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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
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
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
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
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
ML20041G3791982-03-0505 March 1982
Transmits Application for Amend to License NPF-3,extending Length of Fuel Cycle 3
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
1982-01-05
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TOLEDO
%ms EDISON Docket No. 50-346 name License No. NPF-3 Serial No. 819 July 7, 1982 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
On November 25, 1981 (Serial Nc. 757), Toledo Edison submitted a license amendment request, which included the safety grade Anticipatory Reactor Trip System (ARTS) for Davis-Besse Nuclear Power Station Unit No. 1.
This amendment request was revised by our March 5, 1982 (Serial No. 787) submittal.
On October 3, 1979 (Serial No. 540) Toledo Edison responded to a staff request for additional information.
Since then, operational consider-ations have dictated a need for revisions to the information contained in Attachment B of our October 3, 1979 submittal. The two revised sections should read as follows:
1.
Operating Bypasses - There are two operating bypasses. The first bypass consists of blocking the turbine generator status input when the reactor power is equal to or less than 25 percent. The bypass is automatically initiated and is automatically removed when the reactor power is above 25 percent. The bypass signals are part of the protective system and originate from the Reactor Protection System (RPS).
The second bypass relates to the main feedwater pump status input when operating the unit in Mode 2.
In Mode 3, during start up and at very low (approximately 1%) power levels, the electric motor
() )
driven start up feedwater pump is the only source of feedwater to the steam generators. At this power there is sufficient steam THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 8207120091 820707 PDR ADOCK 05000346 P
PDR
I Docket No. 50-346 License No. NPF-3 Serial No. 819 July 7, 1982 Page 2 i
produced to start a main feedwater pump.
Following a brief overlap l
of running both the start up feedpump and a main feedpump l
simultaneously, the start up feedpump is stopped. The operating bypass consists of blocking the main feedwater pump trip input to the ARTS using the Test Trip Bypass. The bypass is manually initiated under administrative control just prior to stopping the main feedpump during shutdown and removed after the main feedpump is started during unit startup. This second bypass is also used in Mode 3, 4, and 5, when the ARTS is not required to be operable.
2.
Indication of Bypasses - Initiation of the Test Trip Bypass will be continuously indicated at the system cabinets, the Station computer, and Control Room annunciator.
Initiation of the operating bypasses will aleo be continuously indicated at the system cabinets, the Station computer, and Control Room annunciator. The bypass indication is in accordance with IEEE 279, Section 4.13 " Indication of Bypasses",
if the protective action of some part of the system has been bypassed or daliberately rendered inoperative for any purpose, this fact shall be continuously indicated in the Control Room."
Very truly yours, f [YW~
RPC:FRM:TKR: lab cc:
DB-1 NRC Resident Inspector
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