Letter Sequence Meeting |
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Results
Other: ML17328B057, ML19249A376, ML19249A382, ML19317H481, ML19340D243, ML19343B503, ML19343B506, ML19350E266, ML20003D588, ML20009C888, ML20024E960, ML20069N118, ML20076H115, ML20080G331, ML20086C757, ML20132F461, ML20151H856, ML20206M021
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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
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
ML19249A3721979-07-26026 July 1979
Forwards Amend 18 to License NPF-3,safety Evaluation & Notice of Issuance & Availability
Project stage: Approval
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
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
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
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
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
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
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
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
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
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
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
ML20053E5241982-06-0202 June 1982
Safety Evaluation Supporting Requested Mods to 10CFR50 & 10CFR50.48 App R
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
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
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
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
ML20212P2741987-01-21021 January 1987
Responds to Stolz 861217 Request for Addl Info Re Fire Protection & Meeting to Discuss Issues.Fire Protection Program in Conformance W/App a to BTP Apcsb 9.5-1 as Accepted by 790726 Ser.Meeting Schedule to Be Established
Project stage: Meeting
ML20206M0211987-04-0909 April 1987
Advises That Fire Protection & Alternate Shutdown Sys Mods Required to Meet 10CFR50.48 Scheduled to Be Completed by End of Sixth Refueling Outage,Per Generic Ltr 86-10, Implementation of Fire Protection Requirements
Project stage: Other
1982-11-23
[Table View] |
Text
TOLEDO Docket No. 50-346 EDISON License No. NPF-3 JOEWILLIAMS JR.
s, va %-wwr Serial No. 1340 (4191249 2xo (419]249 5223 January 21, 1987 United States Nuclear Regulatory Commission Document Control Desk' Washington, D. C.
20555 Gentlemen:
Toledo Edison has reviewed Mr. Stolz's letter dated December 17, 1986, (Log No. 2166) transmitting a request for additional information (RAI) regarding fire protection and requesting a meeting to discuss the issues.
That letter further addresses Toledo Edison's method of compliance with Appendix A to BTP APCSB 9.5-1 which won previously accepted by the NRC in the Davis-Besse Fire Protection Safety Evaluation Report (SER) dated July 26, 1979 (Log No. 409).
In a telep'ione conversation between representatives of the NRC and Toledo Edison on January 5, 1987, it was clarified that the NRC does not intend to reopen any fire protection issues previously closed by the SER or to force costly modifications, but rather intends to address those fire protection issues not specifically mentioned by the SER.
Toledo Edison believes that the current Davis-Besse Fire Protection Program is in conformance with Appendix A to BTP APCSB 9.5-1 as accepted by the NRC SER.
Previous meetings with the NRC regarding the status of this Fire Protection Program have proven beneficial. Toledo Edison welcomes the opportunity to explain its method of compliance to Appendix A j
of BTP APCSB 9.5-1 and the extent to which this issue was previously l
reviewed and accepted by the hTC. Toledo Edison will establish a meeting schedule with Mr. A. W. DeAgazio, the Davis-Besse NRR Project Manager.
Very truly yours, W
j JW: MAL:plf j
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cc: DB-1 NRC Resident Inspector J. G. Keppler, Regional Administrator boob B701300627 870121 i
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PDR ADOCK 05000346 F
PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OH:0 43652 l
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