Letter Sequence Other |
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Results
Other: ML17268A104, ML19347F660, ML20003B230, ML20010G846, ML20010G862, ML20032A736, ML20063F261, ML20065N032, ML20067D230, ML20079Q273, ML20079Q282, ML20133E265
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MONTHYEARML19257A5131979-12-28028 December 1979
Forwards Addl Response to ,Per Joint Nrc/B&W Owners Group 790913 Meeting.Addresses Noncondensible Gas Discussion & Small Break & Power Operated Relief Valve stuck-open Discussion
Project stage: Meeting
ML20003B2301981-01-30030 January 1981
Informs That Certain Mods Will Be Made to Existing Small Break LOCA Model,In Response to NRC .Revised Model Documentation Will Be Provided by 820301
Project stage: Other
ML20003B6721981-02-16016 February 1981
Submits Addl Comments on NUREG-0737,Items II.B.2 & II.K.3.30.Design Review Completed Re Plant Shielding for Spaces Outside Containment That May Be Used in post-accident Operations
Project stage: Request
ML19347F6601981-05-19019 May 1981
Responds to RW Reid Re Small Break LOCA Model to Predict Small Break Behavior.Discusses L3-1 & S-07-10D Test Prediction Comparisons.Earlier Pretest Predictions Being Reviewed & Results to Be Submitted by 810615
Project stage: Other
ML17268A1041981-05-31031 May 1981
B&W Post-Test Evaluation of Loft Test L3-1
Project stage: Other
ML20010G8621981-06-0909 June 1981
B&W Post-Test Analysis for Semiscale Test S-07-10D
Project stage: Other
ML20010G8461981-09-15015 September 1981
Forwards B&W Post-Test Analysis for Semiscale Test S-07-10D & B&W Post-Test Evaluation of Loft Test L3-1, in Response to NRC Re Small Break LOCA Model to Predict Small Break Behavior
Project stage: Other
ML20032A7361981-10-23023 October 1981
Requests That Buchholz to Eisenhut Be Added to Facility Dockets as Final Response to NUREG-0737,Item II.K.3.30 Re Small Break LOCA
Project stage: Other
ML20052A0611982-03-25025 March 1982
Summarizes NRC Views Resulting from 811217 Meeting W/B&W Owners Group Re Small Break LOCA Analysis Model & Provides Addl Info for Planning Verification Program. Model Verification Endorsed
Project stage: Meeting
ML20062M1431982-08-13013 August 1982
Responds to Requesting Schedule for Submittal of Supplemental ECCS Calculations Using Cladding Models of NUREG-0630.Calculations Will Be Submitted by 830301
Project stage: Supplement
ML20063F2611982-08-25025 August 1982
Discusses Program for Resolution of NUREG-0737,Item II.K.3.30, Revised Small Break LOCA Methods to Show Compliance w/10CFR50,App K. B&W Will Forward Description of Gerda Test Program
Project stage: Other
ML20065A8891982-09-0909 September 1982
Submits Details of Cooperative Evaluation Program,Requested at 820720 Meeting Re NUREG-0737,Item II.K.3.30, Revised Small Break LOCA Methods to Show Compliance w/10CFR50,App K. Program Will Lead to Development of Research Priorities
Project stage: Meeting
ML20065N0321982-10-19019 October 1982
Responds to Requesting Implementation Schedule for Mods to ECCS Evaluation Models.Mods Will Be Undertaken as Extension of NUREG-0737,Item II.K.3.31.Schedule Will Be Provided 60 Days After NRC Approval of Item II.K.3.30
Project stage: Other
ML20067D2301982-12-0707 December 1982
Endorses B&W Topical Repts BAW-10154P, B&W Small Break LOCA ECCS Evaluation Model & BAW-10092P,Revision 3, CRAFT-2, in Effort to Complete Small Break LOCA Methods Program Response to NUREG-0737,Item II.K.3.30
Project stage: Other
ML20023B8711983-04-0505 April 1983
Public Version of Temporary Mod Request T-7104 to Emergency Plan Implementing Procedure Ei 1300.07, Technical Support Ctr Activation. Rev 27 to Index Encl
Project stage: Request
ML20079Q2821983-05-0606 May 1983
Bounding Analytical Assessment of NUREG-0630 on LOCA & Operating Kw/Ft Limits
Project stage: Other
ML20079Q2731983-05-0606 May 1983
Forwards Bounding Analytical Assessment of NUREG-0630 on LOCA & Operating Kw/Ft Limits, Per
Project stage: Other
ML20133E2651985-07-0303 July 1985
Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 Re Small Break LOCA Evaluation Model CRAFT2 (Rev 3).CRAFT2 in Compliance W/Evaluation Criteria of 10CFR50,App K
Project stage: Other
1982-10-19
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Text
7 TOLEDO Docket No. 50-346 EDISON License No. NPF-3 Froumo p cnow a, m m.m Serial No. 945 N<**
msma va May 6, 1983 Director of Nuclear Reactor Regulation At ention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Divisio.: of Operating Reactors United States Nuc1 car Regulatory Commission Washington, D.C. 20555
Dear Mr.Stolz:
In our letter dated April 5, 1983 (Serial No. 929), Toledo Edison Provided our plan to submit supplemental ECCS calculations using the cladding models of NUREG-0630 by May 9, 1983. Attached is the results of the analysis.
The impact of NUREG-0630 for Davis-Besse Unit 1, is an additional 0.5 KW/ft reduction in LOCA limits at the 2 foot elevation.
Very truly yours, f$ P (' w w x
/T%h RPC:FYC cc: DB-1 NRC Resident Inspector i
00l 0305110437 830506 DR ADOCK 05000346 PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652
