Letter Sequence Other |
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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
[Table View] |
Text
CCPLERAyED DI~~BUTION DE M04 STR+ 0~
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8903080122 DOC.DATE: 89/02/28 NOTARIZED: NO FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee AUTH.NAME AUTHOR AFFILIATION GRIDLEY,R.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000260
SUBJECT:
Provides corrections to TOL heater sizing criteria submitted by TVA 880923 ltr.
DISTRIBUTION CODE:
D030D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: TVA Facilities Routine Correspondence NOTES:1 Copy each to: S.Black, J.G.Partlow, B.D.Liaw, F.McCoy 05000260 S
RECIPIENT ID CODE/NAME SIMMS,M GEARS,G INTERNAL: ACRS NUDOCS-ABSTRACT 6~~
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 1578 Lookout Place FEB RS 1383 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Hashington, D.C.
20555 Gentlemen:
Docket No. 50-260 In the Matter of
)
Tennessee Valley Authority
)
BRONNS FERRY NUCLEAR PLANT (BFN) THERMAL OVERLOAD (TOL) HEATERS (TAC NO. 62260-F)
Reference:
TVA letter to NRC dated September 23,
- 1988, "BFN-Response to Request For Additional Information Overload Protection of The Motor Control Center Circuits (TAC 62260-F)"
This letter provides corrections to the TOL heater sizing criteria submitted by the referenced letter.
Since that time TVA has revised the TOL heater-sizing criteria and calculation methodology.
This change was required based on evaluations of the Safety System Functional Inspection (SSFI) observations and nuisance trip problems experienced during the motor operated valve (MOV) operability verifications.
The SSFI inspection documented inadequacies in the application of TOL heater sizing criteria and manufacturer data in the sizing calculations.
These errors,,which were subsequently documented in a condition adverse to quality report, resulted in overly conservative motor,protection and insufficient margin for MOV operational loads.
Based on indepth evaluations and discussions with MOV manufacturers, TVA has issued a Quality Information Report to specify the following criteria:
Current l.
200'/ Nominal Torque Current (141'L Full Load Current)
T~i5 ttl
> duty cycle and
< 8 minutes (not applicable for dc) 2.
Locked Rotor Current a.
ac b.
dc a.
< 15 seconds (10 seconds preferred) b.
< 10 seconds 3903030i22 390223 PDR ADOCK 05000260 P
PDC I
An Equal Opportunity Employer 30 i)o
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U.S. Nuclear Regulatory Commission FEB RS 'I%8 Use of this criteria along with proper application of manufacturer's data has resulted in larger size TOL heaters thus ensuring that motor operation is prioritized.
TVA has resized the TOL heaters and cycled those HOVs required for fuel load operations to ensure that nuisance tripping does not occur.
Additionally, TVA will revise the calculations, resize the TOLs as appropriate, and cycle the other safety related HOVs before restart.
The tracking and closure of the CAQR will ensure that the TOL heaters are properly sized and the sizing calculations are appropriately revised.
If you have any questions, please telephone Patrick P. Carier, BFN Site Licensing, at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY cc:
Hs.
S.
C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One Hhite Flint, North 11555 Rockville Pike Rockvi lie, Maryland 20852 Mr. F.
R. HcCoy, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Harietta Street, NH, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637
- Athens, Alabama 35609-2000 R. 'Cri ley, anager Nuclear Licensing and Regulatory Affairs
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