ML20003C510
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Letter Sequence Other | |
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TAC:42266, (Approved, Closed) | |
Administration Questions
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MONTHYEARIR 05000302/19790151979-05-25025 May 1979
[Table View]IE Insp Rept 50-302/79-15 on 790507-11.Noncompliance Noted: Failure to Prepare Procedures for Identifying Containers of Radioactive Matl & Improper Shipments of Solid Wastes Project stage: Request ML19225D1361979-07-0303 July 1979 Safety Evaluation Supporting Amend 20 to License DPR-72 Project stage: Approval ML19320D5931980-07-0101 July 1980 Forwards Questions Re Fuel Assembly Holddown Spring Failure. NRC Is Interested in Knowing Results of Spring Insps & Safety Significance of Operating W/Broken Springs in Core. Response Requested within 60 Days of Ltr Receipt Project stage: Other ML19331C2711980-08-0101 August 1980 Amend 32 to License DPR-72,revising App a Tech Specs to Permit Power Operation During Cycle 3 at Currently Authorized Power Level of 2452 MW Project stage: Other ML19331C2751980-08-0101 August 1980 Safety Evaluation Supporting Amend 32 to License DPR-72 Project stage: Approval ML19331C2771980-08-0101 August 1980 Notice of Issuance & Availability of Amend 32 to License DPR-72 Project stage: Other ML19337A2841980-09-0303 September 1980 Forwards Response to NRC 800701 Request for Addl Info Re Fuel Assembly Holddown Springs Project stage: Request ML19340B5291980-10-31031 October 1980 Cycle 3 Startup Rept Project stage: Other ML20003C5101981-02-23023 February 1981 Requests Commitment to Perform Surveillance of Fuel Assembly Holddown Springs in Core During Next Refueling Outage & to Rept Any Spring Failures Noted.Commitment Should Be Submitted within 30 Days Project stage: Other ML19350C7721981-03-30030 March 1981 Provides Response to Re Future Surveillance of Fuel Assembly Holddown Springs.Visual Exam Will Be Performed for All Assemblies During Next Refueling Outage Project stage: Other ML19345H5421981-05-13013 May 1981 Informs of Subcommittee on B&W Reactors Rept on Util Request to Increase Facility Power Level Discussed at 253rd ACRS Meeting in Washington,Dc.Further Review Not Needed.No ACRS Objection to Increased Levels Up to 2,544 Mwt Project stage: Meeting ML20009A8491981-07-0909 July 1981 Application to Amend License DPR-72,changing App a Tech Specs Re Reactor Protection Sys Set Points,Safety Limits & Operating Limits to Allow Cycle III Operation at 2544 MW Thermal.Amend Fee & Certificate of Svc Encl Project stage: Request ML20009H2451981-07-21021 July 1981 Notice of Issuance & Availability of Amend 41 to License DPR-72 Project stage: Other ML20009H2401981-07-21021 July 1981 Amend 41 to License DPR-72,authorizing Facility Power Level Increase & Correcting Typographical Error on Tech Spec Page 3/4 3-8 Project stage: Other ML20009H2421981-07-21021 July 1981 Safety Evaluation Supporting Amend 41 to License DPR-72 Project stage: Approval ML20009G4161981-07-24024 July 1981 Forwards Explanation of Changes to Specific Sections of Security Plan & Revised Pages of Security Plan in Response to Violations Noted in Security Event Rept 81-06 & 810605 Meeting.Info Withheld (Ref 10CFR2.790) Project stage: Request ML20009F9031981-07-27027 July 1981 Application for OL Amend,Consisting of Tech Spec Change Request 70,Suppl 1,allowing Delayed Implementation of Recently Issued Tech Spec Amend.Amend Includes Reactor Coolant Pump Power Monitor Functional Requirements Project stage: Request ML20030C7231981-08-12012 August 1981 Amend 42 to License DPR-72,changing Effective Date of Amend 41 to Be Effective When Reactor Coolant Pump Power Monitors Are Fully Implemented & Operable Project stage: Other ML20030C7271981-08-12012 August 1981 Safety Evaluation Supporting Amend 42 to License DPR-72 Project stage: Approval ML20030C7291981-08-12012 August 1981 Notice of Issuance & Availability of Amend 42 to License DPR-72 Project stage: Other ML20010J5491981-09-25025 September 1981 Safety Evaluation Supporting Amend 43 to License DPR-72 Project stage: Approval ML20032E9221981-11-16016 November 1981 Tech Spec Change Request 77 Requesting Amend to App a of License DPR-72 to Incorporate Revised Reactor Core Safety Limits & Trip Setpoints for Reactor Thermal Power & Axial Power Imbalance Project stage: Other ML20032E9291981-11-16016 November 1981 Proposed Tech Specs B2-7 3/4.4 Limiting Safety Sys Settings, Reactivity Control Sys & RCS Reactor Coolant Loops Project stage: Other ML20032E9181981-11-16016 November 1981 Forwards Tech Spec Change Request 77,requesting Amend to App a of License DPR-72 Re Refueling for Cycle 4, & BAW-1684 in Support of Application.Certificate of Svc Encl Project stage: Other ML20033B4351981-11-20020 November 1981 Forwards Responses to NRC 811118 Informal Questions Re Cycle 4 Reload Rept,Per 811118 Telcon Project stage: Other ML20039A9781981-12-0404 December 1981 Amend 46 to License DPR-72,revising Tech Specs to Authorize Cycle 4 Operation Following Refueling Project stage: Other ML20039A9841981-12-0404 December 1981 Notice of Issuance & Availability of Amend 46 to License DPR-72 Project stage: Other ML20038C7701981-12-0808 December 1981 Forwards Tech Spec Change Request 88 for Amend to License DPR-72,App A.Change Reflects Interchange of Safety Rod Groups 1 & 2 During Current Refueling Outage.Affidavit & Certificate of Svc Encl Project stage: Other ML20038C7831981-12-0808 December 1981 Proposed Tech Spec Page 3/4 1-34,reflecting Interchange of Safety Rod Groups 1 & 2 During Current Refueling Outage Project stage: Other ML20038C7761981-12-0808 December 1981 Tech Spec Change Request 88 for Amend to License DPR-72, App A.Change Reflects Interchange of Safety Rod Groups 1 & 2 During Current Refueling Outage Project stage: Other ML20039F1501981-12-10010 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 ML20053D2781982-05-31031 May 1982 Cycle 4 Reload Rept Project stage: Other 1981-12-08 |
| ML20003C510 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/23/1981 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Hancock J FLORIDA POWER CORP. |
| References | |
| TAC-42266, NUDOCS 8103060308 | |
| Download: ML20003C510 (2) | |
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