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MONTHYEARML19225B2461979-07-13013 July 1979
Forwards Application for Amend to License NPF-3 Revising Tech Specs to Reflect Changes Re Interim Anticipatory Reactor Trip Sys & Auxiliary Feedwater Flow Indications. Class IV Amend Fee Encl
Project stage: Request
ML15223A5321979-09-0707 September 1979
Requests Addl Info Re Upgrade of Anticipatory Reactor Trip
Project stage: Other
ML19256C7381979-10-0303 October 1979
Forwards Addl Info Re Upgrading of safety-grade Anticipatory Reactor Trip Sys (Arts),In Response to 790907 Request.One Oversize Drawing Available in Central Files
Project stage: Other
ML20213D0761979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML19257B4161979-12-20020 December 1979
Forwards Safety Evaluation Re Preliminary Design for safety- Grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Main Turbine Generator
Project stage: Approval
ML20009G0981981-07-24024 July 1981
Informs That During Next Refueling Outage in Feb 1982, Anticipatory Reactor Trip Sys Will Be Replaced W/Upgraded Sys.Revised Application Will Be Submitted
Project stage: Other
ML20032A6501981-10-21021 October 1981
Ack Receipt of 810908 Rept Re safety-grade Anticipatory Reactor Sys.Requests That Addl Info Per Encl List Be Forwarded within 14 Days
Project stage: Other
ML20033C8541981-11-25025 November 1981
Forwards Application to Amend License NPF-3
Project stage: Request
ML20033C8651981-11-25025 November 1981
Proposed Tech Specs 6.8.4,3.3.2.3,4.3.2.3 & Tables 3.3-15 & 4.3-15 Re Administrative Controls & Anticipatory Reactor Trip Sys Instrumentation.Safety Evaluation & Bases Encl
Project stage: Other
ML20033C8621981-11-25025 November 1981
Application to Amend License NPF-3,revising Tech Specs to Reflect Proposed Changes to Sys Integrity Measurements & Improved Iodine Monitoring Programs & Anticipatory Reactor Trip Sys
Project stage: Request
ML20039F5871982-01-0505 January 1982
Responds to Questions Raised at 811208 Meeting W/Nrc & Consultants Re Anticipatory Reactor Trip Sys.Proposed Channel Functional Test Will Include Pressure Switch.Light Indicating Level Bypass Will Clear When Level Bypass Clears
Project stage: Meeting
ML20041G3791982-03-0505 March 1982
Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3
Project stage: Request
ML20041G3811982-03-0505 March 1982
Application to Amend License NPF-3,allowing Rector Startup W/O Trip & Changing Tech Specs for safety-grade Anticipatory Reactor Trip Sys
Project stage: Request
ML20052H4931982-05-14014 May 1982
Safety Evaluation Re Final Design & Implementation of safety-grade Anticipatory Reactor Trip on Turbine Trip or Loss of Main Feedwater.Design Satisfies Reactor Protection Sys Safety Requirements & Criteria
Project stage: Approval
ML20054H2231982-06-15015 June 1982
Notifies That Seismic & Environ Qualification Summary Rept for Anticipatory Reactor Trip Sys Complete & Will Be Submitted by 820709
Project stage: Other
ML20054M2011982-07-0707 July 1982
Revises 791003 Response to Request for Addl Info Re Operating Bypasses & Bypass Indications,In Support of 811125 Request for Amend to License NPF-3
Project stage: Request
ML20063E2211982-07-0808 July 1982
Forwards Seismic Qualification Rept 3394-1..., Anticipatory Reactor Trip Sys Seismic Qualification Test Plan, Seismic Simulation Test Program... & Environ Qualification Rept..., in Response to NRC 820514 Request
Project stage: Other
ML20062F2651982-07-27027 July 1982
Concludes That Anticipatory Reactor Trip Sys Bypasses Classification as Operating Bypass Is Unacceptable Unless Addl Features to Alert Operator to Remove Bypasses Are Added
Project stage: Other
IR 05000346/19820191982-07-27027 July 1982
IE Insp Rept 50-346/82-19 on 820713.No Noncompliance Noted. Major Areas Inspected:Followup of Prompt Public Notification/Warning Sys
Project stage: Request
ML20065H9181982-09-29029 September 1982
Responds to Re NUREG-0737,Item II.K.2.10, Anticipatory Reactor Trip Sys (Arts). Adequate Features Available to Alert Operator to Remove Bypass When Automatic Bypass Removal Not Required
Project stage: Other
ML20066G7271982-11-15015 November 1982
Responds to Re NUREG-0737 Tech Specs (Generic Ltr 82-16)
Project stage: Other
ML20071B4701983-02-22022 February 1983
Proposed Revs to Tech Spec Re Anticipatory Reactor Trip Sys,Boration Sys Temp & Corrections to Typographical Errors in Administrative Section
Project stage: Other
ML20071B4681983-02-22022 February 1983
Forwards Proposed Tech Spec Changes Re Anticipatory Reactor Trip Sys,Boration Sys Temp & Corrections to Typographical Errors in Administration Section
Project stage: Other
ML20076F3381983-08-18018 August 1983
Forwards Application for Amend to License NPF-3 to Include Special Leak Rate Requirement for Containment Purge & Exhaust Isolation Valves
Project stage: Request
ML20076F3601983-08-18018 August 1983
Application for Amend to License NPF-3 to Include Special Leakage Test Requirement for Containment Purge & Exhaust Isolation Valves.Safety Evaluation & Significant Hazards Consideration Encl
Project stage: Request
ML20094H1521984-07-25025 July 1984
Amend 73 to License NPF-3,adding New Tech Spec Sections 3.3.2.3 & 4.3.2.3 & Tables 3.3-15 & 4.3-15 to Reflect Addition of Final Anticipatory Reactor Trip Sys
Project stage: Other
1982-03-05
[Table View] |
Text
Nx TOLEDO q
%== EDISON Docket No. 50-346 ACHAno P. CROUSE License No. NPF-3 O~
84191259-5221 Serial No. 757 A-31-202B s f d N f November 25, 1981
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Director of Nuclear Reactor Regulation fsh Attention:
Mr. J Sn F. Stolz Operating Reactor Branch No. 4
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qrg' Division.of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
Under separate cover, we are transmitt.ing (3) three original and forty (40) confomed' 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 6.8.4 2.
Changes in section 3.3.2.3, 4.3.2.3, Table 3.3-15, 4.3-15 and bases The two attachments identify the proposed changes and their safety evaluation.
Item 1 concerns Systems Integrity Measurements and Improved Iodine Monitoring Frograms.
Toledo Edison has impicmented these programs which are currently in effect.
Item 2 concerns Anticipatory Reactor Trip System (ARTS). The original submittal for-the ARTS was on July 13, 1979 (Serial 527).
On July 24, 1981 (Serial 735) we requested no further review because a revised Ogf application would be submitted. This submittal is the revised application for the upgraded ARTS System.
,5
//
8112040421 811125 PDR ADOCK 05000246 P
PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
Docket No. 50-346 License No. NPF-3 Serial No. 757 November 25, 1981 Page 2 This amendment request contains one change of Class _II Type and one revision of a previous submittal requiring no fees.
It is therefore determined to be a Class II amendment.
Enclosed is a check for $1,200 as requested by 10CFR 170.22.
Very truly yours, Y %-f RPC: GAB:sih Attachments cc: D B - 1 NRC Resident Inspector 4
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