ML20126G581
| ML20126G581 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/28/1992 |
| From: | Zeringue O TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9301040151 | |
| Download: ML20126G581 (23) | |
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DEC 2 81992 U.S. Nuclear Regulatory Commission ATTH: Document Control Desk Washington, D.C.
20555 Gentlement In the Matter of
)
Docket Nos. 50-259 Tennessee Valley Authority
)
50-196 BROWS FERRY NUCLEAR PLANT (BFN; - UPDATE OF RESTART TEST PROGRAM (RTP)
SUBMITTAL FOR UNITS 1 AND 3 Referenect TVA letter dated February 18, 1992 - Request for Additional Information Regarding the Restart Test Program (RTP) for Units 1 and 3 TMs letter provides an update to the referenced letter, which described the overall scope of testing planned for BFN Units 1 and 3 for both the RTP and Power Ascension Testing (PAT) Program. In the referenced letter, TVA committed to provide an update to reflect the outcome of Baseline Test Requirements Document (BTRD) evaluations by December 31, 1992.
Presently, three of forty-six BTRD evaluations are complete with the remainder in progress. The table of Enclosure 1 has been revised to reflect the outcome of the three completed BTRD evaluations.
Changes to the table are highlighted for your convenience. TVA expects the remaining BTRDs to be complete.by June 30, 1993, and will provide another update at that time.
A summary list of commitments contained in this letter is provided in.. If you have any questions, please telephone G. D.. Pierce, Interim Site' Licensing Manager,-at (205) 729-7566.
Sincerely, qM.,,w d
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- 0. J. Zeringue i
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= Enclosures cc: See~page 2.'
9301040151L921228-
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'U.S. Nuclear Regulatory Commission DEC 2 81992 Enclosures cc (Enclosures):
NRC Resident-Inspector i
Brovna. Ferry Nucicar Plant Route 12, Box 637 Athens, Alabama = 35611 Mr. Thierry N. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Filnt, North-
-11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A.LWilson, Project Chief U.S. Nuclear Regulatory Commission
' f Region II 101 Marietta Street, IN, Suite 2900 Atlanta, Georgia 30323 T
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N ENCLOSURE 1 Page 1 of 20 TABLE 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNIT 2 TEST 1EST COMMENTS MODE FOR U3 001-01 PROVIDE MAIN TURBINE STOP VALVES < 90% OPEN TRIP 2-BFN RTP 001 YES SIGNAL TO REACTOR PROTECTION SYSTEM (99) 001 02 PROVIDE MAIN STEAMLihE ISOLATION VALVE < 90% OPEN 2-BFN RTP-001 YES 1 RIP SIGNAL TO REACTOR PROTECTION SYSTEM (99) 001 03 CLOSE MAIN STE AMLINE ISOLATION VALVES ON PRIMARY 2-BFN RTP 001 YES CONTAINMENT SYSTEM 1641 GROUP 1 ISOLATlON SIGNAL.
001-04 CLOSE MAIN STEAM DR AIN LINE VALVES ON PRIMARY 2 BFN.RTP-OO1 YES CONTAINMENT SYSTEM 164) GROUP 1 ISOLATION SIGNAL 001 0S OPEN MAIN TURBINE STEAM BYPASS VALVES ON TURBINE 2 BFN RTP 047 YES CONTROL SYSTEM (47) TURBINE TRIP SIGNAL 001 06 CONTROLLED MANUAL DEPRESSURIZATION OF RPV BY 2 BFN RTP 001 YES OPENING ADS SAFETY RELIEF VALVES ($RVS),
001 07 OPEN SAFETY RELIEF VALVES (SRVS) ON HIGH REACTOR 2-BFN-RTP 001 YE0 PRESSURE TO PROVIDE RPV PRES $URE RELfEF.
001 08 AUTO OPENING OF ADS SRVS UPON COINCIDENT 31GNALS OF 2-BFN RTP 001 YES 2 CS PUMPS (75) OR 1 RHR PUMP (74) AND EITHER LWL (Li&L3 FROM SYS 03) HICH DW PRESSURE (SYS 64 AND TIME DELAY OR LWL (L1 FROM SYS 03) AND HIGH DW PRESSURE BYPASS TIME DELAY.
001 09 CLOSE MAIN TURDINE STOP VALVES UPON TUPDINE CONTROL 2 BFN-RTP-047 YES SY3 TEM (47) DIVERSION OF HYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGNAL (SYSTEM 47).
001-11 MANUALLY DEACTIVATE NON ADS SRVS AND MSIV TEST 2-BFN RTP 001 YE3 CIRCUITS TO PREVENT IN ADVERTENT RPV DEPRESSURIZATION AND LOSS OF COOLANT.
001 12 PROVIDE LOW PRESSURE SIGNAL (IN MAIN STEAM LINE AT 2 BFN-RTP 001 YES TURBINE) TO PRIMARY CONT AINMENT SYSTEM (64) GROUP 1 -
ISOLATION LOGIC (RUN MODE).
001 13 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPBL 2 DFN RTP,068 -
YES 001 14 PROVIDE PRIMARY CONTAINMENT BOUND ARY.
2 BFN-RTP-064 A YES 001;15 PROVIDE SECONDARY CONTAINMENT BOUNDAP.Y,
SECONDARY CONTAINI MENT WAS TESTED AS
.l A WHOLE DURING UNIT 2 TESTING 1
001 16 CLOSE FEEDWATER PUMP TURBINF STOP VALVES (To TRIP 2.BFN,RTP OO3B YES-FEEDWATER TURBINE) ON LOSS OF HYDRAULIC PRESSURE DUE TO ENERGIZATION OF FEEDWATER SYSTEM SOLENOID.
001-17 PHOVIDE MAIN STEAM LINE HiGH FLOW AND HIGH STEAM '
2-DFN-RTP 001 YES TUNNEL TEMPERATURE SIGNALS TO PRIMARY CONT AINMENT SYSTEM (S41 GROUP 1 ISOLA TION
..T BD. TO BE DETERMINED.
- BTRD BASELINE TEST REQUIREMENTS DOCUMENT _
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ENCLOSURE 1__
Page 2 of 20 TADLE 1 CORRELATION DETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 001,21 PROVIDE MAIN TURBINE STOP VALVE CLOSURE POSITION 2 DFN RTP 047 YES SIGNALS TO TURBINE CONTROL SYSTEM (47) WHICH INITIATES OPENING OF MAIN TURBINE BYPASS VALVES.
001 22 CLOSE MAIN TURBINE BYPASS VALVES UPON TURBINE 2 DFN RTP-001 YES CONTROL SYSTEM (47) DIVER $10N OF HYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGNAL (SYSTEM 471 I
001 23 PROVIDE > 30% TURBINE FIRST STAGE PRESSURE INTERLOCK 2 BFN HTP 001 YES SIGNAL TO REACTOR PROTECTION SYSTEM (99) Fall SAFE LOGIC.
001-24 PROVIDE MAIN STE AM LiNE PRESSURE SiONAL TO TURBINE 2 BFN RTP 001 YES CONTROL SYSTEM (47) FOR OPERATION OF MAIN TURBINE BYPASS VALVES.
001 2S MANUALLY CLOSE MAIN STE AMLINE ISOLATION VALVES 2-BFN RTP 001 YES (MSIVS) AND MAIN STEAM DRAIN LINE VALVES.
002 06 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2-BFN RTP-06S NO SECOND ARY CONTA%-
MEfJT WAS TESTED As) -'
A WHOLE DURING UNIT 2 TESTING 002 08 PROVIDE PRIMARY CONT AINMENT BOUNDARY.
2 bfN-RTP-064 A YES 003 01-PROVIDE HIGH RE ACTOR VESSEL PRESSURE TRIP SIGNAL TO 2 BFN RTP 003A YES RE ACTOR PROTECTION SYSTEM (99) FAIL S AFE LOGIC.
003-02 PROVIDE RPV LOW WATER LEVEL (L3) TRIP SIGN AL TO 2 BFN RTP 003A YES REACTOR PROTECTION SYSTEM (99).
]
003 03 PROVIDE RPV LOW WATER LEVCL (L2) SIGNAL TO HPCI 2 BFN RTP 003A YES SYSTEM (73).
003 04 PROVIDE RPV LOW WATER LEVEL (L3) PERMISSIVE SIGNAL TO 2,BFN RTP 003 A.
YES MAIN STE AM SYSTEM (01) FOR ADS.
003 05 PROVIDE RPV HIGH WATER LEVEL (L8) SIGNAL TO RCIC 2 BFN RTP-003A YES SYSTEM (71) AND/OR HPCI SYSTEM (73) FOR TURblNE TRIP.
003-06 PROVIDE HIGH REACTOR VESSEL PRESSURE SIGNAL TO 250 2-BFN RTP 003 A YES ATWS WAS TESTED BY VDC SYSTEM (S73) TO OPEN RECIRCULATION PUMP M!G SET 2-BFN RTP 068 RTP4068 DRIVE MOTOR BREAKERS FOR TRIP OF REClRCULATION PUMPS
. AND TO CRD SYSTEM (8S) TO INITIATE ALTERNATE ROD INSERT.
003 07 PROVIDE LOW CONDENSER VACUUM SIGNAL TO ENERQlZE 2 DFN RTP-0030 YES REACTOR FEEDWATER SYSTEM (3) SOLENOID TO CLOSE MAIN STE AM SYSTEM (1) FEEDWATER TURBlNE STEAM SUPPLY STOP VALVES.
003-08 PROVIDE RPV WATER LEVEL INDICATION AT DACKUP CONTROL 2 BFN RTP 003A YES CENTER.
'TBD
.TO DE DETERMINED BTRD BASELINE TEST REQUIREMENTS DOCUMENT
=
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'f ENCLOSURE 1 y op 3 et 20
_.,c, l
TABLE 1 i
CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT l
UNITS 2 AND 3 RESTART TEST PROGRAMS
[
I j
anne-w SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR V3 003 09 PROVIDE LOW RE ACTOR PRESSURE PERMIS$1VE SIGNALS TO 2 DFN RTP 003A YES CORE SPR AY SYSTEM (701 FOR OPENING OF LOW PRESSURE ECCS INJECTION VALVES AND TO RHR SYSTEM (74) FOR CLOSING OF RECIRCULATION PUMP DISCHARGE VALVES.
003-10 PROVIDE RPV LOW WATER LEVEL (L1) SIGN AL TO PRIMARY 2-BFN RTP 003A YES CONTAINMENT SYSTEM (641 GROUP 1 ISOL ATION LOGIC.
003 11 PROVIDE RPV HIGH WATER LEVEL (LB) SIGNAL TO FEEDWATER 2-DFN RTP 003 A YES CONTROL SYSTEM (46) FOR MAIN TURDINE AND RE ACTOR FEEDWATER PUMP TURDINE TRIPS.
i E
003 12 PROVIDE REACTOR CONTAINMENT PRESSURE DOUNDARY 2 DFN RTP-068 YES (RCPBL 003 13 PROVIDE PRIMARY CONTAINMENT DOUNDARY.
2 DFf1RTP 064A YES 003 14 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN RTP 005 fiO SECONDARY CONTAIN-MENT.WAS TfSTED AS '
A WHOLE DURING UNIT 2 TESTING i
003-15 PROVIDE RPV LOW WATER LEVEL (L2) SIGNAL TO 260 SYSTEM 2 BFN RTP-068 YES (573) TO OPEN RECIRCULATION PUMP M/G SET DRIVE MOTOR BREAKERS FOR TRIP OF RECIRCULATION PUMPS AND TO CRD SYSTEM (85) TO INITIATE ALTERN ATE ROD INSERT.
003 16 PROVIDE RPV PRESSURE INDICATION IN MAIN CONTROL ROOM.
2-DFN-RTP 003 A
-YES 003 10 CLOSE MAIN STEAM SYSTEM (11 FEEDWATER TURBINE S1EAM 2 BFN RTP-003A YES SUPPLY STOP VALVES ON LOW CONDENSER VACUUM OR RPV HIGH WATER LEVEL (L8) SIGNALS.
003 19 IN01CATE RPV WATER LEVEL IN THE CONTROL HOOM.
2 BFN RTP-003 A YES 003 20 PROVIDE RPV LOW WATER LEVEL (L2) SIGNAL VIA RHR 2 BFN RTP-003 A YES' SYST EM (74) FOR AUTOMATIC RCIC SYSTEM (71) INITIATION.
i 003 21-PROVIDE RPV LOW WATER LEVEL (L1) SIGNAL TO MAIN STE AM -
2 BFN RTP 003A YES SYSTEM (1) FOR ADS.
-l 003 22 PROVIDE RPV LOW WATER LEVEL (Lil SIGNAL TO CORE SPRAY 2 DFN RTP-003A YES SYSTEM (75) FOR CORE SPRAY RHR LPCI(74) AND DIESEL GENER ATOR (82) ST ART.
003 23 PROVIDE RPV PRES $URE INDICAi.ON AT BACKUP CONTROL FBFN RTP 003 A YES CENTERJ 003 25 THE UPPER LIMIT 'ON FEEDWATER FLOW MUST RESTRICT FLOW' NONE.
TDD PENDING ISSUANCE OF l
J TO ABOUT 130% (RELOAD ANALYSIS ASSUMPTIONL UNIT 3 BTRD j
010 01-PROVIDE PATH FOR MAIN STE AM SYSTEM (1) SRVS STE AM 2 DFN RTP 003A YES' TEST VACUUM <
,1 SLOWDOWN TO PRIMARY CONTAINMENT SYSTEM 164)
BREAKER VALVES ONLY-1 SUPPRES$lON POOL.
010-02 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPD).
2 BFN RTP-068 YES ll TBD TO BE DETERMINED BTRD BASELINE TEST REQUIREMENTS DOCUMENT
~
l N
ENCLOSURE 1 Page 4 of 20
.q TABLE 1 i
CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION -
UNIT 2 TEST TEST COMMENTS -
MODE FOR V3 012 01 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2 DFfJ RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING l
012 02 PROVIDE PRIMARY CONTAINMENT 00VNDARY.
2-DFN RTP-064 A YES 018-01 PROVIDE DIESEL FUEL OIL TO DIESEL GENERATOR SYSTEM 2 DFN RTP 082 40 UNIT 2 TEST 182).
ADE0VATELY S ATISFIED REQUIREMENT 018-02 MAINTalN 7 DAY (LONG TERM) SUPPLY OF FULL OIL IN 2 DFN RTP 082 NO UNIT 2 TEST STORAGE T ANKS IN SUPPORT OF DIESEL OENERATOR SYSTEM ADEQUATELY (8 2),
SATISFIED REGUIREMENT 018 03 MAINTAIN SHORT TERM SUPPLY OF FUEL OIL IN 7 DAY 2 Bf N RTP 082 IJo 1ESTS WERE STORAGE TANKS BY TRANSFERRING FUEL OIL BETWEEN PLRFORMED IN AVAILABLE FUEL Oll STORAGE T ANKS IN SUPPORT OF DIESEL ACCORDANCE WITH GENER ATOR SYSTEM (82).
' UNIT 2 RTP TEST 2 BFNJ NTP 082 REV.0 AND REV.1.1 THESE TESTS.
WERE REVIEWED AND FOUND TO DE ACCEPTABLE TO' VERIFY THE SYSTEM MODE REQUIP.EMENTS FOR UNIT 3 RESTART, 023 01 PROVIDE COOLING WATER TO RHR SYSTEM (74) HE AT-2 DFN RTP 023 YES EXCHANGERS.
023-03 PROVIDE COOLING WATER TO EECW SYSTEM (671 UPON 2 BFN RTF-023 -
YES START OF THE RHR$W PUMPS.
023 04 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
NO
.SECOND ARY CONTAIN-MENT WAS TESTED AS i'
A WHOLE DURING UNif.
2 TESTING P
023 06 PROVIDE WHEELER LAKE LEVEL INDIC ATION/ ALARM AT 2 DFN RTP 023.
NO UNIT 2 TEST SATISFIES ELEVATION 058 FEET AND RISING AS WELL AS AT ELEVATION REQUIREMENTS 564 FEET AND RISING.
023 07 PROVIDE PRIMARY CONTAINMENT 00VNDARY.CLOSE RHR -
2-BFN RTP 023 NO UNIT 2 TEST S ATISFIES.
SERVICE WATER SYSTEM VALVES 1 FSV 23 56 AND REQUIREMENTS 2-FSV.23 56 ON RHR SYSTEM (74) UNIT CROSS-TIE VALVES OPEN POSITION SIGN AL.
023 08 MANUAL RHRSW SYSTEM OPERATION To PUVIDE COOLING 2 BFN-RTP 023 -
YES' WATER TO RHR SYSTEM (741 HEAT EXCHANGERS FROM OUTSIDE OF MAIN CONTROL ROOM.
023 09-PROVIDE SUMP PUMP CAPABILITY
- 2 DFN RTP-023 NO UNIT 2 TEST SATISFIES.
REQUIREMENT $
.TBD TO BE DE1 ERMINED DTRD DASELINE TEST REQUIREMENTS DOCUMENT
ENCLOSURE 1 Page 6 of 20 -
TABLE 1 CORRELATION BETWEEN DROWNS FERRY NUCLEA3 PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR V3 024 01 PROVIDE SECONDARY CONT AINMENT BOUNDARY.
2 BFN RTP-065 NO SECONDARY CONTAIN-MENT WAS 1ESTED AS A WHOLE DURING UNIT 2 TESTING 024 02 PROVIDE PRESSURE BOUNDARY INTEGRITY TO EECW SYS1LM 2 BFN-RTP 024 NO UNIT 2 TEST SAflSFIES (6 7 ),
REQUIREMENTS 024 05 PROV!DE RCW SUPPLY HE ADER LOW PRESSURE PERMISSIVE 2-BFN RTP-024 NO UNIT 2 TEST SATISFIES i
SIGNAL TO 4 KV POWER DISTRIDufl0N SYSTEM (575) FOR REQUIREMENTS STARTING OF RHRSW SYSTEM (23) PUMPS.
024 06 PROVIDE MANUAL CONTROL FROM OUTSIDE THE MAIN 2 BFN RTP BUC NO PENDINO ISSUANCE OF i
" ~ " '
CONTROL ROOM OF RCW PUMPS 10 AND 3D 10 PREVENT
~ ~
UNIT 3, BT,R_D.
OVERLOADING OF DIESEL GENERATORS (SYSTEM 82),
025 01 PROVIDE SECONDARY CONTAINMENT DOUND ARY.
2 BFN RTP 06S NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNil.
l!
2 TESTING-025-04 PREVENT AUTOMATIC START OF HIGH PRE 6SURE FIRE 2.JN RTP 025 NO UNIT 2 TEST SATISFIES _
PROTECTION SYSTEM (26) PUMPS (LOCK 0UT) TO PREVENT REQUIREMENTS OVERLOADING THE DIESFL GENERATORS (SYSTEM 821, 02S05 PREVENT START OF HIGH PRESSURE FIRE PROTECTION 2 BFN RTP BUC No UNIT 2 TEST S ATISFIES SYSTEM (26) PUMPS (FROM OUTSIDE THE MAIN CONTROL REQUIREMENTS ROOM) TO PREVENT OVERLOADING THE DIESEL GFNCRATORS (SYSTEM 82).
026 01 SUPPORT SECONDARY CONTAINMENT FUNCTION.
2 BFN RTP,065 NO SECONDARY CONTAIN.
. MENT WAS TESTED AS' A WHOLE DURINO UNIT 2 TESTING r
027-01 PROVIDE WARM WATER CHANNEL LEVEL INDICATION IN THE 2 BFN-RTP 027 NO UNIT 2 TEST SATISFIES MAIN CONTROL ROOM.
REQUIREMENTS 027 02 PROVIDE FOREBAY LEVEL INDICATION IN THE MAIN CONTROL 2 BFN RTP 027 NO UNIT 2 TEST SATISFIES ROOM FOR MANUAL ACTIONS TO REDUCE POWER OR IF REQUIREMENTS NECESSARY INITIATE SCRAM.
i 027 03' PROVIDE C00UNG TOWER LIFT PUMP DISCHARGE WATER.
NDNE YES MODE (027 03)
HIGH TEMPERATURE SIGNAL TO 4-KV POWER DISTRIBUTION -
DESCRIPTION Witt. Bf SYSTEM (575) FOR TRIPPING OF THE CORRESPONDING S ATISFIED DURING COOLING TOWER LIFT PUMP.
PERFORMANCE OF RTP 4 RTP 027.Ci 027 04 PROVIDE MANUAL VACUUM BREAKING CAPABILITY TO 2 DFN RTP-027 YES MODE (027 04)
' PREVENT BACKFLOW OF COOLING TOWER WARM WATER DLSCRIPTION WILLM '-
OlSCHARGE INTO THE FOREBAY UPON TRIP OF THE CCW S ATISFIED DURING -
PUMPS.
PERFORMANCE OF,RTP -
3 RTP-027 Ci-
' TBD TO BE DETERMINED.
BTRD BASELINE TEST REOUIREMENTS DOCUMENT i=-.
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N ENCLOSURE 1 Page 6 of 20 TABLt 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MUDE DESCR!PilON UNIT 2 TEST TEST COMMENTS MODE FOR U3 027 06 PROVIDE FOREDAY/ WARM WATER CHANNEL DIFFERENTIAL 2-BFN rip 027 NQ THIS MODE 14LETED LEVEL INDICATION IN THE MAIN CONTROL 800M, BY CHANGE NOTtCE.
(CN 2) TO 2/3;6Ffh BTAD=0274 029 Of PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 DFN RTP.066 NO SECONDARY CONTAIN-MENT WAS TESTED AS.
A WHOLE DURING UNIT-2 TESTING 030 01 PROVIDE VENTILATION TO UNITS 1 AND 2 DIESEL GENERATOR 2 BFN RTP 030 No UNIT 2 TEST SATISFIES BUILDING.
REQUIREMEN1S 030-02 PROVIDE VENTILATION TO UNIT 3 DIESEL GENERATOR 2-BFN-RTP 030 NO UNIT 2 TEST SATISFIES BUILDING.
REQUIREMENTS -
030 03 PROVIDE VENTILATION TO 250V BATTERY ROOM 3EB IN THE 2-BFN-RTP-030 NO UNIT 2 TEST SATISFIES UNIT 3 DIESEL GENERATOR BUILDING TO PREVENT A BUILDUP REQUIREMENTG OF HYDROGEN G AS DURING DATTERY CHARGING.
031 01 ISOLATE E,UPPLY DUCTS AND SUPPLY PRESSURIZED FIL1ERED 2 BFN R1P 031B NO UNIT 2 TEST SATISFIES OUTDOOR AIR TO MAIN CONTROL ROOM ON PRIMARY RE QUIREMENTS.
CONTAINMENT SYSTEM (641 GROUP 6 ISOLATION SIGNAL OR RADIATION MONITORING SYSTEM (00)IMTIATION SIGNAL.
031 02 PROVIDE VENTILATION TO REACTOR DUILDING BOARD ROOMS 2 BFN RTP 031B NO UNIT 2 TEST SATISFIES AND CONTROL BAY MECHANICAL EQUIPMENT ROOMS.
REQUIREMENTS 031 03 PROVIDE REClRCULATION AIR COOLING TO REACTOR BUILDING 2 BFN RTP-031D NO UNIT 2 TEST S ATISFIES.
BOARD ROOMS.
REQUIREMENTS 031-04 PROVIDE VENTILATION AND AtR CONDITIONING TO UNIT 3 2-BF N-RT P-031 B NO UNIT 2 TEST SATISFIES blESEL GENERATOR BUfLDING DOARD ROOMS, REQUIREMENTS 031 05 PROVIDE REC 1RCULATION AIR CONDITIONING TO CONTROL 2 BFN RTP 0310 NO UNIT 2 TEST SATISFIES ROOMS AND AUXILIARY INSTRUMENT ROOMS.
REQUIREMENTS 031 00 PROVIDE VENTILATION TO BATTERY ROOMS.
2 BFN-RTP 031B NO UNIT 2 TEST SATISFIES REQUIREMENTS 031-08 PROVIDE MANUAL LINEUP OF HVAC EQUtPMENT WITH TOTAL 2 BFN RTP-03 t A NO UNIT 2 TEST S ATISFIES LOSS OF CONTROL AIR.
REQUIREMENTS 031 09 PROVIDE SECONDARY CONTAINMENT BOUNDARY, 2-BFN-RTP 066 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING VNIT 2 TESTING :
032-01 PERFORM ISOLATION ACTION (S) UPON RECEIVING PHIMARY 2 BFN RTP-032 YES CONTAINMENT SYSTEM (64) GROUP 6 ISOL ATION SIGNALS.
032 02 PROVIDE COMPRESSED AIR TO MAIN STEAM SYSTEM (01) ADS 2-BFN RTP-001.
YES-S AFETY REllEF VALVES (SRVS).
032 03 PROVIDE COMPRESSED AIR FOR CLOSURE OF MAIN STEAM 2-BFN RTP 001 YES ISOLATION VALVES (SYSTEM 01).
TBD.TO DE DETERMINED BTRO BASELINE TEST REQUIREMENTS DOCUMENT
i, ENCLOSURE 1.
' Page 7 of 20 TABLE 1 CORRELATION DETWEEN DROWNS TERRY NUCLEAR PLANT UMTS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNIT 21[ST TEST COMMENTS MODE FOR U3 032 04 PROVIOE COMPRESSED AIR TO EQU;PMENT ACCESS LOCK 2 BFN RTP-032 ido UNIT 2 TEST SATISFl[S SEALS TO PROVIDE SECONDARY CONTAINMENT BOUNDARY.
REQUIREMENTS 032-OS PROVIDE PRIMARY CONTAINMENT DOUNDARY.
2 BFN RTP,064 A YES 032 06 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2 DFN kTP 06S NO SECONDARY CONTAIN-MtNT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 033 01 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 BFN RTP-064 A -
YES 033 02 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2-DFN RTP-06S NO SECONDARY CONTAIN4 MENT WAS TESTED AS -
A WHOLE DURING UNIT 2 TESTING l
037-01 PROVIDE $[CONDARY CONTAINMENT BOUNDARY.
2 BFN RTP Otiu NO SECONDARY CONTAIN-MENT WAS TESTED AG A WHOLE DURING UNIT 2 TESTING 039-01 INHIDIT SPURIOUS CO2 INITIATION SIGNAL WHEN VENTILA110N 2 BFN RTP-039 NO UNIT 2 TEST SATISFIES (SYSTEM 30) IS REQUIRED IN DIESEL GENERATOR DUILDINGS.
REQUIREMENTS 040 01 PROVIDE SECONDARY CONTAINMENT BOUNDARY, 2 BFN dTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE hVRING UNIT 2 TESTING 043-01 PROVIDE REACTOR COOL ANT PRESSURE BOUNDARY (RCPBL 2 BFN RTP-068 YES 043 02 CLOSE S AMPLING AND WATEh OtfALITY SYSTEM ISOLATION 2-DFN-HTP 069 YES VALVES ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGN AL lONLY ON RPV LOW WATER LEVEL (L1)
AND MAIN STEAM LINE HIGH RADIATIONI.
043 03 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN RTP-064 A YES I'
043-04 MAINT AIN RHRSW SYSTEM (23) PRESSURE BOUNDARY 2 BFN-RTP-02)
YES INTEGRITY.
043-OS PROVIDE CAPABILITY OF MANUAL BACKUP CONTROL 2 BFN RTP-BUC YES ISOLATION (VALVE CLOSURE) TO PREVENT LOSS OF RE ACTOR WATER INVENTORY.-
043 06 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN RTP 06S NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 043-07.
CLOSE POST ACCIDENT SUPPLY SYSTEMISOL ATION VALVES NONE YES NEW MODE TESTED BY UPON RECEIVING PRIMARY CONTAINMENT SYSTEM (64)
PMT ON UNIT 2 GROUP 6 ISOLATION SIGNAL TBD TO DE DETERMINED.
BTRD-BASELINE TEST REQUIREMENTS DOCUMENT
ENCLOSURE 1 Page 8 of 80 4
TABLE 1 CORRELATION DETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTIDN UNIT 2 TEST TEST COMMENTP MODE FOR U3 044 01 PROVIDE SECONDARY CONTAINMENT SOUNDARY.
2'BFN RTP 065 NO SECONLARY CONT AIN.
MENT WAS TEST &D AS A WHOLE DURIN^. UNIT 2 TESTING 046 01 PROVIDE RPV HIGH WnTER LEVEL (L8) SIGNAL TO ENERGlZE 2-DrN RTP 0030 YES REACTOR FIEDWATER SYSTEM (3) SOLENOID TO CLOSE MAIN STEAM SYSTEM (1) FEEDWA1ER TURBINE STE AM SUPPLY STOP VALVES.
047-01 PROVIDE MAIN TURBINE CONTHOL VALVE FAST CLOSURE 2 DFN RTP 047 YES=
S10NAL TO RE ACTOR PROTECTION SYSTEM (991.
(
047 03 PROVIDE HYDRAULIC CLOSURE OF MAIN STEAM SYS (Oli 2 BFN RTP 047 YES
~!
TURDINE STOP VALVES UPON LOW CONDENSER VACUUM (APPROXIMATELY 20 HGI SIGNAL.
047 04 PROVIDE HYDRAULIC CLOSURE OF MAIN STE AM SYS (01) MAIN 2 DFN RTP 047 YES TURDINE BYPASS VALVES UPON LOW CONDENSER VACUUM (APPROXIMATELY 7 HO) SIGNAL,
{
047 05 PROVIDE HYDRAULIC CONTROL TO OPEN MAIN S1EAM SYS 2 BFN RTP-047 YES (01) MAIN TURBINE DYPASS VALVES ON TURBINE TRIP (MAIN TURHINE STOP VALVE CLOSUhEl SIGNAL.
053 01 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2 DFN RTP 065 NO SECOND ARY CONTAIN-MENT WAS 1ESTED AS A WHOLE DURING UNIT,
2 TESTING 063 01 M ANUAL INJECTION OF BORON SOLUTION INTO REACTOR 2 DFN RTP-063
. YES GIVEN INDICATION OF INCOMPLETE INSERTION OF CONTROL RODS (CRD SYSTEM 8SI AND REACTOR NOT DEIN0 lN SUBCRITIC AL CONDITION (NMS SYSTEM 92),
063 02 PROVIDE SLCS INITIATION SIGNAL TO RWCU SYSTEM (69) FOR 2 BFN<RTP 069 YES
=[
+
ISOLATION OF RWCU SYSTEM FROM THE REACTOR TO PREVENT ENTRY OF DORON SOLUTION INTO RWCU SYSTEM.
063 03 PROVIDE RE ACTOR COOL ANT PRESSURE BOUNDARY.
2-DFN-RTP 068 YES 063 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 DFN-RTP464A YES t
.064-01 PROVIDE SIGNAL TO ClosE GROUP 1 PRIMARY CONTAINMENT 2 DFN RTP 064A
-YES ISOLATION VALVES IMAIN STEAM SYSTEM (1) AND SWO SYSTEM (4 all, n64 02 PROVIDE SIGNAL TO CLOSE GROUP 2 PRIMARY CONTAINMENT 2-OFN RTP-064A.
YES
-ISOLATION VALVES (RHR SYSTEM G4) CORE SPRAY SYSTEM _
~
(75) AND RADWASTE SYSTEM (77)l, 064-03
~ PROVIDE SIGNAL TO CLOSE GROUP 3 PRIMARY CONTAINMENT 2-BFN RTP 064 A
- YES ISOLATION VALVES IRWCU SYSTEM (6911.
I.
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- TBD-TO BE DETERMINFO "BTRD ' BASELINE TEST REuutREMENTS DOCUMENT
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ENCLOSURE 1 Pap 9 of 20 i
TABLE 1 CORRELAll0N BETWEEN BROWNS f ERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMME NT S MODE FOR U3 004-04 PROVIDE SIGNAL TO CLOSE GROUP 6 PRIMAhY CONT AINMENT 2-DF N RTP-064 A YES ISOL ATION VALVES (SYSTEMS 3243647684 AND 90llSOLATE AC SYSTEM (31) SUPPLY DUCTS TO MCR INITIATE E MERGEtJCY PRESSURIZATION SYSTEM (31) TRIP FANS & POstTION D AMPERS (641 & INtil AT E SGTS 10SL 064OS F ROVIDE SIGtJAL TO CLOSE GROUP 8 ISOLATION VALVES.
2 CFN R1P 004 A YES SYSTEM (94)IS NOT TO PERFORM ACTIVE ISOLATION FUNCTION.
004 00 PRDVIDE FitMARY CONT AINME NT DOUNDARY.
2 Of N RTP 004A YES 064 08 PROVIDE HIGH DRYWELL PRESSURE TRIP SIGNAL TO RE ACTOR 2 0F N RTP 004A YES PROTECTION SYSTEM (99L 064 09 PROVIDE HIGH DR(WELL PRESSURE S!GN AL TO RHR SYSTEM 2 BFN-RTP OC4 A YES (74) FOR LPCI LNITIATION LOGIC AND TO CORE SPR/sY SYSTEM (75) FOR SYST EM INITI AllON LOGIC 400V LO AD SP'D LOGIC DIESEL GENER ATOR ST ART LUGIC AND HPCI SYSTEM 1731 INITI ATION LOGIC.
064 10 PROVIDE V/,CVUM RELIEF SYST EM (VACUUM ESRE AKER 2 [AFN RTP 004A YLS VALVES) TO PREVENT DRYWELL OR SUPPRESSION CHAMBER (TORUS) NEG ATIVE PRESSURE FROM DAMAGING CONT AINMENT STRUCTURE.
064 11 PROVIDE DRYWELL 1EMPER ATURE INDIC ATION IN MAIN 2 BFN RTP 064 A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM (74) DRYWELL SPR AY ICONT AINMENT COOLING) MODE.
064'12 PROVIDE SUPPRESSION POOL TEMPERATURE INDICATION 1N 2 BFN RTP-064 A YES MAIN CONTROL ROOM IN SUPPORT OF RHR SYSTEM (74)
CONTAINMENT COOLING (TORUS COOLING AND ORYWELL/ TORUS SPR AY) MAIN STE AM SYSTEM MANUAL RPV DEPRESSURIZATION AND RPS SYSTEM (991 MANUAL SCRAM.
064 13 PROVIDE SUPPRESSION POOL LEVEL INDIC ATION IN MAIN 2-0FN RTP 064A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM (74)
CONTAINMENT COOLING AND MAIN STE AM SYSTEM (1)
MANU AL RPV DEPRESSuni2ATION. PROVIDE PRESSURE BOUNOARY INTEGRITY TO HPCI SYSTEM (73).
064 14 PROVIDE DRYWELL PRESSURE INDICATION IN MAIN CONTROL 2 BFN RTP-064 A YES ROOM IN SUPPORT OF RHR SYSTEM (74) CONT AINMENT COOLING (DRYWELUTORUS SPRAY) AND CONT AINMENT ATMOSPHERE DILUTION SYSTEM (64) CONTAINMENT VENTING AFTER A LOC A.
064 15 PROVIDE DRYWELL TEMPERATURE INDIC ATION OUTSIDE THE 2 BFN RTP-064 A YES M AIN CONTROL ROOM IN SUPPORT OF MAIN STE AM SYSTEM (1) MANUAL RPV DEPRESSURIZAh0N AND RHR SYSTEM (741 OPERATION FROM OUTSIDE THE MAIN CONTROL ROOM TBD TO Bi DETERM!NED DTRD BASELINE TEST REOUIREMENTS DOCUMENT
- 4 ENCLOSURF1 Page 10 of 20 TABLE 1 CORRELATION DETWEEN BROWNS FERRY NUCLEAR PLANT i
UNITS 2 AND 3 RESTART TEST PROGRAMS i
SYST EM MODE DESCRiPTIDN UNIT 2 TEST -
TEST COMMENTS MODE FOR U3 06 t>16 PROVIDE SUPPRESSION POOL TEMPERATURE INDICATION 2'bFN RTP-064 A YES I
OUTSIDE THE MAIN CONTROL ROOM (MCRIIN SUPPORT OF MAIN STE AM SYSTEM (1) MANUAL RPV DEPRESSURIZATION
.m RHR SYSTEM (74) OPERATION AND REACTOR PROTECTION SYSTEM 199) MANUAL SCRAM FROM OUTSIDE THE MCR, 064 < 17 PROVIDE SUPPRESSION POOL LEVEL INDICATION OUTSIDE THE 2 BFN RTP 064 A YES MAIN CON 1ROL ROOM IN SUPPORT OF MAIN STE AM SYSTEM (1) MANUAL RPV DEPRESSURIZATION RCIC SYSTEM (71)
OPERATION AND RHR SYSTEM (74) OPERATION f ROM OUTSIDE THE MAIN CONTROL ROOM.
064 18 PROVIDE DRYWELL PRESSUAE INDICATION OUTSIDE THE MAIN 2 DFN RTP-064 A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM OPERATION FROM OUTSIDE THE MAIN CONTROL ROOM.
064 21 PROVIDE SECONDARY CONTAINMENT DOUNDARY, 2,DF N-RT P-06S NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 064 23 PROVIDE FORCED AIR COOLING FOR RHR SYSTEM (741 AND 2 DFN-RTP 030 YES CORE SPR AY SYSTEM (75) PUMP MOTORS.
064 2S PROVIDE HIGH DRYWELL PRESSURE SIGNAL TO MAlfJ STEAM 2 DFN RTP 064A YES 1.YSTEM (1) FOR AUTOMATIC DEPRESSURIZATION SYSTEM
( ADS) logic.
064 27 CLOSE PRIMARY CONTAINMENT VENTILATION SYSTEM 2 BFN RTP 065 YES ISOLATION VALVES ON PRIMARY CONTAINMENT SYSTEM (64)
, GROUP 6 l$OLATl0N SIGN AL.
064-28 PERFORM ISOLATION ACTIONIS)(TRIP FANS CLOSURE OF 2-DFN RTP 064A YES DAMPERS OPENING OF DAMPERS TO SOTS (65)l ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOL ATION SIGNALS.
065 01 f,
"TAIN NEGATIVE PRES $URE IN SECONDARY 2 BFN RTP 06S YJS PENDING ISSUANCE OF CD. TAINMEt4T ON PRIMARY CONTAINMENT SYSTEM (64)
UNIT 3 DTAD. ONLY.
d G"
3 ISOLATION SIGNAL, FILTER AIRDORNE PARTICULATE THE INITIATION OF -
At t ilNCLUDING THAT FROM HPC1 SYSTEM (73) & CAD SGTS FROM. UNIT 3.
SYSiE4(3411 PRIOR TO DISCHARGE TO OFF G AS SYSTEM (66).
LOGIC 15 TO BE TESTED) 06503 MAINTAIN NEGATIVE PRESSURE IN SECONDARY 2 BFN RTP-065 VES=
PENDING ISSUANCE OF CONTAINMENT ON PRIMARY CONTA!NMENT SYSTEM (64)
UNIT 3 BTRD.. ONLY SIGNAL DUE TO R ADIATION MONITORING SYSTEM REFUELING THE INITIAll0N OF '
ZONE HIGH RADIATION SIGNAL. FILTER AIR 00RNE SGTS FROM.UNii 3 PARTICULATE & G ASES PRIOR 70 DISCH ARGE TO OFF G AS LOGIC l$ TO EZ SYSTEM (66).
TESTED;
'065 04 PROVIDE SECONDARY CONTAINMENT INTEGRITY.
2-BFN RTP 06S NO UNIT 2 TEST SATISFIES
- REQUIREMENTS 066-02 PROVIDE FLOW PATH INTEGRITY FOR THE RELEASE OF THE 2 BFN-RTP 065 NO PENDING ISSUANCE OF'-
FILTERED ST ANDBY G AS TREATMENT SYSTEM (SSI G ASES TO
~
UNIT 3 BTRD -
THE STACKS, TBD - TO BE DETERMINED
.'l BTAD BASELINE TEST REQUIREMENTS DOCUMENT l
u
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'a ENCLOSURE 1 Pm 11 of 20 -
TABLE 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DISCRIPTION UNIT 2 TEST TEST COMMifJTS MODE FOR U3 066 04 OFF-G AS DILUTION FAN ISOLATION DAMPERS SHALL DE 2 DFN RTP-06S NO LINIT 2 TEST SATISFIES CLOSED ON fNITIATION OF THE SGT SYSTEM (BS).
REQUIREMENTS 06 F01 PROVIDE COOLING WATER TO AC SYSTEM (31) CHILLERS RHR 2 DFN RTP=067 YES SYSTEM 474) PUMP SEAL COOLERS CIS (76) 02 & H2 (4 AS ANALYZERS DIESEL ENG!NES (821 RHR & CORE SPRAY EQUIPMENT ROOM COOL [R$ (64) & FUEL POOL (79). MAINTAIN EECW SYSTEM (231 PRESSURE DOUNDARY.
067.02 PROVIDE SECONDARY CONT AINMENT 00VNDARY.
2-DFN RTP 06S NO UNIT 2 TEST SATISFIES P.EQUIREMENTS 067 03 FOR SHUTDOWN FROM OUTSIDE OF MAIN CONTROL ROOM:(1) 2-DFN RTP 067 YES PROVIDE COOLING WA1ER TO RHR & CORE SPRAY EQU1PMENT ROOM COOLERS (64) RHR SYSTEM (74) PUMP SE AL COOLERS DIESEL ENGINES (82) & FUEL POOL (79)(2) MAINTAIN EECW SYSTEM (23) PRESSURE BOUNDARY.
067 05 ATTACH A FIRE HOSE TO EECW TO MAINTAIN WATER LEVEL IN 2 BFN RTP.067 NO PENDING ISSUANCE OF THE FUEL POOL.
UNIT 3 BTRD 068-01 CLOSE RECIRCULATION PUMP DISCHARGE VALVES ON RHR 2 DFN RTP 068 YES SYSTEM (74) AUTOMATIC LPCI MODE INITIATION SIGNAL.
068 02 OPEN RECIRCULATION PUMP MOTOR BRE AKERS ON REACTOR 2 DFN RTP-068 YES PROTECTION SYSTEM (99) SIGNAL DUE TO > 30% TURDINE L
FIRST STAGE PRESSURE AND EITHER MAIN TURBINE CONTROL l
VALVE FAST CLOSURE OR MAIN TURDINE STOP VALVES <90%
OPEN MANUALLY ENA8 LED END-OF-CYCLE RPT),
06803 CLOSE RECIRCULATION PUMP DISCHARGE VALVES MANUALLY 2 BFN RTP-068 YES IN SUPPORT OF MANUALLY INITIATED RHR SYSTEM (74)
SHUTDOWN COOLING MODE AND LPCI MODE (FROM MAIN CONTROL ROOM AND OUTSIDE MA6N CONTROL ROOM).
068-04 PROVIDE REACTOR COOLANT PREbsURE BOUNDARY (RCPD).
2-BFN RTP-068 YES
-)
068 05 PROVIDE LOW REACTOR PRESSURE PERMISSIVE SIGNALS TO 2 BFN RTP 068
-YES CORE SPRAY SYSTEM (7S) AND RHR SYSTEM (74).
068-06 TRIP RECIRCULATION PUMP MOTOR MOTOR-GENERATOR SET 2-DrN RTP 06S YES ON OPENING OF 4KV POWER DISTRIBUTION SYSTEM (S75) M G SET drive MOTOR BRE AKERS OUE TO HIGH RE ACTOR PRESSURE OR LOW WATER LEVEL (L21.
i-06908 PROVIDE PRIMARY CONT AINMENT BOUNDARY.
2-BFN RTP 064 A YES 069 01 PROVIDE PRIMARY CONT AINMENT BOUNDARY.
2-DFN-RTP 064 A YES 069-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN-RTP-06S NO SECOND ARY. CONTAIN<
MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING
~TBD TO BE DETERMINED
- BTRD BASELINE TEST REQUIREMENTS DOCUMENT
y ENCLOSURE 1 -
Page 12 of 20 3
TABLE 1 CORRELATION DETWEEN DROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS l
5 _-_
SYSTEM MODE DESCRIPTION UNIT 2 TEST 1EST COMMENTS MODE FOR U3 I
069 03 CLOSE HWCU SYSTEM ISOLATION VALVES ON PRIMARY 2 BFN RTP-069 YES CONTAINMENT SYSTEM (64) GROUP 3 ISOL ATION SIGN AL.
069 04 CLOSE RWCU SYSTEM SUCTION LINE ISOLATION VALVES ON 2-DFfJ RTP 069
-YES ST ANDBY LIQUID CONTROL SYSTEM (63) INITIATION SIGN AL TO PREVENT ENTRY OF BORON SOLUTION If4TO RWCU SYSTEM.
069 05 PROVIDE HIGH RWCU SYSTEM LOUIPMENT AREA ATMOSPHERE 2 BFN RTP 069 YES AND DRAIN TEMPERATURE SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 3 ISOL ATION LOGIC.
069 06 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPla 2 EJN RTP 068 YES 069 07 PROVIDE SYSTEM PRESSURE DOUNDARY SUPPORT (CHECK 2 DFN RTP-069 YES VALVEl TO HPC! SYSTEM (73) TO PREVENT DIVERSION OF HPCI SYSTEM CORE COOLING WATER FROM RE ACTOR VESSEL.
L 009 08 PROVIDE FLOW PATH FOR RCIC SYSTEM (71) CORE COOLING 2-DFN RTP-069 YES WATER TO RE ACTOR FEEDWATER SYSTEM (3) SPARGERS.
069 09 PROVIDE CAPADILITY OF MANUAL BACKUP CONTROL 2-BFN RTP BUC YES ISOLATION IVALVE CLOSUREI TO PREVENT LOSS OF RE AC10R WATER INVENTORY.
070-01 PROVIDE PRIMARY CONT AINMENT BOUND ARY.
2 NN RTP 064A YES 070 02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2.BFN RTP 06S NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT -
2 TESTING 070 03 PROVIDE DRYWELL COOLING WHEN POWER AND COOLING 2 BFN RTP-030 NO PENDING ISSUANCE OF WATER ARE AVAILABLE.
UNIT 3 BTRD 071 01 AUTOMATIC RCIC SYSTEM INITIATION ON REACTOR 2-BFN RTP-071 YES.
FEEDWATER SYSTEM (3) RPV LOW WATER LEVEL (L2) SIGNAL TR ANSMITTED VIA RHR SYSTEM (74L AUTOMATIC RCIC SYSTEM SHUTOFF (IF OPERATING) ON REACTOR FEEDWATER SYSTEM (31 RPV HIGH WATER LEVEL (LSI SIGN AL.
071 02 MANUAL RCIC INITI ATION AND TPilP TO CONTROL LEVEL.
24FN RTP-071 YES (NON-LOCA UNIT)-
071 03.
CLOSE RCIC SYSTEM STE AM SUPPLY LINE ISOLATION VALVES 2 BFN RTP-071 YES ON RCIC SYSTEM GROUP S ISOLATION SIGNALS (HIGH STEAM -
LINE DIFFERENTIAL PRESSURE HIGH STEM LINE SPACE TEMPERATURE OR LOW STEAM LINE PRESSUREL 071 04 MANUALLY CLOSE Aclc SYSTEM STE AM SUPPLY LINE 2-BFN RTP-071 YES ISOLATION VALVES ON REACTOR FEEDWATER SYSTEM (3) tNDICATION OF LOW RPV PRESSURE.
071 05 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY IRCPBl.
2 BFN RTP-068 YES l
071 07 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 BFN-RTP-064 A YES
. TBD TO BE DETERMINED BTRO BASELINE TEST REQUIREMENTS DOCUMENT y
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4 ENCLOSURE 1
- Page is of 20 -
C TABLE 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS i
t
$YSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 071 08 PROVIDE SYSTEM PRESSURE BOUNDARY IN SUPPORT OF RHR 2 BFN RTP 069 YES SYSTEM (74) CONT AINMENT ITokUS) COOLING FUNCTION.
071 09 MANUAL RCIC SYSTEM OPERATION FROM OUTSIDE THE MAIN 2-BFN RTP 071 YES
(
CONTROL ROOM TO MAINTAIN NORMAL RPV WATER INVENTORY WHILE RPV PRESSURE IS ABOVE 100 PSIG.
071 10 PHOVIDE POWER TO ECCS DIVISION I AND ll ANALOG TRIP 2 0FN RTP 071 YES UNITS (RE ACTOR FEEDWATER SYSTEM (3) PRIMARY j
CONTAINMENT SYSTEM 1641 REACTOR WATER RECIRCULATION SYSTEM (68) RCIC SYSTEM (71) AND HPCI SYS T E M (73)l.
{
071 11 PROVIDE SPONDARY CONTAINMENT 00VNDARY.
2 DFN RTP 066 NO SECONDARY CONTAIN.
NENT WAS TESTED AS 4
A WHOLE DURING UNIT 2 TESTING l
073 01 AUTOMATIC HPCI SYSTEM INITIATION ON REACTOR 2 DFN RTP-073 YES FEEDWATER SYSTE M 13) RPV LOW WATER LEVEL (L2) SIGN AL.
AUTOMATIC HPCI SYSTEM GHUTOFF (IF OPERATING) ON RE ACTOR FEEDWATER SYSTEM (3) RPV HIGH WATER LEVEL
[
(L8) SIGN AL, 073 03 CLOSE HPCI SYSTEM STE AM SUPPLY LINE ISOLATION VALVES 2 BFN RTP 073 YES ON HPCI SYSTEM GROUP 4 ISOL ATION SIGN ALS (HIGH STE AM LINE DIFFERENTIAL PRESSURE HIGH STE AM LINE SPACE TEMPERATURE OA LOW STEAM LINE PRESSURE).
073-04 MANUALLY CLOSE HPCI SYSTEM STE AM SUPPLY LINE
.2 DFN RTP-073 YES ISOLATION VALVEB ON RE ACTOR FEEDWATER SYSTEM (3)
INDICATION OF LOW RPV PRESSURE.
073 OS PROVIDE RE ACTOR COOLANT TRESSURE BOUNDARY (RCPB) 2 DFN RTP 068-YES DURING HPCI SYSTEM STANDBY.
073 06 PROVIDE RE ACTOR COOLANT PRESSURE DOUNDARY (RCPB) 2 DFN-RTP-068 YES DURING HPCI SYSTEM OPERATION.
073 07
- PROVIDE PRIMARY CONT AINMENT DOUNDARY DURING HPCI-2 BFN RTP 064 A YES SYS1EM ST ANDBV, 073 08 PRO' VIDE PRIMARY CONTAINMENT BOUNDARY DURING HPCI-2 BFN RTP 064 A' YES SYSTEM OPERATION.
073 09 MANUALLY TRIP HPCI SYSTEM FROM OuTf;'DE THE MAIN 2-DFN RTP 073 YES
- [
CONTROL ROOM TO PREVENT RPV OVERFILL.
073 11 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2 BFN RTP 066 NO' S ECOND ARY 'CONTAINI i
MENT WAS TESTED AS.
- A WHOLE OURING UNIT:
's 2 TESTING '
i t
I
~ TBD-- TO BE DETERMINED -
BTRO BASELINE TEST REQUIREMENTS DOCUMENT.
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9 CNCLOSURE1 Peue 14 of 20 TAl3LE 1 CORRELAllON BETWEEN BROWNS FERRY NUCLEAR PLANT UNll S 2 AND 3 REST ART TES1 PROGRAMS
$YST[M MODE DLSCRiPTION UNIT 2 TIST TEST COMME NT S MODE FOR V3 073,12 PROVIDE POWER TO PRIMARY CONT AINMENT SYSTLM (541 2 Of N RTP 004 A YLS DRYWELL PRISSURE INDICATORS IN SUPPORT OF RHR SYSTEM DRYWlLL/ TORUS SPRAY MDDE AND CONT AINfAENT ATMOSPHERC DILUTION SYSTEM POST LOCA CONT AINMLNT VIfJTING MODE.
074 01 AUTOMATIC LPCI MODE INITIATION ON RPV LOW WATER 2 DIN RTP 074 YES LEVIL (Lil SIGN AL OR HIGH DRYWELL PRESSURE SIGN AL WITH
~~
CONCURRENT LOW RPV PRESSURL PERMISSIVE SIGN AL.
MANUAL LPCI MODE INITIATION IROM THE MAIN CONTROL ROOM t
074 02 PROVIDE SUPPRESSIOf4 POOL WATER COOLING TO MAINT AIN 2 Bf N RTP 074 YES SUPPRESSION POOL WATER TIMPER ATURE DELOW LIMITS TO ASSURE THAT FUMP NPSH REOutR[MENTS ARE NLT ANO TH AT COMPLETE CONDtNS ATION OF DLOWDOWN STE AM iROM A DISIGN DASIS LOC A C AN DE EXPECl[D.
074 03 PROVIDE SPR AY TO DRYWELL AND TORUS TOR CONT AINMINT 2-[JN H1P 074 YES COOLING AND LOWERING OF CONT AINMENT PRESSURL UNDER POST. ACCIDENT CONDITIONS.
074 04 PROVIDE SHUTDOWN COOLING MODE (MANUAll10 RESTORE 2 blN RTP 074 YES Rf ACTOR 1[MPERATURE TO NORMAL.
074 09 PROVIDE SECONDARY CONT AINMENT DOUNDARY.
2 Df N R1P 06S NO SLCONDARY CONTA;N=
MCNT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 074-10 PROVIDE RE ACTOR COOL ANT PRESSURE COUNDARY (RCPOL 2 DfN RTP Of.B YES 074 11 PROVIDE PRIMARY CONT AINMENT DOUNDARY.
2 Rf N RTP Otm A YES 074 12 PROVIDE SIGN AL (1H AT A RHH PUMP 15 RUNNING) TO M AIN 2 din RTP 074 YES STE AM SYSTEM (1) AUTOMAllC DEPRLSSURIZATION SYSl(M s
( ADS) INITI ATION L OGIC.
n 074 17 PROVIDE AUTOMATIC LPCI MODE INITIATION SIGNAL FOR 2 Bf N RTP 074 YES CLOSURE OF RE ACTOR W AllR RLCIRCUt ATION SYSTEM RBI PUMP DISCHARGE VALVES.
074 19 MANUAL RHR SYSTLM OPERATION (LPCI TORUS COOLING AND 2 DrN RTP DUC YES SHUTDDWN COOLING MODES) FROM OUTStDE THE MAIN CON.T. ROL ROOM.
074 20 PROVIDE FLOW PATH AND PRISSUfa DOUNDARY IfJTEGRiTY 2 DFN RTP 074 YES FOR RHR SIRVICE WAT(R SYST M (23) COOLANT TO THL MAIN RHR SYSTEM HEAT EXCHANGERS.
074 21 PROVIDE RE ACTOR TEEDWATf R SYSTEM {3) MPV LOW WATER 2 GrN RTP-071 YES LEVEL (L2) SIGN AL FOR AUTOMATIC RCIC SYST[M (71)
INITI ATION.
TUD TO DE DETERM:NED DTRD BASELINE TEST REQbiREMENTS DOCUMENT
._ ~.
L.,
ENCLOSURE 1 Pe9* 15 of 20 TABLE 1 1
-I CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 ftESTART TEST FH0 GRAMS SYSTEM MODE DESCRIP110N UNIT 2 TEST TEST COMMENis MODE FDR U3 074 22 PROVIDt RHR SYS EM UNIT CROSD Tit VALVES OPEN 2 DFN-RTP-023 YES PENDING ISSUANCE OF POSITION SIGNAL TO RHR SERVICE WATER SYSTEM (231 FOR UNIT J tiTRD CLOSURE OF RHR SERVICE WATER VALVES TO MAINT AIN PRIMARY CONT AINMENT BOUNDARY.
074-23 RHR ISOL ATION SIGNAL TRIPPED ON SIGNAL FROM PRIMARY 2 WN RTP 004A YES CONT AINMENT SYSTEM (64).
07S~01 SUPPLY COOLING WA1ER TO REACTOR AUTC INITIATION.
- 2 DFN RTP-075 YES l 075 03 PROVIDE CS PUMP POWER DISCONNECT FROM OUTSIDE MCA.
2 DFN-RTP 075 YES 07S 04 PROVIDE REACTOR COOLANT PRLSSURE DOUNDARY.
2 DFN RTP-068 YES 07 SOS PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 DFN RTP-044 A YES-L 075 06 PROVIDE ACCIDENT SIGNAL INPUT TO 480V LOAD SHED 2 DFN-RTP-075 YES LOGIC.
075 07 PROVIDE START SIGNAL TO DIESEL GENERATOR ON LOW 2 BFN RTP 07S YES LEVEL (L1) OR HIGH DRYWELL PRESSURE.
07S OB PROVIDE PRIMARY CONT AINMENT SYSTEM (641 HIGH 2 DFN RTP-073 YES DRYWELL PRESSURE SIGNAL FOR AUTOMATIC HPCI SYSTEM c
(73) OPERATION.
07S 10 PROVIDE SIGNALS (THAT CORE SPRAY PUMPS ARE RUNNINGl 2 DFN RTP 075 YES TO MAIN STEAM SYSTEM (11 AUTOMATIC DEPRESSURIZATION SYSTEM ( ADS) INifl ATION LOGIC.
r 075 11 PROVIDE REACTOR FEEDWATER SYSTEM (3) RPV LOW WATER 2 DFN RTP 074 YES LEVEL (L1) GIGNAL TO RHR SYSTEM (74) LPCI MODE INITIATION -
LOGIC.
l 076 12 PROVIDE REACTOR FEEDWATER SYSTEM (3) AND REACTOR 2 DFN RTP,068 YES
=
WA1!R RECIP,CULATION SYSTEM (68J LOW RE ACTOR PRESSURE SIGN ALS TO RHR SYSTEM (74) LPCI MODE
_=
INITI ATION LOGIC.
SE' ONDARY CONTAIN-75 13 PROVIDE SECONDARY CONTAINMENT DOUNDARY.
2 BFN41TP-065 NO C
MENT WAS TESTED AG-si A WHOLE DURING UNIT -
i.
2 TESTING i
075 14 PERFORM ISOLATION ACTIONS UPON RECEiVLNG ISOLATION 2 DIN RTP 064A YES SIGNAL (LOW LEVEL L3 Of1 HIGH DRYWELL PRESSURE) FROM THE PRIMARY CONTAINMENT SYSTEM (64).
076 01
- CLOSE CONTAINMENT INERTING SYSTEM ISOLATION VALVES 2 BFN RTP OS4
.YES
(!'
i.
ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOL ATION SIG N AL.
s TDQ' TO DE DETEP. MINED -
I' BTP.Gl BASELINE 7EST REQUIREMENTS DOCUMENT l
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.. _ _ _ _ _. _. _. _.. _ _ _ _ _ _ _ _. _ ~. _.. ~. _ _. _ _.. _. _. _ _ _.
.i ENCLOSURE 1 Peo.16 of 20 TABLE 1
.I CORRELATION BETWEEN DROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TESI PROGRAMS I
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3
_ _ _ - - ~ _ _.. - - -
076-02 PROVIDE OXYGEfJ AND HVDROGEN GAS AfJALYZERS AND 2-BrN RTP OB4 YES INDIC ATORS TO MONITOR G AS CONCENTR ATIONS INSIDE THE PRIMARY CONTAINMENT IN SUPPORT OF CONTAINMENT ATMOSPHEHE DILUTION,SYST(M (84) OPER ATION.
076-03 PROVIDE PRIMARY CONTAINMENT DOUNDARY, 2 Bf N RTP-064 A YES-076 04 PROVIDE SECONDARY CONTA!NMENT BOUNDARY.
2 BrN RTP 005 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT-2 TESTING t
077 01 CLOSE RADWASTE SYSTEMISOLATION VALVES ON PRIMARY 2 DFN RTP 024 YES CONT AINMENT SYSTEM (64) GROUP 2 ISOL ATION SIGN ALS.
077 02 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 EITN RTP-004A YES 077 03 PROVIDE SECON9ARY CONTAINMENT BOUNDo.RY.
2 DFN-hTP'065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLF DURING UNIT 2 TESTING 07.8-01 PROVIDE SECONDARY CONT.4lNMENT BOUNDARY.
2 BFN RTP 065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING y
078 02 PROVIDE PRES $URE BOUNDARY INTEGRITY AT RHRlFPC 2 BFN RTP 074 fBD PENDING ISSUANCE OF INTERFACE.
UNIT 3 BTRD 070 03
' PREVENT IN ADVERTENT SIPHONING OF THE SPENT CUEL POOL.
2-DFN RTP-069 YfS 079 01 PROVIDE SAFE TUEL HANDLING USING REFUEL BR!DGE &
2mDFN RTP 079 NO
- UNIT 2 TEST SATISFIES -
EQUIPMENT.
REQUIREMENTS 079 02 -
PROVIDE INTERLOCKS TO CRD SYSilM DURING FUEL 2 BFN RTP 085 YES MOVEMENT.
082-01 START STANDBY AC POWER SOURCE FOR 4KV SYSTEM (57S) 2-DFN RTP-082 YES PENDING iSSU ANCE OF UNIT 3 BTRD
-082 02 PROVIDE POWER TO 4KV SYSTEM 1575) UPON D/G 2 DFN RTP-OB2 YES AVAIL ABILITY AND LOSS UF OFF. SITE POWER.-
OD2 03 PROVIDE D/G POWER TO DIESEL FUEL' TR ANSFER 2 BFN RTP-OS2 NO UNIT 2 TEST S ATISFIES PUMPS (SYSTEM 18),
ALL REQUIREMENTS-084-01 PROVIDE Dil,UTION OF THE PRIMARY CONTAINMENT '
2 BFN RTP 084 VES-PENDING ISSU ANCE OF 3
ATMOSPHERE Wl_TH NITROGEN AFTER A LOCA TO MAINTAIN UNIT 3 BTRD.
COMBUSTIBLE GAS (OAYGEN AND HYDROGEN)
CONCENTRATIONS DELOW LEVELS lOXYGEN S% BY VOLUME)
WHICH COULD) PRODUCE A COMBUSTIBLE G AS M!XTURE.
~
' TBD~ ' TO BE DETERMINED ~
BTHD DASELINE TEST REQUIREMENTS DOCUMENT
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, M$4 5NCLOSUREb Fia*17offo r e,
TAbtE 1 y
CORRELATION NE15MENN BROWNS FERR NUCLEAR PLANT UNIT 3 2 ANO 3 RESTART TtIST PROGRAMS j
w.. wxarrarswawawmvaw.mmwwuma--mmsrmawmem.wm.wn:=.w-=--
wemume arm-wreve===.ma SYGYTM M0cr DESCRIPUCN UNIT 2 7tsf TisT COMMENTS.
-e MODE FOR t
U3 r
km:v.wnnu.w.a rxuanstr.:c~ -
- -w
~.aoxuw-~rcr,:csanaas mar
-- aws,ww:
C34 03 PCOVOt PRrMARY CONT AINVENT 80VHDARY.
24FN VP-Oo4A YES j.
I e+
00404 PAOVIDE SECONDARY CONTAINMENT BCUNDARY, 7 RFN HTP-005 NO SECONDARY CONTAith MENT WAfi TESTED A5 I
A WHOLE DLlRtN4 UMT 1 2 TESTING -
- J
)i 084-05 PF16VtOf NITROGEN TO THF. CONTROL AlH SYSTErA (32)W NONE _'
YSD tJNIT 2 TCETING DY SUPPORT OF LONG TEA,N OPERAB4 TTY OF MAIN STEAM SOST MODIFICATK h l
SYSTEM A D3 S AFETY RO.lO VALVLJ $PM) APPENDa( A.
-TES*(. VNIT 3 pet: DING =
ISSUANCE OF FITitD.~
O
=:
_a
.084 06 CLOW CAD SYSTEM VENT VA1,.VES ON PPJMAfW 2 BFfeRTP 084 YES i
CONT AINMENT UYSTEM (64) CROLA 6 (SO( ATION LGN AL.
[
085-0 t Pfl0 VIDE SCRAM M1 AND CLOSE OV VENT ORklM VALVES.
'YES'
_y.
- L 085 02 PROVIDE PR(MARY CONTAINM5NT BOUND ARY.
2 DFN ATP 064A VLS t
s y
085-03 PROVIDE SECONCARY CONTAWMENT SOUNOARY.
2 BFN RTPO65 NO, SEcottshY CONTAlfQ
[
MINT WAS 7ESTEG A3 i '
?
8 AVMCLFbORING UNIT _
d
'I
,z
-1 TESTING..
s 4
08r04 PROVIDE Pt? ACTOR r.'OOLANT PMES$URE 000NOARY (RCPB).
2-BFN RTP-068 JYES :
r M
y 08'i 05 PPEVENT ROD WIDiDRAWA(,
2-BFN RTP 085 -
"N l-q.
085 08 PR0v10E MOR riOD POSITION (NDICATION.
2 BFN4TP,C80 YESi 4
x d
085-Oh Pf40 VIDE SCG rJA DISChARdE WGH WATER LEVEL StGNAL.
2 CD) RTP 085 -
YES i 0610-
' PROVIDE SCHAM OfSCHARGE LOW AIR HEADER PAISuuRL-2WN-RTP-085 '
'YES m
IE S'tillAL 08011-PROVIDE REMOTE BACKVP CONTROL H10M QVTSIDE TH~ MAtM 2 BFN RTP dud
- YF.S '
+
P
' Cf1NTROL ROOM.'
D31514 '
PROW)E ALTERNATE ROD INSERTION 8Y OPERNG BACKUP
' : BN RTP-085 -
.YES - l h
SCO AM VALVE 3 ON t *EDWATER SYSTr# (3) OPV LOW WATER -
~,
LLEVEL IL2) SIGAL CA HIGH RE ACT08 VE0SEL PRESSURE w-3_ j..
p.
gSIGNAL.
a n
q
. i
. l 3
L i
4 1
+3
. q 1TBD. TO SE DFTEFM.hiD 1
M,t flTRD 1 BASCUNE TEST REQUlP.tMWT5 OOCUMENT -
j >
t Ml' 7
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- ENCi.0SURE 1:
i Paos 18 of :D ?
r
?
S'k TABLE 1 4
CORRELAllON DETWEEN BROWNS FERRY NUCLEAR PLANT UlllTS 2 AND 3 RESTART TEST PROGRAMS saw _-
.mw
=
g Y$ TEM S
MODA DESCRIPTION UNIT 2 TEST -
TEST COMMENTS.
i -
MODE FOR
?
U3
- -ww.r.
- OH 0)
Mov!DE DIESEL STARTING AIR TO DIESEL GENERATOR 2 DFN-RTP.082 NO TESTS WERE SYSTEM (02L PERFOfMED IN d
ACCORDANCE WITW2+
BFN RTP 082 REV Q ANO 10THE RESULTS G
OF THESE TESTS WERE iI f1EWEWED AND FOUND.
_Q TO SE ACCEPTABLE TO VERIFY SYSTEM MODE.
REQUIREMENJS FOR "
UNIT 3.
6
~..
OEO 01 PROVIDE MAIN STEAM LIVE HIGH RAL,l ATION SIGNAL 70 2 BFN-RTP-090 YES REACTOR PROTECTION SYSTEM (99).-
090 02 PROVIDE PRIMARY CONTAINMENT BOUNDARY (UP TO 2 BFN-RTP 064 A YES 2 -FCV-90-2S4 A B-2SS-257 A B).
2 Ga&O3 "9 VIDE REACTOR BOU.'ING VENTILATION EXHAUST LINE AND 2 BhbRTP 090 VES r 'NG ZONE AREA ( ADJACENT TO THE FUEL POOLS) HIGH
. - " SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64)
Uf.AT!ON LOGIC.
000-04 9 ONTROL r aCM INTAKE AIR DUCTS EXCESSIVE 2 BFN-RTP 031B No' UNIT 2 TEST' S ATiSFIES.
c 3
RAb
.;N S!GNALTO AIR CONDITIONING SYSTEM (31) FOR REQUIREMENTS -
INITIATION OF CONTROL h00M EMERGENCY VENTILATION (ISOLATION OF INTAKE DUCTS AND SUPPLY OF PRESSURIZED FILTERED OUTDOOR AlR).
09005 CLOSE val ?ES ON SUCTION AND RETURN LINES TO THE '
2 BFN-RTP 090 YES DHYWELL RADIOACTWE PARTICULATE LODINE AND GASEOUS MUNITOR ON PRIMARY CONTAINMENT SYSTEM (E A) GROUP 6 IS_OLATI,ON SIGNAL.
090-08 PROVIDE SECONDARY CONTAINMENT BOUNDARY 2 BFN RTP 06S NO SECONDARY CONTAIN-MENT WAS TESTED AS l
- A WHOLE DURING UNIT 2 TESTING -
4 092-01 PROVIDE IRM HIGH NEUTRON FLUX TRIP SIGN AL TO REACTOR 2 BFN-RTP-092 YES PROTECTION SYSTEM I
'YES' 092,02 PROVIDE APRM HIGH NEUTRON FLUX TRIP S!GNAL TO REACTOR PHOTECTION SYSTEM (99).
092-07 PROVIDE REACTOR COOL ANT PRFSSURE BOUNDARY (RCPB).
-2 BFN RTP 068 YES 094-01 PROVIDE PR! MARY CONTAINMENT INTEGRITY.
2 DFN RTP-064A:-
YES 094-03
. PROVIDE REACTOR COOL ANT PRESSURE BOUNDARY (RCPB1 2 BFN_-RTP 064A YES-
-(PASSIVE FUNCTION ONLYi l
099 01
. PROVIDE AUTO SCRAM 8. SDV VENT /9R AIN VALVE ISOLATION 2-BFN-RTP 099 YES SIGN AL TO CRD SYSTEM (BS).
L tTBD TO BE DETERMINED
- BTRO BASELINE TEST REQUIREMENTS DOCUMENT
-,-m
ENCLOSURE 1-
[Poge 19 of 20 TABLE 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART-TEST PROGRAMS m
n 3
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 099 02 PROVtDE MANUAL SCRAM SIGNAL AND SDV VENT /DR AIN 2-BFN f4TP 099 YES VALVE ISOLATION SIGN ALS TO CRD SYSTEM (85).
099 03 PROVIDE 'RUN' MODE SGNL TO PCIS (04) FOR LOW STEAMUNE 2 DFN RTP-099 YES PRESSURE ISOLATION PERMISSIVE.
,-)
099-04 PROVIDE REFUEL INTERLOCK TO RE ACTOR MANUAL CONTROL 2 BFN-RTP 085 YES l
SYSTEM. (85) 099 05 PROVIDE TRIP SIGNAL TO RECIRC PUMP MOTOR BREAKERS 2 BFN RTP 068 YES
-(SYSTEM 68).
-a M
099-06 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 UNIT 2 TEST SATISFIES -
SHUTDOWN FROM OUTSIDE THE MCR.
REQUIREMENTS -
~?
'303 04 SECONDARY CONTAINMENT LEAKAGE RATE CRITERIA MUST 2 BFN RTP 065 NO UNIT 2 TEST SATISFIESI i
BE MAINTAINED BY THE RE ACTOR ButLDING.
REQUIREMENTS -
E,71 OI PROVIDE 125V DC CONTROL POWER TO DG CIRCUITRY 2 BFN RTP 571 NO PENDING ISSUANCE OF.
(SYSTEM 82).
UNIT 3 BTRD 572 02 PROVIDE UNIT PREFERRED POWER DISTRIBUTION.
2-BFN RTP 57 2 NO PENDING ISSUANCE OF7 UNIT 3 BTRD 5
i 572 03 PROVIDE 120V AC POWER FOR RPS SYSTEM.
2 BFN RTP-b7-2 NO PENDING ISSUANCE OF UNIT 3 BTRD
- (
~
573 PROVLDE CONTROL & LOGIC POWER TO 4KV & 480V 2 BFN RTP 57 3 NO-PENDING ISSUANCE OF SWITCHG E AR.
UNIT 3 BTRD -
573 03 PROVIDL MOTIVE POWER & LOGIC POWER TO EQUIPMENT.
2-BFN-RTP 57 3 NO PENDING ISSUANCE OF :
UNIT 3 BTRD.
3' 573-05 PROVIDE LOG!C POWER TO 480V LOAD SHED LOGIC.
2-BFN RTP 57 3 fjo -
- PENDING ISSUANCE OF.
UNIT 3 BTRD.
574-01 PROVIDE 480V SWITCHGEAR DISTRIBUTION.
2 BFN-RTP 57-4 h0-PENDING ISSUANCE OF -
BTRD 574 O2 PROVIDE 480V MCC DISTRIBUTION.
2 BFN-RTP 57-4 YES
_PENDING ISSUANCE OF ~
.(
BTRD 574-03 PROVIDE 4BOV LOAD SHED LOGIC SYSTEM.
2 BFN RTP-57 4 NO' PENDING ISSUANCE OF.
BTRD=
574-04 PROVIDE 480V AC DISTRIBUTION BACKUP CONTROL.
2 BFN RTP BUC NO UNIT 3 SCOPE PENDING,
ISSUANCE OF BTRD 575 01 PROVIDE 4 KV POWER DISTRIBUTION FOR DG LOADING 2 BFN RTP 57-5_
YES PENDING ISSUANCE Of (SYSTEM 82).
BTRD -
d 575-02 PROVIDE RECIRCULATION PUMP TR!P UPON StGNAL.
2-BFN-RTP 068 YES TBD TO BE DETERMINED BTRO BASELINE TEST REQUIREMENTS DOCUMENT
.4, ENCLOSURE 1 Page 20 of 20 -
- -. 3A e.y
=
. TABLE 1 CORRELATION BETWEEN BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 RESTART TEST PROGRAMS SYSTEM MODE DESCRIPTION UNsT 2 TEST TEST COMMENTS -
- MODE
- FOR..
U3 575 03 Ph0 VIDE INSTRUMENTATION FOR DG PARALLELING (SYSTEM 2-BFN-RTP-57 5 ~
NO.
UNIT 3 SCOPE PENDING 82)
ISSUANCE OF BTRD 575 04 PROVIDE INITIATION SIGNAL TO DIESELS (SYSTEM 82).
2-BFN RTP 57 5 NO-UNIT 3 SCOPE PENDING--
ISSUANCE OF BTRD 575 06-BACKUP CONTROL FOR 4KV FEEDER BREAKERS OUTSIDE THE 2-BFN RTP-BUC NO-UNIT 2 TEST SATISFIES CONTROL BAY, REQUIREMENTS ~
575 07 LOAD SHEDDING TO PREVENT OVERLOADING OF 4KV SYSTEM 2-BFN RTP 57 5
.NO UNIT 3 SCOPE PENDING -
(575),
ISSUANCE OF BTRD.
- SYSTEM MODES IN WHICH A UNIT 2 TEST WAS NOT PERFORMED AND A UNIT 3 TEST IS NOT REQUIRED HAVE BEEN REMOVED FROM ;
THE T ABLE, i
4 t
i y
l i
I-
.TBD -- TO BE DETERMINED -
BTRO BASELINE TEST REQUIREMENTS DOCUMENT
.b 4_
ENCLOSURE 2 -
SUMMARY
OF COMMITMENTS -
TVA expects the remaining BTRDs to be complete by June 30,1993, and will provide:
another update at that time.
s' 3