Letter Sequence Other |
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MONTHYEARML19259D1761979-05-16016 May 1979
Anticipatory Trip Functions for 177 Fuel Assembly Plants
Project stage: Other
ML19225B2461979-07-13013 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
ML15223A5311979-09-0707 September 1979
Notifies of Review of Responses to IE Bulletin 79-05B. Requests Addl Info Re Proposed Design Description & Implementation Schedule for safety-grade Anticipatory Reactor Trip
Project stage: Approval
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
ML19259D1741979-10-0909 October 1979
Forwards Anticipatory Trip Functions for 177 Fuel Assembly Plants
Project stage: Other
ML19257A9711979-12-20020 December 1979
Forwards Safety Evaluation Approving Preliminary Design for safety-grade Anticipatory Reactor Trip on Loss of Feedwater & Turbine Trip.Requests Addl Info for Final Design Approval
Project stage: Approval
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
ML20213D0721979-12-20020 December 1979
Forwards Safety Evaluation Approving Preliminary Design for safety-grade Anticipatory Reactor Trip on Loss of Feedwater & Turbine Trip.Requests Addl Info for Final Design Approval
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
ML20214J2801979-12-20020 December 1979
Safety Evaluation Re Preliminary Design for Upgrading Present control-grade Anticipatory Reactor Trip Sys for Loss of Main Feedwater & Turbine Trip to safety-grade
Project stage: Approval
ML20214J2911979-12-20020 December 1979
Safety Evaluation Re Preliminary Design for safety-grade Anticipatory Reactor Trips on Loss of Main Feedwater &/Or Turbine Trip
Project stage: Approval
ML19326D9901980-07-21021 July 1980
Notifies That Equipment Being Added to Reactor Protection Sys Cabinets Is of Sufficient Mass as to Require New Seismic Analysis of Cabinets.Analysis Requires Approx 20 Wks.Info Will Be Provided in Time to Allow for Final Design Approval
Project stage: Other
ML20009B0071981-07-0303 July 1981
Revises Submittal Date to 810814 for Final Design for Safety Grade Anticipatory Reactor Trip & Design Info for Safety Grade Initiation & Flow Indication of Auxiliary Feedwater Sys,Per NUREG-0737,TMI Items II.E.1.2 & II.K.2.10
Project stage: Other
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
ML20010G0141981-09-0808 September 1981
Forwards B&W Rept Auxiliary Feedwater Sys & 36 Oversize Drawings,Per 810703 Commitment to Submit Final Design Info Re NUREG-0737,Items II.K.2.10 & II.E.1.2.Aperture Cards Are Available in PDR
Project stage: Other
ML20031G5731981-10-19019 October 1981
Responds to Requesting Addl Info Safety Grade Anticipatory Reactor Trip.Forwards Procedure I-111,Revision 9, Reactor Protection Sys Channel Calibr & Procedure I-108A,Revision 17, Reactor Protection Sys Channel a Test
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
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
ML20033C8541981-11-25025 November 1981
Forwards Application to Amend License NPF-3
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
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
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
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
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
1981-07-24
[Table View] |
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h, OCTOBER 21 z.31 8
g DISTRIBUTION:
ORB #4 Rdg Gray File Docket File DEisenhut NRC PDR JStolz L PDR RIngram TERA DGarner NSIC H0rnstein Docket Ho. 50-346 EBlackwood OELD AE0D IE-3 lir. Richard P. Crouse ACRS-10 Vice President, Nuclear Toledo Edison Company Edison Plaza - Stop 712 300 Madison Avenue Toledo, Ohio 43652
Dear !!r. Crouse:
In our review of your September.8,1981, submittal regarding the safety grade Anticipatory Reactor Trip System for Davis-Desse, we have_'.dentified the need for further infomation. This information is identified in,the enclosure. We are working toward a closeout of this issue by the end of November and there-
- ore request that responses be forwarded to _us,eithin 14 days of receipt of t.his letter.
If there are any difficulties meuing this request date, please contact your Project Manager.
Sincerely,
' O RI G u a h u x c u r.D s i JOHNF. STOL;"
John F. Stolz, Chief Operating < Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
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Toledo Edison Company ecw/ enclosure (s):
Mr. Donald H. Hauser, Esq.
U.S. Nuclear Reg *ulatory Commission The Cleveland tie.ctric Resident Inspector's Office Illuminating Company 5503 N. State Route 2 P. O. Box 5000 Oak Harbor. Ohio 43449 Clevelar.d. Ohio 44101 Mrs. Julia Baldwin, Librarian Gerald Charnoff, Esq.
Government Documents Co,11ection Shaw, Pittman, Potts William Carlson Library and Trowbridge University of Toledo 1800 M Street, N.W.
2801 W. Bancroft Avenue Washington, D. C.
20036 Toledo, Ohio 43606 Leslie Henry, Esq.
' : Fuller, Seney, Henry and Hodge 300 Madison Avenue Toledo, Ohio 43604 Regional Radiation Representative EPA Region V fir. Robert B. Boi Lum
/
230 South Dearborn Street Babcock & Wilcox Chicago, Illinois 60604 Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road
,Bethesda, Maryland 20014 Ohio Department of Health ATTil:
Radiological Health Program Director P. O. Box 118
' President, Board of County Colurchus, Ohio 43216 l
Commissioners of Ottawa County Port Clinton, Ohio 43452 Attorney Gene'ral Department of A^torney General 30 East Broad Street Columbus, Ohio 43215 l
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Harold Kahn, Staff Scientist P~ower Siting Commission 361 East Broad Street Columbus, Ohio 43216 I
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Mr. Ted Myers Manager, Nuclear Licensing Toledo Edison Company Edison Plaza 300 Madison Avenue Tolado;,0hio 43652
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Encloaure REQUEST FOR A.iDITIONAL INFORMATION
~
SAFETY-GRADE ANTICIPATORY I
REACTOR TRIP Off LOSS OF MAIN t
FEEDWATER AND TURBINE TRIP t
i FOR DAVIS-BESSE UtlIT NO. 1 2
Relating to your September 8,1981 (Serial 744),.you are requested to provide:
1.
Electrical schematic; and control panel layout diagrams which show the locations cf the RESET and BLOCK switches, now these switches are wired, and the interconnections between these switches and the anticipatory l
reactor trip system (ARTS) logic shown on Figure 1.
2.
Electrical schematics whien show which contacts of the ARTS relays-(KA, KE, etc. shown on Figure 1) are used in the control rod drive breaker trip string and how these contacts are wired into the trip string.
3.
.'. RPS check-out procedure which will demonstrate the operability of the new trip circuitry.
4.
A discussion on whether the ARTS design permits a channel functional test which includes the operability of the pressure sensors (not calibration or set point verification) during plant operation.
If pressure sensors are not included in the channel functional test, discuss the extent to which the channel functional test capability demonstrates the operability of the system.
5.
A description of the isolators (including ratin ) shown on Figure 1.
1
.
