Letter Sequence Request |
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MONTHYEARML19322D1691978-06-0606 June 1978
Notifies That Lead Engineer Assignments Designated Re B&W Instrumentation in Response to 780517 Request.Forwards Task Definitions, & Lists Target Completion Schedule & Estimated Personpower Requirements
Project stage: Other
ML20003A9241980-12-30030 December 1980
Final Version of Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater. Info Re power-operated Relief Valve Opening Probability Encl
Project stage: Other
ML20003A9161981-01-30030 January 1981
Follows Up 801230 Response to NUREG-0737.Forwards Reactor Vessel Brittle Fracture Analyses During Small Break LOCA Events W/Extended Loss of Feedwater & Info Re power-operated Relief Valve Opening Probability
Project stage: Other
ML19247E4321981-03-0303 March 1981
Provides fracture-mechanics Parametric Analysis of Overcooling Accident at Facility,In Response to Request
Project stage: Other
ML19247E4331981-04-10010 April 1981
Updates Re Safety Implications of Control Sys & Dynamic Characteristics of Nuclear Facilities.Pressurized Thermal Shock Phenomena & Control Sys Implications to Safety Have Not Been Analyzed
Project stage: Other
ML19247E4271981-04-28028 April 1981
Forwards Preliminary Assessment of Thermal Shock to PWR Reactor Pressure Vessels,In Response to 810416 Memo
Project stage: Other
ML20004B9341981-05-22022 May 1981
Contends That 810512 B&W Rept Re Reactor Vessel Brittle Fracture Concerns Combined W/Encl Description of Facility Design Features Provide Sufficient Info to Identify That Reactor Vessel Thermal Shock Issue Is Not Safety Concern
Project stage: Other
ML20030A7701981-07-20020 July 1981
Notification of 810728,29 & 30 Meetings W/B&W,Westinghouse & C-E Owners Groups in Bethesda,Md to Discuss Thermal Shock to Reactor Pressure Vessel Issue
Project stage: Meeting
ML20041C6781982-02-25025 February 1982
Responds to NRC 820104 Request for Addl Info in Response to NUREG-0737 Item II.K.2.13 Re Thermal Mechanical Rept.Small Break LOCA Will Not Result in Brittle Fracture to Reactor Vessel.Further Operator Training Unwarranted
Project stage: Request
ML20041D7681982-03-0303 March 1982
Submits Correction to Util Re NUREG-0737,Item II.K.2.13, Thermal-Mechanical Rept - Effect of HPI on Vessel Integrity for Small Break LOCA W/No Auxiliary Feedwater
Project stage: Other
1981-04-10
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Text
Docket No. 50-346 7otsoo License No. NPF-3 RCHAn0 P. CAOUSE Serial No. 786 vu prman ww-February 25, 1982 Ir@U
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Mg 5 -I Director of Nuclear Reactor Regulation g
Attention:
Mr. John F. Stolz Operating Reactors Branch No. 4 Lg 3
Division of Operating Reactors
.p. //
United States Nuclear Regulatory Commission N"
Washington, D.C.
20555 M
cn
Dear Mr. Stolz:
This is to respond to your questions in the letter to all B&W reactor plants dated January 4, 1982 concerning our submittal for NUREG-0737, item II.K.2.13 " Thermal Mechanical Report - Effect of HPI on Vessel Integrity for SBLOCA with no AFW."
Toledo Edison has made a submittal on May 22, 1981 (letter Serial No.
718) outlining the features of Davis-Besse #1 to identify that the reactor vessel thermal shock issue is not a concern requiring immediate remedial action for our facility.
Since that time, B&W has performed a specific analysis for Davis-Besse #1 using the general approach as described in BAW-1628.
It was concluded that, for at least the first 6 EFTY of operation, a 0.023 ft.2 Small Break Loss of Coolant Accident, with no loss of auxiliary feedwater and no operator action to throttle HPI, will not lead to brittle fracture of our vessel.
This is the worst limiting case identified to date.
As a result, Toledo Edison has no need to establish procedures to instruct operators to throttle HPI and maintain 100 F subcoolin;; margin following a SBLOCA with no auxiliary feedwater.
Therefore, no ?. raining has been conducted to familiarize our operators with such operations.
Very truly yours, lo%
RPC:FYC: sic cc:
DB-1 NRC Resident Inspector g
8203020453 820225 PDR ADDCK 05000346 P
PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
