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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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TOLEDO Dc,cket No. 50-346 A Carteror Eq Cmyvy License No. NPF-3 DONALD C. SHELTON Serial No. 1542 va **m*-
f4191249 23CO June 9, 1988 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.
20555 Subj ect: Confirmation of NUREG-0737 Item II.K.3.5 Implemention (TAC No. 49662)
Gentlemen:
Teluo Edison (TED) received your letter dated May 24, 1988 (Log No. 2594),
recit -st$ng that TED advise the NRC of the date that implementation of THI Act ion Item II.K.3.5 vas completed at the Davis-Besse Nuclear Pover Station.
As indicated in the Company's response to Generic Letter 86-05 (Serial No.
1339 dated December 19, 1986) all actions necessary to implement this item are complete. The Davis-Besse procedure referenced in that response, addressing Reactor Coolant Pump (BCP) trip criteria, became effective on October 24, 1984.
In its response to Item A.1 of Generic Letter 86-05, TED advised the NFC that sixteen selected core exit thermocouples vould be upgraded to nuclear safety grade and environmentally qualified. These upgrades vill be completed during the current 5th refueling outage.
Vhile revieving the NRC Safety Evaluation attached to the May 24, 1988 letter, it was noted that Section 3.A states that the RCP vill be tripped if the indicated subcooling margin falls belov 25' F.
Please note that TED's December 29, 1986 response stated that Davis-Besse procedures require RCP trip when the Reactor Coolant System subcooling margin falls belov 20' F.
This is consistent with the Babcock & Vilcox Owner Group guidelines that require RCP trip prior to the RCS becoming saturated.
If there are any further questions, please contract R. V. Schrauder at (419) 249-2366.
Very truly yours,
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SBS:tlt cci A. B. Davis, Regional Administrator A. V. DeAgazio, DB-1 Project Manager DB-1 Resident Inspector 8806170149 C80609 PDR ADOCK 05000346 THE TOLEDO EDtSObm EDISON RAZA 300 MADtSON AVENUE TOLEDO OH10 43652
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