-07-12012 July 1983 Amend 64 to License DPR-72,extending 18-month Surveillance Requirements to 24 Months to Correspond to Extended Core Lifetime for Cycle 5 Project stage: Other ML20078H2301983-07-31031 July 1983 Reactor Containment Bldg Integrated Leak Rate Test, Jul 1983 Project stage: Other ML20105B8631983-09-0606 September 1983 Provides Results of Review of NSHC Package Re Cycle 5 Reload.Justification for Denial Needed Project stage: Approval ML20078H2241983-10-11011 October 1983 Forwards Reactor Containment Bldg Integrated Leak Rate Test, Jul 1983 Project stage: Other 1983-06-17
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Power COmponata0N October 11,1983 3F-1083-13 Mr. Ha old R. Denton, Director Office af Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Reactor Containment Building Local Leak Rate Test
Dear Mr. Denton:
Florida Power Corporation hereby submits the attached " Local Leak Rate Test Report" for the leak rate test completed July 11, 1983. This report is submitted in accordance with 10 CFR 50, Appendix 3,Section V.B and Regulatory Guide 10.1, Rev. t+, Item 78.
If you have any questions concerning this report, please contact this office.
Very truly yours, I
G.R. Westafer Manager Nuclear Operations Licensing and Fuel Management Attachment DVH:jcf cc: Mr. James P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 h
Atlanta, GA 30303
- l. I 8310140079 831011 PDR ADOCK 05000302 l
PDR p
General Office 320i wty-fourtn street soutn. P O. Box 14042. St. Petersburg Flonda 33733 813-866-5151
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