ML18033B686
| ML18033B686 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/03/1991 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105070044 | |
| Download: ML18033B686 (8) | |
Text
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Tenneage Vattey Aotnerity. 1101 Maraet Street, Chattanaaga.
Tenneaaee 3)C02 U,S, Nuclear Regulatory Commission ATTN; Document Control Desk Mashington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Mos. 50-260 BROWNS FERRY NUCLEAR PLANT (BFM) - REQUEST FOR AMZTIOMALINFORMATION OM TVA'S DESIGN BASELINE VERIFICATIOM PROGRAM (DBVP) PHASE XX The purpose, of this letter is to pr'ovide the information that Commissioner Rogers requested during the BFM Unit 2 Restart Commission Briefing that was held on April 23, 1991.
Specifically, the Commissioner requested a listing of the systems that make up Phase II of DBVP.
As TVA indicated during the briefing, Phase I of DBVP was camprised of those systems required for safe shutdown of the plant, as identified in Chapter 14 af BFM's FSAR.
Phase II will extend the program to include the balance of the safety related functions of systems and campanents of Uni.t 2.
The Enclosure provides the listing af the systems or portions of systems covered by Phase XX of the DBVP.
This listing cantains a description of the var'iaus functional areas within the system(s).
These systems were identified by evaluating the results of the Phase I program, reviewing the FSAR, and a review af known special events identified by separate MRC commitments.
The scope of Phase XX will be to ident.ify the safety relaied functions of these systems or portions of systems for the averall design basis of the plant including special events, operational transients and normal operations.
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COd Nd >8:81 l5 'GO 'SO U.S. Nuclear Regulatory Commission MAY 03 $8'l BROWNS FERRY'UCLEAR PLAMT (BFH) REQUEST FOR ADDITIONAL IMFORMATXOM OH TVA'S DESXGM BASELIME VERXFXCATIOH PROGRAM (DBVP) PHASE ZX There are no commitments contained in this submittal.
Zf you have any questions, please telephone Patrick P. Carier, at (205) 729-3566.
Very truly yours, TEMHESSEE VALLEY AUTHORITY E.
G. Wallace, Manager Muclear Licensing and Regulatory Affairs cc (Enclosure):
Ms. S.
C, Black, Deputy Director Project Directorate ZZ-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike, Rockville, Maryland 20852 MRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637
- Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U.S. Huclear Regulatory Commission One White Flint, North 11555 Roc'kville Pike Rockville, Maryland 20852 Mr. B. A, Wilson, Project Chief U.S. Nuclear Regulatory Commission Reg,ion II 101 Marietta Street, HW, Suite 2900 Atlanta, Georgia 30323 EB'd T98EEt'WTBET6 Ol BNISN33I l I Zll. -
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.1 of 4 S stem/Descri tion 01 Main Steam 02 Condensate Storage 03 Feedwatex 05 Extraction Steam 18 Fuel Oil 23 RHR Service Water 24 Raw Cooling Water 25 Raw Service Water S stem Mode Descri tion Open Main Steam Bypass Valves Close Main Turbine Stop Valves Upon Low Condenser Vacuum Signal.
Trip Feedwater Pump Turbines on Low Cond.
Vacuum
& High Water Level (L8) Signals Provide Turbine Stop Valve Closure Signals to Turbine Control System (System 47).
Close Main Turbine Bypass Valves Upon Low Cond.
Vacuum Signal From System 47.
Provide Hain Steam Line Pressure Signal To Turbine Control System (47).
Loss of Feedwater Heating Provide High RPV Pressure Signal for ATWS Recirculation Pump Trip.
Tripping of Feedwatex Pumps From Low Condenser Vacuum Provide High RPV Water Level (LS) Signal For Trip Of Main &
Feedpump Turbines.
Provide RPV Water Level (L2) For ATWS Recir-culation Pump Trip.Provide Hydraulic Control Signal Feedwater Pump Tuxbine Trips.
Loss of Feedwater Heating.
Loss of Feedwatex Heating Fill 7 Day Storage Tanks At Truck Fill Box To Maintain 7 Day (Long Term) Supply.
Transfer Fuel Oil Between Diesel 7 Day Storage Tanks-Short Term Supply.
0 Provide Flood Warning Provide Backup Control To RCW Pumps 1D and 3D.
Provide Backup Control To HPFP PumpsB'd
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~s BROMNS PERRY - UNIT 2 DESIGN BASELINE VERIFICATION PROGRAM PHASE II Page 2 of 4 S stem/Descri tion 26 High Pressure Fire Protection 27 Condenser Circulating Water S stem Mode Descri tion (Included in System 25)
Provide Warm Mater Channel Level Indication In MCR.
Provide Forebay Level Indication In MCR.
Provide Trip To Control Towers Lift Pumps Upon High Temperature At Discharge.
Provide Vacuum Breaking Capability (FCV-27-118A, -118B, FSV-27-117).
Provide Forebay/Warm Mater Channel Differential Level Indication In MCR.
32 Control Air Provide Compressed Gas to MSRVs To Support Event 32E.
Provide Plow Path Integrity For Supply Of Control Nitrogen To CAD Vent Path Valves 40 Station Drainage 43 Sampling and Mater guality Prevent Backflooding Through Drainage System Provide Manual Control From Backup Control Room (Outside Main Control Room).
46 Feedwater Control 47 Turbine Generator EHC Provide RPV High Mater Level (L8) Signal For Naia Turbine Trip.
Provide Turbine Stop Valve Closure Hydraulic Control Upon Low Cond.
Vacuum (20"HG).
Provide Turbine Bypass Valve Closure Hydraulic Control Upon Low Cond.
Vacuum (7"HC).
Provide Turbine Bypass Valve Opening Hydraulic Control Upon Turbine/Generator Trip.
52 Seismic Monitoring 57-3 250V DC Power Supply 57-5, 4kv Power Distribution None Provide Switchyard (500kv-161kv)
Relaying 6 Tripping Power Provide Recirculation Pump Trip Upon Signal, Provide Cooling Tower Lift Pump Trip.
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BROWNS FERRY UNIT 2 DESIGN BASELINE VERIFICATION PROGRAM PHASE EI Page 3 of 4 S stem/Descxi tion S stem Mode Descri tion 57-6 SOOkv/l6lkv Offsite Power and Miscellaneous Distribution Provide Off-Site Power To 4kv Distribution.
64 Primary Containment Provide Drywell Pressure Indication At Backup Contxol Panel.
Provide Containment Atmosphere Dilution Vent Path.
66 Off Gas 68 Reactor Recirculation Backflooding Prevention Functions Trip Recirculation Pump With Coastdown Meeting Reload Analysis Requirement.
Provide Trip Signal To Recixculation Pumps.
Provide Flow Signal TO NMS Rod Block Function.
Assure That MG-Set Speed Changes Stay Within Analyzed Limits.
69 Reactor Water Cleanup WW 77 Radwas te 79 Fuel Handling and Storage 84 Containment Atmosphere Dilution Provide Control From Remote Shutdown Panel Provide Reactor Building Floor Drain Transfer System.
Detect Flood Level In Reactor Building Using Flood I.evel Switches - Initiate Alarms In MCR.
Prevent Backflooding of Radwaste Building thru SGT Building, Off-Gas Building, and Off-Gas Stack Drains.
Provide Safe Fuel Handling Using Refuel Bridge and Equipment.
Provide Interlocks to CRD System During Fuel Movement.
Provide Safe Storage For New and Spent Fuel.
Provide Containment Venting After a LOCA.
Provide Nitrogen To The Control Aix System Appendix R.
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Page 4 oi 4 BROWNS FERRY UNIT 2 DESIGN BASELINE VERIFICATION PROGRAM PHASE II S stem/Descri tion S stem Node Descri tion 85 Control Rod drive Prevent Rod Withdrawal Provide MCR Rod Position Indication.
Provide Remote Backup Control From Outside The Hain Contxol Room Pxovide Alternate Rod Insertion (ARI) By Opening Backup Scxam Valves on Feedwater System (3} RPV Low Water Level (L2) Signal or High Reactor Vessel Pressure Signal.
92 Neutron Monitoring Provide Rod Block To The Reactox'anual Control Subsystem of CRD (System 85}.
Provide Power/Neutron Level To Monitor Condition Of The Reactor.
96 Recirculation Control None 99 Reactor Protection Provide Refuel Interlock To Reactor Manual Control System Provide Trip Signal To Recirculation Pump Motor Breakers (System 68).
Provide Instrument Power to RPS Analog Trip Units 111 Cxanes (110 Ton Refuel Floor)
Reactor Building Crane Is To Be Tied Down under Tornado Conditions With This Provision.
The Crane Must Withstand Full Design Loads (Passive) 244 Backup Control Communications Provide Communication From Local Panels For Shutdown From Outside The MCR.
303 Stxuctures Maintain Configuration Integrity Of Stxuctures Du"ing Earthquake.
Provide Protection Against The Effects Of Flooding.
Maintain Configuration Integrity Of Structures During Tox'nado.
Meteoxological MonitorinIx 7,'Rsv s'+trxAs'xF ni None ANIc NR lI I Hhl IJnAA JH APT
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