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MONTHYEARML20005B1351981-07-0101 July 1981
Responds to NUREG-0737,Item II.D.1.A Re Capability of Safety & Relief Valves to Operate Satisfactorily Under Operating & Accident Conditions.Interim Data Rept for EPRI PWR Safety & Relief Valve Test Program Sent in
Project stage: Other
ML20050B5681982-03-31031 March 1982
Advises That Evaluation of NUREG-0737,Item II.D.1 Re Testing of Pressurizer Code Safety & Power Operated Relief Valves Underway.Resolution Available for Required 820701 Submittal
Project stage: Other
ML20054L1831982-07-0101 July 1982
Responds to NUREG-0737,Item II.D.1 Re Pressurizer Code Safety & Pilot Operated Relief Valve Testing.Util Participated in EPRI Administered Safety & Relief Valve Testing Program.Evaluation to Be Submitted by 821231
Project stage: Other
ML20128N8361982-09-30030 September 1982
Performance Test Program for Increased Blowdown on Crosby 4M16 HB-BP-86 Pressurizer Safety Valve
Project stage: Other
ML20070H7671982-12-17017 December 1982
Advises That Final Evaluation Re EPRI Relief & Safety Valve Testing Per NUREG-0737,Item II.D.1, Reliability Engineering, Will Not Be Submitted Until 830131.Summary of Evaluation Submitted
Project stage: Other
ML20070T0961983-02-0101 February 1983
Forwards Rev 0 to Davis-Besse Analysis & Evaluation of Safety/Relief Valve Discharge Sys Per NRC NUREG-0737, Technical Rept,In Response to Items II.D.1.2 & II.D.1.3
Project stage: Other
ML20028G0701983-02-0202 February 1983
Forwards Response to 821227 Request for Info Re Plant Computer Sys & non-nuclear instrumentation-X Power Failure
Project stage: Request
ML20128N8071985-07-19019 July 1985
Provides Partial Response to 850607 Request for Addl Info Re NUREG-0737,Item II.D.1 Concerning Selection of Transients & Valve Inlet Conditions,Valve Operability & Analysis of Inlet & Discharge Piping
Project stage: Request
ML20137Y5621985-10-0101 October 1985
Forwards Response to Question 2 of 850719 Request for Addl Info Re NUREG-0737,Item II.B.1 Concerning Expected Blowdowns at Current Ring Settings.Actual Percent Blowdown of Safety Valves Has No Adverse Effect Upon Core Cooling
Project stage: Request
ML20138A7731985-12-0606 December 1985
Forwards Partial Response to 850607 Request for Addl Info Re NUREG-0737,Item II.D.1.Safety Valves Removed from Original Location in Valve Room to Direct Mount on Pressurizer Nozzles
Project stage: Request
1982-09-30
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Text
TOLEDO h EDISON RO(Ano P. CAOUSE
$u.5~
Docket No. 50-346 wiw ass saai License No. NPF-3 Serial No. 727 July 1, 1981 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
.This letter is in response to Item II.D.A.A of NUREG 0737, Clarification of TMI Action Plan Requirements, relating to the capability of safety and relief valves to operate satisfactorily under expected operating and accident conditions at the Davis-Besse Nuclear Power Station Unit No.
1.
By letter dated July 1, 1981, R. C. Youngdahl (Consumers Power Company) transmitted the Interim Data Report for the EPRI PWR Safety and Relief Valve Test Program. This report summarizes the test data collected to date.
The Toledo Fdison Company is following the EPRI Test Program and is bound by the schedules provided in the R. C. Youngdahl letter of December 15, 1980 and modified on July 1, 1981.
Very truly yours,
[
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DB-1 NRC Resident Inspector s
Ifo THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENL;t TOLEDO, OHIO 43652 8107060350 8107 1 PDR ADOCK OS @ 46
,P is DR
