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MONTHYEARML19261C5191979-02-27027 February 1979 Forwards Safety Evaluation Rept for Fire Protection Program. Concludes Program,W/Scheduled Mods,Meets General Design Criterion 3 & Is Therefore Acceptable Project stage: Approval ML19261C5211979-02-27027 February 1979 Fire Protection Safety Evaluation Rept. Until Scheduled Improvements Are Made,Present Fire Protection Tech Specs Provide Sufficient Protection Against Fire Threatening Safe Shutdown Project stage: Approval ML19249A3761979-07-26026 July 1979 Amend 18 to License NPF-3,adding License Condition Re Completion of Facility Mod for Fire Protection & Modifying Tech Specs to Require Five Individuals W/Fire Protection Training on Site Project stage: Other ML19249A3721979-07-26026 July 1979 Forwards Amend 18 to License NPF-3,safety Evaluation & Notice of Issuance & Availability Project stage: Approval ML19249A3781979-07-26026 July 1979 Fire Protection Safety Evaluation Supporting Amend 18 to License NPF-3 Project stage: Approval ML19249A3821979-07-26026 July 1979 Notice of Issuance & Availability of Amend 18 to License NPF-3 Project stage: Other ML19317H4811980-05-19019 May 1980 Forwards Proposed Rule Entitled, Fire Protection Program for Nuclear Power Plants Operating Prior to 790101. Rule Adds New Section 50.48 & App R to 10CFR50 & Is Expected to Be Published in Fr by End of May Project stage: Other ML19318A4791980-06-0505 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 ML19351D6201980-10-0707 October 1980 Application for Amend to License NPF-3,providing Tech Specs for Fire Detection Sys Per License Condition 2.c(4) Project stage: Request ML19343B5061980-11-18018 November 1980 Notice of Issuance & Availability of Amend 34 to License NPF-3 Project stage: Other ML19343B5031980-11-18018 November 1980 Amend 34 to License NPF-3,modifying Tech Specs to Include Fire Detection Instrumentation Mods Project stage: Other IR 05000346/19800161980-11-18018 November 1980 IE Insp Rept 50-346/80-16 on 800609-11 & 1020-24.No Noncompliance Noted.Major Areas Inspected:Refueling Outage Maint,Plant Operations Review & Equipment Calibr Project stage: Request ML17328B0571980-11-24024 November 1980 Ltr to All Power Reactor Licensees W/Plants Licensed Prior to 790101.Forwards Revised Section 10CFR50.48 & App R Re Fire Protection Features in Nuclear Power Plants & List of Requirements for Resolution of Open Issues.W/O Encl Project stage: Other ML19340D2431980-11-24024 November 1980 Forwards Revised 10CFR50.48 & App R to 10CFR50 Re Five Protection Features of Nuclear Power Plants.Rules Take Effect 810217.Summary Listing of Open Items Re Fire Protection Features of Facility 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 ML20003D5881981-03-19019 March 1981 Responds to Re Submittal of Plans,Schedules & Design Descriptions of 10CFR 50,App R,Mod for Fire Protection.Forwards Design Description of Alternate Svc Water Capability Project stage: Other ML19350E2661981-06-10010 June 1981 Requests re-evaluation of Class III Fees Assessed for 810319 Proposal for Alternate Svc Water Capability.Review of Amend 18,Item B Requirements Stated No License Amend Fee Required for Response to Proposal.Class III Fee Encl Project stage: Other 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 ML20009C8841981-07-10010 July 1981 Forwards Application for Amend of License NPF-3,requesting Revisions to Tech Specs 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 ML20054C9511982-04-0808 April 1982 Submits List of Drawings Needed for Consideration Re Proposed Facility Mods for App R,Per 820323 Meeting Project stage: Meeting ML20053E5241982-06-0202 June 1982 Safety Evaluation Supporting Requested Mods to 10CFR50 & 10CFR50.48 App R Project stage: Approval ML20053E5221982-06-0202 June 1982 Forwards Safety Evaluation of Util Requested Mods to Comply w/10CFR50 App R Sections Iii.G,Iii.J & Iii.O Re Alternate Svc Water Capability.Proposed Mods Acceptable Project stage: Approval ML20067C1711982-11-23023 November 1982 Safety Evaluation Supporting Exemption from Certain Requirements of App R to 10CFR50 Project stage: Approval ML20069N1181982-11-23023 November 1982 Notifies That Alternate Dedicated Svc Water Sys Will Be Installed within 30 Months of NRC 820602 Acceptance Date,Per 10CFR50.48(c)(4) Project stage: Other 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 ML20073R6881983-05-0202 May 1983 Forwards Application for Amend to License NPF-3 Revising Tech Spec Section 4.8.1.2,Tables 4.3-11 & 3.6-2 Re Surveillance Requirements for Automatic Load Sequencer & Monthly Testing of Auxiliary Feedwater Sys Logic Project stage: Request ML20073R6951983-05-0202 May 1983 Application for Amend to License NPF-3 Revising Tech Spec Section 4.8.1.2,Tables 4.3-11 & 3.6-2 Re Surveillance Requirements for Automatic Load Sequencer & Monthly Testing of Auxiliary Feedwater Sys Logic Project stage: Request ML20073R7051983-05-0303 May 1983 Proposed Changes to Tech Spec Revising Section 4.8.1.2, Tables 4.3-11 & 3.6-2 Re Surveillance Requirements for Automatic Load Sequencer & Monthly Testing of Auxiliary Feedwater Sys Logic Project stage: Request 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 ML20071G7311983-05-17017 May 1983 Forwards Response to 830411 Request for Addl Info Re Deletion of Surveillance Requirements for Auxiliary Feedwater Pump Turbine Speed Switches.Water Level in Steam Generator Controlled at 35 Inches 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 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 ML20076H1151983-08-26026 August 1983 Forwards Plans & Evaluation Addressing Understanding Findings Identified by NRC Following 830725-29 Fire Protection Audit,Per 830816,18 & 22 Requests.Adequate Fire Protection Features in Place to Return to Cycle 4 Operation Project stage: Other ML20024E9601983-08-31031 August 1983 Forwards Revised Action Summary Table to Util 830826 Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan Project stage: Other ML20080G3311983-09-13013 September 1983 Forwards Revised Evaluation of NRC 830725-29 App R Audit Findings & Corrective Action Plan,Superseding Info Submitted w/830826 & 31 Ltrs.Findings & Plan Justify Continued Operation Project stage: Other ML20151H8561983-09-19019 September 1983 Reviews Licensee short-term & long-term Compensatory Actions on Insp Findings Re 10CFR50,App R Shutdown/Fire Protection deficiencies.Short-term Actions Acceptable Project stage: Other 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 ML20086C7571983-11-23023 November 1983 Forwards Revised Schedule for Plan to Address Findings of NRC 10CFR50,App R Audit.Schedule Updates 830913 Commitment. Extension Needed to Incorporate Concerns of IE Info Notice 83-69, Improperly Installed Fire Dampers.. Project stage: Other ML20155C9641984-08-0606 August 1984 Summary of 840612 Meeting W/Util in Bethesda,Md Re Program to Correct Fire Protection Deficiencies in Facility Fire Protection Features & non-compliance W/Respect to Requirements of App R to 10CFR50.Related Info Encl Project stage: Meeting ML20098H1881984-08-27027 August 1984 Amend 75 to License NPF-3,changing Tech Specs to Correct Errors in Surveillance Testing of Diesel Generators to Demonstrate Operability Project stage: Other ML20098H1911984-08-27027 August 1984 Safety Evaluation Supporting Amend 75 to License NPF-3 Project stage: Approval ML20132F4611985-09-26026 September 1985 Forwards List of Facility Change Requests Re Fire Protection Scheduled for Completion at End of Fifth Refueling Outage to Begin in Sept/Oct 1986.List Prioritized 25 Most Important to Nuclear Safety Project stage: Other 1982-04-08
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a TOLEDO EDISON Docket No. 50-346 n.CHAHO P. Cnots License No. NPF-3 L"".,*2 w Serial No. 731 am July 10, 1981 on I I k /
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Director of Nuclear Reactor Regulation P;
I Attention:
Mr. John F. Stolz L
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Operating Reactor Branch No. 4
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Division of Operating Reactors M'p' United States Nuclear Regulatory Commission 4
Washington, D.C.
20555 A
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Dear Mr. Stolz:
Under separate cover, we are transmitting three (3) original and forty (40) conformed copies of an application for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No.
1.
This application requests that the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes include:
1.
Changes in Section 4.7.1.2.d; 2.
Changes in Sections 3.4.2, 3.4.3, 4.4.3 and Bases; 3.
Changes in Sections 4.8.1.1.2.C.2 and 4.8.1.2; 4.
Changes in Sections 3.1.3.6, 3.2.1, 3.2.5, and Figures 3.1-3a; 5.
Changes in Section 6.5.2.2, Figures 6.2-1 and 6.2-2; 6.
Changes in Section 3.7.10.
The six attachments identify the proposed changes and their safety eva bations.
Item 1 concerns the Surveillance Requiretoents on the Auxiliary Feedwater Pump Turbine Speed Switches.
Item 2 concerns the
}od setpoint index for pressurizer electromatic relief and code safety valv es.
Item 3 concerns Surveillance Requirements for the Emergencf Diesel Generator as requested in Inspection Report 50-346/ 80-29 and load rejection capabilities.
Item 4 concerns administrative errors in f f Technical Specifications and a revised safety evaluation for Toledo f
f Edison's amendment request submitted February 11, 1980 (Serial No. 590).
gfj l
/ Gooo.oo THE TOLEDO EDlbON COMPANY EDi3ON PLAZA 300 MAOISON AVENUE TOLEDO. OHIO 43652 8107220100 810710 PDR ADOCK 05000346 P
PDR
.F Docket No. 50-346 License No. NPF-3 Serial No. 731 July 10, 1981
. Item S concerns a revision to the amendment request dated December 26, 1980 (Serial 669) which reflected the reorganization of Toledo Edison.
Item 6, which conerns the Fire Barrier Penetration is in response to Mr.
R. W. Reid's letter dated September 23, 1980 (Log No. 609) and additional information requested to complete our submittal dated December 26, 1980 (Log 669).
This amendment requests three changes of Class III type and three changes requiring no fees.
Items 4, 5, and 6 consist of technical errors and required additional information or revisions to previous submittals.
It is therefore determined to be a Class III amendment. Enclosed is a check for $12,000 as requested by 10CFR170.22.
Very truly yours, RPC: GAB Attachment pp b/2-3 cc:
DB-1 NRC Resident Inspector i
1