ML20093M657
| ML20093M657 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/19/1995 |
| From: | Salas P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9510270013 | |
| Download: ML20093M657 (26) | |
Text
,
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' Tennessee Valley Authority, Post Office Box 2000. Decatur Alabama 35609 October _ 19, 1995 o
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555-
- Gentlemen:
In the Matter of
)
Docket No. 50-296 Tennessee Valley Authority
)
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - CHANGES TO RESTART TE8T PROGRAM AND POWER ASCENSION PROGRAM During recent BFN restart review board meetings with NRC, TVA has described several areas of difference between the test programs conducted for Unit 2 and the planned test program for Unit 3.
These areas include Training Criticals, Management Assessment Hold Points, and Control Rod Drive Friction Testing.
One additional area of difference which has not been previously described involves testing of Drywell Piping Vibration.
A description of each of these differences is included in Enclosure 1.
Additionally, changes to the Baseline Test Requirement Documents have resulted in a revision to the table listing the correlation between BFN Unit 2 and 3 Restart Test programs.
This table was most recently submitted by TVA's letter to NRC dated July 19, 1993, " Restart Test Program Update for Unit 3."
The revision to this table is provided as Enclosure 2.
Shaded areas indicate changes from the July'19, 1993 submittal.
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9510270013 951019 PIMR-ADDCK 05000296' D;
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U'.S.LNuclear Regulatory Commission-Page.2
' October = 19, 1995
)
l There are'no newicommitments contained in this letter.
.If you have any questions, please contact me at (205) 729-2636.
LManager of Site Licensing _
Enclosure-cc (Enclosure):-
j Mr. Stewart D.
Ebneter Regional Administrator i
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Mark S.
Lesser, Acting Branch Chief U.S.
Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900
-Atlanta, Georgia 30323 NRC Resident Inspector i
Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 i
Mr. J. F Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 1
1
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWN 8 FERRY NUCLEAR PLANT (BFN)-
UNIT 3 POWER ASCENSION PROGRAM (PAP) 1.
Training Criticals Training criticals, performed prior to Unit 2 return to service, will not be performed prior to Unit 3 operation.
Prior to Unit 2 return to service in 1991, a BFN unit had not operated since 1985.
Since Unit 2 return to service in 1991, operators and procedures have been exercised routinely on Unit 2 and the simulator.
Consequently training criticals are not required for Unit 3 restart.
2.
Management Assessment Hold Points i
During the Unit 2 PAP, seven hold points were established for management assessments.
For the Unit 3 PAP, five hold points have been established for management assessments as listed below:
Completion of Open Vessel Testing Prior to Mode Switch to RUN Prior to Exceeding 35 percent Core Thermal Power Prior to Exceeding 55 percent Core Thermal Power Completion of Testing - Final Assessment For the Unit 2 PAP, there were management assessment hold points after training criticals were performed and prior to exceeding 80 percent power.
Since training criticals will not be performed during Unit 3 restart, a management assessment at this point is no longer required.
Due to the limited testing performed between 55 percent and 80 percent core thermal power, no meaningful management assessment would be realized with a hold point prior to exceeding 80 percent power.
s For Unit 2, a hold point was established prior to exceeding 25 percent power.
This assessment will be performed for Unit 3 prior to exceeding 35 percent core thermal power.
1 3.
Control Rod Drive (CRD) Friction Testing For the Unit 2 PAP, CRD friction testing was performed for each control rod by measuring the pressure differential 1
1
between the insert and withdraw lines during control rod movement.
In this method of testing, excessive differential pressure is indicative of high drive friction.
For Unit 3, CRD friction testing will be performed by measuring notch to notch times during continuous rod movement.
Abnormal drive friction is indicated by a slower than normal time between notches.
Additional diagnostic testing using the differential pressure method can be used 4
should any CRDs exhibit high drive friction as indicated by the notch to notch times.
4.
Drywell Piping Vibration Testing For the Unit 2 PAP, vibration qualification testing was performed for piping determined to be impacted by design changes and modifications.
For those systems on Unit 3 where similar modifications have been performed, no additional vibration qualification testing is required.
On Unit 3, design changes and modifications have been made to the recirculation system piping.
Vibration testing is planned to be performed on the impacted piping in conjunction with other recirculation system testing conducted in the open vessel test phase, d
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d El-2
ENCLOSURE 2 P g31 cf 22 i
TABt2 timme ATION SETWEEN BRUWFPS PEERY NU(LEAR (DFf4 15ETE 2 Ape 3 BarrART TEET ymmAM (RTP)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 001-01 PROVIDE MAIN TURBINE STOP VALVES < 90% OPEN TRIP 2-BFN-RTP-001 YES SIGNAL TO REACTOR PR0rrECTION SYSTEM (99) 001-02 PROVIDE MAIN STEAMLINE ISOLATION VALVE < 90% OPEN 2-BFN-RTP-001 YES TRIP SIGNAL TO REACTOR PROTECTION SYSTEM (99) 001 03 CLOSE MAIN STEAMLINE ISOLATION VALVES ON PRIMARY 2-BFN-RTP-001 YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGNAL.
001-04 CLOSE MAIN STEAM DRAIN LINE VALVES ON PRIMARY 2-BFN-RTP-OOl YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGNAL 001-05 OPEN MAIN TURBINE STEAM BYPASS VALVES ON TURBINE 2-BFN-RTP447 YES CONTROL SYSTEM (47) TURBINE TRIP SIGNAL 001-06 CONTROLLED MANUAL DEPRESSURIZATION OF REACTOR 2-BFN-RTP-001 YES PRESSURE VESSEL (RPV) BY OPENING AtJTOMATIC DEPRESSURIZATION SYSTEM (ADS) SAFETY RELIEF VALVES j
(SRVS).
l 001-07 OPEN SAFETY RELIEF VALVES (SRVS) ON HIGH REAcrOR 2-BFN-RTP-001 YES PRESSURE TO PROVIDE RPV PRESSURE RELIEF.
001-08 AUTO OPENING OF ADS SRVS UPON COINCIDENT SIGNALS OF 2 2-BFN-RTP-001 YES CORE SPAY (CS) PUMPS (75) OR 1 RESIDUAL HEAT REMOVAL (RHR) PUMP (74) AND EITHER LOW WATER LEVEL (LWL)
(Ll&L3 FROM SYS 03) HIGH DRYWELL (DW) PRESSURE (SYS 64)
AND TIME DELAY OR LWL (Lt FROM SYS 03) AND HIGH DW PRESSURE BYPASS TIME DELAY.
001-09 CLOSE MAIN TURBINE STOP VALVES UPON TURBINE CONTROL 2-BFN-RTP-047 YES SYSTEM (47) DIVER $10N OF HYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGNAL (SYSTEM 47).
001-11 MANUALLY DEACTIVATE NON-ADS SRVS AND MAIN STEAM 2-BFN-RTP-001 YES ISOLATION VALVE (MSIV) TEST CIRCUTTS TO PREVENT INADVERTENT RPV DEPRESSURIZATION AND LOSS OF COOLANT.
001-12 PROVIDE LOW PRESSURE SIGNAL (IN M AIN STEAM LINE AT 2-BFN-RTP-001 YES TonBINE) 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 2 001-15 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP465 NO SECONDARY CONTAIN-4 MENT WAS TESTED AS A WHOLE Dt < NG UNrf 2 TESTING 001 16 CLOSE FEEDWATER PUMP TURBINE STOP VALVES (TO TRIP 2-BFN-RTP-003B YES FEEDWATER TURBINE) ON LOSS OF HYDRAULIC PRESSURE DUE TO ENERGIZATION OF FEEDWATER SYSTEM SOLENOID.
E2-1
ENCLOSURE 2 POOO 2 cf 22 TAal2 l
l pnames avgen guywggw paging pummy punzAs gypg ENTE 3 AFS 3 ENTART1957 FwmW (ETF)
I SYSTEM MODE DESCRIFFION UNrr 2 TEST TEST COMMENTS I
MODE FOR U3 001-17 PROVIDE MAIN STEAM LINE HIGH FwW AND HIGH STEAM 2-BFN-RTP-001 YES TUNNEL TEMPERATURE SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION 001-21 PROVIDE MAIN TURBINE STOP VALVE CLOSURE Postr10N 2-BFN-RTP-047 YES SIGNALS TO TURBINE CONTROL SYSTEM (47) WHICH INITIATES OPENING OF MAIN TURBINE BYPASS VALVES.
001-22 CI.DSE MAIN TURBINE BYPASS VALVES UPON TURBINE 2-BFN-RTP-001 YES CONTROL SYSTEM (47) DIVERSION OF HYDRAULIC PRESSURE DUE TO LOW CONDENSER VACUUM SIGNAL (SYSTEM 47).
001-23 PROVIDE >30% TURBINE FIRST STAGE PRESSURE INTERLOCK 2-BFN-RTP-001 YES SIGNAL TO REACTOR PROTECTION SYSTEM (99) FA!!< SAFE LOGIC.
001-24 PROVIDE MAIN STEAM LINE PRESSURE SIGNAL TO TURBINE 2-BFN-RTP-001 YES CONTROL SYSTEM (47) FOR OPERATION OF M AIN TURBINE BYPASS VALVES.
001-25 MANUALLY CLOSE M AIN STEAMLINE ISOLATION VALVES 2-BFN-RTP-001 YES (MS!VS) AND MAIN STEAM DRAIN LINE VALVES.
002-06 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 No SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 002-08 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 003-01 PROVIDE HIGH REACTOR VESSEL PRESSURE'IRIP SIGNAL TO 2-BFN-RTP-003A YES REACTOR PROTECTION SYSTEM (99) FAH< SAFE LOGIC.
003-02 PROVIDE RPV thW WATER LEVEL (L3) TRIP SIGNAL TO 2-BFN-RTP-003A YES REACTOR PROTECTION SYSTEM (99).
00343 PROVIDE RPV LOW WATER LEVEL (L2) SIGNAL TO HPCI 2-BFN-RTP-003A YES SYSTEM (73).
003-04 PROVIDE RPV LDW WATER LEVEL (L3) PERMISSIVE SIGN AL TO 2-BFN-RTP-003A YES MAIN STEAM SYSTEM (01) FOR ADS.
00345 PROVIDE RPV HIGH WATER LEVEL (L8) SIGNAL TO REACTOR 2-BFN-RTP-003 A YES CORE ISOLATION COOLING (RCIC) SYSTEM 01) AND/OR HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM G3) FOR j
003-06 PROVIDE HIGH REACTOR VESSEL PRESSURE SIGNAL TO 250 2-BFN-RTP-003A YES ANTICIPATED VDC SYSTEM (573) TO OPEN RECIRCULATION PUMP M/G SET 2-BFN-RTP-068 TRANSIENT WITHOLTI DRIVE MOTOR BREAKERS FOR TRIP OF RECIRCULATION PUMPS SCRAM WAS TESTED l
AND TO CONTROL ROD DRIVE (CRD) SYSTEM (85) TO INrrtATE BY RTP468 ALTERNATE ROD INSERT.
l i
E2-2 i
1
i ENCLOSURE 2 P;g) 3 af 22 TAatz fYumM ATION BETWEEN BROWNB FERRT NU(3 EAR OM9 LOWT5 3 AfEB 3 BENTART TNT FROGMAM (ETF)
SYSTEM MODE DESCRIPTION UNrr 2 TEST TEST COMMENTS MODE FOR U3 00347 PROVIDE LOW CONDENSER VACUUM SIGNAL TO ENERGlZE 2-BFN-RTP403 B YES REACTOR FEEDWATER SYSTEM (3) SOLENOID TO CLOSE MAIN STEAM SYSTEM (1) FEEDWATER TURBINE STEAM SUPPLY STOP VALVES.
003-08 PROVIDE RPV WATER LEVEL INDICATION AT BACKUP 2-BFN-RTP403A YES CONTROL CENTER.
003-09 PROVIDE IAW REAC10R PRESSURE PERMISSIVE SIGNALS TO 2-BFN-RTP-003A YES CORE SPRAY SYSTEM GS) FOR OPENING OF LOW PRESSURE EMERGENCY CORE COOLING SYSTEM (ECCS) INJECTION VALVES AND TO RHR SYSTEM G4) FOR CLOSING OF RECIRCULATION PUMP DISCH ARGE VALVES.
003 10 PROVIDE RPV LOW WATER LEVEL (LI) SIGNAL TO PRIMARY 2-BFN-RTP-003A YES CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION LOGIC.
003 11 PROVIDE RPV HIGH WATER LEVEL (L8) SIGNAL TO 2-BFN-RTP-003A YES FEEDWATER CONTROL SYSTEM (46) FOR MAIN TURBINE AND REACTOR FEEDWATER PUMP TURBINE TRIPS.
003 12 PROVIDE REACTOR COOLANT PRESSURE TlOUNDARY (RCPB).
2-BFN-RTP-068 YES 003 13 PROVIDE PRIM ARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 003 14 PROV10c SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNTT l
2 TESTING 003 15 PROVIDE RPV LOW WATER LEVEL (L2) SIGNAL TO 250 SYSTEM 2-BFN-RTP-068 YES (573) TO OPEN RECIRCULATION PUMP MOTOR GENERATOR (M/G) SET DIE 1VE MOTOR BREAldRS FOR 75tlP OF RECIRCULATION PUMPS AND TO CRD 'YSTEM (85) TO INTflATE ALTERNATE ROD INSERT.
003 16 PROVIDE RPV PRESSURE INDICATION IN M AIN CONTROL 2-BFN-RTP-003A YES j
ROOM.
i l
003-18 CLOSE MAIN STEAM SYSTEM (1) FEEDWATER TURBINE STEAM 2-BFN-RTP-003 A YES SUPPLY STOP VALVES ON LOW CONDENSER VACUUM OR RPV HIGH WATER LEVEL (L8) SIGNALS.
)
003-19 INDICATE RPV WATER LEVEL IN THE CONT 1tOL ROOM.
2-BFN-RTP-003A YES 003 20 PROVIDE RPV LDW WATEFI LEVEL (L2) SIGNAL VIA RHR 2-BFN-RTP-003A YES SYSTEM G4) FOR AITTOMATIC RCIC SYSTEM 01) INrrlATION.
003-21 PROVIDE RPV IDW WATER LEVEL (L1) SIGNAL TO MAIN 2-BFN-RTP-003 A YES STEAM SYSTEM (1) FOR ADS.
l 003-22 PROVIDE RPV LOW WATER LEVEL (LI) SIGNAL TO CORE SPRAY 2-BFN-RTP-003A YES SYSTEM G5) FOR CORE SPRAY RHR LOW PRESSURE COOLANT INJECrlON (LPCI) G4) AND DIESEL GENERA *1DR (82) START.
l l
E2-3
ENCLOSURE 2 P qo 4 cf 22 TAEt2 cuassIAftGN BETWEEN BROWNB FERET NUCLEAR (BfM tsers 2 AMs 3 mEETANT11 Err FmN'aW A t
F SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 003 23 PROVIDE RPV PRESSURE INDICATION AT BACKUP CONTROL 2-BFN-RTP403A YES CENTER.
003-25 THE UPPER LIMrr ON FEEDWATER FLOW MUST RESTRICT NONE YES FLOW TO ABOUT 130% (REIAAD ANALYSIS ASSUMPTION).
003 26 PROVIDE 2/3 CORE COVERAGE PERMISSIVE SIGNAL TO RHR NONE YES SYSTEM FOR CONTAINMENT COOLING MODES 003-27' PROVIDE REACTOR VESSEL HIGH WATER LEVEL (L8) SIGNAL NONE YES TO RCIC SYSTEM Gl) TURBINE TRIP 01041 PROVIDE PATH FOR MAIN STEAM SYSTEM (I) ERVS STEAM 2-BFN-RTP-003A YES TEST VACUUM SLDWDOWN TO PRIMARY CONTAINMENT SYSTEM (64)
BRLAKEa VALVES SUPPRES$10N POOL.
ONLY 1
010-02 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 012-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONITARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNTT j
2 TESTING j
i 012-02 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 BFN-RTPO64A NO SEE NOTE 2 1
01841 PROVIDE DIESEL FUEL OIL TO DIESEL GENERATOR SYSTEM 2-BFN-RTP-082 NO UNIT 2 TEST (82).
ADEQUATELY SATISFIED REQUIREMENT 018-02 MAINTAIN 7 DAY (LONG TERM) SUPPLY OF FUEL OIL IN 2-BFN-RTP-082 NO UNTT 2 TEST STORAGE TANKS IN SUPPORT OF DIESEL GENERATOR SYSTEM ADEQUATELY (82).
SATISFIED REQUIREMENT 01843 MAINTAIN SHORT TERM SUPPLY OF FUEL OIL IN 7 DAY 2-BFN-RTP-082 NO TESTS %TRE STORAGE TANKS BY TRANSFERRING FUEL OIL BETWEEN PERFORMED LN AVAILABLE FUEL OIL STORAGE TANKS IN SUPPORT OF DIESEL ACCORDANCE %TrH GENERATOR SYSTEM (82).
UNIT 2 RTP TEST 2.BFN-RTP-082 REV. O AND REV.1. THESE TESTS WERE REVIEWED AND FOUND TO BE ACCEPTABLE TO VERIFY THE SYSTEM MODE REQUIREMENTS FOR UNrr 3 RESTART.
023-01 PROVIDE COOLING WATER TO RHR SYSTEM G4) HEAT 2-BFN-RTP-023 YES EXf: HANGERS.
02343 PROVIDE COOLING WATER TO EECW SYSTEM (67) UPON START 2-BFN-RTP-023 YES OF THE RESIDUAL HEAT REMOVAL SERVICE WATER (RHR$W)
PUMPS.
E2-4
ENCLOSURE 2 P:ga 5 cf 22 t
i TAatz l
1 l
cnememsow arrwsun anome summf MUCUEAR (BR$
UMrfs 2 Afe 3 marrAltf TENT FROGRAM ptTF) j l
SYSTEM MODE DESCRIITION UNrr 2 TEST TEST COMMENTS MODE FOR U3 l
1 02344 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 02346 PROVIDE WHEELER LAKE LEVEL INDICATION / ALARM AT 2-BFN-RTP-023 NO UNrr 2 TEST SATISFIES ELEVATION 558 FEET AND RISING AS WELL AS AT ELEVATION REQUIREMENTS 564 FEET AND RISING.
023-07 PROVIDE PRIM ARY CONTAINMENT BOUNDARY. CLOSE RHR 2 BFN RTP-023 NO UNir 2 TEST SATISFIES SERVICE WATER SYSTEM VALVES l-FSV 23-56 AND 2-FSV-23-56 REQUIREMENTS. SEE ON RHR SYSTEM 04) UNrr CROSS-TIE VALVES OPEN POSITION NOTE 2
)
SIGNAL.
023-08 M ANUAL RHR$W SYSTEM OPERATION TO PROVII% COOLING 2-BFN-RTP-023 YES WATER TO RHR SYSTEM C4) HEAT EXCIIANGERS HtOM OITr$1DE OF MAIN CONTROL ROOM.
023-09 PROVIDE SUMP PUMP CAPABILrrY 2-BFN-RTP-023 NO UNrr 2 TEST SATISFIES REQUIREMENTS 02441 PROVIDE SECONDARY CONTAINME.Vr B.)UNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED A3 A WHOLE DURING UNrr l
2 TESTING j
024-02 PROVIDE PRESSURE BOUNDARY INTEGRTTY TO EECW SYSTEM 2-BFN-RTP-024 NO CHECK VALVES (67).
REMOVED BY;i DCN.W272993
)
4 04 PROVIDE A FLOW PATH THROUGH UNrrS 1 AND 2 CONTROL 2-BFN-RTP-031 A NO UNrr 2 TEST SATISFIES ROOM CHILLERS REQUIREMENTS 02445 PROVIDE RCW SUPPLY HEADER IDW PRESSURE PERMISSIVE 2-BFN RTP-024 NO UNTT 2 TEST SATISFIES SIGNAL TO 4-KV POWER DISTRIBUTION SYSTEM (575) FOR REQUIREMENTS STARTING OF RHRSW SYSTEM (23) PUMPS.
024-06 PROVIDE MANUAL CONTROL FROM OtfrSIDE THE MAIN 2-BFN-RTP-BUC NO UNrr 2 TEST SATISFIES CONTROL ROOM OF RCW PUMPS ID AND 3D TO PREVENT REQUIREMENTS OVERLOADING OF DIESEL GENERATORS (SYSTEM 82).
025-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 025-(M PREVENT AUTOMATIC START OF HIGH PRESSURE FIRE 2-BFN-RTP425 NO UNrr 2 TEST SATISFIES PROTECTION SYSTEM (26) PUMPS (LOCK-OITT) TO PREVENT REQUIREMENTS OVERLOADING THE DIESEL GENERATORS (SYSTEM 82).
02545 PREVEPT START OF HIGH PRESSURE FIRE PROTECTION 2-BFN-RTP-BUC NO UNIT 2 TEST S ATISFIES SYSTEM (26) PUMPS (FROM OUTSIDE THE M AIN CONTROL REQUIREMENTS ROOM) TO PREVENT OVERLOADING THE DIESEL GENERATORS (SYSTEM 82).
E2-5 1
ENCLOSURE 2 Pgo 6 ef 22 TAE:A
- ATs0M BE1TEWWI EBOWNB PERET NUCLEAR (RFI4 LM(TE 3 APED 3 RWTANT TWF FROGRAM (RTT)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 026-01
$UPPORT SECONDARY CONTAINMENT FUNCTION.
2-BFN RTP-065 NO SECONDARY CONTADI-MENT WAS TESTED AS A WHOLE DURING UNrr 2 'l ESTING 026-02 VERIFY HIGH PRESSURE FIRE PRUTECTION (HPFP) 2-BFN-RTP-025 NO UNrr 2 TEST SATISFIES AUTOM ATIC-START INHIBir LOGIC REQUIREMENTS 027-01 PROVIDE WARM WATER CHANNEL LEVEL INDICATION IN Tl:E 2-BFN-RTP-027 NO MODE DELETED FROM MAIN CONTROL ROOM.
BASELINE TEST REQUIREMENT DOCUMENTS (BTRD) 027-02 PROVIDE FOREBAY LEVEL INDICATION IN THE MAIN CONTROL 2-BFN-RTP-027 NO MODE DELETED FROM ROOM FOR MANUAL ACTIONS TO REDUCE POWER OR IF BTRD NECESSARY INrrIATE SCRAM.
02743 PROVIDE COOLING TOWER LIFT PUMP DISCHARGE WATER NONE NO REQUIRED ONL7POR HIGH TEMPERATURE SIGNAL TO 4-KV POWER DISTRIBUTION OPIIRATION IN CU) SED SYSTEf f (575) FOR TRIPPING OF THE CORRESPONDING h40DBiOPERATIOEIN COOLING TOWER LIFT PUMP.
CLOSED MODE PROHIBrrED.UNTH, RESOLUTION OF $ CAR RP8CA9200016 (NOp ~ "
AllQUREDMUNK3 RESTART) 027-04 PROVIDE MANUAL VACUUM BREAKING CAPABILTTY 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 3-71410 027-05 PROVIDE FOREBAY / WARM WATER CHANNEL DIFFERENTIAL 2-BFN-RTP427 NO THIS MODE DELETED LEVEL INDICATION IN THE MAIN CONTROL ROOM.
BY CHANGE NOTICE (CN-2) TO 2/3-BFN-BTRD-027.
02941 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING 030-01 PROVIDE VENTILATION TO UNrrS 1 AND 2 DIESEL GENERATOR 2-BFN-RTP-030 NO UNrr 2 TEST SATISFIES BUILDING.
REQUIREMENTS 03002 FROVIDE VENTILATION TO UNrr 3 DIESEL GENERATOR 2-BFN-RTP-030 NO UNrr 2 TEST SATISFIES BUILDING.
REQUIREMENTS 03043 PROVIDE VENTILATION TO 250V BATTERY ROOM 3EB IN THE 2-BFN-RTP,030 NO UNrr 2 TEST SATISFIES UNrr 3 DIESEL GENERATOR BUILDING TO PREVENT A BUILDUP REQUIREMENTS OF HYDROGEN GAS DURING BATIERY CHARGING.
l E2-6 4
EMCLOSURE 2 P p 7 of 22 TAAEA i
N110N N BAOURS punsY Mut32AR M RSWIB 3 AfW 3 BWTART TWr yawwmm (ggy) l 4
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS l
MODE FOR U3 03141 ISOLATE SUPPLY DUCTS AND SUPPLY PRESSU.11 ZED FILTERED 2-BFN-RTP43. B NO UNIT 2 TEST SATISFIES OUTDOOR AIR TO MAIN CONTROL ROOM ON PhlMARY REQUIREMENTS CONTAINMENT SYSTEM (64) GROUP 6 ISOLATIOM SIGNAL DE RADIATION MONfrORING SYSTEM (90) INITIATYJN SIGNAL.
031-02 PROVIDE VENTILATION TO REACTOR BUILDING BOARD ROOMS 2-BFN-RTP-0318 NO UNIT 2 TEST SATISFIES AND CONI OL BAY MECHANICAL EQUIPMEN_T ROOMS.
REQUIREMENTS 03143 PROVIDE RECIRCULATION AIR COOLING TO REACTOR 2-BFN-RTP-031B NO UNrr 2 TEST SATISFIES BUILDING BOARD ROOMS.
REQUIREMENTS 031-04 PROVIDE VENTILATION AND AIR CONDirlONING TO UNrr 3 2-BFN-RTP-031B NO UNTT 2 TEST SATISFIES DIESEL GENERATOR BUILDING BOARD ROOMS.
REQUIREMENTS 031-05 PROVIDE RECIACULATION AIR CONDITIONING TO CONTROL 2-BFN-RTP-031B NO UNTT 2 TEST SATISFIES ROOMS AND AUXILIARY INSTRUMENT ROOMS.
REQUIREMENTS 031-06 PROVIDE VENTILATION TO BATTERY ROOMS.
2 BFN-RTP-031B NO UNIT 2 TEST SATISFIES REQUIREMENTS 031-08 PROVIDE M ANUAL LINEUP OF HEATING, VENTING, & AIR 2-BFN-RTP-031 A NO UNrr 2 TEST SATISFIES CONDITIONING (HVAC) EQUIPMENT Y'TTH TOTAL IDSS OF REQUIREMENTS
~
CONTROL AIR.
5 031-09 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING 03241 PERFORM ISOLATION ACTION (S) UPON RECEIVING PRIMARY 2-BFN-RTP-032 YES CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNALS.
i 03242 PROVIDE COMPRESSED AIR TO MAIN STEAM SYSTEM (01) ADS 2-BFN-RTP-001 YES SAFETY RELIEF VALVES (SRVS).
03243 PROVIDE COMPRESSED AIR FOR CLOSURE OF MAIN STEAM 2-BFN-RTP401 YES ISOLATION VALVES (SYSTEM 01).
03244 PROVIDE COMPRESSED AIR TO EQUIPMENT ACCEf,S LOCK 2-BFN-RTP432 NO UNTT 2 TEST SATISFIES SEALS TO PROVIDE SECONDARY CONTAINMENT BOUNDARY.
REQUIREMENTS 032-05 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 4
032-06 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNTr i
2 TESTING 032-09 VERIFY FLOW PATH INTEGRTTY FOR CONTAINMENT NONE NO POST MOD TESTING ATMOSPHERE DILtTTION (CAD) NTTROGEN TO THE TORUS TO (PMT) FOR DCN
)
REACTOR BLDG VACUUM BREAKER VALVES W17933A SATISFIES 1
THIS REQUIREMENT 033-01 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064 A NO SEE NOTE 2 E2-7 l
EINEOSURE 2 Fags 8 ef 22-TAMA-
- aftEBI N m M pman gappg 45 STB 5 Afe 3 MART W FEDGRAM A SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 033-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 03741 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS.
A WHOLE DURING UNTT 2 TESTING 039-Cl -
INHIBfr SPURIOUS CO2 INrrlATION SIGNAL WHEN 2-BFN-RTP-039 NO UNrr 2 TEST SATISFIES VENTILATON (SYSTEM 30) 15 REQUIRED IN DIESEL REQUIREMENTS GENERATOk EUILDINGS.
04441 PROVIDE SECONDARY CONTAINMENT BOUNDA!'Y.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 043-01 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 04342 CLOSE SAMPLING AND WATER QUAL TTY SYSTEM ISOLATION 2-BFN-RTP-069 YES VALVES ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 1 ISOLATION SIGNAL [ONLY ON RPV LOW WATER LEVEL (LI)
AND MAIN STEAM LINE HIGH RADIATION).
04343 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 043-04 MAINTAIN RHRSW SYSTEM (23) PRESSURE BOUNDARY 2-BFN-RTP-023 YES INTEGRrrY.
043-05 PROVIDE CAPABILrrY OF MANUAL BACKUP CONTROL 2-BFN-RTP-BUC YES ISOLATION (VALVE CLOSURE) TO PREVENT IDSS OF REACTOR WATER INVENTORY.
043-06 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 04347 CLOSE POST ACCIDENT SUPPLY SYSTEM ISOLATION VALVES NONE NO NEW MODE TESTED BY UPON RECEIVING PRIMARY CONTAINMENT SYSTEM (64)
PMT ON UNrr 2.
WILL OROUP 6 ISOLATION SIGNAL.
BE TESTED BY Phrr FOR DCN W17460A FOR UNrr 3.
044-01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 04641 PROVIDE RPV HIGH WATER LEVEL (L8) SIGNAL TO ENERGIZE 2-BFN-RTP-003B YES REACTOR FEEDWATER SYSTEM (3) SOLENOID TO CLOSE MAIN STEAM SYSTEM (1) FEEDWATER TURBINE STEAM SUPPLY STOP VALVES.
l 4
E2-8
ENCLOSURE 2 P::g3 9 of 22 TAal2
-A110N BETWEEN BRotMS PEasY NUQAAR (Brpt IDefs 3 AND 3 BABFAlrF TWWF FDDGEAhl(Irm SYSTEM MODE DESCRIPTION UNTT 2 TEST TEST COMMENTS MODE FOR U3 047-01 PROVIDE MAIN TURBINE CONTROL VALVE FAST CLOSURE 2-BFN-RTP-047 YFS SIGNAL'IV REACTOR PROTECTION SYSTEM (99).
047-03 PROVIDE HYDRAUUC 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 HYDRAUUC CUEURE OF MAIN STEAM SYS (01) MAIN 2-BFN-RTP-047 YES TURBINE BYPASS VALVES UPON LOW CONDENSER VACUUM (APPROXIMATELY 7 HG) SIGNAL.
04745 PROVIDE HYDRAUUC CONTROL TO OPEN MAIN STEAM SYS 2-BFN-RTP-047 YES (01) M AIN TURBINE BYPASS VALVES ON TURBINE TRIP (MAIN TURBINE STOP VALVE CLOSURE) SIGNAL.
050-01 VERIFY ; HAT THE NaOCf 'CNBCE VALVES PROVIDE PRESSURE 2-BFN-RTP-067 W
NMTBSTEDTA8iBTRDj WDR(MBORrrYMTHREECW SYSTM N VALVB8 TESTED PER ASME ssCmNyg 0 $14 2.23 053-01 PROVIDE SECONDARY CONTA!NMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING 063-01 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 CONDITION (NEUTRON MONTTORING SYSTEM (NMS) SYSTEM 92).
063-02 PROVIDE STANDBY UQUID CONTROL SYSTEM (SLCS) 2-BFN-RTP-069 YES INTTIATION SIGNAL TO REACTOR WATER CLEANUP (RWCU)
SYSTEM (69) FOR ISOLATION OF RWCU SYSTEM FROM THE REACTOR TO PREVENT ENTRY OF BORON SOLUTION INTO RWCU SYSTEM.
M343 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY.
2-BFN-RTP-068 YES 063-04 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN RTP464A NO SEE NOTE 2 064-01 PROVIDE SIGN AL TO CLOSE GROUP 1 PRIM ARY CONTAINMENT 2 BFN-RTP-064A YES ISOLATION VALVES (MAIN STEAM SYSTEM (1) AND SAMPLE AND WATER QUALrrY (SWQ) SYSTEM (43)).
06442 PROVIDE SIGNAL TO CLOSE GROUP 2 PRIMARY CONTAINMENT 2-BFN-RTP-064A YES ISOLATION VALVES [RHR SYSTEM (74) CORE SPRAY SYSTEM (75) AND RADWASTE SYSTEM (77)].
06443 PROVIDE SIGNAL TO CLOSE GROUP 3 PRIM ARY CONTAINMENT 2 BFN-RTP-064A YES ISOLATION VALVES [RWCU SYSTEM (69)l.
E2-9
ENCLOSURE 2 P g3 10 cf 22 TASEA smem ATNNE WTWEEN BAKMMS PERRY NUGAAR (BH4 l#WT5 3 AND 3 ENTART 1957 PROCEAM ORTT) l SYSTEM MODE DESCRIPTION UNTT 2 TEST TEST COMMENTS MODE FOR U3 06444 PROVIDE SIGNAL TO CLOSE GROUP 6 PRIMARY CorfrAINMENT 2-BFN-RTP-064A YES ISOLATION VALVES (SYSTEMS 32,43/4,76,84 AND 90) ISOLATE AC SYSTEM (31) SUPPLY DUCTS TO M AIN CONTROL ROOM (MCR) INrrlATE EMERGENCY PRESSURIZATION SYSTEM (31)
TRIP FANS & POStrlON DAMPERS (64) & INTTIATE SGTS (65).
06445 PROVIDE SIGNAL TO CLOSE GROUP 8 ISOLATION VALVES.
2-BFN.RTP-064A YES SYSTEM (94) IS NOT TO PERFORM ACTIVE ISOLATION FUNCTION.
06446 PROVIDE PRIMARY CONTAINMEPfr BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 06448 PROVIDE MIGH DRYWELL PRESSURE TRIP SIGNAL TO REACTOR 2-BFN-RTP464A YES PROTECTION SYSTEM (99).
06449 PROVIDE HIGH DRYWELL PRESSURE SIGNAL TO RHR SYSTEM 2-BFN-RTP-064A YES G4) FOR LPCI INrflATION LOGIC AND TO CORE SPRAY SYSTEM G5) FOR SYSTEM INITIATION LOGIC 480V LOAD SHED LOGIC i
DIESEL GENERATOR START LOGIC AND HPCI SYSTEM G3)
INTilATION LOGIC.
064-10 PROVIDE VACUUM RELIEF SYSTEM (VACUUM BREAKER 2-BFN-RTP-064A YES VALVES)1V PREVENT DRYWELL OR SUPPRESSION CHAMBER (TORUS) NEGATIVE PRESSURE FROM DAMAGING CONTAINMENT STRUCTURE.
064-11 PROVIDE DRYWELL TEMPERATURE INDICATION IN MAIN 2-BFN-RTP-064A YES CONTROL ROOM IN SUPPORT OF RHR SYSTEM G4) DRYWELL SPRAY (CONTAINMENT COOLING) MODE.
i 064-12 PROVIDE SUPPRESSION POOL TEMPERATURE INDICATION IN 2 BFN-RTP-064A YES M AIN CONTROL ROOM IN SUPPORT OF RHR SYSTEM G4)
CONTAINMENT COOLING (TORUS COOLING AND DP,YWELl/rORUS SPRAY) MAIN STEAM SYSTEM MANUAL RPV DEPRESSURIZATION AND RPS SYSTEM (99) M ANUAL SCRAM.
064-13 PROVIDE SUPPRESSION POOL LEVEL INDICATION IN MAIN 2-BFN-RTP-064A YES COff!1tOL ROOM IN SUPPORT OF RHR SYSTE! f G4)
CONTAINMENT COOLING AND MAaN tYLJJ.*.;YSTEM (1)
MANUAL RPV DEPRESSURIZATION. PROVIDE PRESSURE 1
BOUNDARY INTEGRITY TO HPCI SYSTEM G3).
064 14 PROVIDE DRYWELL PRESSURE INDICATION IN MAIN CONTROL 2-BFN-RTP464A YES
^
ROOM IN SUPPORT OF RHR SYSTEM G4) COPfrAINMENT COOLING (DRYWEll/rORUS SPRAY) AND COPTTAINMENT ATMOSPHERE DILUTION SYSTEM (64) CONTAINMENT VENTING AFTER A LOCA.
064-15 PROVIDE DRYWELL TEMPERATURE INDICATION OtfrSIDE THE 2-BFN-RTP464A YES M AIN COP (FROL ROOM IN SUPPORT OF MAIN STEAM SYSTEM (1) MANUAL RPV DEPRESSURIZATION AND RHR SYSTEM G4)
OPERATION FROM OUTSIDE THE MAIN CONTROL ROOM.
E2-10
m_. _.
_ ~
I ENCICCURE 2 F gs 11 of 22 b
Tasta casamA19Em sem papups puest prs man gang a
I Isets S Age 3 MANT M reoERAM A l
SYSTEM MODE DESCRIFrlON UNIT 2 TEST TEST COMMENTS i
MODE' POR j
1 U3 I
064-16 PROVIDE SUPPRESSION POOL TEMPERATURE INDICATION 2-BFN-RTP-064A YES 6
OLTrSIDE THE MAIN CONTROL ROOM (MCR) IN SUPPORT OF l
MAIN STEAM SYSTEM (1) MANUAL RPV DEPRESSURIZATION
)
RHE SYSTEM G4) OPERATION AND REACTOR PROTECTION SYSTEM (99) MANUAL SCRAM FROM OUTSIDE THE MCR.
l 4
064-17 PROVIDE SUPPRESSION POOL LEVEL INDICATION OUTSIDE THE 2-BFN RTP-064A YES
. i MAIN CONTROL ROOM IN SUPPORT OF MAIN STEAM SYSTEM (1) MANUAL RPV DEPRESSURIZATION RCIC SYSTEM GI) i OPERATION AND RHR SYSTEM G4) OPERATION PROM OUTSIDE THE MAIN CONTROL ROOM.
064-18 PROVIDE DRYWELL PRESSURE INDICATION OUTSIDE THE 2-BFN-RTP-064A YES
~
MAIN COPfrROL ROOM IN SUPPORT OF RHR SYSTEM l
OPERATION FROM OUTSIDE THE MAIN CONTROL ROOM.
i 064-21 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY COffrAIN-MENT WAS TESTED AS A WHOLE DURING UNIT l
2 TESTING 064-23 PROVIDE FORCED AIR COOLING FOR RHR SYSTEM G4) AND 2 BFN-RTP-030 YES CORE SPRAY SYSTEM G5) PUMP MOTORS i
064-25 PROVIDE HIGH DRYWELL PRESSURE SIGNAL TO M AIN STEAM 2 BFN-RTP-064A YFS SYSTEM (1) FOR AUTOMATIC DEPRESSURIZATION SYSTEM j'
(ADS) LOGIC.
I 1
1 064-27 CIDSE PRIMARY CONTAINMEffT VENTILATION SYSTEM 2-BFN-RTP-065 YES l
j.
ISOLATION VALVES ON PRIMARY CONTAINMENT SYSTEM (64)
GROUP 6 ISOLATION SIGN AL.
)
064-28 '
PERFORM ISOLATION ACTION (S) [ TRIP FANS CLOSURE OF 2-BFN-RTP 064A NO UNrr 2 TEST SATISFIES l
DAMPERS OPENING OF DAMPERS TO SGTS (65)] ON PRIMARY 2-BFN-RTP-065 REQUREMENTS CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNALS.
l C15-01 MAINTAIN NEGATIVE PRES $URE IN SECONDARY 2-BFN-RTP&5 W
l@@ p l $
CONTAINMEPfr ON PRIM ARY COPrrAINMENT SYSTEM (64)
VNFr;21EKEATEMD 1
GROUP 6 ISOLATION SIGNAL. FILTER AIRBORNE PARTICULATE R8QUE BfENTS, j'
SYSTEM (34)1 PRIOR TO DISCHARGE TO OFF-GAS SYSTEM (66).
& GASES IINCLUDING TH AT FROM HPCI SYSTEM (73) & CAD I
0654)3 MAINTAIN NEGATIVE PRES $URE IN SECONDARY 2-BFN-RTP-065 Nd F *P 3 UNft21387SATWFED COP (TAINMENT ON PRIMARY CONTAINMENT SYSTEM (64) -
SIGNAL DUE TO RADIATION MONITORING SYSTEM REFUELING kBQUEBfENTS ZONE HIGH RADIATION SIGNAL. FILTER ARBORNE i "
PARTICULATE & GASES PRIOR TO DISCHARGE TO OFF-GAS SYSTEM (66).
2:-
06544.
PROVIDE SECONDARY CONTAINMENT IffrEGRITY.
2-BFN-RTP465 NO UNIT 2 TEST SATISFIES REQUREMENTS DE02 '
PROVIDE FLOW PATH IfffEGRrrY FOR THE RELEASE OF THE 2-BFN-RTP-065 NO UNrr 2 TEST SATISFIES j
FILTERED STANDBY GAS TREATMENT SYSTEM (65) GASES TO REQUIREMENTS j
THE STACKS.
4 E2-11 4
d
- .,r w - -,. -
.--.,m.
y
l
.ERICLOSURE 2 PMo 12 sf 22 TAM 2 i
(
enmaan ATsues sampunt geoque puesY manuam pegg 18515 3 Age 3 EMAEt'TWF FROGRAM STF) a SYSTEM MODE DESCRIPTION UNrr 2 TEST TEST COMMENTS MODE FOR l
U3 l
066-04 OFF4AS DILUTION FAN ISOLATION DAMPERS SHALL BE 2-BFN-RTP-065 NO PMT FOR DCN W17999A CLOSED ON INITIATION OF THE SOT SYSTEM (65).
SATISFIES REQUREMENTS C 7-01 PROVIDE COOLING WATER TO AC SY STEM (31) CHILLERS RHR 2-BFN-RTP-067 YES SYSTEM G4) PUMP SEAL COOLERS CIS 06) 02 & H2 GAS ANALYZERS DIESEL ENGINES (82) RHR & CORE SPRAY EQUIPMENT ROOM COOLERS (64) & PUEL POOL C9). MAINTAIN EECW SYSTEM (23) PRES $URE BOUNDARY.
067-02 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN-RTP-065 NO UNrr 2 TEST SATISFIES REQUREMENTS 06743 FOR SHUTDOWN FROM OUTSIDE OF MAIN CONTROL ROOM: (1) 2-BFN-RTP-067 PAR RIR$W M5(RACEUP PROVIDE COOLING WATER TO RHR & CORE SPRAY EQUIPMENT TIAE TEstC00flBOL M ROOM COOLERS (64) RHR SYSTEM G4) PUMP SEAL COOLERS TESTBDINj DIESEL ENGINES (82) & FUEL POOL 09) (2) MAINTAIN EECW 2/3 M SYSTEM (23) PRESSURE BOUNDARY.
HEADR98VBfMRT Tast N UMNBCES.$AR..Y s
TESTED 75t"AEM8 sBCn0N10Sy45t2#
AND.M4M geoocuAxEur;u AIANOTEBM W kMOOE AND VALVES.CAN'EW M4NUALLY AUGNED
~
70 AcccMMJeal REQUREMENT l
067-05 ATTACH A FRE HOSE TO EECW TO M AINTAIN WATER LEVEL 2 BFN-RTP-067 YES IN THE FUEL POOL.
e 068-01 CLOSE RECRCULATION PUMP DISCHARGE VALVES ON RHR 2-BFN-RTP-068 YES SYSTEM C4) AUTOMATIC LPCI MODE INrt1ATION SIGNAL.
j 06842 -
OPEN RECRCULATION PUMP MOTOR BREAKERS ON REACTOR 2 BFN-RTP-068 YES l
PROTECTION SYSTEM (99) SIGNAL DUE TO >30% TURBINE FRST STAGE PRESSURE AND EITHER MAIN TURBINE CONTROL VALVE FAST CLOSURE OR MAIN TURBINE STOP VALVES <90%
OPEN MANUALLY ENABLED END-OF-CYCLE RPT).
068-03 CLOSE RECRCULATION PUMP DISCHARGE VALVES 2 BFN-RTP468 YES MANUALLY IN SUPPORT OF MANUALLY INrrlATED RHR j
SYST'i.M G4) SHUTDOWN COOLING MODE AND LPCI MODE (FROM MAIN CONTROL ROOM AND OUTSIDE MAIN CONTROL ROOM),
i 068-04 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2 BFN-RTP468 YES i
E2-12 c
a,
w
ENCLOSURE 2 P:gn 13 of 22 TAALE Orm AT90N BETWREM BatMFIS FHERY MLELEAR WFI9 ISWTW 3 APS 3 RMART TM F90 GRAM (ETF)
SYSTEM MODE DESCRIITION UNTT 2 TEST TEST COMMENTS MODE FOR U3 06845 PRO'.DE LOW REACTOR PRESSURE PERMISSIVE SIGNALS TO 2-BFN-RTP468 YES CORE SPRAY SYSTEM C5) AND RHR SYSTEM G4).
C28-06 TRIP RECIRCULATION PUMP MOTOR MOTOR-GENERATOR SET 2-BFN-RTP-068 YES ON OPENING OF 4KV POWER DIS"IltIBUTION SYSTEM (575) M-G SET DRIVE MOTOR BREAKERS DUE TO HIGH REACTOR PRESSURE OR LOW WATFR LEVEL (L2).
06847 PROVIDE A PROPORTIONAL CORE FLOW SIGNAL TO THE NONE YES NEUTRON MONTTORING SYSTEM (092) FOR ROD BLOCK LOGIC 05848 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP464A NO SEE NOTE 2 068-09 MAINTAIN MO SET SPEED CHANGES WTTHIN ANALYZED NONE YES LIMTTS J
068-10 REQUIREMENTS FOR LOOP WARMUP PRIOR TO RECIRC PUMP NONE NO PROCEDURALLY START CONTROLLED 069-01 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 06942 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP465 NO SECONDARY CONTAIN-2 MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 069-03 CLOSE RWCU SYSTEM ISOLATION VALVES ON PRIMARY 2 BFN-RTP469 YES CONTAINMENT SYSTEM (64) GROUP 3 ISOLATION SIGNAL.
06944 CLOSE RWCU SYSTEM SUCTION LINE ISOLATION VALVES ON 2-BFN-RTP-069 YES STANDBY LIQUID CONTROL SYSTEM (63) INITIATION SIGNAL TO PREVENT ENTRY OF BORON SOLUTION INTO RWCU SYSTEM.
069-05 PROVIDE HIGH RWCU SYSTEM EQUIPMENT AREA 2-BFN-RTP-069 YES ATMOSPHERE AND DRAIN TEMPERATURE SIGNALS TO PRIM ARY CONTAINMENT SYSTEM (64) GROUP 3 ISOLATION LOGIC.
06946 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 069-07 PROVIDE SYSTEM PRESSURE BOUNDARY SUPPORT (CHECK 2-BFN-RTP469 YES VALVE) TO HPCI SYSTEM G3) TO PREVENT DIVERSION OF HPCI SYSTEM CORE COOLING WATER FROM REACTOR VESSEL.
069-08 PROVIDE FLOW PATH FOR RCIC SYSTEM Gl) CORE COOLING 2-BFN-RTP-069 YES WATER TO REACTOR FEEDWATER SYSTEM (3) SPARGERS.
06949 PROVIDE CAPABILTTY OF M ANUAL BACKUP CONTROL 2 BFN-RTP-BUC YES ISOLATION (VALVE CLOSURE) TO PREVENT LOSS OF REACTOR WATER INVENTORY.
4 07(M)1 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 9
E2-13 i
ENCLOSURE 2 P g3 14 cf 22 TAat2 airm ATEGN MTyrtRN BROWfS PERET NUCIAAR (BR4 (M13 3 APGD 3 RENTART TWf PROCEAM (RTF) j SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS MODE FOR U3 07042 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2 BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS l
A WHOLE DURING UNTT 2 TESTING 07043 PROVIDE DRYWELL COOLING WHEN POWER AND COOLING 2-BFN-RTP-030 YES j
WATER ARE AVAILABLE.
071-01 AITTOMATIC RCIC SYSTEM INTTIATION ON REACTOR 2-BFN-RTP-071 YES FEEDWATER SYSTEM (3) RPV LOW WATER LEVEL (L2) SIGNAL TRANSMTITED VIA RHR SYSTEM G4). AUTOMATIC RCIC i
SYSTEM SHUTOFF OF OPERATING) ON REACTOR FEEDWATER
]
SYSTEM (3) RPV HIGH WATER LEVEL (L8) SIGNAL.
071-02 MANUAL RCIC INTT!ATION AND TRIP TO CONTROL LEVEL.
2-BFN-RTP-071 YES 1
(NON-LOCA UNIT) 1 071-03 CLOSE RCIC SYSTEM STEAM SUPPLY LINE ISOLATION VALVES 2-BFN-RTP-071 YES ON RCIC SYSTEM GROUP 5 ISOLATION SIGNALS (HIGH STEAM LINE DIFFERENTIAL PRESSURE HIGH STEM LINE SPACE l
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 (3)
INDICATION OF IDW RPV PRESSURE.
071-05 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 071-07 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 071-08 PROVIDE SYSTEM PRESSURE BOUNDARY IN SUPPORT OF RHR 2-BFN-RTP-068 YES SYSTEM G4) CONTAINMENT (TORUS) COOLING FUNCTION.
071-09 MANUAL RCIC SYSTEM OPERATION FROM OIJTSIDE THE M AIN 2-BFN-RTP-071 YES CONTROL ROOM TO MAINTAIN NORMAL RPV WATER INVENTORY WHILE RPV PRES $URE 13 ABOVE 100 PSIG.
071-10 PROVIDE POWER TO ECCS DIVIslON I AND II ANALOG TRIP 2-BFN-RTP-071 YES UNITS [ REACTOR FEEDWATER SYSTEM (3) PRIMARY CONTAINMENT SYSTEM (64) REACTOR WATER RECIRCULATION SYSTEM (68) RCIC SYSTEM G1) AND HPCI SYSTEM G3)).
071 11 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
NENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING 073-01 AITTOM ATIC HPCI SYSTEM INITIATION ON REACTOR 2 BFN-RTP-073 YES FEEDWATER SYSTEM (3) RPV LOW WATER LEVEL (L2) SIGNAL.
AITTOMATIC HPCI SYSTEM 3HUTOFF OF OPERATING) ON REACTOR FEEDWATER SYSTEM (3) RPV HIGH WATER LEVEL (L8) SIGNAL.
07342 PROVIDE MCR INDICATION OF AUTO TRANSFER OF SUCTION NONE YES PATH ON LOW CONDENSATE LEVEL i
E2-14 1
ENCLOSURE 2 P g3 15 ef 22 i
TAAE2 l
-nan asTween seems sums? -- see 45Me S Afe 3 MART TIWF FEDGAAM WTF)
]
I SYSTEM MODE DESCRIPTION UNrr 2 TEST TEST COMMENTS MODE POR U3 07343 CLOSE HPCI SYSTEM STEAM SUPPLY LINE ISOLATION VALVES 2-BFN-RTP-07J YES ON HPCI SYSTEM OROUP 4 ISOLATION SIGNALS (HIGH STEAM LINE DIFFERENTIAL PRESSURE HIGH STEAM LINE SPACE i
TEMPERATURE OR LOW STEAM LINE PRESSURE).
073-04 MANUALLY CLOSE HPCI SYSTEM STEAM SUPPLY LINE 2-BFN-RTP-073 YES 1
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 IIPCI SYSTEM STANDBY.
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-064A NO SEE NOTE 2 SYSTEM STANDBY.
073-08 PROVIDE PRIMARY CONTAINMENT BOUNDARY DURING HPCI 2-BFN-RTP-064A NO SEE NOTE 2 SYSTEM OPERATION.
073-09 M ANUALLY TRIP HPCI SYSTEM FROM OUTSIDE THE MAIN 2-BFN-RTP473 YES CON 11tOL ROOM TO PREVENT RPV OVERFILL.
073-11 PROVIDE SECONDARY CONTAINME,NT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 073-12 PROVIDE POWER TO PRIM ARY CONTAINMENT SYSTEM (64) 2-BFN-RTP-064A NO M &IODE N0l' DRYWELL PRESSURE INDICATORS IN SUPPORT OF RHR SYSTEM
~'
RBQUREDPOR UNT)j DRYWELLfrORUS SPRAY MODE AND COKTAINMENT INDICA'Itts POWBSD ATMOSPHERE DILUTION SYSTEM POST-LOCA CONTAINMENT PROM SYS;054 VENTING MODE.
074-01 AUTOMATIC LPCI MODE INITIATION ON RPV LOW WATER 2-BFN-RTP-074 YES
}
LEVEL (L1) SIGNAL OR HIGH DRYWELL PRESSURE SIGNAL WrrH CONCURRENT LOW RPV PRESSURE PERMISSIVE SIGNAL.
1 MANUAL LPCI MODE INITIATION FROM THE MAIN CONTROL l
ROOM.
074-02 PROVIDE SUPPRESSION POOL WATER COOLING TO MAINTAIN 2-BFN-RTP-074 YES i:
SUPPRESSION POOL WATER TEMPERATURE BELOW LIMrrS TO j
ASSURE THAT PUMP NPSH REQUIREMENTS ARE NET AND TH AT COMPLETE CONDENSATION OF BLOWDOWN STEAM FROM A DESIGN BASIS LOCA CAN BE EXPECTED.
074-03 PROVIDE SPRAY TO DRYWELL AND TORUS FOR CONTAINMENT 2-BFN-RTP-074 YES COOLING AND 1DWERING OF CONTAINMENT PRES $URE UNDER POST-ACCIDENT CONDirlONS.
074-04 PROVIDE SHtTTDOWN COOLING MODE (MANUAL) TO RESTORE 2-BFN-RTP-074 YES REACTOR TEMPERATURE TO NORMAL.
h E2-15
ENCLO!URE 2 Pag 3 16 ef 22 TABf2 rinaam AygoN BETWuRN BROWIS PERRY MUCIAAR 9894 i
INT 5 2 Am 3 RWTANT1My panrum (RTF)
SYSTEM MODE DESCRHTION UNrr 2 TEST TEST COMMENTS MODE FOR U3
]
07449 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP465 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 074-10 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB),
2-BFN-RTP-068 YES 074-11 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP 064 A NO SEE NOTE 2 074-12 PROVIDE SIGNAL (THAT A RHR PUMP IS RUNNING) TO MAIN 2-BFN-RTP-074 YES STEAM SYSTEM (1) AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)INTilATION LOGIC.
074-17 PROVIDE AUTOMATIC LPCI MODE INrr!ATION SIGNAL FOR 2-BFN-RTP-074 YES CLOSURE OF REACTOR WATER RECIRCULATION SYSTEM (68)
PUMP DISCH ARGE VALVES.
074-19 MANUAL RHR SYSTEM OPERATION (LPCITORUS COOLING AND 2-BFN-RTP-BUC YES SHUTDOWN COOLING MODES) FROM OUTSIDE THE MAIN CONTROL ROOM.
074-20 PROVIDE FLOW PATH AND PRESSURE BOUNDARY INTEGRrrY 2-BFN-RTP 074 YES FOR RHR SERVICE WATER SYSTEM (23) COOLAKr TO THE MAIN RHR SYSTEM HEAT EXCHANGERS.
074-21 PROVIDE REACTOR FEEDWATER SYSTEM (3) RPV LOW WATER 2-BFN-RTP-071 YES LEVEL (L2) SIGNAL FOR AUTOMATIC RCIC SYSTEM (71)
INITIATION.
074-22 PROVIDE RHR SYSTEM UNIT CROSS-TIE VALVES OPEN 2-BFN-RTP-023 NO NOT PART OF'SAFB POSITION SIGNAL TO RHR SERVICE WATER SYSTEM (23) FOR
~ ' ' '
$liUTDO,WNMALYSl8]
CLOSURE OF RHR SERVICE WATER VALVES TO MAINTAIN PRIM ARY CONTAINMENT BOUNDARY.
074-23 RHR ISOLATION SIGNAL TRIPPED ON SIGNAL FROM PRIMARY 2-BFN-RTP-064A YES CONTAINMENT SYSTEM (64).
075-01 SUPPLY COOLING WATER TO REACTOR - AUTO INirtATION.
2-BFN-RTP-075 YES 075-03 PROVIDE CS PUMP POWER DISCONNECT FROM OUTSIDE MCR.
2-BFN-RTP-075 YES l
075 04 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY.
2-BFN-RTP-068 YES 07545 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2 BFN-RTP-064A NO SEE NOTE 2 1
075-06 PROVIDE ACCIDENT SIGN AL INPUT TO 480V LOAD SHED 2-BFN-RTP-075 14 0 NOT TESTED 35 BT. RD....
TESTED AS PART OF QWJ6AND W21284A E2-16
.-... ~... -.
. - -. - -.. ~ - _ -.
l l
)
EHC145URE 2 F g2 17 of 22 l
TAata -
i nrummaggan amm magspis e amarma pseg 55555 3 Af53 MASTTWWF fROGRAM A i
i f
I 4
SYSTEM MODE DESCRIrrlON UNfr 2 TEST TEST COMMENTS i
MODE FOR i
U3 i
i 1
07547 PROVIDE START SIGNAL TO DIESEL GENERATOR ON LOW 2-BFN-RTP-075 YES LEVEL (L1) OR HIGH DRYWELL PRESSURE.
i 075-08 PROVIDE PRIMARY CONTAINMENT SYSTEM (64) HIGH 2-BFN-RTP-073 YES l
DRYWELL PRESSURE SIGNAL POR AUTOMATIC HPCI SYSTEM t
(73) OPERATION.
)
075-10 PROVIDE SIGNALS (THAT CORE SPRAY PUMPS ARE RUNNING) 2-BFN-RTP-075 YES TO MAIN STEAM GYSTEM (1) AUTOMATIC DEPRESSURIZATION
+
SYSTEM (ADS) INftlATION LOGIC.
5 075-11 PROVIDE REACIVR FEEDWATER SYSTEM (3) RPV LOW WATER 2-BFN-RTP-074 YES i
LEVEL (L1) SIGNAL TO RHR SYSTEM (74) LPCI MODE INrr!ATION LOGIC.
075-12 PROVIDE REACTOR FEEDWATER SYSTEM (3) AND REACTOR 2-BFN-RTP-068 YES
. WATER RECIRCULATION SYSTEM (68) LOW REACTOR PRESSURE SIGNALS TO RHR SYSTEM (74) LPCI MODE f
INfflATION LOGIC.
075 13 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 075-14 PERFORM ISOLATION ACTIONS UPON RECEIVING ISOLATION 2-BFN-RTP-064A YES SIGNAL (LOW LEVEL L3 OR HIGH DRYWELL PRESSURE) FROM THE PRIMARY COKrAINMENT SYSTEM (64).
i 075 17 PROVIDE LOAD SHEDDING SIGNAL TO 480V AC SYSTEM (574) 2 BFN-RTP-111eA MO NOT;TBOTBD148W 1
ON REACIDR LOW WATER LEVEL (LI) OR COINCIDENT HIGH RBQUR B4Bl874 DRYWELL PRESSURE AND LOW REACTOR PRESSURE TESTED:A5 PART;Og DCN W201pMND i
wal2344 075-18 PROVIDE START SIGNAL TO CONTAINMENT RADIATION NONE PU>lCTIOpf DB1&TE(St j
MONITORING RECORDERS ON LOW LEVEL (L1) OR HIGH DCMylP$6 l
DRYWELL PRESSURE 076-01 CLOSE CONTAINMENT INERTING SYSTEM ISOLATION VALVES 2-BFN-RTP-084 YES ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNAL.
T 076-02 PROVIDE OXYGEN AND HYDROGEN GAS ANALYZERS AND 2 BFN-RTP-084 YES i
INDICATORS TO MONfrOR GAS CONCENTRATIONS INSIDE THE PRIMARY CONTAINMENT IN SUPPORT OF CONTAINMENT ATMOSPHERE DILUTION SYSTEM (84) OPERATION.
076-03 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 076-04 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS l
I A WHOLE DURING UNrr 2 TESTING 4
E2-17
ENCLOSURE 2 P.igo 18 of 22 TAat2 (MME AlitM BETWEEN SBOURS NRRY MUGEAR (EppS LOWTE 3 Afe 3 RMFART TNT F30GRAAt (RTF)
SYSTEM MODE DESCRIPTION UNTT 2 TEST TEST COMMENTS MODE FOR U3 07741 CLOSE RADWASTE SYSTEM ISOLATION VALVES ON PRIMARY 2 BFN-RTP-024 YES CONTAINMENT SYSTEM (64) GROUP 2 ISOLATION SIGNA 13.
077-02 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 07743 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING 078 01 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN.
MENT WAS TESTED AS A WHOLE DURING UNIT 2 TESTING 078-02 PROVIDE PRESSURE BOUNDARY INTEGRTTY AT RHR/FPC 2-BFN-RTP-074 YES INCLUDED IN SYSTEM INTERFACE.
74 BTRD 078-03 PREVENT IN ADVERTENT SIPHONING OF THE SPENT FUEL 2-BFN-RTP-069 NO TESTED POOL.
SATISFACTORILY PER I
PMT-BF-78.003 079-01 PROVIDE SAFE FUEL HANDLING USING REFUEL BRIDGE A 2-BFN-RTP-079 YES EQUIPMENT.
079-02 PROVIDE INTERLOCKS TO CRD SYSTEM DURING FUEL 2 BFN-RTP-085 YES MOVEMENT.
022-01 START STANDBY AC POWER SOURCE FOR 4KV SYSTEM (575) 2-BFN-RTP-082 NO UNTT 2 TEST SATISFIES REQUIREMENTS C22-02 PROVIDE POWER TO 4KV SYSTEM (575) UPON DIESEL 2-BFN-RTP-082 YES GENERATOR (D/G) AVAILABILITY AND LOSS OF OFF-STTE POWER.
022 03 PROVIDE D/G POWER TO DIESEL FUEL TRANSFER 2-BFN-RTP-082 NO UNIT 2 TEST SATISFTES PUMPS ($YSTEM 18).
ALL REQUIREMENTS C;4-01 PROVIDE DILITTION OF THE PRIMARY CONTAINMENT 2-BFN-RTP-084 YES ATMOSPHERE WITH NTTROGEN AFTER A LOCA TO MAINTAIN COMBUSTIBLE GAS (OXYGEN AND HYDROGEN)
CONCENTRATIONS BELOW LEVELS (OXYGEN 5% BY VOLUME)
WHICH COULD) PRODUCE A COMBUSTIBLE GAS MIXTURE.
C24-03 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN RTP-064A NO SEE NOTE 2 084 04 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP465 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNTT 2 TESTING E2-18
f ENCLOSURE 2 P::gs 19 of 22 TAAE2 nmmme ATeoM esTwumM aspWNI PEERY MUCIAAB (BFMI tsWT5 3 Afe 3 RMART TWr ParM3 RAM (RTT)
SYSTEM MODE DESCRIPTION UNrr 2 TEST TEST COMMENTS MODE FOR U3 064 45 PROVIDE NrTROGEN TO THE CONTROL AIR SYSTEM (32)IN NONE NO TESTING WILL BE DONE SUPPORT OF LONG TERN OPERABILrrY OF MAIN STEAM BY FMT FOR DCN17937 SYSTEM ADS SAFETY RELIEF VALVES (SRYS)- APPENDIX R.
08446 CLOSE CAD SYSTEM VENT VALVES ON PRIMARY 2-BFN-RTP-084 YES CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNAL.
C541 PROVIDE SCRAM (99) AND CLOSE SDV VENT DRAIN VALVES.
2-BFN-RTP-085 YES CC5-02 PROVIDE PRIMARY CONTAINMENT BOUNDARY.
2-BFN-RTP-064A NO SEE NOTE 2 a
C:543 PROVIDE SECONDARY CONTAINMENT BOUNDARY.
2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING C;544 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES C05-05 PREVENT ROD WrrHDRAWAL.
2-BFN-RTP-085 YES CC5-08 PROVIDE MCR ROD POSITION INDICATION.
2-BFN-RTP485 YES C15-09 PROVIDE SCRAM DISCHARGE HIGH WATER LEVEL SIGNAL.
2-BFN-RTP485 YES C;510 PROVIDE SCRAM DISCHARGE LOW AIR HEADER PRESSURE 2-BFN-RTP-085 YES l
SIGNAL.
C25 ll PROVIDE REM 0rrE BACKUP CONTROL FROM OtrTSIDE THE 2-BFN-RTP-BUC NO MODE N6 LONGER _
MAIN CONTROL ROOM.
REQUIRED BY. SAM!
SHUTDOWN ANALY318 C2514 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 REACTOR VESSEL PRESSURE W19321 SIGNAL.
025-16 PROVIDE ROD SELECT IDENTIFICATION 2-BFN-RTP-085 YES 08641 PROVIDE DIESEL START 7NG AIR TO DIESEL GENERATOR 2-BFN-RTP482 NO TESTS WERE SYSTEM (82).
PERFORMED IN ACCORDANCE WrrH 2 BFN-RTP-082 REV 0 AND
- 1. THE RESULTS OF THESE TESTS WERE REVIEWED AND FOUND TO BE ACCEPTABLE TO VERIFY SYSTEM MODE REQUIREMENTS FOR UNIT 3.
09401 PROVIDE MAIN STEAM LIVE HIGH RADIATION SIGNAL TO 2-BFN-RTP-090 NO PUNCTiON DELETED' BY REACTOR PROTECTION SYSTEM (99).
DCN W22478A E2-19
E3fCLOSURE 2 P gn 20 cf 22 TABER
- AftoN BETWEEN BAOEMS pgmRT Mut32AR (Eng INTE 2 APS 3 RaffART TWF FROCEAM (NTF)
SYSTEM MODE DESCRIPTION UNIT 2 TEST TEST COMMENTS FOR MODE U3 090-02 PROVIDE PRIMARY CONTAINMENT BOUNDARY (UP TO 2 BFN-RTP-064A NO PASSIVE FUNCTION SEE NOTE 2 2 FCV 90-254AB-255-257AB).
090-03 PROVIDE REACTOR BUILDING VENTILATION EXHAUST LINE 2-BFN-RTP490 NO UNIT 2 TEST SATISFIES AND REFUELING ZONE AREA (ADIACENT TO THE FUEL POO13)
REQUIREMENTS HIGH RADIATION SIGNALS TO PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION LOGIC, 090-04 PROVIDE CONTROL ROOM INTAKE AIR DUCTS EXCESSIVE 2-BFN-RTP-03 ) B NO UNrf 2 TEST SATISFIES RADIATION SIGNAL TO AIR CONDTrlONING SYSTEM (31) FOR REQUIREMENTS INTTIATION OF CONTROL ROOM EMERGENCY VENTILATION (ISOLATION OF INTAKE DUCr5 AND SUPPLY OF PRESSURIZED FILTERED OUTDOOR AIR).
09045 CIDSE VALVES ON SUCTION AND RETURN LINES TO THE 2-BFN-RTP-090 YES DRYWELL RADIOACTIVE PARTICULATE IODINE AND GASEOUS MONITOR ON PRIMARY CONTAINMENT SYSTEM (64) GROUP 6 ISOLATION SIGNAL.
090-07 PROVIDE RHR$W SYSTEM PRESSURE BOUNDARY NONE YES INCLUDED IN SYSTEM 23 BTRD 090-08 PROVIDE SECONDARY CONTAINMENT BOUNDARY 2-BFN-RTP-065 NO SECONDARY CONTAIN-MENT WAS TESTED AS A WHOLE DURING UNrr 2 TESTING 092-01 PROVIDE IRM HIGH NELT110N FLUX RIP SIGNAL TO REACTOR 2-BFN-RTP-092 YES PROTECTION SYSTEM 002-02 PROVIDE APRM HIGH NELTTRON FLUX TRIP SIGN AL TO 2-BFN-RTP-092 YES REACTOR PROTECTION SYSTEM (99).
I 092-04 PROVIDE ROD BLOCK MONrrOR TRIP SIGN AL [VAd!ABLE WTTH NONE YES RECIRC SYSTEM (68) FLOW) TO THE REACTOR M ANUAL CONTROL SUBSYSTEM (85) TO INHIBrf CONTROL ROD WTTHDRAWAL 092-05 PROVIDE INDICATION IN M AIN CONTROL ROOM OF NONE YES POWER /NELTTRON FLUX LEVEL AS MONrrORED ON LPRM/APRMS 09247 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB).
2-BFN-RTP-068 YES 094-01 PROVIDE PRIM ARY CONTAINMENT INTEGRTTY.
2-BFN-RTP-064A YES 094-03 PROVIDE REACTOR COOLANT PRESSURE BOUNDARY (RCPB) 2-BFN RTP-064A YES (PASSIVE FUNCTION ONLY) 099-01 PROVIDE AUTO SCRAM & SDV VENT / DRAIN VALVE ISOLATION 2-BFN-RTP-099 YES SIGNAL TO CRD SYSTEM (85).
09942 PROVIDE MANUAL SCRAM SIGNAL AND SDV VENT /DRALN 2 BFN-RTP-099 YES VALVE ISOLATION SIGN ALS TO CRD SYSTEM (85).
E2-20 t
)
ENCIASURE 2 Pago 21 of 22
. TABBA
- ATMBI N N M IEK32AE M tsWT5 3 Af53 MART TIWF FtoGRAM WTF)
SYSTEM MODE DESCRIFilON UNrr 2 TEST TEST COMMEfGS MODE FOR U3 099-03 PROVIDE 'RUN' MODE SIGNAL TO PCl3 (64) POR LDW 2-BFN-RTP 099 YES STEAMLINE PRESSURE ISOLATION PERMISSIVE.
099-04
' PROVIDE REFUEL INTERLOCK TO REACTOR MANUAL 2-BFN-RTP-085 -
YES CONTROL SYSTEM. (85) 09945 PROVIDE TRIP SIGNAL TO RECRC PUMP MorOR BREAKERS 2-BFN-RTP-068 YES (SYSTEM 68).
099-06 PROVIDE SIGNALS TO PRIMARY COPEAINMEPG ISOLATION 2-BFN-RTP-099 YES SYSTEM (64) LOGIC.
24441 PROVIDE COMMUNICATION FROM LOCAL PANELS FOR 2-BFN-RTP-244 NO UNrr 2 TEST SATISFIES SHlTrDOWN FROM OUTSIDE THE MCR.
REQUREMENTS 303 04 SECONDARY COPEAINMENT LEAKAGE RATE CRrrERIA MUST 2-BFN-RTP-065 NO UNrr 2 TEST SATISFIES BE MAINTAINED BY THE REACTOR BUILDING.
REQUREMENTS 571-01 PROVIDE 125V DC CONTROL POWER TO DG CIRCUrrRY 2-BFN-RTP-57-1 NO UNrr 2 TEST SATISFIES (SYSTEM 82).
REQUREMENTS 572-02 PROVIDE UNIT PREFERRED POWER DISTRIBUTION.
2-BFN-RTP-57-2 NO UNIT 2 TEST SATISFIES REQUREMENTS 572-03 PROVIDE 120V AC POWER FOR REACTOR PROTECTION SYSTEM 2-BFN-RTP-57-2 NO UNrr 2 TEST SATISFIES (RPS) SYSTEM.
REQUIREMENTS 57244 PROVIDE CONTROL OF THE 120V AC POWER FOR RPS SYSTEM 2-BFN-RTP-57-2 NO UNrr 2 TEST SATISFIES REQUREMENTS 573-01 PROVIDE CONTROL A LOGIC POWER TO 4KV & 480V 2-BFN-RTP-57-3 NO UNrr 2 TEST SATISFIES SWITCHGEAR.
REQUIREMENTS 573-03 PROVIDE MOTIVE POWER & LOGIC POWER TO EQUIPMENT.
2-BFN-RTP-57 3 NO UNrr 2 TEST SATISFIES REQUIREMENTS j
573 05 PROVIDE LOGIC POWER TO 480V LOAD SHED LOGIC.
2 BFN-RTP-57-3 NO UNIT 2 TEST SATISFIES REQUIREMENTS 574-01 PROVIDE 480V SWTTCHGEAR DISTRIBUTION.
2-BFN-RTP-57-4 NO UNrr 2 TEST SATISFIES REQUIREMENTS 57442 PROVIDE 480V MCC DIS 7RIBLTTION.
2-BFN-LTP-57-4 YES 574-03 PROVIDE 480V LOAD SHED LOGIC SYSTEM.
2-BFN-RTP-57-4 NO TO BE TE$TED BY PMT FOR DCN W21284A 574-04 PROVIDE 480V AC DISTRIBUTION BACKUP CONTROL.
2-BFN-RTP-BUC VR4 htODB D64419BT BACEUPf.COKtROL$M avAc commes psaDans i
57445 PROVIDE 480V LOAD SHED ON DEGRADED VOLTAGE 2-BFN-RTP-57-4 yBs 3400E37405'T8815 CONDirIONS UNDERVOLTAGE IAnti i
sumoonio.paa.~.u.,~ve.,.
E2-21
.. - ~.
ENCLOSURE 2 Pcg3 22 cf 22 TAB 12
--sm aneN BrtWEEM BADMS PERRY MUOLEAR (BH4 15Sr5 2 APED 3 RESTART TWT Fm0 GRAM (R17)
SYSTEM MODE DESCRIPTION UNrr 2 TEST TEST COMMENTS MODE FOR U3 575-01 PROVIDE 4 KV POWER DISTRIBUTION FOR DO IDADINO 2-BFN-RTP-l/1-A NO UNTT 2 TEST SATISFIES
($YSTEM 82).
REQUIREMENTS 57542 PROVIDE RECIRCULATION PUMP TptP UPON SIGNAL.
2-BFN-RTP-068 YES 575-03 PROVIDE INSTRUMENTATION FOR DO PARALLELING (SYSTEM 2-BFN-RTP-57-5 NO UNrr 2 TEST SATISFIES 82)
REQUIREMENTS 575 04 PROVIDE INirIATION SIGNAL TO DIESElJ (SYSTEM 82).
2-BFN-RTP-57-5 NO UNrr 2 TEST SATISFIES REQUILEMENTS 57545 PROVIDE COOLING TOWER llFT PUMP TRIP ON CIRCULATING NONE NO REQURED'ONLY PCR COOLING WATER SYSTEM (27) LIFT PUMP DISCHARGE WATER
'~
OPERATION IN r's neun HIGH TEMPERATURE SIGNAL
$40064OPERAT90(M CLOSED MODE PROHIBITED UNTIL l
nBsownON orieg RFSCA9200016 (NOT WNMEM s
masTART) 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 NOT TESTED'AS PART (575).
OF STRDfTESTED AS POST MODIFICATION TEST M DCNS.MQ AND W23484
)
Me 1; System nxxles in which a Unit 2 test was not performed and a Unst 3 test is not required have been renwved from the table.
)
Ncta 2: All active functions which support the primary containment pressure boundary (e.g., primary containment isolation) shall be covered by the baseline test i
requirernent document (BTRD) of the system performing the active function. All functional tests for the isolation logic of the primary containment isolation l
symm are addressed by BTRD464D. Piping and components which form and supply the primary containment pressure boundary must be leak rate tested in accordance with 10 CFR 50 Appendix J and shall be hydrustatically tested under the ASME Section XI program. Therefore, testing for these modes are not required as part of the restart test program.
l i
E2-22
-