ML20046A115
| ML20046A115 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/19/1993 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9307260212 | |
| Download: ML20046A115 (22) | |
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' JUL 191993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk
-Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-259-~
Tennessee Valley Authority
)
50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - RESTART TEST PROGRAM (RTP) UPDATE FOR UNITS 1 AND 3 In reference to a TVA [[letter::05000296/LER-1992-006-03, :on 921203,3D EDG Inadvertently Started & EDG Ground Alarm Received in Control Room.Caused by Short Circuit in Test Leads Connected to EDG Start Circuit.Faulty Test Leads Replaced|letter dated December 28, 1992]], " Update'of Restart Test Program (RTP)-Submittal for Units l'and 3," TVA committed to provide NRC with an update of the evaluations for-the remaining baseline test requirement documents!(BTRD). On June 29, 1993, the' evaluations on the remaining forty-three'BTRD vere completed.
The table of the enclosure has been revised to reflect the outcome of the BTED' evaluations. Changes to the table are highlighted for your convenience. Pursuant to a conversation on July 14, 1993, with Joseph F.
Williams of the.NRR staff, the due date^for this-submittal was extended to July 21, 1993.
-If-you have any questions, please telephone me at (205) 729-2636..
o Sincerelyi tJ SW
- Manager of Site-Licensing Enclosure cc: See page 2.
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' U.S. Nuclear Regulatory Commission JUL iL9.1993 Enclosure cc (Enclosure):
j NRC Resident Inspector Browns Ferry Nuclear Plant t
Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. V. Crlenjak,-' Project Chief i
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900
' i I
Atlanta, Georgia 30323 Mr. Joseph F. Williams.
U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville,' Maryland 20852 s y
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ENCLOSURE Page 1 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (UFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
)
SYSTEM MODE DESCRWTION UNIT 2 TEST TEST CGMMENTS MODE FOR U3 00141 PROVIDE MAIN TURBINE STOP VAi,VES < 90% OPEN TRIP 2 BFN-RTP-001 YES SIGNAL TO REACTOR PROTECrlON SYSTEM (99) 00142 PROVIDE M AIN STEAMLINE ISOLATION VALVE < 90% OPEN 2-BFN-RTP-001 YES TRIP SIGN AL TO REACTOR PROTECTION SYSTEM (99) 001-03 CLOSE MAIN STEAMLINE ISOLATION VALVES ON PRIMARY 2-BFN-RTP401 YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGNAL.
001-04 CLOSE MAIN STEAM DRAIN LINE VALVES ON PRIMARY 2-BFN R'i P-OOl YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGNAL 001-05 OPEN M AIN TURBINE STEAM BYPASS VALVES ON TURBINE 2-BFN RTP-047 YES CONTROL SYSTEM (47) TURBINE TRIP SIGN AL 001-06 CONTROLLED M ANUAL DEPRESSURIZATION OF REACTOR 2-BFN-RTP-001 YES PRESSURE VESSEL (RPV) BY OPENING AUTOM ATIC DEPRESSURIZATION SYSTEM (ADS) SAFETY RELIEF VALVES (SRVS).
001-07 OPEN SAFETY RELIEF VALVES (SRVS) ON HIGli REACTOR 2-BFN-RTP-001 YES PRESSURE TO PROVIDE RPV PRESSURE RELIEF.
001-08 AUTO OPENING OF ADS SRVS UPON ColNCIDENT SIGNALS OF 2 2-BFN-RTP 001 YES CORE SPAY (CS) PUMPS (75) OR I RESIDUAL HEAT REMOVAL (RHR) PUMP (74) AND ErrilER LOW WATER LEVEL (LWL)
(Ll&lJ FROM SYS 03) lilGil DRYWELL (DW) PRESSURE (SYS 64)
AND TIME DELAY OR LWL (LI FROM SYS 03) AND !!!Gil DW i
PRESSURE BYPASS TIME DELAY.
001-09 CLOSE M AIN TURBINE STOP VALVES UPON TURBINE CONTROL 2-BFN-RTP-047 YES SYSTEM (47) DIVERSION OF HYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGN AL (SYSTEM 47).
l 001-11 MANUALLY DEACTIVATE NON-ADS SRVS AND M AIN STEAM 2-BFN RTP-001 YES ISOLATION VALVE (MSIV) TEST CIRCUITS TO PREVENT INADVERTENT RPV DEPRESSURIZATION AND LOSS OF COOLANT.
001 12
' PROVIDE II)W PRESSURE SIGNAL (IN M AIN STEAM LINE AT 2-BFN-RTP-001 YES
'l TURBINE) TO PRIM ARY CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION LOGIC (RUN MODE).
001 13 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 001-14 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN RTP-064A -
NO SEE NOTE 2 I
001-15 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BF N-RTP-065 NO SECONDARY CONTAIN--
J MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 001 16 CLOSE EEEDWATER PUMP TURBINE STOP VALVES (TO TRIP 2-BFN-RTP-003 B YES FEEDWATER TURBINE) ON LOSS OF HYDRAULIC PRESSURE DUETO ENDtGlZATION OF FEEDWATER SYSTEM SOLENO!D.
IL
i ENCLOSURE Page 2 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (HFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP) l SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMEtGS MODE FOR U3 CDI 17 PROVIDE MAIN STEAM LINE lilG}I FLOW AND HIGH STEAM 2-BFN-RTP-001 YES TUNNELTEMPERATURE SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION C01-21 PROVIDE M AIN TURBINE STOP VALVE CLOSURE POSITION 2-BFN-RTP-047 YES SIGNAlE TO TURBINE CONTROL SYSTEM (4?) WHICH INrrlATES OPENING OF MAIN TURB!NE BYPASS VALVES.
C01-22 CLOSE M AIN TURBINE BYPASS VALVES UPON TURBINE 2-BFN-RTP-001 YES CONTROL SYSTEM (47) DIVERSION OF liYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGN AL (SYSTEM 47).
001-23 PROVIDE >30% TURBINE FIRST STAGE PRESSURE INTERLOCK 2-BFN-RTP-001 YES SIGNAL TO REACTOR PROTECTION SYSTEM (99) FAII S AFE LOGIC.
001-24 PROVIDE M AIN STF AM LINE PRESSURE SIGNAL TO TURBINE 2-BFN-RTP-001 YES CONTROL SYSTEM i. i FOR OPERATION OF M AIN TURBINE BYPASS VAL /ES.
001-25 MANUALLY CLOSE MAIN STEAMLINE ISOLATION VALVES 2-BFN-RTP-001 YES (MSIVS) AND MAIN STEAM DRAIN LINE VALVES.
00246 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A W}lOLE DURING UNrr 2 TESTING 002-08 PROVIDE PRIMARY CONTAINMENT BOUND ARY.
2-BFN-RTP-064A NO SEENGTE2 00341 PROVIDE If!Gli REACTOR VESSEL PRESSURE TRIP SIGNAL TO 2-BFN-RTP-003 A YES REACTOR PROTECTjoN SYSTEM (99) FAIL-SAFE LOGIC.
003-02 PROVIDE RPV LOW WATER LEVEL (L3) TRIP SIGN AL TO 2-BFN-RTP-003A YES REACTOR PROTECTION SYSTEM (99).
i 003-03 PROVIDE RPV LOW WATER LEVEL (L2) SIGN AL TO IIPCI 2-BFN-RTP-003 A YES SYSTEM G3).
003-04 PROVIDE RPV LOW WATER LEVEL (L3) PERMISSIVE SIGNAL TO 2-BFN-RTP-003 A YES MAIN STEAM SYSTEM (01) FOR ADS.
003-05 PROVIDE RPV lilGil WATER LEVEL (L8) SIGN AL TO REACTOR 2-BFN-RTP-003 A YES CORE ISOLATION COOLING (RCIC) SYSTEM GI) AND/OR HIGli PRESSURE COOLANT INJECrlON (11PCI) SYSTEM (73) FOR TURBINE TRIP.
003-06 PROVIDE HIGli REACTOR VESSEL PRESSURE 3IGN AL TO 250 2-BFN-RTP-003 A YES ANTICIPATED VDC SYSTEM (573) TO OPEN RECIRCULATION PUMP M/G SCT 2-BFN-RTP4M8 TRANSIENT WrrilOUT DRIVE MOTOR BREAKER 3 FOR TRIP OF RECIRCULATION PUMPS SCR AM WAS TESTED AND TO CONTROL ROD DRIVE (CRD) SYSTEM (85) TO INrrlATE BY RTP-068 ALTERNATE ROD INSERT.
003-07 PROVIDE LOW CONDENSER VACUUM SIGNALTO ENERGlZE 2-BFN-RTP-003B YES 1
REACTOR FEEDWATER SYSTEM (3) SOLENOID TO CLOSE M AIN i
STEAM SYSTEM (1) FEEDWATER TURBINE STEAM SUPPLY STOP
)
VALVES.
00348 PROVIDE RPV WATER LEVEL INDICATION AT BACKUP 2-BFN-RTP-003A YES CONTROL CENTER.
1 i
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. ENCLOSURE Page-3 of 20.
TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
[
SYSTEM MODE DESCRIFTION UNIT 2 TEST TEST COMMENTS MODE FOR i
U3 003-09 PROVIDE LOW REACTOR PRESSURE PERMISSIVE SIGNALS TO 2-BFN-RTP4K)3 A YES CORE SPRAY SYSTEM G5)10R OPENING OF LOW PRESSURE 4
EMERGENCY CORE COOLING SYSTEM (ECCS) INJECTION VALVES ANDTO RliR SYSTEM G4) FOR CLOSING OF RECIRCULATION PUMP UlSCHARGE VALVES.
003-10 PROVIDE RPV LOW WATER LEVEL (L1) SIGN AL TO PRIMARY 2-BFN-RTP4)D3A YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION LOGIC.
003-11 PROVIDE RPV lilGil WATER LEVEL (L8) SIGN AL TO 2-BFN-RTP-003 A YES FEEDWATER CONTROL SYSTEM (46) FOR M AIN TURHINE AND REALTOR FEEDWATER PUMP TURBINETRIPS.
C03-12 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 003-13 PROVIDE PRIMAR,Y CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 f
003-14 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNTT 2 TESTING 003-15 PROVIDE RPV LOW WATER LEVEL (L2) SIGN AL TO 250 SYSTEM 2-DFN-RTP-068 YES (573) TO OPEN RECIRCULATION PUMP MOTOR GENERATOR (M/G) SET DRIVE MOTOR BREAKERS FOR TRIP OF RECIRCULATION PUMPS AND TO CRD SYSTEM (85) TO INITIATE ALTERNATE ROD INSERT.
p 003-16 PROVIDE RPV PRESSURE INDICATION IN MAIN CONTROL 2-BFN-RTP-003 A YES ROOM.
003-18 CLOSE MAIN STEAM SYSTEM (1) FEEDWATER TURBINE STEAM 2-DFN-RTP-003 A YES-SUPPLY STOP VALVES ON LOW CONDENSER VACUUM OR RPV 111011 WATER LEVEL (LH) SIGNALS.
CD3-19 INDICATE RPV WATER LEVEL IN TIIE CONTROL ROOM.
2 BFN-RTP-003A YES l
003-20 PROVIDE RPV LOW WATER LEVEL (L2) SIGNAL VIA RIIR 2-BFN-RTP-003 A YES i
SYSTEM G4) FOR AUTOMATIC RCIC SYSTEM 01) INITIATION.
C03-21 PRO'llDE RPV LOW WATER LEVEL (LI) SIGNAL TO M AIN 2-BFN RTP-003A YES STEAM SYSTEM (1) FOR ADS.
003-22 PROVIDE RPV LOW WATER LEVEL (LI) SIGNAL TO CORE SPR AY 2-BFN-RTP 003 A YES SYSTEM 03) FOR CORE SPRAY RIIR-LOW PRESSURE COOLANT INIECTION (LPCI) 04) AND DIESEL GENERATOR (82) START.
003-23 PROVIDE RPV PRESSURE INDICATION AT BACKUP CONTROL 2-BFN-RTP 003 A YES CENTER.
003-25 TIIE UPPER LIMTT ON TEEDWATER FLOW MUST RESTRICT NONE YES FLOW TO ABOUT 130% (RELOAD ANALYSIS ASSUMPTION).
0 % 26 1% OVIDE 2/3) CORE COVERAGE PERMISSIVE SIGN AL TO.RliR NONE YES SYSTEM FOR CONTAINMENT COOLING MODES 003-27 PROVIDE REACTOR VESSEL filGli WATER l LEVEL'(L8) SIGNAL NONE YES.
TO RCIC SYSTEM GI) TURDINE TP.lP
(
ENCLOSURE Page 4 of 20 TABLE i
CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (UFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRUTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 1
010 01 PROVIDE PATH FOR M AIN STEAM SYSTEM (1) SRVS STEAM 2-BFN-RTP-003 A YES TEST VACUUM
)
SLOWDOWN TO PRIM ARY CONTAINMENT SYSTEM (64)
BREAKER VALVES SUPPRESSION POOL.
ONLY 010-02 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 012-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT % AS TESTED AS A WiiOLE DURING UNrr 2 TESTING P
01242 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SE2 NOTC 2 01841 PROVIDE DIESEL FUEL OIL TO DIESEL GENERATOR SYSTEM 2-BFN-RTP-082 NO UNIT 2 TEST (82).
ADEQUATELY SATISFIED REQUIREMENT 018-02 M AINTAIN 7 DAY (LONG TERM) SUPPLY OF FUEL OIL IN 2-BFN-RTP-082 NO UNrr 2 TEST STORAGE TANKS IN SUPPORT OF DIESEL GENERATOR SYSTEM ADEQUATELY (82).
SATISFIED REQUIREMENT 01843 MAINTAIN SIIORT TERM SUPPLY OF FUEL O!L IN 7 DAY 2-BFN-RTP-082 NO TESTS WERE STORAGE TANKS BY TRANSFERRING FUEL OIL BETWEEN PERFORMED IN AVAILABLE FUEL OIL STORAGE TANKS IN SUPPORT OF DIESEL ACCORDANCE WITH GENERATOR SYSTEM (82).
UN!T 2 RTP TEST 2-BFN-I RTP-082 REV. O AND REV.1. TilESE TESTS -
WERE REVIEWED AND k
FOUND TO BE ACCEITABLE TO VERIFY THE SYSTEM MODE REQUIREMENTS FOR UNrr 3 RESTART.
023-01 PROVIDE COOLING WATER TO RHR SYSTEM (74) IIEAT 2-BFN RTP-023 YES EXCHANGERS.
023-03 PROVIDE COOLING WATER TO EECW SYSTEM (67) UPON START 2-BFN-RTP-023 YES OF THE RESIDUAL HEAT REMOVAL SERVICE WATER (RilRSW)
PUMPS.
023-04 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 02346 PROVIDE WilEELER LAKE LEVEL INDICATION / ALARM AT 2-BFN-RTP-023 NO UNIT 2 TEST SATISFIES ELEVATION 558 FEET AND RISING AS WELL AS AT ELEVATION REQUIREMENTS 564 FEET AND RISING.
023-07 PROVIDE PRIMARY CONTAINMENT BOUNDARY. CLOSE RHR 2-BFN-RTP-023 NO UNrr 2 IEST SATISFIES SERVICE WATER SYSTEM VALVES 1-FSV-23-56 AND 2-FSV-23-56 REQUIREMEWS. SEE ON Rl!R SYSTEM (74) UNrr CROSS-TIE VALVES OPEN POStrlON NME.2 SIGNAL.
1
ENCLOSURE Page 5 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP) i SYSTEM MODE DESCRIFrlON UNIT 2 TEST TEST COMMENTS MODE FOR U3 023-08 M ANUAL RHRSW SYSTEM OPERATION TO PROVIDE COOLING 2-BFN-RTP423 YES WATER TO RilR SYSTEM (74) IIEAT EXCHANGERS FROM OUTSIDE OF M AIN CONTROL ROOM.
023-09 PROVIDE SUMP PUMP CAPABILrrY 2-BFN-RTP423 NO UNIT 2 TEST SATISFIES REQUIREMENTS 024-01 PROVIDE SECOND ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 02442 PROVIDE PRESSURE BOUNDARY INTEGRITY TO EECW SYSTEM 2-BFN RTP-024 YES (67).
024-G4 PROVIDE A FLOW PATH T!! ROUGH.UNTIS 1 AND 2 CONTROL 2-BFN-RTP-031 A NO UNrr 2 TTST SATISFIES RQOM CHILLFRS REQUIREMENTS 02M5 PROVIDE RCW SUPPLY HEADER LOW PRESSURE PERMISSIVE 2-BFN-RTP-024 NO UNTI 2 TEST SATISFIES SIGNAL TO 4-KV POWER DISTRIBUTION SYSTEM (575) FOR REQUIREMENTS i
STARTING OF RHRSW SYSTEM (23) PUMPS.
024-06 PROVIDE MANUAL CONTROL FROM OUTSIDE THE M AIN 2-BFN-RTP-BUC NO UNrf 2 TEST $ATISFIES CONTTiOL ROOM OF RCW PUMPS ID AND 3D TO PREVENT REQUIREMENTS OVERLOADING OF DIESEL GENERATORS (SYSTD182).
025-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECOND ARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 025-04 PREVENT AUTOMATIC START OF HIGH PRESSURE FIRE 2-BFN-RTP-025 NO UNIT 2 TEST SATISFIES PROTECTION SYSTEM (26) PUMPS (LOCK-OUT) TO PREVENT REQUIREMENTS OVERLOADING Tile DIESEL GENERATORS (SYSTEM 82).
02545 PREVENT START OF HIGH PRESSURE FIRE PROTECrlON 2 BFN-RTP-BUC NO UNrr 2 TEST SATISFIES SYSTEM (26) PUMPS (FROM OUTSIDE Tile M AIN CONTROL RE.QUIREMENTS ROOM) TO PREVENT OVERLOADING THE DIESEL GENERATORS (SYSTDi 82).
026-01 SUPPORT SECONDARY CONTAINMENT FUNCrlON.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 026y2 KERIFY HIGifPRESSURE FIRE PROTECTION (HPFP) 2cBFf6RTP-025 NO UNIT 2 TEST SATISFIES AUTOM ATid-START INHIBTT LOGIC REQUIREMENTS 027-01 PROVIDE WARM WATER CH ANNEL LEVEL INDICATION IN THE 2-BFN-RTP-027 NO MODE DELETED FROM M AIN CONTROL ROOM.
BASELINETEST l
REQUIREMENT DOCUMENTS (UTRD) 027-02 PROVIDE FOREBAY LEVEL INDICATION IN THE MAIN CONTROL 2-BFN-RTP427 NO MdDG DELETED FROM ROOM FOR MANUAL ACTIONS TO REDUCE POWER OR IF BTRD NECESSARY INrflATE SCRAM.
I
4 ENCLOSURE Page 6 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNfr 2 TEST TEST COMMENTS s
MODE FOR i
U3 027-03 PROVIDE COOLING TOWER LIIT PUMP DISCHARGE WATER NONE YES MODE (027-03)
HIGH TEMPERATURE SIGN AL TO 4-KV POWER DISTRIBtfrlON DESCRIFFION WILL BE SYSTEM (575) FOR TRIPPING OF THE CORPESPONDING SATISFIED DURING COOLING TOWER LIFT PUMP, PERFORMANCE OF RTP 3-RTP-027-C.
027-04 PROVIDE MANUAL VACUUM BREAKING CAPABILrrY TO 2-BFN-RTP-027 YES MODE (027-04)
PREVENT BACKFLOW OF COOLING TOWER WARM WATER DESCRIPTION WILL BE DISCHARGE INTO THE FOREBAY UPON TRIP OF THE CCW SATISFIED DURING PUMPS.
PERFORMANCE OF RTP 34tTP-027-C.
027-05 PROVIDE FOREBAY / WARM WATER CH ANNEL DIFFERENTIAL 2-BFN RTP-027 NO THis MODE DELETED LEVEL INDICATION IN THE MAIN CONTROL ROOM.
BY Cil ANGE NOTICE (CN-2) TO 2/3-BFN-BTRD-027.
029 01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WiiOLE DURING UNIT 2 T'/ STING 030-01 PROVIDE VENTILATION TO UNITS I AND 2 DIESEL GENERATOR 2-BFN-RTP-030 No UNTT 2 TEST SATISFIES BUILDING.
REQUIREMENTS 030-02 PROVIDE VI.NTILATION TO UNrr 3 DIESEL GENERATOR 2-BFN-RTP-030 NO UNrr 2 TEST SATISFIES
- BUILDING, REQUIREMENTS i
030-03 PROVIDE VENTILATION TO 250V BATTERY ROOM 3EB IN THE 2-BFN-RTP-030 NO UNrr 2 TEST S ATISFIES UNIT 3 DIESEL GENERATOR BUILDINGTO PREVENT A BUILDUP REQUIREMENTS OF HYDROGEN GAS DURING BATTERY CHARGING.
031 01 ISOLATE SUPPLY DUCTS AND SUPPLY PRESSURIZED FILTERED 2-BFN-RTP-03 t B
' NO UNrr 2 TEST SATISFIES OUTDOOR AIR TO MAIN CONTROL ROOM ON PRIMARY REQUIREMEN'rS CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGN AL OR
]
RADIATION MONITORING SYSTEM (90) INITIATION SIGNAL.
031-02 PROVIDE VENTILATION TO REACTOR BUILDING BOARD ROOMS 2-BFN-RTP-031 B NO UNIT 2 TEST SATISFIES AND CONTROL BAY MECllANICAL EQUIPMENT ROOMS.
REQUIREMENTS l
031 03 PROVIDE RECIRCULATION AIR COOLING TO REACTOR 2-BFN-RTP-031 B NO UNIT 2 TEST SATISFlES
]
BUILDING BOARD ROOMS.
REQUIREMENTS 031-04 PROVIDE VEPTTILATION.AND AIR CONDITIONING TO UNIT 3 2-BFN-RTP-031B NO UNIT 2 TEST S ATISFIES DIESEL GENERATOR BUILDING BOARD ROOMS.
REQUIREMENTS 031-05 PROVIDE RECIRCULATION AIR CONDITIONING TO CONTROL 2-BFN-RTP-031B NO UNrr 2 TEST SATISFIES ROOMS AND AUXILIARY INSTRUMENT ROOMS.
REQUIREMENTS I
031-06 PROVIDE VENTILATION TO BATTERY ROOMS.
2-BFN-RTP-031 B NO UNrr 2 TEST SATISFIES REQUIREMENTS 031 08 PROVIDE MANUAL LINEUP OF IIEATING, VENTING & AIR 2-BFN-RTP4131 A NO UNIT 2 TEST SATISFIES CONDITIONING (HVAC) EQUlrMENT %Tril TOTAL LOSS OF REQUIREMENTS CONTROL AIR.
'l l
.~
ENCLOSURE Page 7 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BIW)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 P
031-09 PROVIDE SECONDARY CONTAINMENT BOUNDARY, 2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING _
032-01 PERFORM ISOLATION ACTION (S) UPON RECEIVING PRIMARY 2-BFN RTP-032 YES COWAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNALS.
032-02 PROVIDE COMPRESSED AIR TO MAIN STEAM SYSTEM (01) ADS 2-BFN-RTP-001 YES SAFETY RELIEF VALVES (SRVS).
032 03 PROVIDE COMPRESSED AIR FOR CLOSURE OF MAIN STEAM 2-BFN-RTP-001 YES ISOLATION VALVES (SYSTEM 01),
t 032-04 PROVIDE COMPRESSED AIR TO EQUIPMENT ACCESS LOCK 2 BFN-RTP-032 NO UNfr 2 TEST SATISFIES SEAIJ TO PROVIDE SECONDARY CONTAINMENT BOUNDARY.
REQUIREMENTS 03245 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 032-06 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING (r2-09 VERIFY FLOW PATH INTEGRITY FOR ' CONTAINMENT NONE FO POST MOD TESTING ATMOSPilERE DILUTION (CADiNITROGEN TO THE. TORUS.TO (PMT) FOR DCN REACTUR BLDG VACUUM BREAKER VALVES W17933 A SATISFIES TIIIS REQUIREMENT 033-01 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 033-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING 03741 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY COSTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING 039-01 INiilBIT SPURIOUS CO2 INTT!ATION SIGNAL WilEN 2-BFN-RTP-039 NO UNIT 2 TEST SATISFIES
)
VENTILATION (SYSTEM 30)IS REQUIRED IN DIESEL REQUIREMENTS GENERATOR BUILDINGS.
j 040-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS I
A WilOLE DURING UNIT 2 TESTING 043-01 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 043-02 CIDSE SAMPLING AND WATER QUALITY SYSTEM ISOLATION 2-BFN-RTP-069 YES VALVES ON PRIM ARY CONTAINMENT SYSTEM (64) GROUP I ISOLATION SIGNAllONLY ON RPV LOW WATER LEVEL (L1)
AND MAIN STEAM LINE 111G11 RADIATION).
~I 04343 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 I
1
.I 1
i
I ENCLOSURE Page 8 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR l
U3 043-04 MAINTAIN RHRSW SYSTEM (23) PRESSURE BOUNDARY 2-BFN-RTP-023 YES IBTI~EGRrrY.
043-05 PROVIDE CAPABILrrY OF M ANUAL BACKUP CONTROL 2-BFN-RTP-BUC YES ISOLATION (VALVE CLOSURE) TO PREVENT LOSS OF REACTOR WATER INVENTORY.
043-06 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A Wl? OLE DURING UNIT 2 TESTING 04347 CLOSE POST ACCIDENT SUPPLY SYSTEM ISOLATION VALVES NONE NO NEW MODE TESTED BY UPON RECEIVING PRIMARY CONTAINMENT SYSTEM (64)
PMT ON UNTT 2.
WILL GROUP 6 ISOLATION SIGN AL.
BE TESTED SY;PMT FOR DCN W17460A FOR UNIT 3.
044-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTFD AS A WHOLE DURING UNIT 2 TESTING l
046-01 PROVIDE RPV HIGil WATER LEVEL (L8) SIGN AL TO ENERGlZE 2-BFN-RTP-003B YES REACTOR FEEDWATER SYSTEM (3) SOLENOID TO CLOSE MAIN STEAM SYSTEM (1) FEEDWATER TURBINE STEAM SUPPLY STOP VALVES.
0474)!
PROVIDE MAIN TURBINE CONTROL VALVE FAST CLOSURE 2-BFN-RTP-047 YES SIGNAL TO REACTOR PROTECTION SYSTEM (99).
047-03 PROVIDE HYDRAULIC CLOSURE OF MAIN STEAM SYS (01) 2-BFN-RTP-047 YES TURBINE STOP VALVES UPON LOW CONDENSER VACUUM (APPROXIMATELY 20 HG) SIGNAL.
047-04 PROVIDE HYDRAULIC CLOSURE OF MAIN STEAM SYS (01) MAIN 2-BFN-RTP-047 YES TURBINE BYPASS VALVES UPON LOW CONDENSER VACUUM (APPROXIM ATELY 7 HG) SIGNAL.
047-05 PROVIDE IlYDRAULIC CONTROL TO OPEN M AIN STEAM SYS 2-BFN-RTP-047 YES (01) MAIN TURBINE BYPASS VALVES ON TURBINE TRIP (M AIN TURBINE STOP VALVE CLOSURE) SICNAL.
056el VERIFY THAT THE NaOCl SYSTEM PRESSURE REDUCING 2.BFN-RTP447 YES ORIFICES AND CHECK VALVES PROVIDE PRESSURE _BOUNDRY INTEGRITY TO THE EECW SYSTEM 0534)!
PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO
. SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 06341.
MANUAL INJECTION OF BORON SOLUTION INTO REACTOR 2-BFN-RTP-063 YES GIVEN INDICATION OF INCOMPLETE INSERTION OF CONTROL RODS (CRD SYSTEM 85) AND REACTOR NOT BEING IN SUBCRITICAL CONDrrlON (NEUTRON MONTTORING SYSTEM (NMS) SYSTEM 92).
ENCLOSURE Page 9 of 20 4
TABLE r
CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 06342 PROVIDE STANDBY LIQUID CONTROL SYSTEM (SLCS) 2-BFN-RTP-069 YES INITIATION SIGN AL TO REACTOR WATER CLEANUP (RWCU)
SYSTEM (69) FOR ISOLATION OF RWCU SYSTEM FROM THE REALTOR TO PREVENT ENTRY OF BORON SOLUTION INTO RWCU SYSTEM.
C53-03 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY.
2-BFN-RTP468 YES 063-04 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NQ SEE NOTE 2 f
C54-01 PROVIDE SIGNAL TO CLOSE GROUP 1 PRIM ARY CONTAINM ENT 2-BFN-RTP-064 A YES ISOLATION VALVES [M AIN STEAM SYSTEM (1) AND SAMPLE AND WATER QUALITY (SWQ) SYSTEM (43)).
064 02 PROVIDE SIGNAL TO CLOSE GROUP 2 PRIM ARY CONTAINMENT 2-BFN-RTP-064 A YES ISOLATION VALVES {RHR SYSTEM G4) CORE SPRAY SYSTEM
- 05) AND RADWASTE SYSTEM 071).
054-03 PROVIDE SIGNAL TO CLOSE GROUP 3 PRIM ARY CONT AINMENT 2-BFN-RTP-064 A YES ISOLATION VALVES [RWCU SYSTEM (69)l.
06444 PROVIDE SIGN AL TO CLOSE GROUP 6 PRIM ARY CONTAINMENT 2-BFN-RTP464 A YES ISOLATION VALVES (SYSTEMS 32,43.64.76.84 AND 90) ISOLATE AC SYSTEM (31) SUPPLY DUCTS TO M AIN CONTROL ROOM t
(MCR) INTTIATE EMERGENCY PRESSURIZATION SYSTEM (31)
TRIP FANS & POSITION DAMPERS (64) & INITIATE SGTS (65),
j 064-05 PROVIDE SIGNALTO CLOSE GROUP 8 ISOLATION VALVES.
2-BFN-RTP464A YES
)
SYSTEM (94) IS NOT TO PERFORM ACTIVE ISOLATION FUNCTION.
064-06 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO
$EE NOTE 2 064-08 PROVIDE HIGH DRYWELL PRESSURE TRIP SIGNALTO REACTOR 2-BFN-RTP-064A YES PROTECTION SYSTEM (99).
064 09 PROVIDE HIGH DRYWELL PRESSURE SIGNAL TO RHR SYSTEM 2-BFN-RTP-064 A YES G4) FOR LPCI INITIATION LOGIC AND TO CORE SPRAY SYSTEM G5) FOR SYSTEM INTTIATION LOGIC 480V LOAD MIED LOGIC DIESEL GENERATOR START LOGIC AND HPCI SYSTEM 03)
INTilATION LOGIC.
064-10 PROVIDE VACUUM RELIEF SYSTEM (VACUUM WEAKER 2-BFN RTP464A YES VALVES) TO PREVENT DRYWELL OR SUPPRESSION Cll AMBER (TORUS) NEG ATIVE PRESSURE FROM DAMAGING CONTAINMENT STRUCTURE.
064-11 PROVIDE DRYWELL TEMPERATURE INDICATION IN M AIN 2-BFN-RTP-064 A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM 04) DRYWELL SPRAY (CONTAINMENT COOLING) MODE, C5412 PROVIDE SUPPRESSION POOL TEMPERATURE INDICATION IN 2-B FN-RTP-064 A YES MAIN CONTROL ROOM IN SUPPORT OF RilR SYSTEM G4)
CONTAINMENT COOLING (TORUS COOLING AND DRYWELI/ TORUS SPRAY) MAIN STEAM SYSTEM M ANU AL RPV DEPRESSURIZATION AND RPS SYSTEM (99) MANU AL SCRAM.
ENCLOSURE Page 10 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP) l SYSTEM MODE DESCRII' TION UNIT 2 TEST TEST COMMENTS MODE FOR U3 064-13 PROVIDE SUPPRESSION POOL LEVEL INDICATION IN MAIN 2-BFN-RTP4M4A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM G4)
CONTAINMENT COOLING AND M AIN STEAM SYSTEM (1)
M ANUAL RPV DEPRESSURIZATION. PROVIDE PRESSURE BOUNDARY INTEGRITY TO HPCI SYSTEM G3).
064-14 PROVIDE DRYWELL FRESSURE INDICATION IN MAIN CONTROL 2-BFN-RTP-064A YES ROOM IN SUPPORT OF RHR SYSTEM G4) CONTAINMENT COOLING (DRYWEll/ TORUS SPRAY) AND CONTAINMENT ATMOSPHERE DILUTION SYSTEM (64) CONTAINMENT VENTING AFTER A LOCA.
064-15 PROVIDE DRYWELL TEMPEkATURE INDICATION OUTSIDE THE 2-BFN-RTP464A YES M AIN CONTROL ROOM IN SUPPORT OF M AIN STEAM SYSTEM (t) MANUAL RPV DEPRESSURIZATION AND RHR SYSTEM G4)
OPERATION FROM OtrTSIDETHE M AIN CONTROL ROOM.
064-16.
PROVIDE SUPPRESSIC 9 POOL TEMPERATURE INDICATION 2-BFN-RTP-064A YES OLTTSIDE THE MAIN (. TNTROL ROOM (MCR) IN SUPPORT OF MAIN STEAM SYSTEM (1) M ANUAL RPV DEPRESSURIZATION RHR SYSTEM G4) OPERATION AND REACTOR PROTFCTION SYSTEM (99) MANUAL SCRAM FROM OUTSIDETHE MCR.
064-17 PROVIDE SUPPRESSION POOL LEVEL INDICATION OUTSIDE THE 2 BFN-RTP-064 A YES M AIN CONTROL ROOM IN SUPPORT OF MAIN STEAM SYSTEM (1) M ANUAL RPV DEPRESSURIZATION RCIC SYSTEM pl)
OPERATION AND RHR SYSTEM G4) OPERATION FROM OUTSIDE THE MAIN CONTROL ROOM.
064-18 PROVIDE DRYWELL PRESSURE INDICATION OUTSIDE THE 2-BFN-RTP-064 A YES M AIN CobrTROL ROOM IN SUPPORT OF Rl!R SYSTEM OPERATION FROM OUTSIDE THE M AIN CONTROL ROOM.
064-21 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 064-23 PROVIDE FORCED AIR COOLING FOR RHR SYSTEM (74) AND 2 BFN-RTP-030 YES CORE SPRAY SYSTEM G5) PUMP MOTORS.
064 25 PROVIDE HIGH DRYWELL PRESSURE SIGN AL TO M AIN STEAM 2-BFN-RTP-064 A YES SYSTD1 (1) FOR AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) LOGIC.
034-27 CLOSE PRIMARY CONTAINMENT VENTILATION SYSTEM 2-BFN-RTP-065 YES ISOLATION VALVES ON PRIMARY CONTAINMENT SYSTD1 (64)
GROUP 6 ISOLATION SIGNAL.
064-28 PERFORM ISOLATION ACTION (S) [ TRIP FANS CLOSURE OF 2 BFN-RTP-064A UNTI' 2 TEST SATISFIE$
DAMPERS OPENING OF DAMPERS TO $GTS (65)] ON PRIMARY 2-BFN-RTP-065 REQUIREMENTS CONTAINMENT SYSTD1 (64) GROUP 6 ISOLATION SIGN ALS.
06541 MAINTAIN NEGATIVE PRESSURE IN SECONDARY 2-BFN-RTP4165 YES CONTAINMENT ON PRIM ARY COBrTAINMENT SYSTEM (64)
ONLY THE INTTIATION GROUP 6 ISOLATION SIGNAL. FILTER AIRBORNE PARTICULATE OF SGTS FROM UNTT 3
& GASES (INCLUDING TH AT FROM HPCI SYSTEM G3) & CAD LOGIC IS TO BE SYSTD1 (34)! PRIOR TO DISCH ARGE TO OFF-G AS SYSTEM (66).
TESTED.
1
4 ENCLOSURE Page 11 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIFTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 065-03 MAINTAIN NEGATIVE PRESSURE fN SECONDARY 2 BFN-RTP-065 YES
.. 2y CONTAINMENT ON PRIM ARY CONTAINMENT SYSTEM (64)
ONLY THE INirlATION SIGNAL DUE TO RADIATION MONITORING SYSTEM REFUELING OF SGTS FROM UNrr 3 ZONE HIGH RADIATION SIGNAL. FILTER AIRBORNE LOGIC IS TO BE PARTICULATE & G ASES PRIOR TO DISCil ARGE TO OFF-GAS TESTED.
SYSTEM (66).
065-04 PROVIDE SECONDARY CONTAINMENT INTEGRITY.
2 BFN RTP-065 NO UNIT 2 TEST SATISFIES REQUIREMENTS 066-02 PROVIDE FLOW PATH INTEGRITY FOR THE RELEASE OF Tile 2-BFN-RTP-065 NO UNIT 2 TEST S ATISFIES FILTERED STANDBY GAS TREATMENT SYSTEM (65) GASLS TO PEQUIREMElfTS THESTACKS.
066-04 OFF-GAS DILUTION FAN ISOLATION DAMPERS SilALL BE 2-BFN-RTP-065 NO PMT FOR 'DCN.Wl7999A CIDSED ON INrrIATION OF TIIE SGT SYSTEM 165).
SATISFIES REQUIRG1ENTS 067-01 PROVIDE COOLING WATER TO AC SYSTEM (31) CHILLERS RilR 24FN-RTP-067 YES SYSTEM G4) PUMP SEAL COOLERS CIS (76) 02 & H2 GAS ANALYZERS DIESEL ENGINES (82) Ri!R & CORE SPRAY EQUIPMENT ROOM COOLERS (64) & FUEL POOL G9). M AINTAIN EECW SYSTEM L23) PRESSURE BOUNDARY.
057-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO UNrr 2 TEST S ATISFIES REQUIRD1ENTS 067-03 FOR SHUTDOWN FROM OUTSIDE OF M AIN CONTROL ROOM: (1) 2-BFN-RTP-067 YES PROVIDE COOLING WATER TO RHR & CORE SPRAY EQUIPMENT ROOM COOLERS (64) RHR SYSTEM G4) PUMP SEAL COOLERS DIESEL ENGINES (82) & FUEL POOL 09) (2) M AINTAIN EECW SYSTEM (23) PRESSURE BOUNDARY.
06745 ATTACH A FIRE IlOSE TO EECW TO MAINTAIN WATER LEVEL 2-BFN-RTP-067 YES IN THE FUEL POOL.
C58-01 CLOSE RECIRCULATION PUMP DISCHARGE VALVES ON RilR 24FN-RTP-068 YES SYSTEM 04, AUTOMATIC LPCI MODE INITIATION SIGNAL.
058-02 OPEN RECIRCULATION PUMP MOTOR BREAKERS ON REACTOR 2-BFN-RTP-(68 YES PROTECTION SYSTEM (99) SIGN AL DUE TO >30% TURBINE FIRST STAGE PRESSURE AND EITHER MAIN TURBINE CONTROL VALVE FAST CLOSURE OR M AIN TURBINE STOP VALVES < 90%
OPEN M ANUALLY ENABLED END-OF-CYCLE RFF).
06& 43 CLOSE RECIRCULATION PUMP DISCilARGE VALVES 2.BFN.RTP-068 YES M ANUALLY IN SUPPORT OF M ANUALLY INITIATED RilR SYSTEM G4) SHITFDOWN COOLING MODE AND LPCI MODE (FROM MAIN CONTROL ROOM AND OUTSIDE MAIN CONTROL ROOM).
068-04 PROVIDE REAcrOR COOLANT PRESSURE BOUNDARY (RCPB).
2 BFN-RTP-068 YES i
068 45 PROVIDE LOW REACTOR PRESSURE PERMISSIVE SIGN ALS TO 2-BFN-RTP N8 YES CORE SPRAY SYSTEM (75) AND RllR SYSTEM G4).
~
ENCLOSURE Page 12 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIITION UNIT 2 TEST TEST COMMENTS MODE FOR U3 068-06 TRIP RECIRCULATION PUMP MOTOR MOTOR-GENERATOR SET 2-BFN-RTP-068 YES ON OPENING OF 4KV POWER DISTRIBUTION SYSTEM (575) M-G SET DRIVE MO'R)R BREAKERS DUE TO HIGli REACTOR PRESSURE OR LOW WATER LEVEL (L2).
06847 PROVIDE'X PROPORTIONAL CORE FLOW $1GN AL TD TIIE NONE YES
'~
NEUTRON MON 1TORING SYSTEM (092) FOR ROD BLOCK LOGIC 068-08 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 068,-09 MAINTAIN...MG.SE. T S. PEED. C. l!AN.GES. W.rrlIIN. ANAL.YZED.
N.oNE
.YES D68'-J D REQUIREMENTS FOR LOOP'WARMU.P PRIOR TO RECIRC PUMP NONE NO PROCEDlJRALLY START CONTROLLED i
069-01 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO
$EE NOTE 2 00942 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN.RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WllOLE DURING UNTT 2 TESTING 069-03 CLOSE RWCU SYSTEM ISOLATION VALVES ON PRIMARY 2-BFN-RTP-069 YES CONTAINMENT SYSTEM (64) GROUP 3 ISOLATION SIGN AL.
06944 CLOSE RWCU SYSTEM SUCTION LINE ISOLATION VALVES ON 2-BFN-RTPA9 YES STANDBY LIQUID CONTROL SYSTEM (63) INTTIATION SIGNAL TO PREVENT ENTRY OF BORON SOLUTION INTO RWCU SYSTEM.
06945 PROVIDE HIGli RWCU SYSTEM EQUIPMENT AREA 2-BFN-RTP-069 Y2S ATMOSPliERE AND DRAIN TEMPERATURE SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 3 ISOLATION LOGIC.
069-06 PROVIDE REACTOR CCX)LANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES C5947 PROVIDE SYSTEM PRESSURE BOUNDARY SUPPORT (CllECK 2-BFN-RTP-069 YES VALVE) TO 11PCI SYSTEM (73) TO PREVENT DIVERSION OF llPCI SYSTEM CORE COOLING WATER FROM REACTOR VESSEL.
059-08 PROVIDE FLOW PATil FOR RCIC SYSTEM (71) CORE COOLING 2-BFN-RTP-069 YES WATER TO REACTOR FEEDWATER SYSTEM (3) SPARGERS.
C59-09 PROVIDE CAPABILITY OF M ANUAL BACKUP CONTROL 2-BFN-RTP-EUC YES ISOLATION (VALVE CLOSURE)TO PREVENT LOSS OF REAcrOR I
WATER INVENTORY.
070-01 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 070-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-B) N-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A W110LE DURING UNTT 2 TESTING 070-03 PROVIDE DRYWELL COOLING WilEN POWER AND C(X) LING 2-BFN-RTP-030 YES WATER ARE AVAILABLE.
f
s i
ENCLOSURE Page 13 of 20 TABLE CORREL--ATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
I UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 071-01 AUTOMATIC RCJC SYSTEM INITIATION ON REACTOR 2-BFN-RTP-071 YES FEEDWATER SYSTEM Q) RPV LOW WATER LEVEL (L2) SIGN AL TRANSMTITED VIA RilR SYSTEM G4). AUTOMATIC RCIC SYSTEM SilUTOFF(IF OPERATING) ON REACTOR FEEDWATER SYSTEM Q) RPV lilGil WATER LEVEL (L8) SIGN AL.
071-02 M ANUAL RCIC INTFIATION AND TRIP TO CONTROL LEVEL.
2-BFN-RTP-071 YES (NON-LOCA UNIT) 071-03 CLOSE RCIC SYSTEM STEAM SUPPLY LINE ISOLATION VALVES 2-BFN-RTP-071 YES ON RCIC SYSTEM GROUP 5 ISOLATION SIGN ALS (IllGli STEAM LINE DIFFERENTIAL PRESSURE !!IGli STEM LINE SPACE TEMPERATURE OR LOW STEAM LINE PRESSURE),
071-04 MANUALLY CLOSE RCIC SYSTEM STEAM SUPPLY LINE 2 BFN-RTP-071 YES ISOLATION VALVES ON REACTOR FEEDWATER SYSTEM Q)
INDICATION OF LOW RPV PRESSURE.
071-05 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 071 07 PROVIDE PRIMARY CONTAINMENT DOUNDARY.
2-BFN-RTPMA NO SEE NOTE 2 071-08 PROVIDE SYSTEM PRESSURE BOUNDARY IN SUPPORT OF RilR 2-BFN-RTP-068 YES SYSTEM G4) CONTAINMENT (TORUS) COOLING FUNCTION.
[
071-09 M ANUAL RCIC SYSTEM OPERATION FROM OUTSIDE THE M AIN 2 BFN-RTP-071 YES CONTROL ROOM TO MAINTAIN NORMAL RPV WATER INVENTORY WHILE RPV PRESSURE IS ABOVE 100 PSIG.
071-10 PROVIDE POWER TO ECCS DIVISION I AND 11 AN ALOG TRIP 2 BFN-RTP-071 YES UNTTS [ REACTOR FEEDWATER SYSTEM Q) PRIM ARY CONTAINMENT SYSTEM (64) REACTOR WATEk RECIRCU3 ATION SYSTEM (68) RCIC SYSTEM Gl) AND IIPCI SYSTEM G3)).
071-11 PROVIDE SECONDARY CON'FAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-NENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING r
073-01 AUTOM ATIC IIPCI SYSTEM INITIATION ON REACTOR 2-BFN-RTP-073 YES FEEDWATER SYSTEM Q) RPV LOW WATER LEVEL (L2) SIGNAL.
AUTOM ATIC HPCI SYSTEM SHUTOFF (IF OPERATING) ON REACTOR FEEDWATER SYSTEM (3) RPV lilGli WATER LEVEL i
(L8) SIGNAL.
07342 PROVIDE MCR INDICATION OFl AUTO TRANSFER OF $UCTION NONE YES
~ ' "
PATH ON LOW CONDENSATE LEVEL ^~
~
' ' '~~ ~
"~
073-03 CLOSE IIPCI SYSTEM STEAM SUPPLY LINE ISOLATION VALVES 2-BFN-RTP-073 YES ON IIPCI SYSTEM GROUP 4 ISOLATION SIGN ALS (illGH STEAM LINE DIFFERENTIAL PRESSURE 111G11 STEAM LINE SPACE TEMPERATURE OR LOW STEAM LINE PRESSURE).
073-04 MANUALLY CLOSE HPCI SYSTEM STEAM SUPPLY LINE 2 BFN-RTP-073 YES ISOLATION VALVES ON REACTOR FEEDWATER SYSTEM (3)
INDICATION OF LOW RPV PRESSURE.
07345 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB) 2-BFN-RTP-068 YES DURING HPCI SYSTEM STANDBY.
j
1 ENCLOSURE Page 14 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP) l l
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 073-06 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB) 2-BFN-RTP-068 YES DURING HPCI SYSTEM OPERATION.
073-07 PROVIDE PRIMARY CONTAINMENT BOUNDARY DURING HPCI 2-BFN-RTP-064 A NO SEE NOTE 2 SYSTEM STANDBY.
073 08 PROVIDE PRIMARY CONTAINMENT BOUNDARY DURING IIPCI 2-BFN-RTP-064 A NO SEE NOTE l2 SYSTEM OPERATION.
l 073-04 M ANUALLY TRIP IIPCI SYSTEM FROM OUTSIDE TIIE MAIN 2-BFN-RTP-073 YES CONTROL ROOM TO PREVENT RPV OVERFILL 073-11 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING 073 12 PROVIDE POWER TO PRIMARY CONTAINMENT SYSTEM (64) 2-BFN-RTP-064 A YES DRYWELL PRESSURE INDICATORS IN SUPPORT OF RHR SYSTEM DRYWELLfrORUS SPRAY MODE AND CONTAINMENT ATMOSPilERE DILUTION SYSTEM POST LOCA CONTAINMENT VENTING MODE.
074-01 AUTOM ATIC LPCI MODE INTTIATION ON RPV LOW WATER 2-BFN-RTP-074 YES LEVEL (L1) SIGNAL OR HIGli DRYWELL PRESSURE SIGNAL WITH CCNCURRENT LOW RPV PRESSURE PERMISSIVE SIGNAL.
M ANUAL LPCI MODE INirlATION FROM THE M AIN CONTROL ROOM.
074-02 PROVIDE SUPPRESSION POOL WATER COOLING TO M AINTAIN 2-BFN-RTP-074 YES SUPPRESSION POOL WATER TEMPERATURE BELOW LIMirS TO ASSURETHAT PUMP NPSH REQUIREMENTS ARE NET AND TH AT COMPLETE CONDENSATION OF BLOWDOWN STEAM FROM A DESIGN BASIS LOCA CAN BE EXPECTED.
07403 PLOVIDE SPRAY TO DRYWELL AND TORUS FOR CONTAINMENT 2-BFN-RTP-074 YES COOLING AND LOWERING OF CONTAINMENT PRESSURE UNDER POST-ACCIDENT CONDirlONS.
07444 PROVIDE SIIUTDOWN COOLING MODE (MANU AL) TO RESTORE 2-BFN-RTP-074 YES REACTOR TEMPERATURE TO NORMAL l
07449 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNTI 2 TESTING 074-10 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES
]
074-11 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2 BFN-RTF 4)64A NO SEE NOTE 2 074-12 PROVIDE SIGNAL (TilAT A RIIR PUMP IS RUNNING)TO MAIN 2-BFN-RTP-074 YES STEAM SYSTEM (1) AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INITIATION LOGIC.
074-17 PROVIDE AUTOMATIC LPCI MODE INITIATION SIGNAL FOR 2-BFN-RTP-074 YES CLOSURE OF REACTOR WATER RECIRCULATION SYSTEM (68)
PUMP DISCllARGE VALVES.
ENCLOSURE Page 15 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BlW)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIFFION UNTT 2 TEST TEST COMMENTS '
MODE FOR U3 074-19 MANUAL RHR SYSTEM OPERATION (LPCI TORUS COOLING AND 2-BFN-RTP-BUC YES Sif UTDOWN COOLING MODES) FROM OUTSIDE TiiE MAIN COffrROL ROOM.
074-20 PROVIDE FLOW PATil AND PRESSURE BGUNDARY INTEGRITY 2 BFN-RTP-074 YES FOR RHR SEkVICE WATER SYSTEM (23) COOLANT TO THE MAIN RHR SYSTEM HEAT EXCHANGERS.
074-21 PROVIDE REACTOR FEEDWATER SYSTEM (3) RPV LOW WATER 2-BFN-RTP471 YES LEVEL (L2) SIGNAL FOR AUTOMATIC RCIC SYSTEM 01)
INTTIATION.
074-22 PROVIDE RHR SYSTEM UNTT CROSS-TIE VALVES OPEN 2-BFN-RTP-023 YES POSITION SIGNALTO RilR SERVICE WATER SYSTEM (23) FOR CLOSURE OF RilR SERVICE WATER VALVES TO MAINTAIN PRIMARY CONTAINMENT BOUNDARY.
074-23 RHR ISOLATION $1GN AL TRIPPED ON SIGNAL FROM PRIM ARY 2.BFN-RTP464A YES CONTAINMENT SYSTEM (64).
075-01 SUPPLY COOLING WATER TO REACTOR - AUTO INTTIATION.
2 BFN-RTP-075 YES 07543 PROVIDE CS PUMP POWER DISCONNECT FROM OUTSIDE McR.
2-BFN-RTP-075 YES t
075-04 PROVIDE REACTOR COC
.NT PRESSURE BOUNDARY.
2-BFN-RTP-068 YES 075-05 PROVIDE PRIMARY CONTAINMENT BOUNDARY.-
2-BFN-RTP-064 A NO SEE NOTE 2 075-06 PROVIDE ACCIDENT SIGN AL INPUT TO 480V LOAD SHED 2-BFN-RTP-075 YES LOGIC.
075-07 PROVIDE START SIGNAL TO DIESEL GENERATOR ON LOW 2-BFN-RTP-075 YES LEVEL (LI) OR HIGH DRYWELL PRESSURE.
075 08 PROVIDE PRIM ARY CONTAINMENT SYSTEM (64) lilGH 2-BFN-RTP473 YES DRYWELL PRESSURE SIGNAL FOR AUTOM ATIC llPCI SYSTEM G3) OPERATION.
075-10 PROVIDE SIGNAIS (TilAT CORE SPR AY PUMPS ARE RUNNING) 2-BFN-RTP-075 YES TO MAIN STEAM SYSTEM (1) AUTOM ATIC DEPRESSURIZATION SYSTEM (ADS) INITIATION LOGIC.
075-11 PROVIDE REACTOR FEEDWATER SYSTEM (3) RPV LOW WATER 2 BFN-RTP-074 YES LEVEL (LI) SIGNALTO RHR SYSTEM G4) LPCI MODE INITIATION LOGIC.
075-12 PROVIDE REACTOR FEEDWATER SYSTEM (3) AND REACTOR 2-BFN RTP468 YES WATER RECIRCULATION SYSTEM (68) LOW REACTOR PRESSURE SIGNALS TO RllR SYSTEM G4) LPCI MODE INITIATION LOGIC.
075-13 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO
~ SECONDARY CONTAliJ-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING
ENCLOSURE Page 16 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIIrTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 075-14 PERFORM ISOLATION ACTIONS UPON RECEIVING ISOLATION 2-BFN-RTP-064 A YES SIGNAL (LOW LEVEL L3 OR lilGH DRYWELL PRESSURE) FROM THE PRIMARY CONTAINMENT SYSTEM (64).
D7h17 PROVIDE LOAD $HEDD1No SIGNALTO 480V AC SYSTEM (574) 2-EFN-RTi% DIM YES ON. REACTOR LOW.. WATER LEVEL (L1) OR COINCIDENT lilGII DRY %TiLL PRESSURE AND 1.DW REACTOR PRESSURE 07@
PROVIDE' START SIGNALTO CONTkINMENT RXDIATION NONE YES MONITORING RECORDERS OQLOW LEVELL(LD OR HIGil DRYWELL PRES $URE 07641 CLOSE CONTAINMENT INERTING SYSTEM ISOLATION VALVES 2-BFN-RTP-084 YES ON PRIMARY CONTAINMFhT SYSTEM (64) GROUP 6 ISOLATION SIGNAL.
076-02 PROVIDEOXYGEN AND HYDsOGEN GAS ANALYZERS AND 2-BFN-RTP-084 YES INDICATORS TO MONITOR GAS CONCENTRATIONS INSIDE TllE PRIM ARY CONTAINMENT IN SUPPORT OF COffrAINMENT ATMOSPHERE DILUTION SYSTEM (84) OPERATION.
076-03 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN RTP-064A NO SEE NOTE 2 07644 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING 077-01 CLOSE RADWASTE SYSTEM ISOLATION VALVES ON PRIM ARY 2-BFN-RTP-024 YES CONTAINMENT SYSTEM (64) GROUP 2 ISOLATION SIGN ALS.
07742 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 BFN-RTP-064A NO SEE. NOTE 2 077-03 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 078 01 PROVIDE SECONDARY CONTAINMENT IK)UNDARY.
2-BFN-RTP465 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 078-02 PROVIDE PRESSURE BOUNDARY INTEGRITY AT Rl!R/FPC 2 BFN-RTP-074 YES INCLUDED IN S1(STEM INTERFACE, 74 BTRD 07843 PREVENT INADVERTENT SIPHONING OF Tile SPENT FUEL 2-BFN-RTP-069 NO TESTED
- POOL, SATISFACTORILY PER -
PMT.BFa78.003 079-01 PROVIDE SAFE FUEL HANDLING USING REFUEL BRIDGE &
2-BFN-RTP479 YES EQUIPMENT.
079-02 PROVIDE INTERLOCKS TO CRD SYSTEM DURING FUEL 2-BFN-RTP485 YES MOVEMENT.
i 4
- ~
ENCLOSURE Page 17 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 082-01 START STANDBY AC POWER SOURCE FOR 4KV SYSTEM (575) 2 BFN-RTPM2 NO UNrr 2 TEST SATISMES RE@EMENTS 08242 PROVIDE POWER TO 4KV SYSTEM (575) UfoN DIESEL 2-BFN-RTP 082 YES GENERATOR (D/G) AVAILABILITY AND LOSS OF OFF-SITE foWER.
082-03 PROVIDE D/G POWER TO DIESEL FUEL TRANSFER 2 BFN-RTP-082 NO UNIT 2 TEST SATISFIES PUMPS (SYSTEM 18).
ALL REQUIREMENTS 084-01 PROVIDE DILUTION OF Tif E PRIM ARY CONTAINMENT 2-M N -kTP-G34 iS ATMOSPiiERE Wrril NITROGEN ATTER A LOCA TO M AINTAIN COMBUSTIBLE GAS (OXYGEN AND llYDROGEN)
CONCENTRATIONS BELOW LEVELS (OXYGEN 5% BY VOLUME)
Wi!!Cil COULD) PRODUCE A COMBUSTIBLE G AS MIXTURE.
08443 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A No SEE NOTE 2 084-04 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WilOLE DURING UNIT 2 TESTING 08445 PROVIDE NITROGEN TO Tile CONTROL AIR SYSTEM (32)IN NONE NO TE$TINO WILL.BE DONE SUPPORT OF LONG TERN OPERABILrrY OF M AIN STEAM BY PMT FOR DCN17937 SYSTEM ADS SAFETY RELIEF VALVES (SRVS)- APPENDIX R.
08446 CU)SE CAD SYSTEM VENT VALVES ON PRIM ARY 2-BFN-RTP-084 YES CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNAL.
085-01 PROVIDE SCRAM (99) AND CLOSE SDV VENT DRAIN VALVES.
2-BFN-RTP-085 YES 085-02 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-Bf N-RTP-064 A NO
$EE NOTE 2 085-03 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS I
A WilOLE DURING UNrr 2 TESTING ~
085-04 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 085-05 PREVENT ROD WITilDRAWAL.
2-BFN-RTP-085 YES 08548 PROVIDE MCR ROD POstrlON INDICATION.
2-BFN RTP-085 YES 085-04 PROVIDE SCR AM DISCil ARGE lilGli WATER LEVEL SIGN AL.
2-BFN-RTP485 YES 085-10 PROVIDE SCRAM DISCllARGE LOW AIR llEADER PRESSURE 2-BFN-RTP-085 YES SIGNAL.
085-11 PROVIDE REMOTE B ACKUP CONTROL FROM OUTSIDE Tile 2-BFN-RTP-BUC YES M AIN CONTROL ROOM.
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ENCLOSURE Page.18 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIFFION UNIT 2 TEST TEST COMMENTS MODE FOR U3 085-14 PROVIDE ALTERNATE ROD INSERTION BY OPENING BACKUP 2-BFN-RTP-085 NO TESTING WILL' BE DONE SCRAM VALVES ON FEEDWATER SYSTEM (3) RPV LOW WATER PER PMT FOR'DCN LEVEL (L2) SIGNAL OR HIGH REAcrOR VESSEL PRESSURE W19321 SIGNAL.
055 l6 PROVIDE ROD SELECT IDENTIFICATION 2-BFN-RTP-085 YES 086-01 PROVIDE DIESEL STARTING AIR TO DIESEL GENERATOR 2-BFN-RTP-082 NO TESTS WERE SYSTEM (82).
PERFORMED IN ACCORDANCE %Till 2-BFN-RTP-082 REV O AND
- 1. THE RESULTS OF THESE TESTS WERE REVIEWED AND FOUND TO BE ACCEPTABLE TO VERIFY SYSTEM MODE REQUIREMENTS FOR UNrr 3.
040-01 PROVIDE MAIN STEAM LIVE HIGH RADIATION SIGN AL TO 2-BFN-RTP-090 YES REACTOR PROTECTION SYSTEM (99).
000-02 PROVIDE PRIM ARY CONTAINMENT BOUNDARY (UP TO 2-BFN-RTP-064 A No PASSIVE FUNCTION 2-FCV-90-254 AB-255-257AB).
SEE NOTE 2 09043 PROVIDE REACTOR BUILDING VENTILATION EXII AUST LINE 2-BFN-RTP440 NO UNTT 2 TEST SATISFIES AND REFUELING ZONE AREA (ADJ ACENT TO THE FUEL POOLS)
REQUIREMFNTS HIGil RADIATION SIGN ALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION LOGIC.
090-04 PROVIDE CONTROL POOM INTAKE AIR DUCTS EXCESSIVE 2-BFN-RTP-031 B NO UNIT 2 TEST SATISFIES RADIATION SIGNALTO AIR CONDITIONING SYSTEM (31) FOR REQUIREMENTS INITIATION OF CONTROL ROOM EMERGENCY VENTILATION GSOLATION OF INTAKE DUCTS AND SUPPLY OF PRESSURIZED 1
FILTERED OUTDOOR AIR).
]
l 090-05 CLOSE VALVES ON SUCFION AND RETURN LINES TO TIIE 2-EFN-RTP-090 YES DRYWELL RADIOACTIVE PARTICULATElODINE AND GASEOUS 1
MONITOR ON PRIM ARY CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGN AL.
1 000-07 MOVIDB RHRSW SYSTEM PRESSURE BOUNDARY NONE YES INCLUDED IN SYSTEM 23 BTRD 000-08 PROVIDE SECONDARY CONTAINMENT BOUNDARY 2-BFN-RTP-065 No SECONDARY CONTAIN-MENT WAS TESTED AS A W110LE DURING UNIT 2 TESTING 092-01 PROVIDE IRM HIGH NEUTRON FLUX TRIP SIGN AL TO REACTOR 2 BFN-RTP-092 YES PROTECTION SYSTEM 092-02 PROVIDE APRM HIGil NEUTRON FLUX TRIP SIGNALTO 2-BFN-RTP-092 YES j
REACTOR PROTECTION SYSTEM (99).
092-04, PROVIDE ROD ELOCK MONITOR TRIP SIGNAL [ VARIABLE %,*lTI!
NONE YES REClRC SYSTEM (68) FLOWJ To THE REACTOR.M ANUA_L CONTROL SUBSYSTEM (BS) TO INHIBTT CONTROL ROD
%TFHDRAWAL
O-1 ENCLOSURE Page 19 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 2 AND 3 RESTART TEST PROGRAMS (RTP)
SYSTEM MODE DESCRIFTION UNIT 2 TEST TEST COMM ENTS MODE FOR' U3 09245 FROVIDE' INDICATION IN MAIN CONTROL ROOM OF NONE YES POWER / NEUTRON TLUX LEVEL AS MONITORED ON LPRM/APRMS 09247 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 094-01 PROVIDE FR! MARY CONTAINMENT INTEGRITY.
2-BFN-RTP-064A YES 094 43 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB) 2-BFN-RTP-064 A YES (PASSIVE FUNCTION ONLY) 09941 PPOVIDE AUTO SCRAM & SDV VENT / DRAIN VALVE ISOLATION 2 BFN-RTP-099 YES
099-02 PROVIDE MANUAL SCRAM SIGNAL AND SDV VENT / DRAIN 2 BFN-RTP-099 YES VALVE ISOLATION SIGNALS TO CRD SYSTEM (85).
099-03 PROVIDE 'RUN' MODE SIGNAL TO PCIS (64) FOR LOW 2-BFN-RTP-099 YES STEAMLINE PRESSURE ISOLATION PERMISSIVE 099-04 PROVIDE REFUEL INTERLOCK TO REACTOR M ANUAL 2 BFN-RTP-083 YES CONTROL SYSTEM. (85) 099-05 PROVIDE TRIP SIGN AL TO RECIRC PUMP MOTOR BREAKERS 2-BFN-RTP-068 YES (SYSTEM 68).
049-06 PROVIDE SIGNALS TO PRIMARY CONTAINMENT ISOLATION 2-BFN-RTP-099 YES SYSTEM (64) LOGIC.
244-01 PROVIDE COMMUNICATION FROM LOCAL PANELS FOR 2-BFN-RTP-244 NO UNrr 2 TEST SATISFIES SHUTDOWN FROM OUTSIDE TIIE MCR.
REQUIREMENTS 303-04 SECONDARY CONTAINMENT LEAKAGE RATE CRrrERIA MUST 2-BFN-RTP-065 NO UNIT 2 TEST S ATISFIES BE MAINTAINED BY THE REACTOR BUILDING.
REQUIREMENTS 571-01 PROVIDE 125V DC CONTROL POWER TO DG CIRCUITRY 2-BFN-RTP-57 1 NO UNIT-2 TEST SATISpES (SYSTEM 82).
REQUIREMENTS 57242 PROVIDE UNIT PREFERRED POWER DISTRIBUTION.
2-BFN-RTP-57-2 NO UNTT 2 TEST SATISFIES REQUIREMENTS 57243 PROVIDE 120V AC POWER FOR REALTOR PROTECTION SYSTEM 2-BFN-RTP-57-2 NO UNTT:2 TEST SATISFIES (RPS) SYSTEM.
REQUIREhfENTS R2N PROy!DEpONTROLLOF TijE 120V AC POWTR FOR RPS SYSTEM 2-BFN;RTPf57 2 NO UNIT 2 TEST SATISFIES REQUIREMENTS 573-01 PROVIDE CONTROL & LOGIC POWER TO 4KV & 480V 2-BFN RTP-57 3 NO UNrt2 TEST SATISFIES -
SWTTCHGEAR.
REQUIREMENTS 57343 PROVIDE MOTIVE POWER & LOGIC POWER TO EQUIPMENT.
2-BFN RTP-57 3 NO UNIT 2 TEST S ATISFIES REQUREMENTS 573-05 PROVIDE LOGIC POWER TO 480V LO AD SHED LOGIC.
2-BFN-RTP-57-3 NO UNIT 2 TEST SATISFIES REQUIREMENTS 57441 PROVIDE 480V SWTTCHGEAR DISTRIBUTION.
2-BFN-RTP 57-4 NO UNTT 2 TEST SATISFIES REQUIREMENTS
- e.-
ENCLOSURE Page 20 of 20 TABLE CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT (UFN)
UNITS 2 AND 3 RESTART TEST l'ROGRAMS (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST
- TEST COMMENTS MODE FOR U3 57442 PROVIDE 480V MCC DISTRIBUTION, 2-BFN-RTP-57-4 YES 574-03 PROVIDE 480V LOAD SHED LOGIC SYSTEM.
2-BFN RTP-57-4 NO TO BE TESTED BYxPMT '
FOR DCN W21284A
.57444 PROVIDE 480V AC DISiltlBtTTION BACKUP CONTROL.
2-BFN-RTP-BUC NO UNIT 2 TEST SATi$FIE$.
REQUIREMENTS
$74f)$.
190 VIDE 480V LOAD SilED ON DEGRADED VOLTAGE 2-BFN-RTP-$7-4 NO UNfr 2 TEST SATISFIES CONDITIONS REQUIREMENTS 575-01 PROVIDE 4 KV POWER DISTRIBUTION FOR DG LOADING 2-BFN-RTP-UL-A NO UNIT 2 TEST $ATISFIES (SYSTEM 82).
'~
REQUIREMENTS
~
575-02 PROVIDE RECIRCULATION PUMP TRIP UPON SIGN AL.
2 BFN-RTP-068 YES 575-03 PROVIDE INSTRUMENTATION FOR DG PARALLELING (SYSTEM 2-BFN-RTP-57-5 NO UNfr 2 TEST SATI$EIES 82)
REQUIREMENTS i
575-04 PROVIDE INITIATION SIGNAL TO DIESELS (SYSTEM 82).
2 BFN RTP-57-5 NO UNIT 2 TEST SATISFIES REQUIREMENTS
$750$
PROVIDE COOLING TOWER LIFT PUMPTRIP DN CIRCULATING NONE 27 BTRD' ' '
~~
COOLING. WATER SYSTEM (27) LIIT PUMP DISCllARGE WATER
' ~ '
YES INCLUDEDIN SYSTEM HIGH TEMPERATURE $1GNAL
$75-06 BACKUP CONTROL FOR 4KV FEEDER BREAKERS OUTSIDE THE 2-BFN-RTP-BUC NO UNIT 2 TEST SATISFIES CONTROL BAY.
REQUIREMENTS 57547 LOAD SHEDDING TO PREVENT OVERLOADING OF 4KV SYSTEM 2-BFN-RTP-57-5 YES (575).
~ Note I: System modes in which a Unit 2 test was not performed and a Unit 3 test is not required have been removed from the table, Note 2: All active functions which suppon the primary containment pressure boundary (e.g, primary containment isolation) shall be covered by the baseline test requirement document (BTRD) of the system performing the active function. All functional tests for the isolation logic of the primsry containnwu isolation system are addressed by BTTLD-064D. Piping and components which form and supply the primary containment pressure hotmdary must be leak rate tested in accordance with 10 CFR 50 Appendix J and shall be hydrostatically tested under the ASME Section XI program. Therefore, testing for these nodes arc not required as part of the restart test program.
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