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MONTHYEARML20064N2771983-02-0808 February 1983
Forwards Addl Info Re Training for Mitigating Core Damage. Station Superintendent Receives Adequate Experience in Regular Duties Which Abrogates Need for Formal Training for Mitigating Core Damage
Project stage: Request
ML20072G0341983-03-21021 March 1983
Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Extension to 830701 Requested for Submittal of Schedule for Resolution of Issue
Project stage: Other
ML20090F6971983-06-30030 June 1983
Notifies of Postponement of Submittal of Plans & Schedules for Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump (Generic Ltr 83-10) Until 830815, Due to Delay in Receipt of Generic Rept from B&W
Project stage: Other
ML20080C1031983-08-12012 August 1983
Responds to Generic Ltr 83-10 Re Resolution of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pump. Schedule to Be Submitted by 830930,since B&W Generic Proposal Re Std Lower Loop Configuration to Be Evaluated
Project stage: Other
ML20080N9771983-10-0303 October 1983
Forwards Plan & Schedule for Resolution of NUREG-0737,Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, (Generic Ltr 83-10),per NRC 830208 Request.Operating Procedures for Pumps to Be Revised
Project stage: Other
ML20085N5701983-10-27027 October 1983
Advises of Delay in Submittal of Operating Procedures for Trip of Reactor Coolant Pumps (TMI Item II.K.3.5 & Generic Ltr 83-10).Program Reviewed in Light of Generic Ltr 83-31 Re Abnormal Transient Operating Guidelines
Project stage: Other
ML20091H9241984-05-29029 May 1984
Advises That Rept Re Resolution of TMI Action Item II.K.3.5 Automatic Trip of Reactor Coolant Pumps, in Response to Generic Ltr 83-10,will Be Submitted by 840731
Project stage: Other
ML20097C7021984-07-31031 July 1984
Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis
Project stage: Other
ML20097C6901984-09-0707 September 1984
Forwards Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis, (B&W Document 77-1152840-00) for Raised Loop Plant in Response to Generic Ltr 83-10 & TMI Item II.K.3.5
Project stage: Other
ML20207F6051986-12-29029 December 1986
Forwards Response to Generic Ltr 86-05 Re Implementation of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps, Addressing plant-specific Concerns,Including Instrumentation Uncertainties & Operator Training
Project stage: Other
ML20155G0611988-06-0909 June 1988
Advises That Implementation of NUREG-0737,Item II.K.3.5 Complete.Util 861229 Response Stated That Facility Procedures Require Reactor Coolant Pump Trip When RCS Subcooling Margin Falls Below 20 F
Project stage: Other
1983-08-12
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Text
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Docket No. 50-346 R)LEDO License No. NPF-3
!!EI!EI(IO$
Serial No. 107$
Acaam P. CRAISE Vce Pres
- dent Nxkw September 7, 1984 wisi ess-sa2i Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission
-Washingtoa, D. C.
20555 i
Dear Mr. Stolz:
This is in response to TMI Action Item II.K.3.5 " Automatic Trip of
-Reactor Coolant Pumps" Generic Letter No. 83-10 (G.L. 83-10). Toledo Edison with other members of the B&W Owners Group bave participated
.and endorse the report " Analytical Justification for the Treatment of Reactor Coolant Pumps During Accident Conditions" (B&W Document No. 77-1149091-00). This generic report addresses the treatment of reactor coolant pumps during a_small break loss of coolant accident (SBLOCA) for 177 fuel assembly raised and lower loop units. The treatment for the steam generator tube rupture events in the above report is only applicable to lower loop plants.
l Attached is a copy of "Best Estimate Steam Generator Single Double-Ended Tube Rupture Analysis" (B&W Document No. 77-1152840-00) for the raised
. loop plant. This report together with the generic report provide Toledo Edison response for the treatment of reactor coolant pumps during transients and accidents. The analysis supports manually
-tripping of reactor coolant pumps on indication of " loss of subcooling margin". This will be incorporated into our Abnormal Transient Operating Guidelines Program (ATOG). The operator training on reactor coolant pump ATOG procedures will be completed by the end of the 1984 refueling outage.
Very truly yours,
(( 5 _ -
RPC: GAB j'
mj c/25 cc: DB-1 Resident Inspector 8409170213 840907 PDR ADOCK 05000346 P
PDR l g THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 e
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