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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 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 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 ML20097F0811984-09-0606 September 1984 Forwards Rev 0 to Vols 1 & 2 of App R Compliance Assessment Rept Project stage: Other ML20108B4671985-02-28028 February 1985 Revises 840406 Schedule for Completing Certain Evaluations to Address Audit Findings Identified During 10CFR50,App R Audit.Fire Protection Manual Preplan Revs Scheduled for Completion by 850801 Project stage: Other 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 ML20202F2611986-07-10010 July 1986 Forwards Monthly Status Rept on Activities Re 850609 Loss of Feedwater Event.Corrective Actions on Malfunctioning Equipment & Evaluations & Repairs of safety-related Hangers & Supports Continuing.Ibew Local 245 Still on Strike Project stage: Request ML20207L9151986-11-0707 November 1986 Forwards Schedule of Corrective Actions Being Taken to Resolve Issues Raised by Insp Rept 50-346/83-16 Re Conformance W/App R.Remaining Noncompliances Will Be Resolved by Sixth Refueling Outage Project stage: Other ML20235E9601987-09-21021 September 1987 Requests Meeting W/Nrc to Discuss Util Fire Protection Program by 871030.Schedule to Establish Full Compliance W/ App R by Sixth Refueling Outage May Be Impaired Without NRC Approval of Outstanding Submittals by 871231 Project stage: Meeting 1983-03-17
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f Docket No. 50-346 TOLEDO
!!r!b!ClPd License No. NPF-3.
Serial'No.-1210 JOE VVLUAMS, JR.
Sane Vce prescers-Nucieer December 10, 1985
!E E Mr. John F. Stolz, Director PWR Project Directorate No. 6 Division.of PWR Licensing - B United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
The purpose of this letter.is to discuss Toledo Edisor.'s plans with respect to previous submittals to the NRC. These concern:
.1.
The exemption requests provided in the Appendix R Compliance Assessment Report (CAR) (Serial No. 1076) dated September 6, 1984.
2.
A Facility Operating License Amendment request (Serial No. 669) dated December 26, 1980 which dealt with several proposed fire protection technical specification modifications for the Davis-Besse Nuclear Power Station Unit No. 1.
Concerning the exemption requests, on September 6, 1984, the Toledo Edison Company (TED) submitted the Appendix R CAR which detailed the Davis-Besse Safe Shutdown Analysis and compliance to the requirements of Sections III.G, J, L and 0 of Appendix R to 10 CFR 50.
Each fire area was reviewed for compliance to Appendix R and resolutions were proposed consisting of either plant modifications, procedural modifications or exemption requests to specific Appendix R requirements. TEDS technical evaluation concluded that in certain fire areas, while not meeting the letter of Appendix R, the existing fire protection features met or exceeded the intent of the specific requirement. For these fire protection features, exemptions were requested from the specific Appendix R requirements.
Since that time, however, we have re-evaluated our position relative to Appendix R exemptions based on the following:
1.
Ongoing reviews of recent technical guidance (Generic Letter 85-01 and SECY 85-306) developed by the NRC.
2.
A more detailed review on resolving noncompliances through physical modifications rather than by exemption request.
0 9601130272 95 346 PDR ADOCK PDR i 0 (\\
0 F
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. THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
Dock 2t No. 50-346 Licznca No. NPF-3 Serial No. 1210 December 10, 1985 Page 2 In light of these changes, no further action on our pending Appendix R exemption requests is required. The results of our evaluation finaliz-ation are to be provided in a revised exemption request package prior to March 6, 1986. This submittal is consistent with our current commit-ment for providing Revision 1 to the CAR.
- With regard to the License Amendment request concerning fire protection technical specifications, on December 26, 1980, TED submitted an applica-tion for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1 (Serial No. 669). This application requested that Technical Specification sections 3.3.3.8, 4.3.3.8.2, 3/4 7.9.1., 3/4 7.9.2, 3/4 7.9.3, 3/4 7.9.4, and Tables 3.3-14, 3.7-4 and 3.7-5 be revised. We have reexamined our position and feel that it is necessary to further revise our technical specifications to ensure consistency with the existing plant con-figuration and the planned revisions for the CAR and the Fire Hazards Analysis Report (FHAR) which are scheduled for completion by March 6, 1986. We are therefore withdrawing this License Amendmenc request and will provide your office with a revised License Amendment request prior to June 1,1986.
Very truly yours, Mm
i cc: DB-1 NRC Resident Inspector J. Ulie, NRC Region III}