Letter Sequence Request |
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Results
Other: ML18033A651, ML18033A749, ML18033A816, ML18033A821, ML18033A897, ML18033A983, ML18033B089, ML18033B191, ML20151E710, ML20151E723, ML20151Y171
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MONTHYEARML18031B0841986-12-10010 December 1986 Summary of 861119 Meeting W/Util & GE Re Review Schedules for Startup Issues.Revised Schedule,List of Attendees & List of Upcoming Meetings Encl Project stage: Meeting ML18031B1321987-01-15015 January 1987 Summary of 861210 Meeting W/Util in Bethesda,Md Re Fire Protection Program Mgt & Plant Electrical Design Review Calculations.List of Attendees Encl Project stage: Meeting ML20150C3481988-03-11011 March 1988 Summary of 880229 Meeting W/Tva Re Util Resolution of Concerns on Electrical Cable Ampacity.Meeting Agenda & Viewgraphs Encl Project stage: Meeting ML20151Y1711988-04-28028 April 1988 Submits Addl Info Re Thermal Overload,Splice Review,Fuse Program & Flexible Conduit Review.Encl 1 Describes Issues & Suppls Section III.13.0 of Nuclear Performance Plan Vol 3, Rev 1.Status of Remaining Issues from Section III Listed Project stage: Other ML20151E7231988-06-30030 June 1988 Evaluation of Browns Ferry Nuclear Plant Cable Installation Concerns Project stage: Other ML20151E7101988-07-18018 July 1988 Provides Results of Licensee Program to Resolve Cable Installation Issues Identified in Section III.13.1 of Plant Nuclear Performance Plan & Identify Corrective Actions Required for Each Plant Unit Project stage: Other ML18033A3031988-08-10010 August 1988 Forwards Request for Addl Info Re Listed Restart Issues. Response Requested by 880915 Project stage: RAI ML18033A3071988-08-10010 August 1988 Forwards Request for Addl Info Re Util 880707 Cable Ampacity Program Plan.Response Required by 880915 Project stage: RAI ML20154Q7791988-09-21021 September 1988 Forwards Response to NRC 880810 Request for Addl Info Re Electric Circuit Protection by Current Limiting Fuses, Including Design Stds & Calculation & Tabulation Sheets.W/ Two Oversize Drawings Project stage: Request ML20155B6151988-09-23023 September 1988 Responds to NRC 880810 Request for Addl Info Re Overload Protection of Motor Control Ctr circuits.W/8 Oversize Encls Project stage: Request ML18033A4451988-11-21021 November 1988 Forwards Request for Addl Info Re Electrical issues-cable Ampacity Program,Cable Installation Program,Fuse Program & Thermal Overload Program.Responses Requested by 881209 Project stage: RAI ML20235L8491989-02-15015 February 1989 Summary of 890201-03 & 06 Meetings at Site Re Electrical Cable Installation & Ampacity Issues & Action Plan for Closure.Attendance Rosters & List of Major Items Which TVA Is to Accomplish as Part of Resolution of Cable Issue Encl Project stage: Meeting ML18033A6441989-02-21021 February 1989 Confirms Agreements Reached W/Nrc During 890202 & 09 Meetings Re Electrical Cable Ampacity.Util Plans to Incorporate Div of Operating Reactors Guidelines Into Environ Qualification Program at Facility Project stage: Meeting ML18033A6511989-02-28028 February 1989 Provides Corrections to Thermal Overload Heaters Sizing Criteria Submitted by TVA .Based on in-depth Evaluations & Discussions w/motor-operated Valve Mfgs,Tva Issued Quality Info Rept to Specify Listed Criteria Project stage: Other ML18033A6831989-03-17017 March 1989 Responds to NRC Questions from 890202 Meeting Re Electrical Cable Ampacity Program Project stage: Meeting ML18033A6851989-03-21021 March 1989 Forwards Request for Addl Info on Cable Ampacity Program Plan Submitted by Util 880707 & 0930 Ltrs for Response by 890428 Project stage: RAI ML18033A7261989-04-27027 April 1989 Forwards Response to 890321 Request for Addl Info Re Electrical Cable Ampacity,Consisting of Results of Two NRC Cable Tray Simulation Cases Project stage: Request ML18033A7491989-05-11011 May 1989 Responds to Re Electrical Cable Ampacity.Item a Interpreted as Stating That Cable Does Not Have to Operate During Accident That Creates Transients in Excess of 205 F Project stage: Other ML18033A7521989-05-15015 May 1989 Provides Clarification to Sizing Criteria for Thermal Overload Heaters.Trip Setting for 200% Nominal Torque Current Is 1 Duty Cycle & 8 Minutes (Ac) Project stage: Supplement ML18033A8161989-06-28028 June 1989 Forwards List of Submittals Required of Util to Support NRC Decisions Re Restart.Util Will Be Apprised of Need for Addl Info to Resolve Technical Issues If Submittals Incomplete Project stage: Other ML18033A8211989-07-0707 July 1989 Responds to NRC Which Provided Clarification on Util Use of Div of Operating Reactors Guidelines Re Electrical Cable Ampacity.Util Does Not Intend Qualifying Cables to Guidelines Required to Operate Under Criteria B Project stage: Other ML18033A8971989-08-18018 August 1989 Describes Program Plan for Resolution of Flexible Conduit Installation Issues.Evaluation of Flexible Conduit Providing Background Info,Plan for Resolution,Outline of Acceptance Criteria & Schedule for Completion Encl Project stage: Other ML18033A9831989-10-0606 October 1989 Forwards Details & Summary of Recently Completed Testing of Cable Tray Configurations,Summary of Scope & Results of Ampacity Evaluations & Radon Cable Fill within Tray,Per NRC 890710 Request Project stage: Other ML18033B0891989-12-19019 December 1989 Requests Addl Info on Section III.13.3 of Plant Nuclear Performance Plan Re Flexible Conduit within 60 Days of Ltr Receipt Project stage: Other ML20011D6591989-12-19019 December 1989 Forwards Safety Evaluation Supporting Util Corrective Actions to Resolve Inadequacies in Electrical Design Stds for Cable Ampacity Program,Per Section III.13.2 of Nuclear Performance Plan Project stage: Approval ML18033B1911990-03-0202 March 1990 Responds to NRC for Addl Info Re Flexible Conduit.Calculation Will Be Revised to Reflect Accelerometer Displacement & Summation of Displacement W/Test Table Displacement Will Be Used to Establish Max Top of Cabinet Project stage: Other ML18033B4251990-07-10010 July 1990 Forwards Cable Installation Supplemental Rept,In Response to NRC Request During 900506 Telcon.Rept Contains Results of Walkdowns & Testing Except Work on Ongoing Cable Pullby Issue Project stage: Supplement ML20059L5741990-09-19019 September 1990 Forwards Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions,Sept 1990. Rept Revised to Clarify Cable Bend Radius & Support of Vertical Cable & Document Resolution of Jamming Issues Project stage: Supplement 1989-02-15
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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 37401 SN 1578 Lookout Place SEP 211988 U.S. Nuclear Regulatory Commission ATTN:
Document Control Oesk Hashington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-260
)
50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION,
.ECTRIC CIRCUIT PROTECTION BY CURRENT LIMITING FUSES (TAC NO. 62260-C)
This letter provides TVA's response to NRC's August 10, 1988 request for additional information on the above subject.
Included with this letter are the following documents for your review:
BFN Fuse Substitution Program control document (BF6.12)
Design standard OS-E8.1.1 Appendix C Design standard DS-E8.1.2 Appendix 0 Calculations, (ED-00281-88139) 250V DC Reactor HOV Boards 2A, 28, 2C (ED-QO268-88463) 480V Reactor MOV Boards 3A/B CAQR BFP 870175 Sample fuse tabulation sheet Schematic drawings.
45N714-2 250 VDC Reactor HOV Board 1A 45N799-10 480 V Shutdown Aux, power TVA was asked to provide the condition adverse to quality reports (CAQRs) written to document the inadequate fuses identified during the plant walkdowns. CAQR BFP 870175 was written to document the condition that the requirements of updated design standards were not reflected in the BFN fuse program.
To resolve this condition. BFN is generating calculations using updated design standards to specify the appropriate fuses for each application.
In the conclusions and recomendations section of these calculations, a pass / fall status is given for each fuse.
This status indicates that the fuse specified in the calculation is or is not the same fuse that was previously selected.
3DN 8810040061 880921 FDR ADoCK 05000259 P
PDC f
An Equal Octort;nity E mploy er 4
________________ _ SEP 211988 U. S. Nuclear Regulatory Commtsslon The criteria for sizing the fuses is found in section 2 of the calculations.
A representative sample of schematic diagrams are provided with the calculations.
These schematics are typical of the circuits evaluated.
Please refer any questions or comments concerning this submittal to Patrick Carter at (205) 729-2689.
Very truly yours, TENNESSEE VALLEY AUTHORITY R.GridYey,Manae'"
Nuclea'r Licensing and Regulatory Affairs cc (Enclosure):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Olvision U.S. Nuclear Regulatory Commission One White Flint, North
'1555 Rockville Pike Rockville, Maryland 20852 Mr. F. R. McCoy, Assistant Director for Inspection Programs TVA Projects 01 vision U.S. Nuclear Regulatory Commission Region II 101 Harletta Street, NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611
._