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MONTHYEARML19318A4791980-06-0505 June 1980 Forwards Response to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Review Described in Encl 1 Revealed Error. Decay Heat Pump Suction Was Not Isolated by Containment Isolation Actuation as Stated in Page 2 Project stage: Other ML20126D8351980-06-11011 June 1980 Ltr to All Operating PWRs Requesting Amend to Tech Specs Re Decay Heat Removal Capability.Amend Is Necessary to Provide Permanent long-term Assurance That Redundancy Will Be Maintained Project stage: Other ML19318C4301980-06-26026 June 1980 Forwards Addl Info Re Shift Manning,Licensing,Testing of Power Operated Relief Valve Isolation Sys,Automatic Trip of Reactor Coolant Pumps & Small Break LOCA Methods,In Response to NRC Project stage: Other ML19330B7881980-07-25025 July 1980 Notice of Issuance & Availability of Amend 28 to License NPF-3 Project stage: Other ML19330B7851980-07-25025 July 1980 Amend 28 to License NPF-3,revising Tech Spec Setpoint for Automatic Closure of Decay Heat Removal Sys Isolation Valves & Implementing Pressurizer Heat Interlock Project stage: Other ML19337B6211980-09-23023 September 1980 Notifies That Fire Protection Mods Should Be Completed at End of Current Refueling Outage.Requests Revision of Fire Protection Tech Specs within 60 Days.Fire Protection STS Encl Project stage: Other ML20151B3601980-12-26026 December 1980 Application for Amend of License NPF-3 Changing Tech Specs Re Fire Detection Sys,Decay Heat Removal Capabilities,Low Temp RCS Overpressure Event,Axial Power Shaping Rod Insertion Limits & Util Reorganization Project stage: Request ML20009C8881981-07-10010 July 1981 Marked-up Revised Tech Specs 3.4.2,4.4.2,3.4.3,4.4.3, 3.8.1.2,4.8.1.2,4.8.1.1.2,4.8.1.1.2.C.2,3.1.3.6,3/4.2,3.2.1, 4.2.1,3.2.5,6.5.2.2,6.5.2.3,6.5.2.4,6.5.2.5,6.5.2.6, 3/4.7.10,3.7.10,4.7.10,Pages 3/4.7-5,B 3/4.4-19 & 3.8.1.2 Project stage: Other ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs Project stage: Request ML20009C8871981-07-10010 July 1981 Application for Amend of License NPF-3,revising Tech Specs for Auxiliary Feedwater Pump Turbine Speed Switches,Setpoint Index for Pressurizer Electromatic Relief & Code Safety Valves,Emergency Diesel Generator & Administrative Errors Project stage: Request ML20028G3531983-02-0101 February 1983 Forwards Model Tech Specs for Proposed Amend to App a Tech Specs Re DHR Capability Redundancy.Mod Requested to Assure Redundancy in Mode 3.Response Requested within 45 Days. W/O Encl Project stage: Other ML20069E4511983-03-17017 March 1983 Forwards Explanation on How DHR Redundancy Assured in Mode 3 Operation,In Response to NRC .Tech Specs Will Be Revised to Include Applicable Limits by 830513 Project stage: Other ML20023D5501983-05-13013 May 1983 Advises That Due to Difficulties W/Rev,License Amend Request Re DHR Capability Redundancy Will Be Submitted by 830615 Project stage: Other ML20024C2131983-07-0808 July 1983 Proposed Changes to Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization Project stage: Request ML20024C2111983-07-0808 July 1983 Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization Project stage: Request ML20024C2081983-07-0808 July 1983 Forwards Application for Amend to License NPF-3,changing Tech Specs 6.5.1.2,6.5.2.2,Figure 6.2-1 & Figure 6.2-2 Re Util Reorganization.Fees Previously Submitted w/801226 Amend Request Project stage: Request ML20082F1661983-11-22022 November 1983 Requests Expeditious Issuance of Amend to License NPF-3,per 801223 Application & 810710 Supplemental Submittal Re Fire Barrier Penetrations,Tech Spec (Item 6) Project stage: Supplement ML20136J2191985-12-10010 December 1985 Discusses Plans Re Exemption Requests Provided in 840906 App R Compliance Assessment Rept & Application to Amend License NPF-3 Re Fire Protection Tech Specs.No Further Action on Exemption Request Required.Application Withdrawn Project stage: Request 1981-07-10
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7590-01 l
UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-346 i
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THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Contission (the Commission) has issued l
l Amendment No. 28 to Facility Operating License No. NPF-3, issued to The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees), which revised the license and Tt.chnical Specifications for oper-ation of the Davis-Besse Nuclear Power Station, Unit No.1 (the facility) located in Ottawa County, Ohio. The amendment is effective as of its date of issuance.
This amendment revises the Technical Specification setpoint for the automatic closure of the decay heat removal system isolation valves, and implements a pressurizer heater interlock which deenergizes the heaters if reactor coolant system pressurization is attempted and both decay heat removal system isolation valves are not closed. This action satisfies the
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. requirements of license conditions 2.C.(3)(d) and 2.C.(3)(j).
In addition, the amendment adds a new condition to the license which requires, prior to operation beyond five effective full power years, the Toledo Edison Company to provide a reanalysis and proposed modifications, as necessary, to ensure continued means of protection against low temperature reactor coolant system overpressure events. Therefore, license condition 2.C.(3)(d) is replaced with the above new requirement and condition 2.C.(3)(j) is removed from the license.
8008050 53 9
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- 7590-01 The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ce wission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license a nendment. Prior public notice of this amendment was not required since the amendment does not involve a significant hazards consideration.
The Comission has detennined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 151.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with l
the issuance of this amendment.
For further details with respect to this action, see (1) the application for amendment dated March 20,1978,(2) Amendment No. 2.8 to License No. NPF-3, and (3) the Comission's related Safety Evaluation. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N. W., Washington, D. C., and at the Ida Rupp Public Library, 310 Madison Street, Port Clinton, Ohio. A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Comission, Washington, D. C.
20555, Attention: Director, Division of Licensing.
Dated at Bethesda, Maryland, this 25th day of July 1980.
FOR THE NUCLEAR REGULATORY COMMISSION ML o ert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing l
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