Letter Sequence Other |
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Results
Other: ML19320D593, ML19331C271, ML19331C277, ML19340B529, ML19350C772, ML20003C510, ML20009H240, ML20009H245, ML20030C723, ML20030C729, ML20032E918, ML20032E922, ML20032E929, ML20033B435, ML20038C770, ML20038C776, ML20038C783, ML20039A978, ML20039A984, ML20039F150, ML20053D278
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MONTHYEARIR 05000302/19790151979-05-25025 May 1979
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
[Table View] |
Text
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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 88, APPENDIX A Replace page 3/41-34 of Appendix A to Operating License No. DPR-72 with page 3/4 1-34, attached.
Proposed Change Reflect the interchange of safety rod groups I and 2 in Figure 3.1-7.
All rod locations currently (i.e., Cycle 3) identified as group 1 should be changed to group 2 and vice versa.
Reason for Proposed Change In response to recommendations from our NSSS vendor, Florida Power Corporation intends to administratively maintain some trippable negative reactivity during certain modes of operation (e.g., prolonged hot standby). This will be achieved by
>_1%
Ak/k withdrawing safety group 1 rods during such modes. However, a shutdown margin (SDM) must be maintained with all-rods-in (ARI) and the maximum ejected rod worth stuck out. Therefore, by withdrawing group 1 rods, additional chemical shim (boration) must be added to the reactor coolant system to achieve the SDM requirements. This chemical shim increases waste generation and should be minimized. To minimize the shim, the worth of the withdrawn group rods should also be minimized. The rod group designated safety group 2 in Cycle 3 has less worth than that designated group 1, so an interchange was made.
Safety Analysis of Proposed Change The redesignation of two (2) safety control rod groups has no impact on plant safety. All safety groups (1-4) are fully withdrawn during operation in Modes I and 2 when keff 2 1.0 (see also LIMITING CONDITIONS FOR OPERATION 3.1.3.5) and insert into the core unon receiving appropriate Reactor Protection System inputs. They, therefore, serve their safety function (negative reactivity insertion during transient conditions) without regard to group designation. Having one group withdrawn while in certain modes of operation is not required by technical specification or safety analyses but provides a means for rapid negative reactivity insertion, should it be needed, as compared to boration from available sources.
This approach is, therefore, more conservative than required by the technical l
specifications.
l c
8112140119 811200 PDR ADOCK 05000302 P
PDR
