ML18082A987
| ML18082A987 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/14/1980 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18082A986 | List: |
| References | |
| PROC-800814, NUDOCS 8008260614 | |
| Download: ML18082A987 (153) | |
Text
~- . I-4.0 EMERGENCY INSTRUCTION I-4.0 SAFETY INJECTION INITIATION 1.0 PURPOSE 1.1 THIS INSTRUCTION IS PROVIDED TO PRESENT THE IMMEDIATE AUTOMATIC AND MANUAL ACTIONS RE-QUIRED TO BE PERFORMED ON THE RECEIPT OF ANY SAFETY INJECTION ACTUATION, WHETHER AUTOMATICALLY OR MANUALLY INITIATED, 1.2 THIS INSTRUCTION CONTAINS THE INFORMATION REQUIRED TO DIRECT THE OPERATOR TO THE APPRO-PRIATE EMERGENCY INSTRUCTION TO COPE WITH THE EXISTING PLANT CONDITIONS, 2.0 INITIAL CONDITIONS 2.1 SAFETY INJECT(ON HAS BEEN INITIATED, EITHER AUTOMATICALLY OR MANUALLY, 3.0 IMMEDIATE ACTIONS 3.1 VERIFY THE FOLLOWIMG AUTOMATIC ACTIONS HAVE OCCURRED, 3.1.1 REACTOR TRIP BY VERIFYING ALL CONTROL RODS ARE FULLY INSERTED BY CHECKING THE
- INDIVIDUAL ROD POSITION INDICATIONS AND ROD BOTTOM LIGHTS,
- 1) IF ANY CONTROL RODS DO NOT INDICATE FULL INSERTION, INITIATE A MANUAL REACTOR TRIP, 3.1.2 ACCIDENT LOADING OF THE SAFEGUARDS EQUIPMENT HAS TAKEN PLACE AND THE FOLLOWING EQUIPMENT IS RUNNING BY OBSERVING THE INDICATING LIGHTS ON THE STATUS PANEL ON RP-4 OR BY OBSERVING THE CONTROL BEZELS FOR EACH OF THE FOLLOWING:
- 1. CENTRIFUGAL CHARGING PUMPS
- 2. SAFETY INJECTION PUMPS.
3, RESIDUAL HEAT REMOVAL PUMPS 4, AUXILIARY FEEDWATER PUMPS (MOTOR DRIVEN)
- 5. SERVICE WATER PUMPS 6, CONTAINMENT FAN COIL UNITS IN SLOW SPEED.
7~ DIESEL GENERATORS, 3.1.3 REACTOR COOLANT TEMPERATURE IS DECREASING TO OR BEING MAINTAINED AT 547°F BY EITHER STEAM DUMP OR ATMOSPHERE STEAM RELIEF, 3.1.4 TURBINE TRIP BY VERIFYING THE FOLLOWING:
l, UNIT TRIP LIGHT ON THE EH CONSOLE.
2, TURBINE SPEED DECREASING IF THE TURBINE DOES NOT INDICATE A TRIPPED CONDITION, INITIATE A MANUAL TRIP FROM THE CONTROL CONSOLE, F* [OOJ ~ ~11~1f[~oo rm i w SALEM UNIT l/UNIT 2 REV. 2 8 008260 6 1'i
1-4.0 3,1,5 MAIN FEED PUMPS TRIPPED BY OBSERVING THE INDICATIONS ON THE CONTROL BEZEL, IF EITHER PUMP HAS NOT TRIPPED, TRIP IT MANUALLY, 3.1.6 FEEDWATER ISOLATION BY OBSERVING THE INDICATING LIGHTS ON THE FEEDWATER SECTION OF RP4.
3.2 VERIFY SAFETY INJECTION PUMP FLOW TO THE COLD LEGS FROM THE OPERATING SAFETY INJECTION PUMP(s) BY OBSERVING THE DISCHARGE FLOW METERS ON THE CONTROL .CONSOLE, WHEN RCS PRESSURE DECREASES TO <1500 PSIG AS READ ON THE WIDE RANGE INDICATORS ON THE CONTROL CONSOLE, STOP ALL REACTOR COOLANT PUMPS, 3.3 VERIFY CONTAINMENT PHASE A ISOLATION HAS TAKEN PLACE BY OBSERVING THE INDICATING LIGHTS ON THE STATUS PANEL RP-4, 3.4 ANNOUNCE OVER THE STATION PA SYSTEM TWICE: UNIT 1(2) REACTOR TRIP, SAFETY INJECTION.
4.0 SUBSEQUENT ACTIONS COMMENTS 4.1 VERIFY SAFETY INJECTION IS IN PROGRESS BY 4.1 IlQ. NQl ATTEMPT TO RESET THE CHECKING EACH OF THE FOLLOWING, IF ANY SAFETY INJECTION OR SEC IN EQUIPMENT OR VALVE IS NOT IN THE DESIRED ORDER TO PLACE EQUIPMENT IN CONDITION OR POSITION ATTEMPT TO ESTABLISH DESIRED CONDITION, SYSTEM THE DESIRED CONDITION AT THE INDIVIDUAL DESIGN IS SUCH THAT SUFFICIENT BEZEL ON THE CONTROL CONSOLE, REDUNDANCY IS PROVIDED TO OVERCOME SINGLE FAILURES, 4.1.1 VERIFY, UTILIZING CONSOLE AND/OR 1(2)RP4 STATUS PANEL INDICATIONS, THAT THE LOADS LISTED ON TABLE J HAVE BEEN LOADED ONTO THE VITAL BLISSES, 4.1.2 VERIFY SAFETY INJECTiON FLOW TO THE 4.1.2 IF NO FLOW IS INDICATED, CHECK COLD LEGS THROUGH THE BORON INJECTION OPEN 1(2)SJ4, 5, 12, 13.
TANK BY OBSERVING CHARGING PUMP DIS-CHARGE FLOW ON THE SAFETY INJECTION1 BEZEL, 4.1.3 CHECK THAT THE FOLLOWING VALVES HAVE OPENED BY OBSERVING THE STATUS PANEL ON RP-4. IF ._ANY VALVE FAILS TO OPEN, ATTEMPT TO MANUALLY OPEN FROM THE CONTROL CONSOLE, 1(2)SJ1 CHARGING PUMP SUCTION FROM RWST 1(2)SJ2 CHARGING PUMP SUCTION FROM RWST
- 4.1.4 CHECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4.
lF ANY VALVE FAILS TO CLOSE, ATTEMPT TO CLOSE THE VALVE SALEM UNIT l/UNIT 2 REV. 2
I-4.0 1<2)SJ78 RECIRC TO BORIC ACID TANK 1<2)SJ79 RECIRC TO BORIC ACID TANK 1<2)SJ108 RECIRC TO BORON INJECTION TANK 1<2)CV68 CHARGING SYSTEM STOP VALVE 1<2)CV69 CHARGING SYSTEM STOP VALVE 1<2)CV139 CHARGING PUMP DISCH TO SWHX 1<2)CV140 CHARGING PUMP DISCH TO SWHX 1<2)CV40 VOLUME CONTROL TANK DISCHARGE VALVE 4.1.4 1(2)CV40 &41 WILL NOT CLOS!
1<2)CV41 VOLUME CONTROL TANK DISCHARGE VALVE UNLESS 1(2)SJ1 OR 2 IS FULL' 1<2) CV3 ORIFICE IsoLTATION VALVE (LETDOWN) OPEN, 1<2)CV4 ORIFICE ISOLATION VALVE (LETDOWN) 1<2)CV5 ORIFICE ISOLATION VALVE (LETDOWN) 1C2)CV7 eves LETDOWN LINE 1<2)CV116 REACTOR COOLANT PUMP SEAL WATER DISCHARGE 1<2) CV2.84 REACTOR COOLANT PUMP SEAL WATER DISCHARGE 11C2l)SW20 TURBINE GENERATOR AREA SUPPLY VALVE 13C23)SW20 TURBINE GENERATOR AREA SUPPLY VALVE 1<2)SW26 TURBINE GENERATOR AREA ISOLATION VALVE 4.2 VERIFY AUXILIARY fEEDWATER FLOW IS ESTABLISHED TO AT LEAST TWO STEAM GENERATORS BY CHECKING THE AUXILIARY FEEDWATER FLOW INDICATORS ON THE CONTROL CONSOLE, 4,2,l IF FLOW HAS NOT BEEN ESTABLISHED, PROCEED AS FOLLOWS:
- 1) CHECK THE DISCHARGE PRESSURE ON THE MOTOR DRIVEN AUXILIARY fEEDWATER PUMPS (11, 12 21 &22) WHICH ARE RUNNING, IT SHOULD INDICATE >1350#,
- 2) IF PRESSURE IS LOW (<1350#) DEPRESS 2) THIS WILL REMOVE THE PUMP RUN-THE PRESS OVERRIDE PUSHBUTTON ON THE OUT PROTECTION INTERLOCK ON THE CONSOLE BEZEL FOR EACH AUXILIARY AF21 VALVES AND ALLOW THEM TO FEEDWATER PUMP, OPEN TO THEIR PRESET DEMAND REGARDLESS OF DISCHARGE PRESSURE.
- 3) IF PRESSURE IS >1350# CHECK THE VALVE DEMAND SET AT ~95% FOR 11-14(21-14)
AF21 ON THE CONSOLE BEZEL, ALSO, DEPRESS THE PRESS OVERRIDE PUSH-BUTTON ON THE CONSOLE BEZEL FOR EACH AUXILIARY FEEDWATER PUMP,
- 4) START,_IF NOT ALREADY RUNNING, No, 13(23)
AUXILIARY fEEDWATER PUMP AND VERIFY 11-14 (21-24)AF11 OPEN.
SALEM UNIT l/UNIT 2 REV. 2
1-4.0 4.3 VERIFY THAT PHASE "A" CONTAINMENT ISOLATION HAS TAKEN PLACE BY CHECKING THAT THE VALVES LISTED IN TABLE II ARE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4, SHOULD A VALVE FAIL TO CLOSE, ATTEMPT TO CLOSE IT FROM THE CONTROL CONSOLE, 4.4 VERIFY THAT fEEDWATER ISOLATION HAS TAKEN PLACE DUE TO THE SAFETY INJECTION, 4,4,l CHECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4, IF ANY VALVE HAS FAILED TO CLOSE, ATTEMPT TO CLOSE IT FROM THE CONTROL CONSOLE, 11(2l)BF13 fEEDWATER INLET STOP VALVE 11(2l)BF19 FEEDWATER CONTROL VALVE 11(2l)BF40 FEEDWATER BYPASS VALVE 12(22)BF13 FEEDWATER INLET STOP VALVE 12(22)BF19 fEEDWATER CONTROL VALVE 12(22)BF40 fEEDWATER BYPASS VALVE 13(23)BF13 fEEDWATER INLET STOP VALVE 13(23)BF19 fEEDWATER CONTROL VALVE 13(23)BF40 fEEDWATER BYPASS VALVE
- 4.5 14(24)BF13 14(14)BF19 14(24)BF40 fEEDWATER FEEDWATER fEEDWATER INLET STOP VALVE CONTROL VALVE BYPASS VALVE IF THE REACTOR COOLANT PUMPS HAVE BEEN TRIPPED, 4,5 TAVG IS NOT A RELIABLE INDICATION WITH NO RCP's RUNNING. WIDE INSURE THE STEAM DUMP PRESSURE CONTROLLER IS SET TO 1005# PSIG AND TRANSFER THE STEAM DUMP RANGE TH AND Tc ARE RELIABLE FOR TO PRESSURE CONTROL, RCS TEMPERATURE.
4.6 VERIFY THAT THE 4160V GROUP BussES HAVE TRANSFERRED FROM THE No, 1(2) AUXILIARY POWER TRANSFORMER TO No. 11(12) AND No. 12(22) STATION PowER TRANSFORMERS.
4,6,l CHECK THAT THE FOLLOWING 4160V BREAKERS HAVE OPENED AND ACKNOWLEDGE THEM ON THE APPRO-PRIATE CONTROL CONSOLE BEZEL, 1<2)BGGD 1<2)BFGD 1(2)AEGD 1(2)AHGD 4,6;2 CHECK THAT THE FOLLOWING 4160V BREAKERS HAVE CLOSED AND ACKNOWLEDGE THEM ON THE APPROPRIATE CONSOLE BEZEL:
SALEM UNIT l/UNIT 2
1-4.0 12(22)GSD 12(22)FSD 11<2DESD 11<2DHSD 4.7 IF THE RWST LEVEL IS DECREASING RAPIDLY 4.7 A LARGE LDCA IS THE ONLY ACCI-(> ~ 2 FT/MIN,), PROCEED DIRECTLY TO DENT WHICH WILL CAUSE THE RWST El 1-4, 4, "Loss OF CooLANT", TO DECREASE RAPIDLY,
~
4.8 VERIFY THE FOLLOWING FANS HAVE STOPPED BY OBSERVING THE INDICATIONS AS NOTED, IF ANY FANS ARE STILL RUNNING, ATTEMPT TO STOP THEM MANUALLY, No. 11 & 12(21 & 22) loDINE REMOVAL, (CONTROL CONSOLE)
No. 11, 12, 13, 14<21, 22, 23, ?4)
NOZZLE SUPPORT, (CONTROL CONSOLE)
No. 11 & 12(21 & 22) REACTOR SHIELD, (CONTROL CONSOLE)
No. 11, 12, 13, 14(21, 22, 23, 24)
CONTROL Ron DRIVE, (CONTROL CoNSOLE)
No. 11 & 12(21 & 22) RHR PuMP RooM COOLERS, <RP2)
No. 11 & 12(21 & 22) CHARGING PuMP ROOM COOLERS, <RP2)
No. 11 & 12(21 & 22) CONTAINMENT SPRAY PuMP RooM CooLERS, <RP2) 4.9 VERIFY CONTROL AREA AIR CONDITIONING HAS SHIFTED 4.9 THE CONTROL RooM VENTILATION TO THE ACCIDENT - INSIDE AIR MODE OF OP- FOR THE OTHER UNIT WILL ALSO ERATION AND THE FOLLOWING ACTIONS HAVE BE SHIFTED TO THE ACCIDENT OCCURRED BY OBSERVING THE STATUS PANEL MODE OF OPERATION, HOWEVER, ON RP2 I IF ANY ACTIONS DO NOT OCCUR, ITS NORMAL LIGHT WILL REMAIN MANUALLY INITIATE THEM IAW DI 11-17. ILLUMINATED, 3.2, "CONTROL RooM VENTILATION OPERA-TION", SECTION 5,3, 4.9.1 No. 11, 12, 13(21, 22, 23) CHILLERS ARE RUNNING, 4.9.2 No. 11 &12(21 &.22) CHILLED WATER PUMPS ARE RUNNING, 4.9.3 No. 11, 12, 13(21, 22, 23) CONTROL AREA SUPPLY FANS ARE RUNNING.
4.9.4 No. 11 & 12(21 &22) EMERGENCY CONTROL 1111 U
AREA SUPPL y FANS ARE RUNNING
- Ii' \U) ir6. lill'll11 IU) u11U<:1Utn1 uu,,.iu\l ll\1 \\.
- 1 SALEM UNIT l/UNIT 2 _ _ _R_E_v._2_ _ _ I
1-4,0
- 4.9.5 4.9.6 BATTERY EXHAUST FAN HAS STOPPED.
CONTROL VALVES 1(2)CH30 AND 1(2)CH151 CLOSE TO ISOLATE THE ADMINSTRATION BUILDING.
4,9,7 CONTROL AREA DAMPERS< POSITIONED AS FOLLOWS:
CAAl - CLOSED CAA18 - OPEN CAA2 - CLOSED CAA19 - CLOSED CAA3 - CLOSED CAA20 - CLOSED CAA4 - CLOSED CAA31 - CLOSED CAA5 - OPEN CAA32 - CLOSED CAA14. - CLOSED CAA33 - CLOSED CAA17 - OPEN REV. 2 SALEM UNIT l/LJNIT 2
1-4.0 5.0 IDENTIFICATION OF FOLLOW-UP ACTIONS 5,Q UTILIZE-REDUNDANT INDICATIONS WHERE AVAILABLE TO INSURE PROPER DIAGNOSIS, 5.1 VERIFY THE FOLLOWING ARE CLOSED OR ISOLATED AT THEIR INDIVIDUAL CONTROL BEZELS, 5.1.1 PRESSURIZER SPRAY VALVES <PS-1 &3)
- 1) IF PSl OR PS3 IS OPEN AND WILL NOT CLOSE TRIP THE REACTOR COOLANT PUMP IN THE ASSOCIATED LOOP, 1(2)PS1 - TRIP 11(21) RCP 1(2)PS3 - TRIP 13(23) RCP 5.1.2 PRESSURIZER POWER OPERATED RELIEF VALVES
<PRl &2) 5.1.3 PRESSURIZER OVERPRESSURE PROTECTION VALVES 5.1.3 UNIT 2 ONLY,
<PR47 & 48) 5.2 IF RCS PRESSURE HAS STABILIZED AFTER THE INITIAL DECREASE WHICH INITIATED SAFETY INJECTION AND CONTAINMENT ISOLATION, THE PROBLEM MAY BE IN AN AREA OR SYSTEM WHICH HAS BEEN SUBSEQUENTLY ISOLATED,
' INVESTIGATE THE FOLLOWING:
5.2.1 AUXILIARY BUILDING FOR:
- 1. INCREASES IN RADIATION
- 2. UNEXPLAINED ACCUMULATIONS OF WATER, 5.2.2 PRESSURIZER AUXILIARY SPRAY VALVE (CV75),
ENSURE IT IS CLOSED, SALEM UNIT l/UNIT 2 REV. 2
I-4.0 5.3 UTILIZE THE FOLLOWING MATRIX IN ORDER TO DETERMINE WHICH SUBSEQUENT EMERGENCY
< 1500# BUT < 2000# AND OR CCW TO PRESS LV[ > 22%
RCP's AND ISOLATED HEAT SINK AVAIL*
AND TH < TsAT > 50oF TRIP GO TO EI I-4.2 ALL "RECOVERY FROM RCP's SAFETY INJECTION I
<10% oR TH < TsAT < so°F REINITIATE SAFETY INJECTION I
CONT. RMS INCREASE) LO\~ STM PRESS IN ONE STM GEN BLOWDOWN OR AIR CONT. TEMP.1 PRESS1 OR MORE STM GEN EJECTOR RMS INCREASING HUMIDITY / SUMP LEVEL WITH NO INCREASE IN CONT.
INCREASING PARAMETERS GO TO EI I-4.4 GO TO EI I-4 .6 . GO TO EI I-4 .7 LOSS OF COOLANT ACCIDENT LOSS OF SECONDARY COOLANT STEAM GENERATOR TUBE RUPTURE PART II PREPARED BY- - - - - - - - - - - -
MANAGER - SALEM GENERATING STATION REVIEWED BY ____________
SORC MEETING No. DATE- - - - - - - -
- NOTE: AHEAT SINK EXISTS IF THE FOLLOWING. ARE PRESENT: 4
- 1. TOTAL Aux. FEEDWATER FLOW TO ALLS/G's >42 x 10 LB/HR DR LEVEL IN AT LEAST ONE S/G.
- 2. CORE EXIT T/C AND WIDE .RANGE TH INDICATE sf~kOR1ro~m~1uT~M~~RAaw SALEM UNIT l/UNIT 2 REV, 2
I-4.0
- 1(2)A DIESEL GENERATOR 240/480V BREAKER TABLE I "BLACKOUT WITH SAFETY INJECTION" LOADING SEQUENCE 1C2)B DIESEL GENERATOR 240/480V BREAKER 1C2)C DIESEL GENERATOR 240/480V BREAKER 11 c2D *sr Pu MP 11(21) CHARGING PUMP 12(22) CHARGING PUMP 11(21) RHR PUMP 12(22) RHR PUMP 12(22) SI PUMP 15 (21) SW PUMP 14(24) SW PUMP 11(25) SW PUMP OR OR OR 16(22) SW PUMP 13(23) SW PUMP 12(26) SW PUMP 11(21) CONTAINMENT.FAN 12(22) CONTAINMENT FAN 13(23) CONTAINMENT FAN (Low SPEED) (Low SPEED) (Low SPEED) 11(21) AUXILIARY FEED PUMP 14(24) CONTAINMENT FAN 15(25) CONTAINMENT FAN (Low SPEED) (Low SPEED) 11(21) AUXILIARY BUILDING 12(22) AUXILIARY FEED PUMP EMERGENCY AIR COMPRESSOR EXHAUST FAN 11(21) CH ILLER 12(22) AUXILIARY BUILDING 11(21) AUXILIARY BUILDING SUPPLY VENT FAN SUPPLY VENT FAN 11(21) SWGR ROOM SUPPLY FAN 12(22) AUXILIARY BUILDING 13(23) AUXILIARY BUILDING EXHAUST FAN EXHAUST FAN 12(22) CHILLER 13(23) CHILLER 12(22) SWGR RooM SUPPLY FAN 13(23) SWGR RooM SUPPLY FP NQIE THIS SEQUENCE IS INJTIATED ON ANY SAFETY INJECTION ACTUATION WITH OR WITHOUT A BLACKOUT, ONLY IN A BLACKOUT CONDITION WILL THE DIESEL GENERATOR BREAKERS CLOSE AFTER FIRST STRIPPING THE BUS AND THE LOADS WILL THEN BE SEQUENCED ONTO THE BUS, THIS SEQUENCE ~S ALSO INITIATED WITH A SAFETY INJECTION ~OINCIDENT WITH UNDERVOLTAGE ON ONE 4KV VITAL BUS,
~
ONLY THE LEAD SERVICE WATER PUMP WILL START, HOWEVER IF THE LEAD PUMP FAILS TO START THE BACKUP PUMP BREAKER WILL CLOSE,
~lffi ~OO~-\TI\u~ll~\ll"'"<l l\]u1JILW SALEM UNIT l/UNIT 2 REV. 2
- 4A . .
1- I-4.0 TABLE I I PHASE "A" ISOLATION 1.0 WASTE DISPOSAL SYSTEM 1<2)WU2 RCDT PUMP DISCHARGE 1<2)WU3 RCDT PUMP DISCHARGE 1<2)WL16 CONTAINMENT SUMP PUMP DISCHARGE 1<2)WL17 CONTAINMENT SUMP PUMP DISCHARGE
- 1<2)WL96 GAS ANALYZER FROM RCDT 1<2)WL97 GAS ANALYZER FROM RCDT 1<2)WL98 RCDT VENT 1(2)WL99 RCDT VENT 1C2)WL108 N2 SUPPLY TO RCDT
- 2. SAMPLING SYSTEM 1C2)SS27 ACCUMULATOR SAMPLE 1(2)SS33 Hor LEG SAMPLE 1(2)SS49 SAMPLE FROM PzR WATER SPACE 1C2)SS64 SAMPLE FROM PzR STEAM SPACE 1C2)SS103 ACCUMULATOR SAMPLE 1C2)SS104 Hor LEG SAMPLE
- lC2)SS107 1C2)SS110 11C2l)SS94 12(22)SS94 13C23)SS94 SAMPLE FROM PiR WATER SPACE SAMPLE FROM PzR STEAM SPACE SAMPLE FROM No. 11(21) STM GEN SAMPLE FROM No. 12(22) STM GEN SAMPLE FROM No. 13(23) STM GEN BLownowN BLownowN BLownowN 14C24)SS94 SAMPLE FROM No. 14(24) STM GEN BLownowN
- 3. COMPONENT COOLING 1C2)CC113 EXCESS LETDOWN HEAT EXCHANGER COOLING WATER OUTLET 1C2)CC215 EXCESS LETDOWN HEAT EXCHANGER COOLING WATER [NLET
- 4. STEAM GENERATOR DRAINS AND BLOWDOWN 11C2l)GB4 STEAM GEN OUTLET No. 11(21) 12C22)GB4 STEAM GEN OUTLET No. 12(22) 13(23)GB4 STEAM GEN OUTLET No. 13(23) 14(24)GB4 STEAM GEN.OUTLET No. 14(24)
- 1<2)PR17 1(2) PR18 1<2)NT25 GAS ANALYZER fROM PRT GAS ANALYZER FROM PRT N2 SUPPLY To PRT SALEM UNIT l/UNIT 2 REV. 2
1-4.0 AccUMUTLATORS 1(2)NT32 ACCUMULATOR N2 SUPPLY 7, CONTAINMENT VENTILATION 1(2)VC1 PURGE SUPPLY 1(2)VC2 PURGE SUPPLY .
H2)VC3 PURGE EXHAUST H2)VC4 PURGE "EXHAUST 1(2)VC5 CONT PRESS VAC RELIEF ISOLATION VALVE 1(2)VC6 CONT PRESS VAC RELIEF ISOLATION VALVE 1(2)VC7 CONTAINMENT RADIATION SAMPLE OUTLET H2)VC8 CONTAINMENT RADIATION SAMPLE OUTLET 1(2)VC11 CONTAINMENT RADIATION SAMPLE INLET 1(2)VC12 CONTAINMENT RADIATION SAMPLE INLET
- 8. DEMINERALIZED WATER 1(2)DR29 DM WATER To FLUSHING CONNECTIONS 9 I ' FI RE PROTECT! ON 1(2)FP147 FIRE PROTECTION WATER SUPPLY 10~ SAFETY INJECTION 1(2)SJ123 AccuM TEST STOP VALVE 1(2)SJ60 AccuM DISCH TEST STOP 1(2)SJ53 SJ HDR TEST STOP VALVE
- 12. CONTAINMENT VENTILATION - THE FOLLOWING SAMPLE VALVES RECEIVE NO AUTOMATIC ISOLATION SIGNAL, HOWEVER, THEY SHOULD BE VERIFIED CLOSED, 1<2)VC9 CONTAINMENT RADIATION SAMPLE OUTLET BACKUP 1<2)VC10 CONTAINMENT RADIATION SAMPLE OUTLET BACKUP 1<2)VC13 CONTAINMENT RADIATIOr~ SAMPLE INLET BACKUP 1<2)VC14 CONTAINMENT RADIATION SAMPLE INLET BACKUP lt\.YJUU. UU\lu wuuUUUu-u U U-.::1Ju\!
SALEM UNIT l/LiNIT 2 'REV I 2
I-4.2
- 1.0 PURPOSE EMERGENCY INSTRUCTION I-4.2 RECOVERY FROM SAFETY INJECTION 1.1 To DELINEATE THE STEPS REQUIRED TO TERMINATE SAFETY INJECTION AND RETURN THE UNIT TO A NORMAL, SHUTDOWN ALIGNMENT, 2.0 INITIAL CONDITIONS 2.1 THE CONDITIONS AS DESCRIBED IN ONE OF THE FOLLOWING EMERGENCY INSTRUCTION EXIST SUCH THAT TERMINATION OF SAFETY INJECTION IS REQUIRED OR DESIRABLE.
2.1.1 EI 1-4.0, "SAFETY INJECTION INITIATION" 2.1.2 EI 1-4:~, "Loss OF CooLANT" 2.1.3 EI I-4.6, "Loss OF SECONDARY CooLANT" 2.1.4 El I-4.7, "STEAM GENERATOR TUBE RUPTURE" 3.0 IMMEDIATE ACTIONS 3.1 NoNE COMMENTS
.4.0 SUBSEQUENT ACTIONS 4.1 ONCE SAFETY INJECTION IS RESET 4.1 THE SENIOR SHIFT SUPERVISOR/SHIFT SUPERVISOR IT WILL NOT AUTOMATICALLY RE-SHALL VERIFY THAT THE INITIAL CONDITIONS INITIATE UNTIL AFTER THE REACTOR DESCRIBED IN STEP 2.1 ABOVE ARE SATISFIED TRIP BREAKERS HAYE BEEN RESET, THE OPERATOR SHALL THEN PROCEED AS FOLLOWS:
4.1.1 REFER TO TABLE I. IF ANY OF THE CRITERIA LISTED UNDER THE COLUMN "SAFETY INJEC-TION REINITIATION CRITERIA" FOR THE APPROPRIATE ACCIDENT EXIST AT ANY TIME AFTER SAFETY INJECTION IS RESET, MANUALLY REINITIATE SAFETY INJECTION BY INSERTING THE SAFEGUARDS KEY INTO EITHER TRAIN A OR B SAFETY INJECTION OPERATE BEZEL AND TURN THE KEY, 4.1.2 MAINTAIN SAFETY INJECTION IN OPERATION UNTIL THE CRITERIA LISTED UNDER THE COLUMN "ACTIONS REQUIRED AFTER RE-INITIATION" FOR THE APPROPRIATE ACCIDENT ARE SATISFIED, REY. 9 SALEM UNIT l/UNIT 2
l-4.2 4.2 CONTROL AUXILIARY FEEDWATER FLOW TO MAINTAIN . 4.2 REFER TO APPENDIX 1 TO DETER-AN ACTUAL LEVEL OF ~33% IN THE NARROW RANGE MINE INDICATED LEVEL WHICH WILL IN ALL UNAFFECTED STEAM-GENERATORS, - ASSURE ~33% ACTUAL LEVEL, 4.2.1 lF AUXILIARY FEEDWATER FLOW HAS BEEN 4.2.1 .THIS APPLIES THROUGHOUT THE INTERRUPTED TO ANY STEAM GENERATOR FOR RECOVERY, MORE THAN 5 MINUTES AND THE LEVEL HAS COINCIDENTALLY BEEN <10% IN THE NARROW RANGE FOR MORE THAN 5 MINUTES, FLOW MUST 4
BE MAINTAINED < 10 X 10 LBM/HR. UNTIL THE LEVEL IS >10%,
4,3 RESET THE FOLLOWING SIGNALS: 4,3 IT IS NOT NECESSARY AT THIS TIME TO RESET CONTAINMENT VEN-TILATION OR FEEDWATER ISOLATION.
4.3.1 DEPRESS THE TRAIN nA" AND TRAIN "8" SI RESET PUSHBUTTONS, ON ~HE CONTROL CONSOLE TO RESET THE SAFETY INJECTION SIGNAL.
4,3,2 DEPRESS THE TRAIN "A" AND TRAIN "8" 4.3.2 THE STATUS LIGHTS ASSOCIATED CONT !SOL OA RESET PUSHBUTTONS, ON WITH OA ON RP-4 SHOULD GO OUT.
THE CONTROL CONSOLE, TO RESET THE CONTAINMENT PHASE A ISOLATION SIG-NAL.
4.3.3 DEPRESS THE EMERGENCY LOADING RESET 4.3.3 THE STATUS LIGHTS ON RP-4 PUSHBUTTONS, ON THE CONTROL CONSOLE, ASSOCIATED WITH THE SEC LOADING FOR lA, 18 AND 1CC2A, 28, AND 2C) SHOULD GO OUT, DIESEL GENERATORS TO RESET THE SAFE-GUARDS LOADING SEQUENCE, 4.3.4 DEPRESS THE 230V CONTROL CENTER 4.3.4 THE 23QV CONTROL CENTERS MAY RESET ON THE CONTROL CONSOLE FOR ALREADY BE RESET IF THE 20 lA, 18 AND 1C(2A, 28, AND 2C) MINUTE TIMER HAS TIMED OUT, DIESEL GENERATORS, 4,4 OPEN THE CONTAINMENT CONTROL AIR HEADER 1(2)A 1(2)8 ISOLATION VALVES *
. 11(21) CA330 12C22)CA330 4.5 RETURN THE CHARGING PUMPS TO THEIR NORMAL 4.5 INSURE No. 13(23) CHARGING LINEUP IAW DI Il-3.3.2, "OPERATING THE PUMP IS IN SERVICE BEFORE STOP-CHARGING PUMPS", AND RE-ESTABLISH CHARGING PING No. 11 &12(21 &22)
AND LETDOWN_ FLOW IAW DI Il-3,3.L "EsTAB- CHARGING PUMPS.
LISHING CHARGING, LETDOWN AND SEAL INmrrn nMT mm TION FLOW". wwu°n LI~u@~u\:/u~!r~]~ (OJ)l}~W SALEM UNIT l/UNIT 2 Rev. 9
1-4.2 4.5.l CONTROL ACTUAL PRESSURIZER LEVEL 4.5.1 REFER TO APPENDIX 1 TO DE-TERMINE INDICATED LEVEL WHICH AT '\,22%.
ASSURES '\,22% ACTUAL LEVEL.
4.6 IT JS PREFERRED TO START No. 13 4.6 lF THE REACTOR COOLANT PUMPS ARE NOT (23) RCP INCE THIS LOOP HAS RUNNING, START AT LEAST ONE PUMP JAW OI II-1.3.1, "RCP OPERATION", IN AN BOTH PRESSURIZER SURGE AND SPRAY. IF No. 13(23) IS NOT UNAFFECTED LOOP.
AVAILABLE, START No. 11(21).
4.7 INSURE A DISCHARGE FLOW PATH.
4.7 OPEN THE CENTRIFUGAL CHARGING PUMP MINI-FLOW VALVES, 1(2)CV139 &14D THEN STOP THE FLOW THRU THE BORON INJECTION TANK BY CLOSING INLET VALVES 1(2)SJ4 AND 1(2)SJ5. STOP THE CENTRIFUGAL tHARGING PUMPS WHICH ARE NOT BEING USED FOR NORMAL CHARGING.
4.8 THE PUMPS ARE RUNNING ON RECIRC.
4.8 STOP THE RHR PUMPS AND SAFETY INJECTION PUMPS .
4.9 RETURN THE SERVICE WATER SYSTEM TO NORMAL LINEUP IAW DI V-1.3.1, "SERVICE WATER - NORMAL OPERATION",
4.lD RETURN DIESEL GENERATORS lA, lB AND lC (2A, 2B, AND 2C) TO NORMAL OPERATION IAW 01 IV-16.3.L "EMERGENCY PowER - DIESEL OPERATION",
4.11 RETURN THE CONTAINMENT VENTILATION SYSTEM TO NORMAL OPERATION IAW DI II-16.3.1, "CONTAINMENT VENTILATION OPERATION".
4.12 RETURN THE AUXILIARY BUILDING VENTILATION SYSTEM TO NORMAL OPERATION IAW OI 11-17.3.l, AUXILIARY BUILDING VENTILATION OPERATION".
4.13 RETURN THE CoNTROL*RooM VENTILATION SYSTEM TO NORMAL OPERATI ON I AW 0I I I -17. 3. 2 J "CONTROL RooM VENTILATION OPERATION".
4.14 VERIFY THE EMERGENCY CONTROL AIR COMPRESSOR STOPS WHEN CONTROL AIR PRESSURE IS NORMAL AND RETURN THE CONTROL AIR SYSTEM TO NORMAL oPERATioN IAW 01 v-5 .3 .L "CoNTRoL ArR SYs-rErmrrn TEM OPERATION". lf lililfh REV. 9 SALEM UNIT l/UNIT 2
1-4.2 4.15 RETURN THE FEEDWATER SYSTEM TO THE DESIRED 4.15 THE AUXILIARY FEED PUMPS MAY BE MODE OF OPERATION IAW DI III-9.3.2, "FEED USED TO MAINTAIN STEAM GENERATOR PUMP OPERATION", AND SECURE THE AUXILIARY LEVELS.
FEED PUMPS.
- 1) REFILL THE AUXILIARY FEEDWATER STORAGE THE CONDENSATE PUMPS MAY BE TANK AS NECESSARY. STOPPED IF DESIRED,
- 2) REALIGN THE AUXILIARY FEED SYSTEM FOR POWER OPERATION IAW DI III-10.3.l, "AUXILIARY FEEDWATER SYSTEM OPERATION",
4.16 RETURN THE STEAM GENERATOR DRAINS AND BLOWDOWN SYSTEM TO NORMAL OPERATION IAW DI Ill-13.3.2, "STEAM GENERA*TOR BLOWDOWN - NORMAL OPERATION" I 4.17 RETURN THE CONTAINMENT/PLANT VENT RADIATION MONITOR TO NORMAL OPERATION !AW THE FOLLOWING Di's:
- 1) UNIT 1 - DI IV-11.3.4, "OPERATION OF THE CONTAINMENT/PLANT VENT SAMPLER CR11/Rl2)",
-- 2) UNIT 2 - 01 IV-11.3.2, "OPERATION OF RADIA-TION MONITOR SYSTEM SAMPLERS",
4.18 RETURN THE INLET VALVES TO THE GAS ANALYZER, FROM THE REACTOR COOLANT DRAIN TANK AND PRESSURIZER RELIEF TANK, TO NORMAL BY OPENING THE FOLLOWING VALVES:
1C2>WL96 1C2)WL97 1<2) PR18 1(2) PR17 4.19 DRAIN AND REFILL BORON INJECTION TANK FROM 4.19 D.Q. NQ.l REMOVE THE POWER FROM 1(2)SJ4, 5, 12, 13 AS THIS THE BoRIC Acrn TANKS IAW OI Il-4.3.5, "FLUSHING AND DRAINING THE BORON INJECTION WILL MAKE THE BORON INJECTION TANK INOPERABLE, TANK",
CAUTION: DO NOT ISOLATE THE BORON INJECTION EXPEDITE BECAUSE BIT BORON TANK DURING THE REFILLING PROCESS CONCENTRATION IS BELOW THE OR DURING THE SUBSEQUENT SAMPLING TECH SPEC LIMIT I TO INSURE THE FLOW PATH THRU THE
- 4.20 BIT IS OPERABLE.
RETURN THE SAFE!Y INJECTION.SYSTEM T O , .
IAW DI Il-4.3.L NORMAL OPERATION",
"SAFETY INJECTION Svs *.
SALEM UNIT l/UNIT 2 REV. 9
1-4.2 4.21 MAKE A VISUAL INSPECTION WITHIN THE CONTAIN-MENT WHEN ENTRY IS PERMISSIBLE.
4.22 AFTER THE PLANT HAS STABILIZED, SAMPLE THE REACTOR COOLANT SYSTEM FOR BORON CONCENTRA-TION AND H2. ADJUST BORON AS NECESSARY IAW 01 11-3.3.6, "BORON CONCENTRATION CONTROL" FOR THE DESIRED PLANT CONDITIONS, DEGAS THE RCS AS NECESSARY JAW 01 II-I.3.11, "VOLUME CONTROL TANK DEGASSIFICATI6N",
4.23 CALCULATE THE SHUTDOWN MARGIN JAW THE REACTOR ENGINEER'S MANUAL TO ENSURE THAT THE REACTOR IS SHUTDOWN BY >l,6% lK/K, 4.24 As INDICATED BY PLANT CONDITIONS PROCEED AS FOLLOWS:
TAKE THE UNIT TO COLD SHUTDOWN JAW DI l-3.6 "HOT STANDBY TO COLD SHUTDOWN", OR As AUTHORIZED BY AP-5 1 WITHDRAW THE SHUTDOWN BANKS AS FOLLOWS:
- 1) RESET THE FLUX RATE TRIP BY MOMENTARILY MusT BE RESET FOLLOWING ANY TAKING THE RATE MODE SWITCHES, ON EACH REACTOR TRIP FROM POWER, NIS POWER RANGE A DRAWER, TO THE RESET POSIT ION,
- 2) DEPRESS THE CLOSE-PUSHBUTTON, ON THE CON-TROL CONSOLE, FOR REACTOR TRIP BKR A, VERI-FYING THE BREAKER DOES CLOSE.
- 3) DEPRESS THE CLOSE PUSHBUTTON, ON THE CON-SOLE, FOR REACTOR . TRIP BKR B, VERIFYING THE BREAKER DOES CLOSE.
- 4) DEPRESS THE STARTUP PUBHBUTTON, ON THE CON- 4) IF THE STARTUP PUSHBUTTON HAS TROL CONSOLE, AND VERIFY EACH SHUTDOWN AND BEEN PUSHED PRIOR TO CLOSING CONTROL Ron STEP COUNTERS RESET TO ZERO. THE REACTOR TRIP BREAKERS, A Ron URGEN ALARM CONDITIONS WILL BE PRESENT, THIS CAN BE CLEARED BY PUSHING EITHER THE STARTUP PUSHBUTTON OR THE ALARM RESET PUSHBUTTON .
SALEM UNIT l/UNIT 2 REV, 9
1-4.2
- 5) COMMENCE WITHDRAWING SHUTDOWN BANK AJ BJ C AND DJ IN THAT ORDER) TO THEIR FULLY WITHDRAWN POSITION.
4.25 COMPLETE ATTACHMENT No. 1 AND ATTACH IT TO THE OPERATING INCIDENT REPORT) AP-6.
PREPARED BY _ _ _ _ _ _ _ _ _ _ _ _ __
MANAGER - SALEM GENERATING STATION REVIEWED BY _ _ _ _ _ _ _ _ _ _ _ _ __
SORC MEETING No. ___________ DATE _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 REV. 9
I-4.2 ATTACHMENT NO. 1 .
- INITIAL PRESSURIZER LEVEL POST SAFETY INJECTION DATA FINAL PRESSURIZER LEVEL
_ _ _ _ _PSIG IN1TIAL PRESSURIZER PRESSURE
_ _ _ _ _P,SIG FINAL PRESSURIZER PRESSURE
______ oF INITIAL TAVG
_ _ _ _ _ oF FINAL TAVG
______ oF RWST TEMPERATURE CT0650A)
______MIN.
DURATION OF SAFETY INJECTION RECORDED BY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE _ _ _ _ __
REVIEWED BY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ DATE. _ _ _ _ __
SENIOR SHIFT SUPERVISOR/SHIFT SUPERVISOR SALEM UNIT l/UNIT 2 REV I 9
I-4.2 TABLE I SAFETY INJECTION SAFETY INJECTION ACTIONS REQUIRED SAFETY INJECTION ACTUATION TERMINATION CRITERIA(l) REINITIATION CRITERIAC2) AFTER REINITIATIONCl)
- 1. SPURIOUS SI EI-4.0 1. RCS PRESS >2000 PSIG 1. RCS <1765 PSIG 1. RETURN TO EI-4.0 AND RE-EVALUATE,
- 2. PRZ LEVEL >22% 2. PRZ LEVEL <10% 2. INCREASE SUBCOOLING
. TO 65°F .
OR INCREASE RCS PRESS, TO 2200 PSIG,
- 3. SUBCOOLING >50°F 3. SUBCOOLI NG <50 °F 4
.. SIG LEVEL ~5% NARROW RANGE OS/G)
- 2. SMALL LOCA 1. RCS PRESS >2000 PSIG 1. RCS <1765 PSIG 1. RETURN TO EI-4.0 EI lJ .4 2. PRZ LVL >50% 2 PRZ LVL <20%
I AND RE-EVALUATE, 3, SUBCOOLING >50°F 3. SUBCOOLING <50°F 2. INCREASE SUBCOOL!NG AFW >42xl0 4 LBIHR
- 3. Loss OF SECONDARY 1. RCS PRESS >700 PSIG 1. RCS PRESS DROPS BY 1. RETURN TO EI-4.0 AND COOLANT - ONE TH 2. PRZ LVL >20% BY 200 PSIG RE-EVALUATE,
<350°F EI-4.6 3. SUBCOOLING >50°F 2. PRZ LvL DROPS BY 10% 2. INCREASE SUBCOOLING -
4, AFW >42xl0 4 LB/HR 3. SUBCOOLING <50°F 65°F BY COOLDOWN OR 3. RETURN RCS PRESS. TO SIG LVL ~5% NARROW THE VALUE AT TERMI-RANGE (lS/G) NATION,
- 4. Loss OF SECONDARY 1. RCS PRESS >2000 PSIG 1. RCS PRESS DROPS BY 1. RETURN TO EI-4.0 AND COOLANT - ALL TH 2 PRZ LVL >20%
I 200 PSIG RE-EVALUATE,
>350°F EI-IJ.6 3, SUBCOOLING 4 >50°F
- 2. PRZ LVL'DROPS BY 10% 2. INCREASE SUBCOOLING I i
- 4. AFW >42xl0 LB/HR 3. SUBCOOLING <5Q°F 65°f BY COOLDOWN OR 3. RETURN RCS PRESS, TO S/G LVL ~5% NARROW THE VALUE AT TERM!-
RANGE ClS/G) NATION,
- U) ALL CRITERIA MUST BE MET (2) ANY OF THE CONDITIONS REQUIRE REINITIATION SALEM UNIT l/UNIT 2 REV. 9
I-4.2 APPENDIX 1 DETERMINATION OF ACTUAL PRESSURIZER AND STEAM GENRATOR LEVELS To DETERMINE ACTUAL PRESSURIZER OR STEAM GENERATOR LEVELSJ UTILIZE THE ATTACHED TABLES AS DESCRIBED BELOW, TABLES 1-5 ARE TO BE USED FOR THE STEAM GENERATORS TABLES 6-11 ARE TO BE USED FOR THE PRESSURIZER
- 1. OBTAIN THE AVERAGE CONTAINMENT TEMPERATURE FROM COMPUTER POINT U1304.
- 2. REFER TO THE APPROPRIATE TABLE FOR THE PRESSURE IN THE STEAM GENERATOR AND PRESSURIZER.
- 3. LOCATE THE DESIRED ACTUAL LEVEL UNDER THE COLUMN FOR THE AVERAGE CONTAINMENT TEMPERATURES.
- 4. fROM THE COLUMN HEADED "INDICATED LEVEL(%)" DETERMINE THE INDICATED LEVEL WHICH SHOULD BE MAINTAINED TO ENSURE THE ACTUAL LEVEL IS MAINTAINED AT OR ABOVE THE DESIRED VALUE, till.IE IF THE COMPUTER IS UNAVAILABLE) MAINTAIN INDICATED LEVEL ~35% ABOVE THE DESIRED ACTUAL LEVEL .
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1-4.3 EMERGENCY INSTRUCTION 1-4.3 REACTOR TRIP 1.0 PURPOSE 1.1 A REACTOR TRIP IS INITIATED AUTOMATICALLY BY THE REACTOR PROTECTION SYSTEM IF UNSAFE OPERATING CONDITIONS ARE APPROACHED, IT MAY ALSO BE INITIATED MANUALLY FROM THE CON-TROL CONSOLE, THIS INSTRUCTION PROVIDES THE ACTIONS REQUIRED TO ENSURE THE REACTOR IS IN A SAFE SHUTDOWN CONDITION, 1.2 IN ADDITION TO DE-ENERGIZING THE SHUTDOWN AND CONTROL ROD DRIVE MECHANISMS) A REACTOR TRIP SIGNAL WILL INITIATE A TURBINE TRIP AND) IN CONJUNCTION WITH A LOW TAVG (554°F)
INITIATE A FEEDWATER ISOLATION SIGNAL, THIS INSTRUCTION DELINEATES THE ACTIONS REQUIRED TO ENSURE BOTH OF THESE HAVE OCCURRED, 1.3 IN THE EVENT A REACTOR TRIP IS REQUIRED AND HAS NOT BEEN AUTOMATICALLY INITIATED OR THE REACTOR FAILS TO TRIP WHEN INITIATED) THIS IS IDENTIFIED AS AN "ANTICIPATED TRAN-SIENT WITHOUT A TRIP" EVENT (ATWT EVENT), THIS INSTRUCTION PROVIDES THE NECESSARY ACTIONS TO ENSURE THE REACTOR IS PLACED IN A SAFE SHUTDOWN CONDITION FOR THIS EVENT, 2.0 INlTIAL CONDITIONS 2.1 ANY OF THE FOLLOWING CONDITIONS WILL LEAD TO A REACTOR TRIP AND TO AN AUTOMATIC PLANT SHUTDOWN, THE CONDITION CAUSING THE TRIP WILL BE BACK LIGHTED IN RED ON THE FIRST OUT OVERHEAD ANNUNCIATOR PANEL (SECTION f),
REACTOR TRIP SETPOINT COINCIDENCE INTERLOCK
- 1. MANUAL No NE 1/2 No NE
- 2. PwR. RANGE) HIGH Low SETPOINT - 25% oF 2/4 P-10 NEUTRON FLUX RATED THERMAL PwR.
HIGH SETPOINT - 109% OF 2/4 NONE RATED THERMAL PwR.
- 3. PwR, RANGE) HIGH +/- 5% OF RATED THERMAL 2/4 NONE FLUX RATE TRIP PwR. IN 2 sEc.
- 4. INTERMEDIATE RANGE) CURRENT EQUIVALENT TO 1/2 P-10 HIGH NEUTRON FLUX 25% OF FULL PWR.
- 5. SOURCE RANGE) HIGH 10 5 COUNTS PER SEC, 1/2 P-6 INTERLOCKED NEUTRON FLUX WITH P-10,
- 6.
7, 0vERTEMPERATURE ~T OVERPOWER ~T VARIABLE SETPOINT 2/4 No NE SALEM UNIT l/UNIT 2 REV, 6
I-4.3 REACTOR TRIP SETPOINT COINCIDENCE INTERLOCK 8, Low REACTOR 1865 PSIG 2/4 P-7 COOLANT PRESSURE
- 9. HIGH REACTOR 2385 PSIG 2/4 No NE COOLANT PRESSURE 10, HIGH PRESSURIZER 92% LEVEL 2/3 P-7
- 11. Low REACTOR 90% OF NORMAL FLOW 2/3/LooP P-7 & P-8 COOLANT FLOW
- 12. REACTOR COOLANT PUMP 75% OF NORMAL VOLTAGE WITH A 1/2 TAKEN P-7 UNDER VOLTAGE 0,2 SEC, TIME DELAY TWICE
- 13. REACTOR COOLANT PUMP 56,5 HERTZ WITH A 0.1 SECOND 1/2 TAKEN P-7 UNDER FREQUENCY TIME DELAY TWICE
- 14. REACTOR COOLANT PUMP 10% PwR. 2 BKR, OPEN l/PUMP P-7 & P-8 BREAKER OPEN 36% PwR, 1 BKR. OPEN 6
- 16. Low-Low STEAM 18% LEVEL PER S/G 2/3 PER S/G NONE GENERATOR WTR. LvL 17, TURBINE-GENERATOR 45 PSIG AUTO STOP OIL PRESSURE 2/3 P-7 TRIP OR ALL FOUR STOP VALVES CLOSED 4/4
- 18. SAFETY INJECTION l, MANUAL 1/2 No NE (ACTUATION) 2, PRESSURIZER AT 1765 PSIG 2/3 No NE 3, CONTAINMENT AT 4,7 PSIG 2/3 HIGH CON- NONE TAINMENT PRESSURE 4, ANY ONE S/G 100 PSIG LOWER 1/2 STEAM PRES- NONE THAN ANY OTHER TWO S/G's SURE ON ANY S/G LOWER THAN 1/2 STEAM PRESSURES ON 2/3 OF THE OTHER LOOPS, SALEM UNIT l/UNIT 2 REV, 6
1-4.3 COINCIDENCE INTERLOCK SETPOINT REACTOR TRIP 5, VAIRABLE: STEAM LINE FLOW 1/2 HIGH STEAM NONE 1.4 X 10 6 #/HR, 0-20% LOAD FLOW 2/4 STEAM 6 GEN IN COINCIDENCE INCREASING TO 4,Q X 10 #/HR.
AT 100% PWR, IN COINCEDENCE WITH 2/4 LOW TAVG WITH LOW TAVG 543°F OR LOW OR 2/4 LOW STEAM LI NE PRESSURE,
No NE LOGIC TRAIN "A" & TRAIN "B" IN 19, GENERAL ALARM TEST SIMULTANEOUSLY.
till1£.: THE GENERAL ALARM TRIP IS NOT ALARMED ON THE FIRST OUT ANNUNCIATOR.
No NE RACKING. IN 1 OR ATTEMPTING TO RACK
- 20. TRIP BYPASS BKRS. IN, BOTH REACTOR TRIP BYPASS BKRS, AT THE SAME TIME, till1£.: THE BYPASS BREAKER TRIP IS NOT ALARMED ON THE FIRST OUT ANNUN-CIATOR.
3.0 IMMEDIATE ACTIONS 3.1 8UIOMATIC 3.1.l REACTOR TRIP 3.1.2 TURBINE TRIP 3.1.3 GENERATOR TRIP 3.2 MANUAL 3,2,l lF. AN AUTOMATIC REACTOR TRIP liAs. fiQl OCCURRED AS INDICATED BY REACTOR POWER REMAINING HIGH AND/OR MULTIPLE CONTROL RODS FAILING TO INSERT, THIS IS IDEN-TIFIED AS AN "ANTICIPATED TRANSIENT WITHOUT A TRIP" EVENT CATWT EVENT). PROCEED AS FOLLOWS UNTIL THE REACTOR IS SUCESSFULLY TRIPPED:
- 1) INITIATE A MANUAL REACTOR TRIP WITH EITHER HANDLE ON THE CONTROL CONSOLE*
- 2) INITIATE A MANUAL TURBINE TRIP WITH THE HANDLE ON THE CONTROL CONSOLE .
- 3) OPEN THE REACTOR TRIP BREAKERS MANUALLY FROM THE CONTROL CONSOLE BY DEPRESSIN OPEN PUSHBUTTONS ON BOTH REACTOR TRIP B~EAKER A &B BEZELS.
REV. 6 SALEM UNIT l/UNIT 2
1-4.3
- 4) MANUALLY INITIATE SAFETY INJECTION BY INSERTING THE SAFEGUARD KEY INTO EITHER TRAIN A ORB SAFETY INJECTION OPERATE BEZEL AND TURN THE KEY,
- 5) MANUALLY TRIP BOTH REACTOR TRIP BREAKERS LOCALLY AT THEIR CUBICLE IN THE 84 fT, ELEVATION SWITCHGEAR ROOM,
- 6) MANUALLY TRIP BOTH CONTROL Ron MG SETS AT THEIR CONTROL PANELS IN THE 84 Fr.
ELEVATION SWITCHGEAR ROOM, 3.2.2 IF AN AUTOMATIC REACTOR TRIP HAS_ OCCURRED, PROCEED AS FOLLOWS:
- 1) CHECK THAT ALL FULL LENGTH RODS ARE FULLY INSERTED BY CHECKING INDIVIDUAL ROD POSITION INDICATORS AND ROD BOTTOM LIGHTS,
- 2) IF ANY FULL LENGTH CONTROL ROD DOES NOT INDICATE FULLY INSERTED, MANUALLY INI1IATE A REACTOR TRIP,
- 3) IF ALL FULL LENGTH CONTROL RODS ARE NOT THEN FULLY INSERTED, RAPID BORATE BY 150 PPM FOR EACH ROD NOT INSERTED AS FOLLOWS:
A) SHIFT ONE OR BOTH BORIC ACID TRANSFER PUMPS TO FAST SPEED, B) OPEN 1(2)CV175, RAPID BORATION STOP VALVE, c) BORATE FOR AT LEAST 8 MINUTES FOR EACH ROD NOT FULLY INSERTED (4 MINUTES WITH BOTH PUMPS IN FAST),
3,2,3 VERIFY TURBINE TRIP BY CHECKING THE FOLLOWING:
- 1) UNIT TRIP LIGHT ON E/H CONSOLE ILLUMINATED.
- 2) TURBINE STOP VALVES, GOVERNOR VALVES, INTERCEPTOR VALVES AND REHEAT STOP VALVES CLOSED,
- 3) TURBINE SPEED DECREASING, IF THE TURBINE HAS_ NQ.l TRIPPED, PROCEED AS FOLLOWS UNTIL STEAM FLOW FROM THE STEAM GENERATORS IS TERMINATED,
- 4) INITlA1E A MANUAL TRUBINE TRIP WITH THE HANDLE ON THE CONTROL CONSOLE,
- 5) MANUALLY OPEN THE GENERATOR OUTPUT BREAKERS, 1-5 &5-6 (1-9 &9-10),
- 6) TRIP CLOSED THE MAIN STEAM ISOLATION VALVES, ll-14(21-24)MS167 FROM EITHER THE SAFEGUARD BEZELS OR MAIN STEAM BEZELS,
- IF THE UNCONTROLLED STEAM FLOW HAS CAUSED REACTOR COOLANT SYSTEM PRESSURE TO DECREASE_TO _-<176)#, INSURE SAFETY INJECTION IS ACTUATED. IF SAFETY INJECTION IS NOT ACTUATED, INITIATE IT MANUALLY BY INSERT.ING THE SAFEGUARDS KEY INTO EITHER TRAIN A oR B SAFETY INJEcnaN OPERATE. BEZEL r...~~~~rifHrrA"#n """'cE~rjrt11 ~
I-4. a, "SAFTEY INJECTION IN ITIATIO~rffi ~INLr UJJ 6%u~uik uu ..::11 J'{j U>>J'U lk ~
- SALEM UNIT l/UNIT 2 REV. 6
I-4.3 3,2,4 VERIFY TAVG IS DECREASING TOWARD OR IS BEING MAINTAINED AT 547°F BY EITHER STEAM DUMP OR ATMOSPHERIC STEAM RELIEF, 3.2.5 VERIFY THAT FEEDWATER lsoLATION TAKES PLACE WHEN TAVG DECREASES TO 554°F.
3.2.6 VERIFY AUXILIARY FEEDWATER FLOW IS ESTABLISHED TO ALL FOUR STEAM GENERATORS IF ANY STEAM GENERATOR LEVEL IS <18%.
3.2.7 ANNOUNCE OVER THE PLANT PA SYSTEM TWICE: UNIT NO. 1(2) REACTOR TRIP.
4.0 SUBSEQUENT ACTIONS COMMENTS UTILIZE REDUNDANT INDICATIONS WHERE POSSIBLE TO CONFIRM EVALUATIONS AND ACTIONS, 4.1 VERIFY THE GENERATOR OUTPUT BREAKERS, 4.1 SHOULD OPEN ~30 SECONDS AFTER 1-5 &5-6(1-9 & 9-10) ARE OPEN . THE TURBINE TRIP, IF THEY DO NOT OPEN, OPEN MANUALLY BY DEPRESSING THE OPEN PUSHBUTTON ON THE BEZEL FOR EACH BREAKER ON THE CONTROL CONSOLE, 4.2 CHECK THAT NUCLEAR POWER IS DECREASING BY OBSERVING THE NUCLEAR INSTRUMENTATION, 4.2.1 CHECK THAT THE SOURCE RANGE HIGH 4.2.1 SHOULD OCCUR IN ~15-18 MINUTES VOLTAGE IS REINSTATED BELOW FOLLOWING THE TRIP, 11 5 X 10- AMPS ON BOTH INTER-MEDIATE RANGE CHANNELS,
- 1) !F THE SOURCE RANGE HIGH VOLTAGE DOES NOT ENERGIZE AUTOMATICALLY, MANUALLY DEPRESS THE RESET SOURCE RANGE "A" AND RESET SOURCE RANGE "B" PUSHBUTTONS ON THE CONTROL CONSOLE, 4.2.2 SWITCH THE NUCLEAR POWER RECORDER (NR-45)
TO READ ONE INTERMEDIATE RANGE CHANNEL AND ONE SOURCE RANGE CHANNEL *
. 4.2.3 NOTIFY THE PERFORMANCE DEPARTMENT THAT 4,2,3 THIS SHOULD BE ACCOMPLISHED AS A REACTOR TRIP HAS OCCURRED AND THAT SOON AS PRACTICAL TO INSURE THE COMPENSATING VOLTAGE ON THE INTER- PROPER INTERM!EDIATE RANGE MEDI.ATE RANGE DETECTORS SHOULD BE AD- INDICATION, JUSTED.
SALEM UNIT l/UNIT 2 REV, 6
1-4.3 4,3 VERIFY THAT THE PRESSURIZER PRESSURE AND LEVEL 4.3 TAKE MANUAL CONTROL AS NECESSARY, ARE WITHIN LIMITS, AND UNDER CONTROL, 4.4 VERIFY THAT THE 4160V GROUP BussES HAVE TRANS-FERRED FROM THE No, 1(2) AUXILIARY POWER TRANS-FORMER TO No. 11(21) &No. 12(22) STATION POWER TRANSFORMERS, 4,4,l CHECK THAT THE FOLLOWlNG 4160V BREAKERS 4.4.1 OPEN MANUALLY AS NECESSARY, HAVE OPENED AND ACKNOWLEDGE THEM ON THE APPROPRIATE CONTROL CONSOLE BEZEL; H2>BGGD 1(2)BFGD H2>AEGD 1(2)AHGD 4,4,2 CHECK THAT THE FOLLOWING 4160V BREAKERS 4,4,2 CLOSE MANUALLY AS NECESSARY, HAVE CLOSED AND ACKNOWLEDGE THEM ON THE APPROPRIATE CONTROL CONSOLE BEZEL:
12C22)GSD 12<22)FSD 11<21) ESD 11<2l>HSD 4.5 VERIFY THAT TAVG IS BEING MAINTAINED AT 4.5 CHECK STEAM DUMP VALVE POSITION 547°F DUE TO STEAM DUMP OPERATION, INDICATING LIGHTS.AND THE STEAM DUMP DEMAND INDICATOR, 4.5.1 ENSURE THE MAIN STEAM PRESSURE SET- 4,5,l CHECK THE SETTING FIRST TO POINT IS SET TO MAINTAIN STEAM PREVENT ANY UNWANTED STEAM GENERATOR PRESSURE AT ~1005 PSIG, DUMP OPERATION, THEN TRANSFER THE STEAM DUMP CON-TROL TO MAIN STEAM PRESSURE CONTROL, 4.5.2 IF CONDENSER STEAM DUMP IS NOT AVAIL-ABLE, UTILIZE THE ATMOSPHERIC STEAM RELIEF VALVES, 11-14(21-24)MS10 TO MAINTAIN STEAM GENERATOR PRESSURE AT ~1005 PS!G, 4.6 VERIFY THAT FEEDWATER ISOLATION HAS TAKEN PLACE
.DUE TO THE REACTOR TRIP IN COINCIDENCE WITH LOW TAVG (554°F).
4.6,l CHECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THElR APPROPRIATE BEZEL INDI-CATION:
11(2l)Bfl9 fEEDWATER CONTROL VALVE 12(22)BF19 FEEDWATER CONTROL VALVE SALEM UNIT l/UNIT 2 REV. 6
1-4.3 13(23)Bfl9 fEEDWATER CONTROL VALVE 14(24)Bfl9 fEEDWATER CONTROL VALVE 11(2l)Bf40 fEEDWATER BYPASS VALVE 12(22)Bf40 fEEDWATER BYPASS VALVE 13(23)Bf40 FEEDWATER BYPASS VALVE 14(24)Bf40 fEEDWATER BYPASS VALVE 4.7 TERMINATE ANY RCS DILUTION WHICH IS IN 4.7 PREVENT ANY INADVERTENT RE-PROGRESS, DUCTION IN SHUTDOWN MARGIN, 4.7.1 DEPRESS THE STOP PUSHBUTTON ON THE MAKEUP MODE SELECTOR BEZEL AND ALIGN THE BLENDER FOR AUTO MAKEUP IAW DI II-3.3.6, "BORON CONCENTRATION CONTROL",
4.7.2 BYPASS THE DEBORATING*DEMINERALIZERS BY ALIGNING 1(2)CV27 TO THE VCT.
4.8 RETURN THE LEVELS IN THE STEAM GENERATORS TO 4.8 THE FEED RING DRAINS SLOWLY NORMAL (~33%) AS FOLLOWS~ THROUGH THE LOOSE FIT CON-NECT I ON TO THE FEED INLET PIPING.
CAUTION: IF THE LEVEL IN ANY STEAM GENERATOR HAS BEEN <J.0% ON THE NARROW RANGE FOR MORE IF CONDITIONS REQUIRE MAXIMUM THAN 5 MINUTES AND ALL FEEDWATER FLOW HAS FLOW FOR DECAY HEAT REMOVAL BEEN ISOLATED FOR MORE THAN 5 MINUTES, CONSIDERATIONS, THIS TAKES 4 PRECEDENCE OVER THE WATER FLOW MUST BE LIMITED TO < 10 X 10 LBM/HR, TO THAT STEAM GENERATOR UNTIL THE LEVEL HAMMER CONSIDERATIONS.
IS RETURNED TO >10% IN THE NARROW RANGE, CAUTION: Il.Q. Nor. STOP 11 OR 12(21 OR 22) lF EITHER MOTOR DRIVEN PUMP.
Aux. fEED PuMP WHILE ANY STEAM GENERATOR IS STOPPED WHILE A STEAM GEN-IS -<18%. ERATOR LEVEL IS <J.8%, THE PUMP MUST BE STARTE.D LOCALLY FROM THE Hor SHUTDOWN PANEL, OR THE 125 VDC CONTROL POWER MUST BE CYCLED TO START THE PUMPS FROM THE CONTROL RooM. IF THE LEVEL INCREASES TO >18% THE PUMPS MAY BE RESTARTED NORMALLY.
4.8.1 CONTROL FLOW TO THE STEAM GENRATORS AS REQUIRED BY CONTROLLING THE FOLLOW.ING VALVES:
SALEM UNIT l/UNIT 2 REV. 6
1-4.3
- 2) ll-14(21-24)AF21 IF No. 11 &12 Aux. FEEDWATER PUMPS ARE IN OPERATION, 4.9 ESTABLISH AND MAINTAIN THE Hor STANDBY CONDITION JAW DI 1-3.5, "MINIMUM LoAD TO Hor STANDBY", AND DI 1-3.8, "MAINTAINING Hor STANDBY",
IF Rx TRIP WAS FROM >15% Rx POWER, HAVE THE 4.10 TECH SPEC 3.4.8 TABLE 4.4 4.10 131 133 135 CHEM DEPT. PERFORM AN I J I J I ISOTOPIC ANALYSIS BETWEEN 2 AND 6 HOURS FOLLOWING THE Rx TRIP, 4.11 OBTAIN A SAMPLE OF THE REACTOR COOLANT SYSTEM AND DETERMINE BORON CONCENTRATION. ADJUST BORON CONCENT~ATION AS REQUIRED lAW 01 Il-3.3.6, "BORON CONCENTRATION CONTROL",
4.12 As PER ADMINISTRATIVE PROCEDURE No. 5:
4.12.l NOTIFY THE STATION OPERATING ENGINEER OR CHIEF ENGINEER OF THE REACTOR TRIP
-- AND;
- , 4.13 4.12.2 INITIATE AN OPERATIONAL INCIDENT REPORT IAW AP-6 AND FORWARD IT TO THE STATION OPERATING ENGINEER, JF, AT THIS TIME, IT BECOMES NECESSARY, TAKE 4.13 IF ANY OF THE AUTOMATIC FUNCTIONS REQUIRED (I ,E, REACTOR TRIP, THE PLANT TO THE COLD SHUTDOWN CONDITION JAW TURBINE TRIP, AUXILIARY fEED-DI 1-3.6, "Hor STANDBY TO CoLD SHUTDOWN".
WATER INITIATION) HAVE FAILED TO ACTUATE, IT WILL BE NECESSARY TO PROCEED TO COLD SHUTDOWN lAW TECH SPEC 3.0.3.
4.14 As AUTHORIZED BY AP-5, WITHDRAW THE SHUTDOWN BANKS AS FOLLOWS:
4.14.1 RESET THE FLUX RATE TRIP BY MOMENTARILY 4.14.l ANY REACTOR TRIP FROM POWER TAKING TH~ RATE MODE SWITCHES, ON EACH WILL GENERATE A NEGATIVE RATE TRIP SIGNAL WHICH SEALS NIS POWER RANGE A DRAWER, TO THE RESET IN AND MUST BE MANUALLY POSITION, RESET.
4.14.2 DEPRESS THE CLOSE PUSHBUTTON~ ON THE CONTROL CONSOLE, FOR REACTOR TRIP BKR A, VERIFYING THE BREAKER DOES CLOSE.
~\Ptl ~OOYrlffil~iil:~~ \Nllll REV. 6 SALEM UNIT l/UNIT 2
l-4.3 4.14.3 DEPRESS THE CLOSE PUSHBUTTON, ON THE CONTROL CONSOLE, FOR REACTOR TRIP BKR B, VERIFYING THE BREAKER DOES CLOSE, 4.14.4 DEPRESS THE STARTUP PUSHBUTTON, ON THE 4.14.4 [F THE STARTUP PUSHBUTTON CONTROL CONSOLE, AND VERIFY EACH SHUT- HAS BEEN PUSHED PRIOR TO DOWN AND CONTROL RoD STEP COUNTER RESETS CLOSING THE REACTOR TRIP TO ZERO, BREAKERS, A Ron URGENT ALARM CONDITION WILL BE PRESENT, THIS CAN BE CLEARED BY PUSHING EITHER THE STARTUP PUSHBUTTON OR THE ALARM RESET PUSHBUTTON.
4.14.5 COMMENCE WITHDRAWING SHUTDOWN BANK A, E, ( AN~ D, IN THAT ORDER, TO THEIR FULLY WITHDRAWN POSITION.
4.15 WHEN THE CAUSE OF THE TRIP HAS BEEN DETER-MINED AND CORRECTED, OBTAIN THE PERMISSION OF THE STATION OPERATING ENGINEER OR THE CHIEF ENGINEER, IAW AP-5, TO TAKE THE REACTOR CRITICAL,
- 4.16 WITH STEAM GENERATOR LEVELS WITHIN THEIR NORMAL OPERATING BANDS AND JUST PRIOR TO COMMENCING THE RECOVERY, STARTUP) PERFORM THE FOLLOWING:
4.16.l PLACE THE STEAM GENERATOR FEEDWATER CONTROLS IN MANUAL AND RUN THE VALVE DEMAND TO ZERO, 4.16.2 RESET THE FEEDWATER ISOLATION SIGNAL BY DEPRESSING THE TRAIN "A" AND TRAI~ "B" FEEDWATER ISOLATION RESET PUSHBUTTONS ON THE CONTROL CONSOLE, 4.16.3 MAINTAIN STEAM GENERATOR LEVELS WITHIN THEIR NORMAL OPERATING BANDS BY MANUALLY CONTROLLING fEEDWATER BYPASS VALVES lL
- 12) 13 AND 14(21, 22, 23 AND 14)BF40.
RETURN THE AUXILIARY FEEDWATER SYSTEM 4.16.4 AFW STORAGE TANK LEVEL MAY BE 4.16.4 TO ITS NORMAL AT POWER LINEUP JAW OJ LOW, JJJ-10.3.1) "AUXILIARY FEEDWATER SYSTEM OPERATION",
SALEM UNIT l/UNIT 2 REV. 6
1-4.3 4.17 RETURN ro PowER OPERATION lAW 01 1-3.3J "Hor STANDBY TO MINIMUM LOAD"J AND 01 l-3.4J "POWER OPERATION",
MANAGER - SALEM GENERATING STATION SORC MEETING No. ____________ DATE _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 REV. 6
... I-4.4
- EMERGENCY INSTRUCTION 1-4.4 LOSS OF COOLANT (LEAKAGE GREATER THAN MAXIMUM CHARGING FLO~D 1.0 PURPOSE 1.1 THIS INSTRUCTION PROVIDES THE NECESSARY OPERATOR ACTIONS REQUIRED TO PROVIDE MAXIMUM CORE COOLING TO MINIMIZE COR~ DAMAGE FOLLOWING A LOSS OF COOLANT ACCIDENro.
1.2 THIS INSTRUCTION CONTAINS THE STEPS REQUIRED OF THE OPERATOR TO SWITCH FROM THE INJEC-TION TO RECIRCULATION PHASES OF CORE COOLING AT THE APPROPRIATE TIMES, 1.3 THIS INSTRUCTION INCLUDES THE APPROPRIATE OPERATOR ACTIONS REQUIRED TO COPE WITH THE FOLLOWING FAILURES, 1.3.1 Loss OF A RESIDUAL HEAT REMOVAL PUMP DUE TO EITHER OF THE FOLLOWING:
A, FAILURE OF THE ASSOCIATED SJ44, SIS SUMP VALVE, TO OPEN, B. FAILURE OF AN RHR PUMP.
1.3.2 Loss OF OFFSITE POWER WITHr A, ALL DIESELS OPERATING B, FAILURE OF A SINGLE DIESEL, 2~0 INITIAL CONDITIONS 2.1 SAFETY lN~ECTION HAS BEEN INITIATED AND IT HAS BEEN DETERMINED BY USE OF SECTION 5,0, "IDENTIFICATION OF FOLLOW-UP ACTIONS" OF El 1-4.0, "SAFETY INJECTION INITIATION", THAT A LOSS OF COOLANT ACCIDENT HAS OCCURRED, 3.0 IMMEDIATE ACTIONS 3,1 VERIFY THAT ALL IMMEDIATE AND SUBSEQUENT ACTIONS DESCRIBED IN EI I-4,0, "SAFETY INJECTION INITIATION" HAVE BEEN PERFORMED, COMPLETE ANY ACTIONS WHICH HAVE NOT BEEN PREVIOUSLY COMPLETED, 3.2 IF CONTAINMENT PRESSURE REACHES THE HI-HI SETPOINT OF 23.5 PSIG, VERIFY THE FOLLOWING ~
AUTOMATIC ACTIONS HAVE TAKEN PLACE BY OBSERVING THE INDICATIONS ON THE STATUS PANEL ON RP-4.
3.2.1 CONTAINMENT SPRAY. ACTUATION 3.2.2 CONTAINMENT PHASE "B" ISOLATION 3.2.3 MAIN STEAM ISOLATION SALEM UNIT l/UNIT 2 REV, 10
I-4.4 3.3 IF CONTAINMENT PHASE "B" ISOLATION IS ACTUATED, TRIP ALL REACTOR COOLANT PUMPS WITHIN FIVE MINUTES, 4.0 SUBSEQUENT ACTIONS - PART I - COLD LEG INJECTION COMMENTS 4,0 THE SUBSEQUENT ACTIONS IN THIS INSTRUCTION WILL ADDRESS BOTH THE SMALL LOCA AND THE DBA.
4.1 CHECK THE FOLLOWING INDICATORS ON THE CONTROL CONSOLE TO ENSURE BORATED WATER IS BEING INJECTED INTO THE REACTOR COOLANT SYSTEM, 4.1.1 BORON.INJECTION TANK PRESSURE INDI~ATING RCS PRESSURE.
4.1.2 CHARGING PUMPS DISCHARGE FLOW 4.1.3 No. 11(21) SAFETY INJECTION PUMP DISCHARGE FLOW WHEN RCS PRESSURE IS < ~ 1500 PSIG .
- 4.1.4 4.1.5 No. 12(22) SAFETY INJECTION PuMP DISCHARGE FLOW WHEN RCS PRESSURE IS < ~ 1500 PSIG, No. 11(21) RHR INJECTION FLow WHEN RCS PRESSURE IS < ~ 170 PSIG.
4.1.6 No. 12(22) RHR INJECTION FLOW WHEN RCS PRESSURE IS < ~ 170 PSIG.
4.2 IF CONTAINMENT PRESSURE ~ .tiQI INCREASED 4,2 CONTINUE TO MONITOR CONTAINMENT TO THE Hr-Hr SETPOINT OF 23.5 PSIG, PROCEED PRESSURE, PROCEED TO STEP 4,5, A RELATIVELY SLOW BUILDUP IN CONTAINMENT PRESSURE IS INDI-CATIVE OF A SMALL LOCA.
4.3 JF CONTAINMENT PRESSURE .l::IA£ INCREASED TO THE HI-HI SETPOINT OF 23.5 PSIG, VERIFY THE FOLLOWING BY OBSERVING THE STATUS PANEL ON RP-4 AND/OR THE CONSOLE INDI-CATIONS, SALEM UNIT l/UNIT 2 REY. 10
1-4.4 4,3,l CONTAINMENT SPRAY HAS INITIATED
- 1. CHECK THAT THE FOLLOWING PUMPS HAVE STARTED, IF A PUMP FAILS TO START, ATTEMPT TO START MANUALLY FROM THE CONTROL CON-SOLE, No. 11C21) CONTAINMENT SPRAY PuMP No, 12(22) CONTAINMENT SPRAY PUMP 2, CHECK THAT THE FOLLOWING VALVES HAVE OPENED, IF A VALVE FAILS TO OPEN, ATTEMPT TO OPEN MAN-UALLY FROM THE CONTROL CONSOLE, 11C2l)CS2 DISCHARGE VALVE 12(22)CS2 DISCHARGE VALVE 1(2)CS16 SPRAY ADD TANK DISCH VALVE 1(2)CS17 SPRAY ADD TANK DISCH VALVE 3, CHECK THE ADDITIVE TANK LEVEL INDICATOR AND OUTLET FLOW IN-DICATOR ON THE CONTROL CONSOLE TO ENSURE THAT THE SODIUM HYDROXIDE (NAOH) SOLUTION IS BEING INJECTED INTO THE CONTAINMENT SPRAY SYSTEM, IF THE LEVEL IS NOT DECREASING AND NO FLOW IS I ND I'CATED, DIS-PATCH AN OPERATOR TO VERIFY THE LEVEL LOCALLY AND TO ENSURE THE FOLLOWING MECHANICAL VALVES ARE OPEN, 11(21)CS20 EDucTOR SUPPLY VALVE 12(22)CS20 EDUCTOR SUPPLY VALVE 4,3,2 !SOLATION PHASE "B" HAS TAKEN PLACE l, CHECK* TO SEE THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4 AND ACKNOWLEDGE ON THE APPROPRIATE CONTROL CONSOLE BEZEL, A, IF ANY VALVE HAS FAILED TO CLOSE, ATTEMPT TO CLOSE IT FROM THE CONTROL CONSOLE BEZEL, SALEM UNIT l/UNIT 2 REV. 10
l-4.4 COMPONENT CooLING
- 1(2)CC117 1(2)CC118 1(2)CC136 1(2)CC131 RCP RCP RCP RCP COOLING WATER INLET COOLING WATER INLET BEARING OUTLET THRM BAR DISCH FLOW 1(2)CC190 RCP THERMAL BAR DISCH 1(2)CC187 RCP BEARING OUTLET B,
IF ANY REACTOR COOLANT PUMPS ARE RUNNING, THEY MUST BE TRIPPED AT THIS TIME, 4,3,3 MAIN STEAM ISOLATION HAS TAKEN PLACE l, CHECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL AND ACKNOWLEDGE ON THE APPROPRIATE CONTROL CONSOLE BEZEL, IF ANY VALVE HAS FAILED TO CLOSE, ATTEMPT TO CLOSE IT FROM THE CONTROL CONSOLE BEZEL,
- 11(2l)MS167 12(22)MS167 13(23)MS167 No. 11(21) STEAM GEN STOP VALVE No. 12(22) STEAM GEN STOP VALVE No. 13(23) STEAM GEN STOP VALVE 14(24)MS167 No. 14(24) STEAM GEN STOP VALVE 11C2l)MS18 No. 11C21) STEAM GEN STOP WARMUP VALVE 12C22)MS18 No. 12(22) STEAM GEN STOP WARMUP VALVE 13C23)MS18 No. 13(23) STEAM GEN STOP WARMUP VALVE 14C24)MS18 No. 14(24) STEAM GEN STOP WARMUP VALVE 11C2l)MS7 No. 11(21) STEAM GEN DRAIN VALVE 12C22)MS7 No. 12(22) STEAM GEN DRAIN VALVE 13C23)MS7 No. 13(23) STEAM GEN DRAIN VALVE 14C24)MS7 No. 14(24) STEAM GEN DRAIN VALVE SALEM LiNIT l/LiNIT 2 REV, 10
1-4.4 4.4 IF THE RWST LEVEL IS DROPPING RAPIDLY 4.4 IF RWST LEVEL IS DROPPING
(> ~ 2 FEET PER MINUTE) PROCEED TO STEP RAPIDLY, IT IS EVIDENT A 4.12. LARGE LOCA IS IN PROGRESS AND UNLIKELY THAT RCS PRESSURE WILL STABILIZE AT AN ELEVATED PRESSURE 4.5 CHECK CLOSED THE POWER OPERATED RELIEF 4.5 ELIMINATES PRV's AS THE SOURCE VALVES, 1(2)PR1 &2. OF LEAKAGE I 4,6 IF THE PRODAC 250 IS AVAILABLE:
4.6.1 INITIATE CRT TEST 41. IF THE 4,6,l IF CORE EXIT TEMPERATURE IS CORE EXIT THERMOCOUPLE IS <1200°F, <1200°F, CORE COOLING IS PROCEED TO STEP 4,8, IF THE HIGHEST ADEQUATE.
CORE EXIT THERMOCOUPLE READS ~1200°F, PROCEEP WITH STEP 4.6.2.
4,6,2 INITIATE A SHORT FORM THERMOCOUPLE 4,6,2 REQUIRES ~2-3 MINUTES TO PRINT MAP TO PRINT ON THE TREND TYPEWRITER OUT. CRT TEST 13.
3,6,3 IF FIVE OR MORE CORE EXIT THERMOCOUPLES READ ~1200°F A CONDITION OF INADEQUATE CORE COOLING IS DEVELOPING, PROCEED AS FOLLOWS TO RE-ESTABLISH CORE COOLING:
A, ESTABLISH MAXIMUM AUXILIARY FEEDWATER FLOW TO ALL INTACT STEAM GENERATORS, B, DUMP STEAM AT THE MAXIMUM RATE AVAIL- B, CONDENSER DUMP IS PREFERRED, ABLE FROM ALL STEAM. GENERATORS TO WHICH AUXILIARY FEEDWATER FLOW HAS ATMOSPHERIC DUMP IS ACCEPTABLE, BEEN ESTABLISHED, C, ESTABLISH MAXIMUM SAFETY INJECTION FLOW VIA THE BORON INJECTION TANK.
D, IF NEITHER THE CENTRIFUGAL CHARGING PUMPS SHOULD BE RUNNING.
PUMPS NOR SAFETY INJECTION PUMPS ARE DELIVERING WATER TO THE RCS, AND.,
STEAM.DUMP FROM THE STEAM GENERA- ATMOSPHERIC OR CONDENSER TORS IS NOT AVAILABLE, filID.1 AUXILIARY fEEDWATER IS NOT AVAIL-ABLE TO ANY STEAM GENERATOR, Il::lEN., OPEN BOTH PRESSURIZER PowER OPERATED RELIEF VALVES, INSURE 1(2)PR6 &7 ARE OPEN.
1(2)PR1 &2, TO REDUCE RCS SAFETY INJECTION PUMP SHUTOFF PRESSURE TO THE POINT AT ~1520 PSIG, WHICH SAFETY INJECTIOlf'!i'tmj) nrMf:r'(i'!)f[i)ffi/Al ~R PUMP SHUTOFF ~170 PSIG.
IS BEING DELIVERED TOIJT~iifpRELJLJ'tJf lLJJu~LJ\JLJ! LJ ~J~~ (O)JE~ w SALEM UNIT l/UNIT 2 REV, 10
1-4.4 E, IF NONE OF THE ABOVE ACTIONS RESULT E, THE CRITERIA FOR TRIPPING RCP's IN A REDUCTION IN CORE EXIT THERMO- AT 1500 PSIG DOES NOT APPLY, COUPLES, Arfil, IF COMPONENT COOLING WATER IS AVAIL- THE REQUIREMENTS FOR SEAL ABLE TO THE REACTOR COOLANT PUMP INJECTION FLOW, SEAL LEAKOFF MOTOR COOLERS, IlfEN, START ONE
- FLOW, THERMAL BARRIER CCW FLOW REACTOR COOLANT PUMP AND No, 1 SEAL ~p DO NOT APPLY, 4,7 IF THE PRODAC -250 IS liQI. AVAILABLE:
4.7.1 MONITOR THE WIDE RANGE RCS Hor 4.7.1 ON RECORDERS ON 1(2)RP4.
LEG TEMPERATURES, 4.7.2 IF THREE Hor LEG TEMPERATURES INDI-CATE ~700°F A CONDITION OF INADEQUATE CORE COOLING MAY BE DEVELOPING, PROCEED AS FOLLOWS TO RE-ESTABLISH CORE COOLING:
A, ESTABLISH MAXIMUM AUXILIARY FEEDWATER
. FLOW TO ALL INTACT STEAM GENERATORS, B, DUMP STEAM AT THE MAXIMUM RATE AVAIL- B, CONDENSER DUMP IS PREFERRED ABLE FROM ALL STEAM GENERATORS TO WHICH AUXILIARY FEEDWATER FLOW HAS ATMOSPHERIC DUMP IS ACCEPTABLE.
BEEN ESTABLISHED, C, ESTABLISH MAXIMUM SAFETY INJECTION FLOW VIA THE BORON INJECTION TANK.
D, l F NEITHER THE CENTRIFUGAL (HARG I NG PUMPS SHOULD BE RUNNING.
PUMPS NOR SAFETY INJECTION PUMPS ARE DELIVERING WATER TO THE RCS, Affil, STEAM DUMP FROM THE STEAM GENERA- ATMOSPHERIC OR CONDENSER TORS IS NOT AVAILABLE, Affil, AUXILIARY FEEDWATER IS NOT AVAIL-ABLE TO ANY STEAM GENERATOR, IH.EtL OPEN BOTH PRESSURIZER POWER OPERATED RELIEF VALVES, INSURE 1(2)PR6 &7 ARE OPEN.
1(2)PR1 &2, TO REDUCE RCS SAFETY INJECTION PUMP SHUTOFF PRESSURE TO THE POINT AT "-1520 PSIG, WHICH SAFETY INJECTION FLOW RHR PUMP SHUTOFF "-170 PS!G.
IS BEING DELIVERED TO THE CORE, E, IF NONE OF THE ABOVE ACTIONS RESULT E, THE CRITERIA FqR TRIPPING RCP's IN A REDUCTION IN CORE EXIT THERMO- AT 1500 PSIG DOES NOT APPLY.
COUPLES, Arfil, IF COMPONENT COOLING WATER IS AVAIL- THE REQUIREMENTS FOR SEAL ABLE TO THE REACTOR COOLANT PUMP INJECTION FLOW, SEAL LEAKOFF MOTOR COOLERS, IH.EN,. S~RT ONE FLOW, THERMAL BARRIER ccw FLOW REACTOR COOLANT PUMP, ~[ffi ~WJ~(O)~I~1ftl~ 1 ~~to NOT APPLY If SALEM UNIT l/UNIT 2 REV, 10
I-4.4 4,8 MONITOR FOR THESE CONDITIONS 4.8 SAFETY INJECTION MAY BE TERMINATED IF THROUGHOUT THIS INSTRUCTION.
~OF THE FOLLOWING EXIST, VERIFY RCS PRESSURE BY COM-
INDICATED ON 2/3 PRESSURIZER BIT PRESSURE SHOULD BE SLIGHTLY PRESSURE INDICATORS) Afill, HIGHER,
- 2. CORRECT PRESSURIZER LEVEL FOR
- 2. ACTUAL PRESSURIZER LEV~L IS >20%
REFERENCE LEG HEATUP !AW Afill, APPENDIX 2.
- 3. CORRECT STEAM GENERATOR LEVELS
- 3. TOTAL AUXILIARY fEEDWATER FLOW 4 TO FOR REFERENCE LEG HEATUP IAW ALL STEAM GENERATORS >42xl0 LB/HR OR ACTUAl LEVEL IN AT LEAST ONE APPENDIX 2.
STEAM GENERATOR ~5% AS INDICATED ON 2/3 NARROW RANGE INDICATORS)
AND THE INCORE THERMOCOUPLES AND WIDE RANGE TH ARE STABLE OR DECREASING) Afill.)
- 4. RCS TEMPERATURE IS MORE THAN 50°F
. 4. IF TEMPERATURE REMAINS BELOW THE TSAT -50°f CURVE ON THE SUBCOOLED AS INDICATED BY EITHER PRESSURE-TEMPERATURE CURVE, THE WIDE RANGE TH INDICATORS OR 50°F SUBCOOLING IS ASSURED.
THE INCORE THERMOCOUPLES, 4.8.l EI I-4.2 HAS ALL THE STEPS; 4.8.1 IF ALL OF THE ABOVE ARE MET)
REQUIRED TO TERMINATE SAFETY PROCEED TO EI I-4.2) "RECOVERY INJECTION AND THE CRITERIA FOR FROM SAFETY INJECTION".
RE-INITIATION.
4.9 IF REACTOR COOLANT PRESSURE STABILIZES ABOVE THE SHUTOFF HEAD (~170 PSIG) OF THE RESIDUAL HEAT REMOVAL PUMPS) PROCEED AS FOLLOWS:
4,9,l IF AT ANY TIME AFTER THE SAFETY 4.9.1 RESET SAFETY INJECTION BY DEPRESSING INJECTION AND CONTAINMENT .
BOTH TRAIN "A" AND TRAIN "B" SI RESET SPRAY SIGNALS ARE RESET) A PUSHBUTTONS ON THE SAFEGUARDS ACTUATION BLACKOUT SIGNAL IS RECEIVED, BEZELS ON THE CONTROL CONSOLE.
THE VITAL BLISSES WOULD BE STRIPPED AND THE BLACKOUT LOADS WOULD BE SEQUENCED ON BY THE SEC THE RHR, SAFETY INJECTION, AND CONTAINMENT SPRAY PUMPS AND THE CONTAINMENT fAN COIL UNITS ~
. lilll BE RESTARTED I THESE t1J,J.S.l BE MANUALLY RESTARTED ONCE THE LOADING SEQUENCE IS COMPLETE AS
~@~ ~00~~~1~lT~lOO @00~WNDICATED BY "LOADING COMPLE1E" REV. 10 SALEM UNIT l/UNIT 2
I-4.4 LIGHTS ON THE 18, lB, 1((28, 2B
- 2C) DIESEL BEZELS ON THE CONTROL CONSOLE, THIS IS TO BE ACCOMPLISHED IN SUCH A MANNER AS TO PREVENT OVERLOADING THE DIESELS, THE LOADS SHOULD BE APPLIED AT
~ 10 SEC, INTERVALS, IlQ. liQ1 RESTART THE EQUIPMENT BY MANUALLY INITIATING SAFETY IN-JECTION OR CONTAINMENT SPRAY AS THIS MAY RESULT IN UNDESIRABLE VALVE OPERATIONS, 4,9,2 ,RESET THE SAFEGUARDS LOADING SEQUENCE 4.9.2 THE STATUS LIGHTS ON RP-4 AS-BY DEPRESSING THE EMERGENCY LOADING SOCIATED WITH SEC LOADING RESET PUSHBUTTON ON THE CONTROL SHOULD GO OUT, CONSOLE FOR lA, lB, AND 1C(2A, 2B AND 2C) DIESEL GENERATORS.
4,9,3 STOP No, 11 &12(21 &22) RESIDUAL 4.9.3 THE RHR PUMPS SHOULD NOT BE HEAT REMOVAL PUMPS. ALLOWED TO RUN ON RECIRC FOR MORE THAN ~30 MINUTES SINCE THERE IS NO COMPONENT COOLING TO THE HEAT EXCHANGER, CAUTION: IF REACTOR COOLANT PRESSURE DECREASES TO BELOW THE SHUT-OFF HEAD (~170 PSIG) FOR THE RESIDUAL HEAT REMOVAL PUMPS, RESTART THE PUMPS, 4.9,4 OPERATE THE SAFETY INJECTION PUMPS 4,9,3 Do NOT ATTEMPT TO THROTTLE AS REQUIRED TO MAINTAIN PRESSURIZER THE DISCHARGE FLOW, LEVEL BETWEEN 50% AND 90%.
4.10 COMMENCE TAKING THE PLANT TO COLD SHUTDOWN CONDITIONS BY COOLING DOWN AS FOLLOWS:
4.10.l MANUALLY CONTROL THE AUXILIARY FEEDWATER 4.10.l. CORRECT STEAM GENERATOR LEVELS CONTROL VALVES (Af21) TO MAINTAIN ACTUAL FOR REFERENCE LEG HEATUP IAW STEAM GENERATOR LEVELS AT APPROXIMATELY APPENDIX 2.
33% .
SALEM UNIT l/UNIT 2 REV. 10
l-4.4
- 4.10.2 PLACE THE STEAM DUMP IN MAIN STEAM PRESSURE CONTROL MODE AND PERIODI-CALLY, REDUCE THE PRESSURE SETPOINT OF THE MAIN STEAM PRESSURE CONTROLLER BY DEPRESSING THE SETPOINT DECREASE PUSHBUTTON.
4.10.2 DECREASING THE SETPOINT INCREASES STEAM FLOW, lF THE CONDENSER IS NOT AVAILABLE, USE THE MS-lO's, 4.10.3 As APPLICABLE, TAKE THE PLANT TO 4.10.3 DUE TO ABNORMAL PLANT CON-COLD SHUTDOWN CONDITIONS IAW DI I-3.6, DITIONS SOME STEPS MAY NOT "Hen STANDBY To CoLD SHuTDowN". BE APPROPRIATE AND SOME EQUIPMENT NOT AVAILABLE, 4.10.4 IF THE PRODAC 250 COMPUTER IS 4.10.4 THIS PROVIDES A READILY AVAILABLE, INITIATE CRT TEST No. AVAILABLE DISPLAY OF SUB-41, "CO~E TEMPERATURE/PRESSURE COOLING I MONITOR PROGRAM", IF THE COMPUTER IS NOT AVAIL-ABLE OR THE INDICATIONS ARE CONSIDERED NOT RELIABLE DUE TO ADVERSE CONTAINMENT CON-DITIONS, SUBCOOLING CAN BE DETERMINED FROM EITHER THE PRESSURE-TEMPERATURE CURVE OR FROM THE STEAM TABLES .
4.11 WHEN CONDITIONS PERMIT, RETURN THE 4KV VITAL BussEs TO NORMAL BY:
4.11.1 STOPPING THE EMERGENCY DIESEL GENER-ATORS IAW DI IV-16.3.1, "EMERGENCY POWER - DIESEL OPERATION",
4.11.2 START OR STOP VITAL BUS LOADS, AS REQUIRED.
4.12 CLOSELY MONITOR RWST LEVEL. As IT APPROACHES THE LOW LEVEL ALARM, PREPARE TO CHANGE FROM THE INJECTION PHASE TO THE COLD LEG RECIRCULATION PHASE I PROCEED AS FOLLOWS:
4.12.1 RESET SAFETY INJECTION BY DEPRESSING 4.12.1 IF AT ANY TIME AFTER THE BOTH TRAIN "A" AND TRAIN "B" SI SAFETY INJECTION AND Cr RESET PUSHBUTTONS ON THE SAFEGUARDS TAINMENT SPRAY SIGNALS ARE ACTUATION BEZELS ON THE CONTROL RESET, A BLACKOUT SIGNAL IS CONSOLE, RECEIVED, THE VITAL BLISSES WOULD BE STRIPPED AND THE BLACKOUT LOADS WOULD BE SEQUENCED ON BY THE SEC.
SALEM UNIT l/UNIT 2 REV. 10
1-4.4 THE RHR, SAFETY INJECTION, AND CONTAINMENT SPRAY PUMPS AND THE CONTAINMENT FAN (OIL UNITS~ NQI. BE RESTARTED.
THESE MU.SJ. BE MANUALLY RE-STARTED ONCE THE LOADING SEQUENCE IS COMPLETE AS INDICATED BY THE "LOADING COMPLETE" LIGHTS ON THE lA, lB, 1C(2A, 2B, 2C) DIESEL BEZELS ON THE CONTROL CONSOLE, THIS IS TO BE ACCOMPLISHED IN SUCH A MANNER AS TO PRE-VENT OVERLOADING THE DIESELS, THE LOADS SHOULD BE APPLIED AT~ 10 SEC, INTERVALS, llQ. tiQl RESTART THE EQUIPMENT BY MANUALLY INITIATING SAFETY INJECTION OR CONTAINMENT SPRAY AS THIS MAY RESULT IN UNDESIR-ABLE VALVE OPERATIONS WHICH MAY RESULT IN EQUIPMENT DAMAGE, 4.12.2 RESET THE SAFEGUARDS LOADING 4.12.2 THE STATUS LIGHTS ON RP-4 SEQUENCE BY DEPRESSING THE ASSOCIATED WITH SEC LOADING EMERGENCY LOADING RESET PUSH- SHOULD GO OUT, BUTTONS ON THE CONTROL CONSOLE FOR lA, lB, 1C<2A, 2B, 2C)
DIESEL GENERATORS, 4.12.3 RESET CONTAINMENT SPRAY, IF CONTAINMENT PRESSURE IS LESS THAN 23.5 PSIG ON 3/4 CHANNELS, BY DEPRESSING TRAIN "A" AND TRAIN "B" SPRAY ACT RESET PUSHBUTTONS ON THE SAFEGUARDS ACTUATION BEZELS ON THE CONTROL CONSOLE.
4.12.3 WHEN CONDITIONS PERMIT, RETURN THE 4KV VITAL BusSES TO NORMAL BY:
A, STOPPING THE EMERGENCY DIESEL GEN-ERATORS JAW OJ IV-16.3.1, "EMERGENCY POWER - DIESEL OPERATION",
SALEM UNIT l/UNIT 2 REV' 10
I-4.4
- B, START OR STOP VITAL BUS LOADS, AS REQUIRED, liQIE: lF A LOSS OF OFFSITE POWER HAS OCCURRED IN COINCIDENCE WITH THE LOCA, ALIGN THE ELECTRICAL SYSTEM IN ACCORD-ANCE WITH ~PPENDIX 1, PRIOR PROCEEDING WITH PARTS II OR III OF THIS PROCEDURE, 4.13 PROCEED TO SECTION 5.0, PART II - COLD LEG RECIRCULATION I SALEM UNIT l/UNIT 2 REV I 10
PART I I l-4.4 5.0 SUBSEQUENT ACTIONS - PART II --COLD LEG RECIRCULATION COMMENTS CAUTION THE CHANGEOVER FROM THE SAFETY INJECTION PHASE TO COLD LEG RECIRCULATION MUST BE DONE QUICKLY TO PRECLUDE EMPTYING THE RWST. IF ANY VALVES FAIL TO RESPOND OR COMPLETE THE REQUIRED MOVEMENT, CON-TINUE WITH THE SEQUENCE AND INITIATE ANY CORRECTIVE ACTIONS WHEN THE CHANGEOVER IS COMPLETED, 5.1 VERIFY THAT THE FOLLOWING NORMALLY CLOSED 5.1 THE RH-29's WILL BE CLOSED VSLVES ARE CLOSED: ONLY IF RHR FLOW IS >1000 GPM PER PUMP, 11(2l)SJ40 11(21) D1scH VALVE ro* Hor LEG IF CONTAINMENT SPRAY HAS NOT 12<22)SJ40 12(22) DISCH VALVE TO Hor LEG BEEN ACTIVATED THE RHR PUMP 11(2l)SJ113 SI CHG PUMPS X-OVER VALVE NEED NOT BE ALIGNED TO THE 12(22)SJ113 SI CHG PUMPS X-OVER VALVE SPRAY HEADER.
11<2l)SJ45 REcIRc JsoL VALVE ro SI PuMPs 11(2l)CS36 FROM 11(21) RHX VALVE 12(22)CS36 FROM 12(22) RHX VALVE 1(2)RH2 RHR COMMON SUCTION VALVE 1(2)RH1 RHR COMMON SUCTION VALVE 11(2l)SJ44 SIS SUMP VALVE 12(22)SJ44 SIS SUMP VALVE 1(2)RH20 RHX BYPASS VALVE 1(2)RH26 Hor LEG IsoLATION VALVE 11(2l)RH29 11(21) RHR PUMP BYPASS 12(22)RH29 12(22) RHR PUMP BYPASS 12(22)SJ45 SUCTION FROM RHX (TO CHARGIN~ PUMP) 5.2 OPEN 11(2l)CC16 AND 12(22)CC16 RHR HEAT EXHCANGER OUTLET VALVES, 5,3 VERIFY THAT THERE IS AN ADEQUATE WATER LEVEL IN THE CONTAINMENT SUMP AS INDICATED BY AN ENERGIZED AVA! LAB LE NPSH LIGHT ON THE CONTROL CONSOLE I 5.4 WHEN RWST Low L~vEL ALARM ACTUATES 5.4 ANNUNCIATOR D-36. RECEIPT OF THE STOP THE FOLLOWING PUMPS IF THEY ARE RWST Low LEVEL ALARM INSURES RUNNING, SUFFICIENT NPSH FOR T~E RHR PUMPS, No. 11(21) RHR PUMP No. 12<22) RHR PuMP ONE CS PUMP SHOULD CONTINUE TO
- No. 11(21) CS PUMP OR No. 12(22) CS PUMP, OPERATE UNTIL THE RWST Low-Low IF CONTAINMENT SPRAY ACTUATION HAS OCCURRED. LEVEL ALARM IS RECEIVED OR THE SPRAY ADDITIVE TANK EMPTIES. IF CONTAINMENT PRESSURE IS >23.5 w~~ ~~J(Q)ffi11! J~ ~u\J
~~n w
- s,n l.UJ~~ U10 SALEM UNIT l/UNIT 2
1-4.4 PSIG IT WILL NOT BE POSSIBLE TO STOP EITHER CONTAINMENT SPRAY PUMP.
li.QIE: ALIGNING THE RHR PUMPS AS DESCRIBED IN THE FOLLOWING STEPS WILL PROVIDE FLOW TO THE CHARGING AND SAFETY INJECTION PUMPS AND THE CONTAINMENT SPRAY HEADER.
IF ONE RHR PUMP IS NOT AVAIALBLE TO PROVIDE FLOW THE OTHER PUMP WILL SUPPLY THE CHARGING AND SAFETY INJECTION PUMPS AND THE CONTAINMENT SPRAY HEADER WITH NO ADDITIONAL VALVE OPERATION) HOWEVER)
THE COLD LEG INJECTION FROM THE OPERATING RHR PUMP WILL HAVE TO BE ISOLATED BY CLOSING THE APPROPRIATE SJ-49, IF LOSS OF OFFSITE POWER HAS OCCURRED CONCURRENTLY WITH LOCAJ ~EE APPENDIX 1 FOR INSTRUCTIONS ON SECURING CONTAINMENT SPRAY PUMP.
5.5 CLOSE 11(21)RH4 RHR PUMP SucTION VALVE) IF No. 5,5 11(21)RH4 MUST BE CLOSED IN ORDER 11(21) RHR PUMP IS AVAILABLE. TO OPEN 11(2l)SJ44, 5.6 CLOSE 12(22)RH4 RHR PUMP SUCTION VALVE) 5,6 12(22)RH4 MUST BE CLOSED IN ORDER IF No. 12(22) RHR PUMP 1s AVAILABLE. TO OPEN 12(22)SJ44, 5.7 CLOSE THE BREAKER FOR 1(2)SJ69 AND CLOSE 5.7 1(2)C WEST 230V ViTAL VALVE THE VALVE) AS SOON AS POSSIBLE, CONTROL CENTER, THIS CAN BE COMPLETED IN CONJUNCTION WITH THE REMAINING STEPS, 5.8 REMOVE THE LOCKOUT ON RP4 AND OPEN 11(21)
SJ44 SIS SUMP VALVE) IF No. 11(21) RHR PUMP IS AVAIALBLE, 5.9 REMOVE THE LOCKOUT ON RP4 AND OPEN 12(22)SJ44 SIS SUMP VALVE) IF No. 12(22) RHR PuMP 1s AVAILABLE, 5.10 CLOSE 11(2l)RH19 11(21) RHX CROSS DISCH VALVE, 5.11 CLOSE 12(22)RH19 12(22)RHX CROSS DISCH VALVE.
5.12 START No. 11 &12(21 &22) RHR PUMP .
- 5.13 REMOVE THE LOCKOUT ON RP4 AND CLOSE 1(2)
SJ67J 12(22) MINI FLOW ISOLATION VALV:trfn\fD)
AND 1(2)SJ68 11(21) MINI FLOW lsoLATIUU'lWlITl VALVE. . .
5.13 THERE ARE REDUNDANT SWITCHES
~oorrOJ Wfi~f.~~~.~~~~~~~~~~
ON THE CONTROL co~~oltE OR THESE SWITCHES WILL ALLOW FULL SALEM UNIT l/UNIT 2 REV. 10
I-4.4 OPERATION OF THE VALVES ONCE THE LOCKOUT IS REMOVED, 5.14 OPEN 12C22)SJ45 SucTION FROM RHX, IF No. 5.14 To OPEN 12(22)SJ45, THE 12(22) RHR PUMP IS AVAILABLE. FOLLOWING VALVES MUST BE POSITIONED AS LISTED BELOW:
1(2)RH1 OR 1(2)RH2 - CLOSED 1(2)SJ67 OR 1(2)SJ68 - CLOSED 12(22)SJ44 - OPEN 5.15 OPEN 11C2l)SJ45 RECIRC IsoLATION VALVE TO 5.15 To OPEN 11(2l)SJ45, THE SI PuMP, IF No. 11C2D RHR PuMP 1s AVAILABLE. FOLLOWING VALVES MUST BE POSITIONED AS LISTED BELOW; 1(2)RH1 OR 1(2)RH2 - CLOSED 1(2)SJ67 OR 1(2)SJ68 ~ CLOSED 11(2l)SJ44 - OPEN 5.16 CLOSE THE BREAKER FOR 1(2)SJ3Q AND CLOSE THE 5.16 1(2)C WEST 230V VITAL VALVE VALVE, AS SOON AS POSSIBLE. CONTROL CENTER. THIS CAN BE COMPLETED IN CONJUNCTION WITH THE REMAINING STEPS.
5.17 OPEN 11C21)SJ113 SI CHARGE PUMPS X-OVER VALVE .
- 5.18 5.19 OPEN 12C22)SJ113 SI CHARGE PUMPS X-OVER VALVE.
CLOSE 1(2)SJ1 RWST TO CHARGE PUMP.
5.20 CLOSE 1(2)SJ2 RWST TO CHARGE PUMP.
5.21 VERIFY THAT No. 11(21) SI PUMP 1s OPERATING PROPERLY BY OVSERVING No. 11(21) SI PUMP DISCHARGE PRESSURE INDICATOR AND No. 11(21)
SI PUMP DISCHARGE FLOW INDICATOR.
5.22 VERIFY THAT No. 12(22) SI PuMP Is OPERATING PROPERLY BY OBSERVING No. 12(22) SI PUMP DISCHARGE PRESSURE INDICATOR AND No. 12(22)
SI PUMP DISCHARGE FLOW INDICATOR.
5.23 VERIFY THAT No. 11(21)* CENTRIFUGAL CHARGING PUMP IS OPERATING PROPERLY BY OBSERVING THE CHARGING PUMP IDSCHARGE FLOW INDICATOR AND BORON INJECTION TANK DISCHARGE PRESSURE INDICATOR, 5.24 VERIFY THAT No, 12(22) CENTRIFUGAL CHARGING PUMP IS OPERATING PROPERLY BY OBSERVING THE CHARGING PUMP DISCHARGE FLOW INDICATOR AND BORON INJECTION TANK DISCHARGE PRESSURE INDICATOR.
REV. 10 SALEM UNIT l/UNIT 2 -]4-
I-4.4 N.QJI: IF CONTAINMENT SPRAY HAS NOT BEEN ACTUATED, DELETE STEPS 5.25 THROUGH 5.28.
5.25 WHEN THE RWST Low-Low LEVEL ALARM ACTUATES 5.25 ANNUNCIATOR D-44 STOP THE FOLLOWING PUMP: BOTH CONTAINMENT SPRAY PUMPS No. 11(21) CONTAINMENT SPRAY PUMP OR SHOULD BE IDLE AT THIS TIME, No, 12(22) CONTAINMENT SPRAY PUMP, WHICH- IF CONTAINMENT PRESSURE HAD EVER PUMP IS STILL RUNNING, NOT DECREASED TO BELOW 23.5 PSIG, THE CONTAINMENT SPRAY PUMP CANNOT BE STOPPED FROM THE CONTROL CONSOLE, To STOP THE PUMPS, IT WILL BE NECESSARY TO TRIP THE BREAKERS LOCALLY ON THE lA AND 1CC2A AND 2C) 4KV VITt BLISSES BY TURNING OFF THE 125 VDC CONTROL POWER AND DEPRESSING THE MANUAL TRIP BUTTON INSIDE THE BREAKER CABINET, 5.26 REMOVE THE LOCKOUT AND CLOSE 12(22)SJ49 RHR PUMP DrscH IsoL VALVE. CllC2l)SJ49 IF No. 12(22) RHR PuMP IS NOT AVAILABLE) .
5.27 OPEN THE FOLLOWING CONTAINMENT SPRAY VALVES:
12C22)CS36 CllC2l)CS36 IF No. 12(22) RHR PUMP IS NOT AVAILABLE),
5.28 CLOSE THE FOLLOWING CONTAINMENT SPRAY VALVES:
11C2l)CS2 12C22)CS2 5,28.1 CONTINUE SPRAY OPERATION FOR A 5.28.1 THE EMERGENCY CORE COOLING MINIMUM PERIOD OF 22,5 HOURS IN SYSTEM IS NOW ALIGNED FOR ORDER TO ASSURE CONTAINMENT IN- COLD LEG RECIRCULATION AS TEGRITY AND REMOVAL OF AIRBORNE FOLLOWS:
FISSION PRODUCTS F~OM THE CONTAIN-MENT ATMOSPHERE, RHR PuMP No. 11(21) Is SUPPLYING WATER FROM THE CONTAINMENT SUMP DIRECTLY TO RCS LOOP 11(21) AND 13(21) COLD LEGS VIA VALVE 11(2l)SJ49 AND TO THE SUCTION OF THE SAFETY INJECTION PUMPS THROUGH VALVE 11(21)
SJ45.
~~ ~oorn~~lklrnJ~~ ©]lW SALEM UNIT l/UNIT 2 REY. 10
1-4.4 RHR PUMP No. 12C22) IS SUPPLYING WATER FROM THE CONTAINMENT SUMP DIRECTLY TO THE CONTAINMENT SPRAY HEADER AND TO THE SUCTION OF THE CHARGING PUMPS THROUGH VALVE 12(22)SJQ5, 5.29 CLOSELY MONITOR THE CONTAINMENT Hz CONCENTRATION ON RP-5. WHEN THE CONCENTRATION EXCEEDS ~ 2%J PLACE THE HYDROGEN RECOMBINERS IN SERVICE IAW DI 11-15.3.lJ "HYDROGEN RECOM-BINERS - NORMAL OPERATION",
SALEM UNIT l/LiNIT 2 -lQ.- REV. 10
PART I II 6,0 SUBSEQUENT ACTION - PART III - HOT LEG RECIRCULATION AFTER APPROXIMATELY 22.5 HOURS OF COLD LEG RECIRCULATION, REALIGN THE SAFETY INJECTION SYSTEM FOR Hor LEG RECIRCULATION, THE SEQUENCE FOR THE CHANGEOVER FROM COLD LEG RECIRCULATION TO Hor LEG RECIRCULATION IS AS FOLLOWS:
NQIE IF A LOSS OF OFFSITE POWER HAS OCCURRED IN COINDIDENCE WITH THE LOCA AND ONE OF THE DIESEL GENERATORS HAS FAILED TO START, REFER TO SECTION 4.0 OF PART II, III OR IV OF APPENDIX l, AS APPLICABLE, 6.1 CLOSE 12(22)CS36 FROM 12(22) RHX VALVE.
6.2 OPEN 12(22)RH19 RHX CROSS DISCH VALVE, 6.3 CLOSE THE BREAKER ON 1(2)C EAST 230V VITAL VALVE CONTROL CENTER AND OPEN 1(2)RH26 Hor LEG IsoLAT!ON VALVE, 6.4 REMOVE THE LOCKOUTS ON RP-4 AND CLOSE 11 &12(21 &22)SJ49 RHR PUMP D1scH IsoL VALVES.
6.5 SroP No. 11(21) SAFETY INJECTION PUMP, 6.6 CLOSE 11(2l)SJ134 11(21) SI PUMP DISCHARGE TO COLD LEG.
6.7 CLOSE THE BREAKER ON 1(2) A EAST 230V VITAL VALVE CONTROL CENTER AND OPEN 11(2l)SJ40 D1scHARGE VALVE ro Hor LEG.
6.8 START No. 11(21) SAFETY INJECTION PUMP.
6.9 VERIFY THAT No. 11(21) SAFETY INJECTION PUMP IS OPERATING PROPERLY BY OBSERVING No. 11(21)
SI PUMP DISCHARGE PRESSURE AND FLOW INDICATORS (A PRESSURE OF 175 TO 1520 PSIG AND AN APPROXIMATE FLOW OF 400 GPM SHOULD BE INDICATED),
6.10 STOP No. 12(22) SAFETY INJECTION PUMP.
6.11 CLOSE 12(22)SJ134 12(22) SI PUMP DISCH TO COLD LEG 6.12 CLOSE THE BREAKER ON 1(2)C WEST 230V VITAL VALVE CONTROL CENTER AND OPEN 12(22)SJ40 D1scH VALVE To Hor LEG.
6.13 START No. 12(22) SAFETY INJECTION PUMP.
6.14 VERIFY THAT No. 12(22) SAFETY INJECTION PUMP IS OPERATING PROPERLY BY OBSERVING No .
12(22) SI PUMP DISCHARGE PRESSURE AND FLOW INDICATORS (A PRESSURE OF 175 TO 1520 PS!G AND AN APPROXIMATE FLOW OF 400 GPM SHOULD BE INDICATED),
SALEM UNIT l/UN!T 2 REV, 10
I-4.4 NQI£.
THE RESIDUAL HEAT REMOVAL PUMPS AND SAFETY INJECTION PUMPS ARE NOW ALIGNED FOR Hor LEG RECIRCULATION AS FOLLOWS:
- 1) No, 11(21) RHR PUMP IS SUPPLYING WATER FROM THE CONTAINMENT SUMP TO THE SUCTION HEADER OF THE SAFETY INJECTION PUMPS.
- 2) No. 12(22) RHR PUMP 1s SUPPLYING WATER FROM THE CONTAINMENT SUMP TO THE REACTOR COOLANT SYSTEM THROUGH RCS LOOPS 13(23) AND 14(24)
Hor LEGS AND TO THE SUCTION OF THE CENTRI-FUGAL CHARGING PUMPS,
- 3) No. 11C21) SAFETY INJECTION PUMP 1s SUPPLYING COOLING WATER TO THE REACTOR COOLANT SYSTEM THROUGH RCS LOOPS 13(23) AND 14(24) Hor LEGS,
- 4) No. 12(22) SAFETY INJECTION PuMP 1s SUPPLYING COOLING WATER TO THE REACTOR COOLANT SYSTEM THROUGH RCS LOOPS 11(21) AND 12C22) Hor* LEGS,
- 5) No. 11(21) AND 12(22) CHARGING PUMPS ARE SUPPLYING COOLING WATER TO THE REACTOR COOLANT SYSTEM THROUGH THE BIT VIA THE COLD LEGS.
PREPARED BY _ _ _ _ _ _ _ _ _ _ _ _ __
MANAGER - SALEM GENERATING STATION REVIEWED BY _ _ _ _ _ _ _ _ _ _ _ _ __
SORC MEETING No. _ _ _ _ _ _ _ _ _ _ __ DATE _ _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 REV. 10
I-4.4 APPENDIX I DISCUSSION .~--
IF A LOSS OF OFFSITE POWER HAS OCCURRED IN COINCIDENCE WITH THE LOCA, THE DIESEL GENERATORS WILL BE SUPPLYING POWER TO THE VITAL BUSSES, DURING THE RECIRCULATION PHASE, IT IS NECESSARY TO RUN THE COMPONENT COOLING PUMPS AND THE HYDROGEN RECMOBINERS, IN ORDER TO ACCOMDATE THIS ADDITIONAL LOAD, OTHER EQUIPMENT MUST BE STOPPED"BEFORE THE COMPONENT COOLING PUMPS AND HYDROGEN RECOMBINERS ARE STARTED TO PREVENT OVERLOADING TH~ DIESEL GENERATORS, AFTER THE SAFETY INJECTION AND SEC ARE RESET, PROCEED WITH THE APPROPRIATE SECTION, I - ALL DIESEL GENERATORS OPERATING 1.0 STOP THE FOLLOWING* EQUIPMENT:
lillIE Do NOT STOP BOTH No. 11(21) AND 12(22) CONTAINMENT SPRAY PUMPS UNTIL THE RWST Low-Low LEVEL ALARM ACTUATES, WHEN ENTERING COLD LEG RECIRC,, STOP ONLY ONE CONTAINMENT SPRAY PUMP, EITHER 11(21)
OR 12 (22),
1.1 EQUIPMENT oN 1A<2A) VITAL Bus (POWERED BY 1AC2A) DIESEL/GENERATOR)
- 1. No. 11(21) CONTAINMENT SPRAY PUMP
- 2. No. 11<21) AUXILIARY BUILDING EXHAUST FAN
- 3) No. 11(21) SWITCHGEAR RooM SuPPLY FAN
- 4. No. 11(21) CHILLER 1.2 EQUIPMENT ON 1B<2B) VITAL Bus (POWERED BY 1B(2B) DIESEL/GENERATOR)
- 1. No. 12(22) CONTAINMENT FAN COIL UNIT
- 2. No. 14(24) CONTAINMENT FAN CoIL UNIT 1.3 EQUIPMENT ON 1CC2C) VITAL Bus (POWERED BY 1C(2C) DIESEL/GENERATOR)
- 1. No. 12(22) CONTAINMENT SPRAY PUMP
- 2. No. 11(21) AUXILIARY BuILDING SUPPLY FAN 2.0 START THE FOLLOWING .EQUIPMENT:
CAUTION WHEN ENTERING COLD LEG RECIRC, START ONLY ONE COMPONENT CooLING PUMP. ENSURE THE CoMPONENT~CooLING PUMP TO BE STARTED IS ENERGIZED FROM THE SAME VITAL Bus AS WAS THE CONTAINMENT SPRAY PUMP SECURED IN THE ABOVE STEP, SALEM UNIT l/UNIT 2 REV. 10
1-4.4 2.1 EQUIPMENT ON 1AC2A) VITAL Bus (POWERED BY 1AC2A) DIESEL/GENERATOR)
- 1. No, 11 COMPONENT COOLING PUMP OR 2.2 EQUIPMENT ON 1CC2C) VITAL Bus (POWERED BY 1CC2C) DIESEL/GENERATOR)
- 1. No, 13(23) COMPONENT COOLING PUMP NQIE
!F IRRADIATED FUEL IS STORED IN THE FUEL HANDLING BUILDING, START NO, 11 &12(21 &22) FHB EXHAUST FAN.
3.0 OPEN 11(2l)SW122 AND 12(22)SW133 TO SUPPLY SERVICE WATER TO COMPONENT COOLING.
II - FAILURE OF 1AC2AJ DIESEL GENERATOR 1.0 STOP THE FOLLOWING EQUIPMENT:
1.1 EQUIPMENT ON 1B<2B) VITAL Bus (POWERED BY 1B<2B) DIESEL/GENERATOR)
- 1. No. 11(21) CHARGING PUMP
- 2. No. 12<22) OR No. 14(24) CONTAINMENT FAN COIL UNIT
- 3. No. 12(22) AUXILIARY BUILDING SUPPLY FAN
- 1.2 EQUIPMENT ON 1C(2C) VITAL Bus (POWERED BY 1C(2C) DIESEL/GENERATOR)
- 1. No. 12(22) CONTAINMENT SPRAY PuMP WHEN RWST Low-Low LEVEL ALARM ACTUATES, 2.0 START No, 12(22) COMPONENT COOLING PUMP AND OPEN 12(22)SW122 TO PROVIDE SERVICE WATER TO COMPONENT COOLING,
~
IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING BUILDING, START No. 12C22) FHB EXHAUST FAN.
3.0 THE FOLLOWING SHOULD BE THE ALIGNMENT FOR COLD LEG RECIRCULATION, 3,1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
- 1. No. 12C22) RHR PUMP
- 2. No. 12(22) CHARGING PuMP
- 3. No. 12(22) SAFETY INJECTION PUMP
- 4. No. 12(22) CONTAINMENT SPRAY PUMP, UNTIL RWST Low-Low LEVEL ALARM ACTUATES .
SALEM UNIT l/UNIT 2 REY, 10
l-4.4 3,2 CLOSE VALVES 12(22)RH19 AND 12(22)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 12(22) CHARGING PUMP AND No. 12(22) SAFETY INJECTION PUMP SUCTIONS AND TO INSURE FLOW TO THE CONTAINMENT SPRAY HEADER THROUGH 12(22)CS36 WHEN IT IS OPENED, 3,3 THE COLD LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
l, No, 12(22) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTIONS OF No, 12(22) CHARGING PUMP AND No. 12(22) SAFETY INJECTION PUMP THROUGH 12(22)SJ45J 12(22)SJ113J 11C2l)SJ33J AND 12(22)SJ33.
- 2. No, 12(22) CHARGING PUMP DISCHARGE THROUGH THE BORON INJECTION TANK TO ALL FOUR COLD LEGS I 3, No, 12(22) SAFETY INJECTION PUMP DISCHARGE THROUGH 12(22)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS, 4, 12(22) CONTAINMENT SPRAY PUMP TAKING SUCTION FROM THE RWST AND DISCHARGE TO THE SPRAY HEADER, 4.0 PROCEED AS FOLLOWS FOR Hor LEG RECIRCULATION:
4.1 CLOSE 12(22)CS36 TO STOP CONTAINMENT SPRAY,
- 4.2 4,3 4,4 SroP No. 12(22) SAFETY INJECTION PuMP AND No. 12(22) CHARGING PuMP.
CLOSE 12(22)SJ134 TO ISOLATE COLD LEG RECIRCULATION, CLOSE THE BREAKER ON 1(2)C WEST 230V VITAL VALVE CONTROL CENTER AND OPEN 12(22)SJ40 TO SUPPLY Hor LEG RECIRCULATION.
4.5 START No. 12(22) SAFETY INJECTION PUMP.
4.6 THE Hor LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
l, No, 12(22) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTIONS OF No. 12(22) CHARGING PUMP AND No. 12(22) SAFETY INJECTION PUMP THROUGH 12(22)SJ45J 12C22)SJ113J 11(2l)SJ33J AND 12(22)SJ33.
- 2. No. 12(22) SAFETY INJECTION PUMP DISCHARGING THROUGH 12(22)SJ40 TO No. 11 &12
<21 &22) Hor LEGS.
III - FAILURE OF 1BC2B) DIESEL GENERATORS 3,0 STOP THE FOLLOWING EQUIPMENT:
Nilll Do NOT STOP BOTH 11(21) AND 12(22) CONTAINMENT SPRAY PUMPS UNTIL THE RWST Low-Low LEVEL ALARM ACTUATES.
WHEN ENTERING COLD LEG RECIRC,J STOP ONLY No, 12(22)
CONTAINMENT SPRAY PUMP. ~- ~OOJ@\lt\Wffi&\°\HJ~~ ~~!. lD SALEM UNIT l/UNIT 2
I-4.4 1.1 EQUIPMENT ON 1AC2A) VITAL Bus (POWERED BY 1AC2A) DIESEL/GENERATOR)
- 1. No. 11(21) CONTAINMENT SPRAY PuMP WHEN RWST Low-Low LEVEL ALARM ACTUATES.
1.2 EQUIPMENT ON 1CC2C) VITAL Bus (POWERED BY 1CC2C) DIESEL/GENERATOR)
- 1. No. 12(22) CONTAINMENT SPRAY PUMP
- 2. No, 12(22) SAFETY INJECTION PUMP 2.0 START No, 13(23) COMPONENT COOLING PUMP AND OPEN 11(2l)SW122 TO PROVIDE SERVICE WATER TO COMPONENT COOLING, filill.
IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING BUILDING, START No. 12(22) FHB EXHAUST FAN.
3,0 THE FOLLOWING SHOULD BE THE ALIGNMENT FOR COLD LEG RECIRCULATION:
3,1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
- 1. No. 11(21) RHR PUMP
- 2. No. 12(22) CHARGING PuMP 3.* No. 11C21) SAFETY INJECTION PUMP
- 4.
3.2 No. 11(21) CONTAINMENT SPRAY PUMP, UNTIL RWST LOW-Low LEVEL ALARM ACTUATES, (LOSE VALVE 11(21)RH19 AND 11(2l)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 12(22) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP SUCTIONS AND TO INSURE FLOW TO THE CONTAINMENT SPRAY HEADER THROUGH 11(21)
CS36 WHEN IT IS OPENED, 3, 3 THE COLD LEG REC IRC.ULATION FLOW PATH WOULD BE AS FOLLOWS:
- 1. No, 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTIONS OF No. 12(22) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP THROUGH ll(2l)SJ45, 11(2l)SJ113, 1H2l)SJ33, AND 12(22)SJ33.
- 2. No, 12(22) CHARGING PUMP DISCHARGING THROUGH THE BORON INJECTION TANK TO ALL FOUR COLD LEGS I 3, No, 11(21) SAFETY INJECTION PUMP DISCHARGING THROUGH 11(2l)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS, 4, No. 11(21) CONTAINMENT SPRAY PUMP DISCHARGING TO THE SPRAY HEADER, UNTIL RWST Low-Low LEVEL ALARM ACTUATES .
- 4.0 PROCEED AS FOLLOWS FOR Hor LEG RECIRCULATION:
4.1 CLOSE 11(2l)CS36 TO STOP CONTAINMENT SPRAY,
~@~ ~OOt@~I~ 1~~~ lm~~ W SALEM UNIT l/UNIT 2 . REV, 10
I-4.4 4.2 STOP No. 11C21) SAFETY INJECTION PUMP.
4,3 CLOSE 11(2l)SJ134 TO ISOLATE COLD LEG RECIRCULATION, 4.4 CLOSE THE BREAKER ON 1(2)A EAST 230V VITAL VALVE CONTROL CENTER AND OPEN 11(2l)SJ40 TO SUPPLY HoT LEG RECIRCULATION.
4.5 START No. 11(21) SAFETY INJECTION PuMP.
4.6 THE HoT LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
l, No. 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTION OF No, 11(21) SAFETY INJECTION PUMP THROUGH 11(2l)SJ45, 11(2l)SJ113, 11C2l)SJ33, AND 12(22)SJ33,
- 2. No. 11C2l):SAFETY INJECTION PUMP DISCHARGING THROUGH 11(2l)SJ40 TO No. 13 &14 (23 &24) HoT LEGS,
- 3. No, 12(22) CHARGING PuMP DISCHARGING TO ALL RCS CoLD LEGS, IV - FAILURE OF 1CC2C) DIESEL GENERATOR STOP THE FOLLOWING EQUIPMENT:
1.1 EQUIPMENT ON 1AC2A) VITAL Bus (POWERED BY 1AC2A) DIESEL/GENERATOR)
- 1. No, 11C21) CONTAINMENT SPRAY PuMP, WHEN RWST Low-Low LEVEL ALARM ACTUATES.
- 2. No. 11C21) AuxILIARY FEEDWATER PuMP 1.2 EQUIPMENT oN 1BC2B) VITAL Bus (POWERED BY 1BC2B) DIESEL/GENERATOR)
- 1. No. 12C22) RHR PuMP 2.0 START No, 12(22) COMPONENT COOLING PUMP AND OPEN 11(2l)SW122 TO PROVIDE SERVICE WATER TO COMPONENT COOLING.
t:lOIE IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING BUILDING, START No. 11 &12(21 &22) FHB EXHAUST FAN.
3.0 THE FOLLOWING SHOULD BE :Y:HE -Al.:IGNMENT FOR COLD LEG RECIRCULATION:
3.1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
- 1. No. 11(21) RHR PUMP
- 2.
3.
4.
No.
No.
No.
11(21) 11(21) 11(21)
CHARGING PuMP SAFETY INJECTION PUMP CONTAINMENT SPRAY PUMP, UNTIL RWST Low-Low LEVEL ALARM ACTUATES.
FmJIR! ~!NJJrm~I~ V~JrNJ ([JJ:JJU SALEM UNIT l/LJNIT 2 REv. 10
1-4.4 3.2 CLOSE VALVES 11(21)RH19 AND 11(2l)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 11(21) CHARGING PUMP AND No. 12(22) SAFETY INJECTION PUMP SUCTIONS AND TO INSURE FLOW TO THE CONTAINMENT SPRAY HEADER THROUGH 11(2l)CS36 WHEN IT IS OPENED.
3,3 THE COLD LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
- 1. No, 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTIONS OF No. 11(21) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP THROUGH 11(2l)SJ45, 11<2l)SJ113, 12(22)SJ113, 11C2l)SJ33 AND 12(22)SJ33.
- 2. No, 11(21) CHARGING PUMP DISCHARGING THROUGH THE BORON INJECTION TANK TO ALL FOUR COLD LEGS.
- 3. No, 12(22) SAFETY INJECTION PUMP DISCHARGING THROUGH 12(22)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS,
- 4. No. 11(21) CONTAINMENT SPRAY PuMP DISCHARGING ro SPRAY HEADER, UNTIL RWST Low-Low LEVEL ALARM ACTUATES.
4.0 PROCEED AS FOLLOWS FOR Hor LEG RECIRCULATION:
4.1 CLOSE 11(2l)CS36 TO STOP CONTAINMENT SPRAY.
4.2 SroP No. 11(21) SAFETY INJECTION PuMP.
4.3 CLOSE 11(2l)SJ134 TO ISOLATE COLD LEG RECIRCULATION, 4,4 CLOSE THE BREAKER ON 1(2)A EAST 230V VITAL VALVE CONTROL CENTER AND OPEN 11(2l)SJ40 TO SUPPLY Hor LEG RECIRCULATION.
4.5 START No. 11(21) SAFETY INJECTION PuMP.
4.6 THE Hor LEG RECIRCULATION FLow PATH wouLD BE AS FOLLOWS:
- 1. No, 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE SUCTIONS OF No. 11(21) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP THROUGH 11C2l)SJ45, 11(2l)SJ113, 12C22)SJ113, 11C2l)SJ33, AND 12C22)SJ33.
2 .. No. 11(21) SAFETY INJECTION PUMP DISCHARGING THROUGH 11(2l)SJ40 TO No. 13 &14 (23 &*24) Hor LEGS, 5.0 TRANSFER THE SECURITY SYSTEM TO THE EMERGENCY POWE.R SUPPLY ON lA 230V VITAL Bus .
SALEM UNIT 1/UNIT 2 REV. 10
I-4.4 APPENDIX 2
- DETERMINATION OF ACTUAL PRESSURIZER AND STEAM GENERATOR LEVELS To DETERMINE ACTUAL PRESSURIZER OR STEAM GENERATOR LEVELS) UTILIZE THE ATTACHED TABLES AS DE-SCIBED BELOW:
TABLES 1-5 ARE TO BE USED FOR THE STEAM GENERATORS TABLES 6-11 ARE TO BE'usED FOR THE PRESSURIZER
- 1. OBTAIN THE AVERAGE CONTAINMENT TEMPERATURE FROM COMPUTER POINT Ul304
- 2. REFER TO THE APPROPRIATE TABLE FOR THE PRESSURE IN THE STEAM GENERATOR AND PRESSURIZER.
- 3. LOCATE THE DESIRED ACTUAL LEVEL UNDER THE COLUMN FOR THE AVERAGE CONTAINMENT TEMPERATURE, 4, FROM THE COLUMN HEADED "INDICATED LEVEL.(%)" DETERMINE THE INDICATED LEVEL WHICH SHOULD BE MAINTAINED TO ENSURE IHE ACTUAL LEVEL IS MAINTAINED AT OR ABOVE THE DESIRED VALUE, riQIE IF THE COMPUTER IS UNAVAILABLE) MAINTAIN INDICATED LEVEL ~35% ABOVE THE DESIRED ACTUAL LEVEL, SALEM UNIT l/UNIT 2 REV. 10
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t *- J6.7J 33. 5? J!.135 29.<:JQ 2 J, C_J9 6~.00 46.77 '~ l1 '~ '.::* 35.22 J3.22 70.0() 52.00 51.IJJ 4 '}
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6~i.UO 40.3/ 3~i. 32 J2.52 29.57 '.::'6.51 70.0IJ 53.71 52.06 .rn 14 35.19 32.13
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1-4.6
- - EMERGENCY-INSTRUCTION 1-4.6 LOSS OF SECONDARY COOLANT
- 1. 0 PURPOSE 1.1 THIS INSTRUCTION PROVIDES THE NECESSARY OPERATOR ACTIONS REQUIRED TO LOCATE AND ISOLATE THE SOURCE OF A LOSS OF SECONDARY COOLANT TO MINIMIZE THE UNCONTROLLED COOLDOWN OF THE PRIMARY PLANT, 1.2 THIS INSTRUCTION CONTAINS THE ACTIONS REQUIRED TO ESTABLISH DECAY HEAT REMOVAL FROM THE REACTOR COOLANT SYSTEM VIA THE UNAFFECTED STEAM GENERATORS TO PREVENT THE PRESSURIZER SAFETY VALVES AND POWER OPERATED RELIEF VALVES FROM LIFTING, 1.3 A FEED LINE RUPTURE DOWNSTREAM OF THE FEEDWATER HEADER MANUAL ISOLATION VALVES 11-14 (21-24)BF22 WILL HAVE THE SAME CHARACTERISTICS AS A STEAM LINE RUPTURE AND WILL BE VIRTUALLY INDISTINGUISHABLE, HOWEVER, IT IS IMPORTANT FOR THE FAULTY STEAM GENERATOR TO BE IDENTIFIED AND ISOLATED RAPIDLY TO PRECLUDE .A LOSS OF FEEDWATER FLOW TO ALL STEAM GENERATORS THROUGH THE SINGLE LINE FAILURE, 1.4 THIS INSTRUCTION CONTAINS THE STEPS REQUIRED TO SHIFT FROM THE INJECTION TO THE (OLD LEG RECIRCULATION MODE OF CORE COOLING AT THE APPROPRIATE TIME, 1.5 ALSO INCLUDED ARE THE APPROPRIATE OPERATOR ACTIONS REQUIRED TO COPE WITH THE FOLLOWING FAILURES:
1.5.1 Loss OF A RESIDUAL HEAT REMOVAL PUMP DUE TO EITHER OF THE FOLLOWING:
- 2. FAILURE OF AN RHR PUMP.
1.5.2 Loss OF OFFSITE POWER WITH
- 1. ALL DIESEL OPERATING
- 2. fAILURE OF A SINGLE DIESEL 2.0 INITIAL CONDITIONS 2.1 SAFETY INJECTION HAS BEEN INITIATED AND IT HAS BEEN DETERMINED BY USE OF SECTION 5.0, "IDENTIFIC~TION OF_foLLOW-UP Ac~10Ns" OF EI 1-4.0, "SAFETY INJECTION INITIATION" THAT A LOSS OF SECONDARY COOLANT HAS OCCURRED,
- 3.0 IMMEDIATE ACTIONS 3.1 VERIFY THAT ALL IMMEDIATE AND SUBSEQUENT ACTIONS DESCRIBED IN El 1-4.0, "SAFETY INJEC-TION INITIATION" H~VE ~EEN PERFORMED, COMPLETE ANY ACTIONS WHICH HAVE NOT BEEN PREVIOUS-LY COMPLETED, SALEM UNIT l/UNIT 2
1-4.6 3,2 IF CONTAINMENT PRESSURE REACHES THE HI-HI SETPOINT OF 23.5 PSIG, VERIFY THE FOLLOWING ON RP-4.
3,2,l CONTAINMENT SPRAY ACTUATION 3.2.2 CONTAINMENT PHASE "B" ISOLATION 3.2.3 MAIN STEAM ISOLATION 3.3 IF CONTAINMENT PHASE "B" ISOLATION IS ACTUATED, TRIP ALL REACTOR COOLANT PUMPS WITHIN FIVE MINUTES, 4.0 SUBSEQUENT ACTIONS - PART I - COLD LEG INJECTION COMMENTS 4,0 UTILIZE REDUNDANT INDICATIONS WHERE PRACTICAL TO DETERMINE THE PROPER COURSE OF SUBSEQUENT AC-TIONS, I
4.1 VERIFY THAT MAIN STEAM ISOLATION HAS 4,1 MAIN STEAM ISOLATION MAY OCCURRED, IF IT HAS NOT, MANUALLY NOT BE AUTOMATICALLY INITIATED INITIATE IT BY DEPRESSING THE 11-14 ON A FEEDLINE RUPTURE OR A (21-24) LOOP MAIN STEAM ISOLATION STEAM LINE RUPTURE UPSTREAM
-PUSHBUTTONS ON EITHER TRAIN "A" OR OF THE FLOW ORIFICE, "B" SAFEGUARDS ACTUATION BEZEL, 4,1,l CHECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4 AND/OR THE CONSOLE BEZEL AND ACKNOWLEDGE ON THE APPROPRIATE CONSOLE BEZEL, IF ANY VALVE HAS FAILED TO CLOSE, ATTEMPT TO CLOSE IT FROM THE .
. CONTROL CONSOLE, 11(2l)MS167 No, 11(21) STEAM GENERATOR STOP VALVE 12(22)MS167 No, 12(22) STEAM GENERATOR STOP VALVE 13(23)MS167 No. . 13(23)
. . STEAM GENERATOR STOP VALVE 14(24)MS167 No, 14(24) STEAM GENERATOR STOP VALVE 11C2l>MS18 No. 11(21) STEAM GENERATOR STOP WARMUP VALVE 12C22>MS18 No. 12(22) STEAM GENERATOR STOP WARMUP VALVE 13C23)MS18 No. 13C??> STEAM GENERA~rD)
STOP WARMUP VALVE lr~lnl
\
SALEM UNIT l/UNIT 2 REV, 9
1-4.6 14(24)MS18 No. 14(24) STEAM GENERATOR STOP WARMUP VALVE 11(2l)MS7 No, 11(21) STEAM GENERATOR DRAIN VALVE 12C22>MS7 No. 12(22) STEAM GENERATOR DRAIN VALVE 13(23)MS7 No. 13(23) STEAM GENERATOR DRAIN VALVE 14C24>MS7 No. 14(24) STEAM GENERATOR DRAIN VALVE 4.2 CHECK THE FOLLOWING INDICATIONS ON THE CONTROL CONSOLE TO ENSURE BORATED WATER IS BEING INJECTED INTO THE REACTOR COOLANT SYSTEM, 4.2.1 BORON l~JECTION TANK PRESSURE APPROXIMATELY INDICATING RCS PRESSURE, 4.2.2 CHARGING PUMP DISCHARGE FLOW 4.2.3 No. 11(21) SAFETY INJECTION PUMP DISCHARGE FLOW WHEN RCS PRESSURE Is < '\,1500 PS I G.
4.2.4 No, 12(22) SAFETY INJECTION PUMP DISCHARGE 4.2.4 RCS PRESSURE SHOULD STABILIZE FLOW WHEN RCS PRESSURE IS < ""1500 PSIG, ABOVE THE RHR PUMP, 4.3 lF THE CONTAINMENT PRESSURE HAS NOT INCREASED 4,3 CONTINUE TO MONITOR CONTAIN-TO THE HI-HI SETPOINT, PROCEED TO STEP 4,5, MENT PRESSURE THROUGHOUT THIS INSTRUCTION, 4,4 IF CONTAINMENT PRESSURE HAS INCREASED TO THE HI-HI SETPOINT OF 23,5 PSIG, VERIFY THE FOLLOWING BY OBSERVING THE STATUS PANEL ON RP-4 AND/OR THE CONSOLE INDICATIONS, 4,4,l CONTAINMENT SPRAY HAS INITIATED:
l, CHECK THAT THE FOLLOWING PUMPS HAVE STARTED, lF A PUMP FAILS TO START, ATTEMPT TO START IT MANUALLY FROM THE CONTROL CONSOLE.
No. 11(21) CONTAINMENT SPRAY PUMP No. 12(22) CONTAINMENT SPRAY PUMP
- 2, CHECK
. THAT THE FOLLOWING
. VALVES HAVE OPENED, IF A VALVE FAlLS TO OPEN, ATTEMPT TO MANUALLY OPEN IT FROM THE CONTROL CONSOLE,
~~~ ~OO?lrn~fl~l~J~ IDJOO~W SALEM UNIT I/UNIT 2 REV, 9
I-4.6 11(2l)CS2 DISCHARGE VALVE 12(22)CS2 DISCHARGE VALVE 1(2)CS16 SPRAY ADD TANK DISCH VALVE 1(2)CS17 SPRAY ADD TANK DISCH VALVE 3, CHECK THE ADDITIVE TANK LEVEL IN-DICATOR AND OUTLET FLOW INDICATOR ON THE CONTROL CONSOLE TO ENSURE THE SODIUM HYDROXIDE (NAOH) SOLU-TION IS BEING INJECTED INTO THE CONTAINMENT SPRAY SYSTEM, IF THE LEVEL IS NOT DECREASING AND NO FLOW IS INDICATED DISPATCH AN OPERATOR TO VERIFY THE LEVEL LOCALLY AND TO INSURE THE FOLLOW-ING MECHANICAL VALVES. ARE OPEN, 11(21) EDUCTOR SUPPLY VALVE 11(2l)CS20 12(22) EDUCTOR SUPPLY VALVE 12(22)CS20 4.4.2 PHASE "B" ISOLATION HAS TAKEN PLACE
- 1. (HECK THAT THE FOLLOWING VALVES HAVE CLOSED BY OBSERVING THE STATUS PANEL ON RP-4 AND ACKNOWLEDGE ON THE APPRO-PRIATE CONTROL CONSOLE BEZEL, IF ANY VALVE HAS FAILED TO CLOSE) ATTEMPT TO CLOSE IT FROM THE CONTROL CONSOLE BEZEL, 1(2)CC117 RCP COOLING WATER INLET 1(2)CC118 RCP COOLING WATER INLET l(2)CC136 RCP BEARING OUTLET l(2)CC131 RcP THERM BAR DISCH FLow l(2)CC190 RCP THERMAL BAR DISCH 1(2)CC187 RCP BEARING OUTLET
- 2. IF ANY REACTOR COOLANT PUMPS ARE RUNNING) THEY MUST BE TRIPPED AT THIS TIME.
4.5 DETERMINE THE LOCATION OF THE RUPTURE AS 4,5 IF THE LEAK CANNOT BE IDEN-DESCRIBED BELOW, THE. FOLLOWING INDICATIONS TIFIED) RE-EVALUATE THE IN-AND ACTIONS ASSUME MAIN STEAM ISOLATION DICATIONS IAW EI 1-4.0J "SAFETY HAS OCCURRED, INJECTION INITIATION" WITH PARTICULAR EMPHASIS ON LOCA.
SALEM UNIT l/UNIT 2
1-4.6 4.5.1 DOWNSTREAM OF THE MAIN STEAM ISOLATION VALVES (THIS INCLUDES THE MAIN fEEDWATER HEADER UPSTREAM OF THE BF-221 f EEDWATER HEADER IsoLATION VALVES):
- 1. STEAM FLOW ON ALL LINES SHOULD INDICATE ZERO AND ALL STEAM GENERATOR PRESSURfS SHOULD BE STABILIZED AT APPROXIMATELY THE SAME PRESSURE,
- 2. PROCEED TO SUBSEQUENT ACTION STEP 4.6.
4.5.2 UPSTREAM OF THE MAIN STEAM ISOLATION VALVES (THIS INCLUDES THE MAIN fEED-WATER HEADER DOWNSTREAM ~F THE BF-22, FEEDWATER HEADER ISOLATION VALVES, AND THE SLOWDOWN LINES UPSTREAM OF THE GB-4 CONTAINMENT ISOLATION VALVES).,
- 1. ONE OR MORE STEAM GENERATOR(s) WILL
- 2.
HAVE A DECREASING PRESSURE, THIS IS THE FAULTY STEAM GENERATOR(S),
ISOLATE AUXILIARY fEEDWATER TO THE AFFECTED STEAM GENERATOR(S) BY CLOSING THE FLOW CONTROL VALVES, Afll AND
- 2. A BREAK IN THE PENETRATION AREA MAY CAUSE THE MS-lO's TO OPEN ON BOTH STEAM GENERATORS AF211 TO AFFECTED STEAM GENERATOR(S) I CAUSING A LOW PRESSURE IN BOTH,
- 3. IF THE RUPTURE IS INSIDE THE CONTAIN-
. MENT AN INCREASE IN CONTAINMENT TEMP-ERATURE AND PRESSURE WILL BE INDICATED, 4, IF THE RUPTURE IS OUTSIDE THE CONTAINMENT, THERE SHOULD BE NO CHANGE IN CONTAINMENT TEMPERATURE OR PRESSURE, 4.6 STOP BOTH RHR PUMPS AS FOLLOWS:
4.6.1 RESET THE SAFETY INJECTION SIGNAL BY 4.6.1 AUTOMATIC ACTUATION OF SAFETY DEPRESSING BOTH T~AIN "A: AND TRAIN "B" JNJECTlbN WILL NO LONGER BE SI RESET PUSHBUTTONS ON THE SAFEGUARDS AVAILABLE. ANY SUBSEQUENT ACTUATION BEZELS ON THE CONTROL CONSOLE . ACTUATION OF SAFETY INJECTION MUST BE ACCOMPLISHED MANUALLY BY INSERTING THE SAFEGUARDS KEY INTO EITHER TRAIN "A" OR f'rnr\nn WI TRAIN "B" OPERATE oN THE SAFE-
~~~ LI GUARDS ACTUATION BEZEL, SALEM UNIT l/UNIT 2 REV. 9
I-4.5 IF AT ANY TIME AFTER THE SAFETY INJECTION AND CONTAINMENT SPRAY SIGNALS ARE RESET, A BLACKOUT SIGNAL IS RECEIVED, THE VITAL BLISSES WOULD BE STRIPPED AND THE BLACKOUT LOADS WOULD BE SEQUENCED ON BY THE SEC.
THE RHR, SAFETY INJECTION, AND CONTAINMENT SPRAY PUMPS AND THE CONTAINMENT FAN (OIL UNITS ~
NQI. BE RESTARTED, THESE MUST BE MANUALLY RESTARTED ONCE THE LOADING SEQUENCE IS COMPLETE AS INDICATED BY THE LOl1DING COMPLETE LIGHTS ON THE lA, lB, 1CC2A, 2B, 2() DIESEL BEZELS ON THE CONTROL CONSOLE, D..Q. tiOl RESTART THE EQUIPMENT BY MANUALLY INITIATING SAFETY IN-JECTION OR CONTAINMENT SPRAY AS THIS MAY RESULT IN UNDESIR~BLE VALVE OPERATIONS WHICH MAY RESULT IN EQUIPMENT DAMAGE, THIS IS TO BE ACCOMPLISHED IN sue A MANNER AS TO PREVENT OVERLOADIN THE DIESELS, THE LOADS SHOULD BE APPLIED AT~ 10 SEC, INTERVALS, 4,5,2 RESET THE SAFEGUARDS LOADING SEQUENCE 4,5,2 THE STATUS LIGHTS ASSOCIATED BY DEPRESSING THE EMERGENCY LOADING WITH SEC LOADING ON RP-4 RESET PUSHBUTTONS ON THE CONTROL SHOULD GO OUT, CONSOLE FOR lA, lB, 1C(2A, 2B, 2()
DIESEL GENERATORS, 4.5.3 STOP BOTH RHR PUMPS CAUTION: DO NOT RESET THE PHASE I "A" ISOLATION, FEEDWATER ISOLATION, OR CONTAINMENT VENTILATION AT THIS TIME .
SALEM UNIT l/UNIT 2 REV. 9
1-4.6 4.7 IF THE PRODAC 250 COMPVTER IS AVAIALBLE, 4,7 THIS PROVIDES A READILY AVAIL-INITIATE CRT TEST No. 41, "CoRE TEMPERATURE/ ABLE DISPLAY OF SUBCOOLING, PRESSURE MONITOR PROGRAM", IF THE COMPUTER IS NOT AVAIL-ABLE OR THE INDICATIONS ARE CONSIDERED NOT RELIABLE DUE TO ADVERSE CO_NTAINMENT CONDITIONS, SUBCOOLING CAN BE DETERMINED FROM EITHER THE PRESSURE-TEM-PERATURE CURVE OR FROM THE STEAM TABLES, 4.8 WHEN THE REACTOR COOLANT SYSTEM HAS REACHED A STABLE CONDITION AS DESCRIBED BY ONE OF THE FOLLOWING SETS OF CONDITIONS, TERMINATE SAFETY INJECTION, A. ONE.OR MORE TH IS 2350°F AS READ 1. ATTEMPT TO MAINTAIN TEMPERATURE ON THE WIDE RANGE TEMPERATURE RE- <350°F I CORDERS ON RP-4, IF THE CRITERIA DESCRIBED IN fillli, "l" ARE USED FOR TERMINATION OF SAFETY-INJECTION AND THE REACTOR COOLANT TEMPERATURES INCREASE TO
>350°F, MAINTAIN THE SAFETY INJECTION PUMPS IN OPERATION UNTIL ALL CRITERIA FOR "2" BELOW ARE SATISIFIED, B, REACTOR COOLANT PRESSURE IS
>700 PSIG AND INCREASING, fillli, C, ACTUAL PRESSURIZER LEVEL IS ~20% c. CORRECT PRESSURIZER LEVEL FOR ON AT LEAST 2/3 HOT CALIBRATED REFERENCE LEG HEATUP JAW CHANNELS AND IS INCREASING, APPENDIX 2.
fillli, D, RCS TEMPERATURE IS MORE THAN 50°F D, IF TEMPERATURE REMAINS BELOW THE SUBCOOLED AS INDICATED BY EITHER TSAT - 50°F CURVE ON THE PRES-THE WIDE RANGE TH INDICATION ON SURE-TEMPERATURE CURVE, S0°F THE UNAFFECTED LOOPS OR THE INCORE SUBCOOLING IS ASSURED.
THERMOCOUPLES, ANIL E. EITHER
.. . TOTAL
.. AUXILIARY
.. . . ... . .....FEEDWATER
. E, CORRECT STEAM GENERATO~ LEVELS FLOW TO THE INTACT 4 .- - - STEAM
. . . . GENERATORS
. FOR REFERENCE LEG HEATUP JAW IS ~42xl0 LB/HR,, OR~ ACTUAL LEVEL APPENDIX 2.
IN AT LEAST ONE NON-FAULTED STEAM
- 2, A, GENERATOR IS ~5% AS INDICATED ON 2/3 NARROW RANGE INDICATORS.
ALL FOUR TH ARE >350°f A~ READ ON THE WIDE RANGE TEMPERATURE RECORDERS iin 'R\r.-._n ON RP-4J Atfil, ~@ffi{ ~OO~[]~IB§tl~ uu~li~
SALEM UNIT I/UNIT 2 REV. 9
--**1-4;5**
B. REACTOR COOLANT PRESSURE IS > 2000 PSIG AND IS STABLE OR INCREASING, Atfil, c, ACTUAL PRESSURIZER LEVEL IS ~20% c I CORRECT PRESSURIZER LEVEL FOR ON AT LEAST 2/3 Hor CALIBRATED REFERENCE LEG HEATUP JAW CHANNELS AND IS INCREASING, APPENDIX 2.
8till D. RCS TEMPERATURE IS MORE THAN 50°F D, IF TEMPERATURE REMAINS BELOW THE SUBCOOLED AS INDICATED BY EITHER TSAT - 50°F CURVE ON THE PRES-THE WIDE RANGE TH INDICATION ON SURE-TEMPERATURE CURVE, 50°F THE UNAFFECTED LOOPS OR THE INCORE SUBCOOLING IS ASSURED, THERMOCOUPLES, 8tfil, E. EITHER TOTAL AUXILIARY FEEDWATER E. CORRECT STEAM GENERATOR LEVELS FLOW TO THE INTACT STEAM GENERATORS FOR REFERENCE LEG HEATUP JAW 4
IS >42xl0 LB/HR,, OR, ACTUAL LEVEL APPENDIX 2.
IN AT LEAST ONE NON-F.AUL TED STEAM GENERATOR IS ~5% AS INDICATED ON 2/3 NARROW RANGE INDICATORS, 4.8.1 REFER TO EI l-4.2, "RECOVERY FROM 4.8.1 El J-4,2 HAS THE CRITERIA SAFETY INJECTION", FOR GUIDANCE IN FOR RE-INITIATION OF SAFETY RETURNING ADDITIONAL SUPPORT SYSTEMS INJECTION.
TO OPERATION AS REQUIRED TO ACCOMPLISH THE SUBSEQUENT COOLDOWN, 4.8.2 IF CONTAINMENT SPRAY ~ t:1QI BEEN ACTUATED, PROCEED TO SUBSEQUENT ACTION STEP 4.10 OF THIS INSTRUC-TION, 4.8.3 IF CONTAINMENT SPRAY 1::1AS. BEEN ACTUATED PROCEED TO STEP 4,9 OF THIS INSTRUCTION, 4.9 lF CONTAINMENT SPRAY HAS BEEN ACTUATED, PROCEED AS FOLLOWS WHEN CONTAINMENT PRESSURE DECREASES TO ~ 23,5 PSIG ON 3/4 CHANNSLS, 4.9.1 DEPRESS THE TRAIN "A" AND TRAIN "B" SPRAY ACT.RESET PUSHBUTTONS ON THE SAFEGUARD ACTUAT(ON BEZEL ON THE CONTROL CONSOLE,
- 4.9.2 CLOSELY MONITOR RWST LEVEL. As IT APPROACHES THE Low-Low LEVEL ALARM PREPARE TO CHANGE FROM COLD
~!~1~~J!~~~~~D T~s c~~L~~~: RECIR~(Q)~ mOOJ(Q)~mfill1r~ :oo IDXM~W SALEM UNIT l/UNIT 2 REv. 9
1-4.6
- 1. IF CONTAINMENT PRESSURE IS
<5,0 PSIG, REFER TO EI I-4.2 "RECOVERY FROM SAFETY INJECTION" FOR GUIDANCE IN RETURNING ADDI-TIONAL SUPPORT SYSTEMS TO OPERA-TION AS REQUIRED TO ACCOMPLISH THE SUBSEQUENT COOLDOWN, PROCEED TO SUBSEQUENT ACTION STEP 4.10 OF THIS INSTRUCTION,
- 2. IF CONTAINMENT PRESSURE IS >5,0 PSIG, PROCEED TO SECTION 5,0 OF THIS INSTRUCTION, "SUBSEQUENT ACTIONS PART II - COLD LEG RECIRCULATION",
N.QlE: IF A LOSS OF OFFSITE POWER HAS OCCURRED IN COINCIDENCE WITH THE STEAM LINE RUPTURE, ALIGN THE ELECTRICAL SYSTEM IN ACCORDANCE WITH APPENDIX l, PRIOR TO PROCEEDING TO PART JI OF THIS PROCEDURE, 4.10 RESTART THE FOLLOWING VENTILATION FANS, 4.10.1 NOZZLE SUPPORT FANS 4.10.2 REACTOR SHIELD VENT FANS 4.10.3 CONTROL ROD DRIVE FANS 4.11 WHEN CONDITIONS PERMIT, RETURN THE 4KV VITAL BLISSES TO NORMAL BY:
4.11.1 STOPPING THE EMERGENCY DIESEL GENERATORS IAW DI IV-16.3.1, "EMERGENCY POWER -
DIESEL OPERATION",
4.11.2 START OR STOP VITAL BUS LOADS AS REQUIRED, 4.12 COMMENCE TAKING THE PLANT TO COLD SHUTDOWN CONDITIONS BY COOLING DOWN AS FOLLOWS:
4.12.1 IF THE RUPTURE IS DOWNSTREAM OF THE MAIN
- STEAM LINE ISOLATION VALVES, COOLDOWN USING THE ATMOSPHERIC STEAM RELIEF VALVES, PERIODICALLY, REDUCE THE PRESSURE SETPOINT OF THE CONTROLLER FOR EACH MS10 VAL~lfn DEPRESSING THEIR PRESS SET PT DECRE[JS.!Y)lfil PUSHBUTTONS, SALEM UNIT l/UNIT 2 REV. 9
1-4.6 4.12.2 IF THE RUPTURE IS UPSTREAM OF THE MAIN STEAM LINE ISOLATION VALVES, COOL DOWN USING THE STEAM DUMP TO THE CONDENSER AS FOLLOWS:
- 1. OPEN THE BYPASS VALVES (MS18)
AROUND THE MAIN STEAM ISOLATION VALVES (MS167) ON THE UNAFFECTED STEAM GENERATORS,
- 2. WHEN PRESSURE EQUILIZES, OPEN THE MAIN STEAM ISOLATION VALVES.
- 3. PLACE THE STEAM DUMP IN THE MAIN STEAM PRESSURE CONTROL MODE AND PERIODICALLY REDUCE THE SETPOINT BY DEPRESSING THE SETPOINT DECREASE PUSHBUTTON.
4.12.3 As APPLICABLE, TAKE THE PLANT TO 4.12.3 DUE TO ABNORMAL PLANT CON-COLD SHUTDOWN CONDITIONS IAW 01 DITIONS SOME STEPS MAY NOT 1-3.6, "Hor STANDBY TO COLD BE APPROPRIATE AND SOME SHUTDOWN". EQUIPMENT NOT AVAILABLE, SALEM UNIT l/UNIT 2 REV. ~
I-4.6 5.0 SUBSEQUENT ACTIONS - PART II - COLD LEG RECIRCULATION CAUTION: THE CHANGEOVER FROM THE SAFETY INJECTION PHASE TO COLD LEG RECIRCULATION MUST BE DONE QUICKLY, IF ANY VLAVES FAIL TO RE-SPOND OR COMPLETE THE REQUIRED MOVEMENT, CONTINUE WITH THE SEQUENCE AND INITIATE ANY CORRECTIVE ACTIONS WHEN THE CHANGE-OVER IS COMPLETED, I
- 5.1 VERIFY THAT THE FOLLOWING NORMALLY CLOSED 5.1 THE RH-29's WILL BE CLOSED I
I VALVES ARE CLOSED: ONLY IF RHR FLOW IS >1000 GPM PER PUMP, 11(2l)SJ40 11~21) DISCH VALVE TO Hor LEG 12(22)SJ40 12<22) DISCH VALVE TO Hor LEG 11(2l)SJ113 SI CHG PUMPS X-DVER VALVE 12(22)SJ113 SI CHG PUMPS X-DVER VALVE 11<2l)SJ45 RECIRC !SOL VALVE TO SI PUMP 11(2l)CS36 FROM 11(21) RHX VALVE 12(22)CS36 FROM 12(22) RHX VALVE 1(2)RH2 RHR COMMON SUCTION VALVE
- 1(2)RH1 RHR COMMON SUCTION VALVE 11(2l)SJ44 SIS SUMP VALVE 12(22)SJ44 SIS SUMP VALVE 1(2)RH20 RHX BYPASS VALVE 1(2)RH26 Hor LEG IsoLATION VALVE 11(2l)RH29 11(21) RHR PUMP BYPASS 12(22)RH29 12(22) RHR PUMP BYPASS 12(22)SJ45 SUCTION FROM RHX (ro CHARGING PuMPs) 5,2 VERIFY THAT THERE IS AN ADEQUATE WATER LEVEL IN THE CONTAINMENT SUMP AS INDICATED BY AN ENERGIZED AVAILABLE NPSH LIGHT ON THE CONTROL CONSOLE.
5.3 OPEN 11(2l)CC16 AND 12(22)CC16 "RHR HEAT EXCHANGER OUTLET VALVES, 5.4 WHEN THE RWST Low-Low LEVEL ALARM ACTUATES 5.4 ANNUNCIATOR D-44 STOP--THE. FOLLOW I N.G ~UMl:>S IE THEY _AR!: RUN-: __
NING:
No. 11 &12(21 &22) RHR PuMP No, 11 & 12(21 & 22) CONTAINMENT SPRAY PUMP No. 11 & 12(21 & 22) SAFETY INJECTION PUMPS
No.-11-,-12-&-13-C2L--22-&-23LCHARGJNG__EuMe s SALEM UNIT l/UNIT 2 -12 REV, 9
I-4.6 5.4 IF CONTAINMENT PRESSURE HAS NOT DECREASED TO BELOW 23,5 PSIGJ THE CONTAINMENT SPRAY PUMPS CANNOT BE STOPPED FROM THE CONTROL CON-CONSOLE, To STOP THE PUMPS) IT WILL BE NECESSARY TO TRI? THE BREAKERS LOCALLY ON THE lA AND lC (2A AND 2C) 4KV VITAL BussES BY TURNING OFF THE 125 VDC CONTROL POWER AND DEPRESSING THE MANUAL TRIP BUTTON INSIDE THE BREAKER CABINET, fiQIE: ALIGNING THE RHR PUMPS AS DESCRIBED IN THE FOLLOWING STEPS WILL PRIVIDE FLOW TO.THE CHARGING AND SAFETY IN-JECTION PUMPS AND THE CONTAINMENT SPRAY HEADER. IF ONE RHR PUMP IS NOT AVAILABLE TO PROVIDE FLOW THE OTHER PUMP WILL SUPPLY THE CHARGING AND SAFETY INJECTION PUMPS AND THE CONTAINMENT SPRAY HEADER WITH NO ADDITIONAL VALVE OPERATIONS, 5.5 CLOSE 11(21)RH4 RHR PuMP SUCTION VALVE) IF No.
11(21) RHR PUMP IS AVAILABLE, 5.6 CLOSE 12(22)RH4 RHR PUMP SucTJON VALVE) IF No. 5.6 11(21)RH4 MUST BE CLOSED IN 12(22) RHR PUMP IS AVAILABLE. ORDER TO OPEN 11(2l)SJ44, 12(22)RH4 MUST BE CLOSED IN ORDER TO OPEN 12(22)SJ44, 5.7 CLOSE THE BREAKERS FOR 1(2)SJ30 &69 AND CLOSE 5.7 1(2)( WEST 230V VITAL VALVE THE VALVES, CONTROL CENTER, THIS CAN BE COMPLETED IN CONJUNCTION WITH THE REMAINING STEPS, 5.8 REMOVE THE LOCKOUT ON RP-4 AND OPEN 11(21)SJ44 SIS SUMP VALVE) IF No. 11<21) RHR PuMP 1s AVAIL-ABLE.
5 9 -REM-OVE- TH-E LDC KOUT ON - RP:..-4 ANilOPEN 12 (22) S-J44- -
I SIS SUMP VALVE) IF No. 12C22) RHR PUMP 1s AVAIL-ABLE.
5.10 CLOSE 11(2l)RH19 11(21) RHX CROSS DISCH VALVE.
5.11 CLOSE 12(22)RH19 12(22) RHX CROSS DISCH VALVE.
5.12 START No. 11(21) RHR PUMP, ~(O)\ffi ~\NIJ[l)~\MU~lrU~:IB (ffi\Nl\L'W SALEM UNIT 1/UNJT 2 REV, 9
I-4.6 5.13 START No. 12(22) RHR PUMP.
5.14 REMOVE THE LOCKOUT ON RP-4 AND CLOSE 1(2)SJ67) 5.14 THERE ARE REDUNDANT SWITCHES 12(22) MINI FLOW ISOLATION VALVE) AND 1(2)SJ68 ON 1(2)RP4 TO OPERATE 1(2) 11(21) MINI FLOW ISOLATION VALVE. SJ67 AND 68. EITHER THE PUSH-BUTTON ON THE CONTROL CONSOLE OR THESE SWITCHES WILL ALLOW FULL OPERATION OF THE VALVES ONCE THE LOCKOUT IS REMOVED, 5.15 OPEN 12(22)SJ45 SucTION FROM RHX) IF No.
12(22) RHR PUMP IS AVAILABLE.
5.16 OPEN 11(2l)SJ45 REClRC ISOLATION VALVE TO 5.16 To OPEN 11C2l)SJ45) THE SI PuMP, IF No. 11(21) RHR PuMP IS AVAILABLE. FOLLOWING VALVES MUST BE POSITIONED AS LISTED BELOW, 1(2)RH1 OR 1(2)RH2 - CLOSED 1(2)SJ67 OR 1(2)SJ68 - CLOSED 11(2l)SJ44 - OPEN To OPEN 12(22)SJ45) THE FOL-LOWING VALVES MUST BE POSITIONED
-- AS LISTED BELOW:
1(2)RH1 OR 1(2)RH2 - CLOSED 1(2)SJ67 OR 1(2)SJ68 - CLOSED 12(22)SJ44 - OPEN 5.17 OPEN 11(2l)SJ113 SI CHARGE PUMPS X-OVER VALVE.
5.18 OPEN 12(22)SJ113 SI CHARGE PUMPS X-OVER VALVE I 5.19 START No. 11 &12(21 &22) SAFETY INJECTION PUMPS.
5.20 CLOSE 1(2)SJ1 RWST TO CHARGE PUMP.
5.21 CLOSE 1(2)SJ2 RWST TO CHARGE PUMP.
5.22 *START No. 11 &12(21 &22) CHARGING PUMPS.
5.23 VERIFY THAT No. 11(21) SI PuMP 1s OPERATING PROPERLY BY OBSERVING No, 11(21) SI PUMP DISCHARGE PRESSURE INDICATOR AND No. 11(21)
SI PUMP DISCHARGE FLOW INDICATOR, REV. 9 SALEM UNIT l/UNIT 2
I-4.6 5.24 VERIFY THAT No. 12(22) SI PUMP Is OPERATING PROPERLY BY OBSERVING No, 12(22) SI PUMP DISCHARGE PRESSURE INDICATOR AND No, 12(22)
SI PUMP DISCHARGE FLOW INDICATOR, 5.25 VERIFY THAT No, 11(21) CENTRIFUGAL CHARGING PUMP IS OPERATING PROPERLY BY OBSERVING THE CHARGING PUMP DISCHARGE FLOW INDICATOR AND BORON INJECTION TANK DISCHARGE PRESSURE INDICATOR, 5.26 VERIFY THAT No. 12(22) CENTRIFUGAL CHARGING PUMP IS OPERATING PROPERLY BY OBSERVING THE CHARGING PUMP DISCHARGE FLOW INDICATOR AND BORON INJECTION TANK DISCHARGE PRESSURE INDICATOR, 5.27 REMOVE THE LOCKOUT AND CLOSE 11 & 12(21 &22)
SJ49 RHR PUMP DISCH IsoL VALVES.
5.28 OPEN THE FOLLOWING CONTAINMENT SPRAY VALVE: 5.28 IF 12(22) RHR PUMP IS UNAVAIL-ABLE, SPRAY MUST COME FROM 12C22)CS36 CllC2l)CS36 IF NO. 12(22) RHR PUMP 11(21) RHR PUMP I IS NOT AVAILABLE),
- 5,29 CLOSE THE FOLLOWING CONTAINMENT SPRAY VALVES:
11C2l)CS2 12C22)CS2 5.29.1 CONTINUE SPRAY OPERATION UNTIL 5.29.1 THE EMERGENCY CORE COOLING CONTAINMENT PRESSURE IS < 5,0 PSJG, SYSTEM IS NOW ALIGNED FOR WHEN CONTAINMENT PRESSURE IS <5,0 COLD LEG RECIRCULATION AS PSIG PROCEED TO EI I-4,2, "TERMINA- FOLLOWS:
f!ON OF SAFETY INJECTION".
RHR PuMP No, 11C21) 1s suPPLYINc WATER FROM THE CONTAINMENT SUMP TO THE SUCTION OF THE SAFETY INJECTION PUMPS THROUGH VALVE 11(2l)SJ45, RHR PuMP No. 12(22) 1s SUPPLYING WATER FROM THE CON-TAINMENT SUMP DIRECTLY TO THE CONTAINMENT SPRAY HEADER AND TO THE SUCTION OF THE CHARGING PUMPS THROUGH VALVE 12(22)SJ45.
PREPARED BY_*- - - - - - - - - - - - - -
MANAGER - SALEM GENERATING STATION REVIEWED BY
~rm~ ~OOFrffiLPdl! i~ ~~ mJ~~W
~
SORC MEET! NG No, - - - DATE _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 RJ:v. 9
I-4.6 APPENDIX 1 DISCUSSION lF A LOSS OF OFFSITE POWER HAS OCCURED IN COINCIDENCE WITH THE STEAM LINE RUPTURE, THE DIESEL GENERATORS WILL BE SUPPLYING POWER TO THE VITAL BLISSES. DURING THE RECIRCULATION PHASE, IT IS NECESSARY TO RUN THE COMPONENT COOLING PUMPS. IN RODER TO ACCOMODATE THIS ADDITIONAL LOAD, OTHER EQUIPMENT MUST BE STOPPED BEFORE THE COMPONENT COOLING PUMPS ARE STARTED TO PREVENT OVERLOADING THE DIESEL GENERATORS. .:,..
AFTER THE SAFETY INJECTION AND SEC ARE RESET, PROCEED WITH THE APPROPRIATE SECTION, I - ALL DIESEL GENERATORS OPERATING 1.0 STOP THE FOLLOWING EQUIPMENT:
tiQIE Do NOT STOP BOTH No~ 11(21) AND 12(22) CONTAINMENT SPRAY PUMPS UNTIL THE RWST Low-Low LEVEL ALARM ACTUATES.
DIESEL/GENERATORS) 1.1 EQUIPMENT ON 1AC2A) VITAL Bus CPowERED BY 1AC2A)
A, No. 11<21) CONTAINMENT SPRAY PUMP B, No. 11 (21) AUXILIARY BUILDING EXHAUST FAN
- c. No. 11 (21) SWITCHGEAR RooM SUPPLY FAN D. No. 11(21) CHILLER 1.2 EQUIPMENT oN 1BC2B) VITAL Bus (POWERED BY 1B(2B) DIESEL/GENERATOR)
A, No. 12(22) CONTAINMENT FAN COIL UNIT B, No. 14(24) CONTAINMENT FAN Co1 L UNIT 1.3 EQUIPMENT ON 1CC2C) VITAL Bus (POWERED BY 1CC2C) DIESEL GENERATOR)
A. No. 12(22) CONTAINMENT SPRAY PUMP B. No. 11(21) AUXILIARY BUILDING SUPPLY FAN 2.0 START THE FOLLOWING EQUIPMENT:
CAUTION WHEN EN:tERI_NG COLD LEG RECIRC, START ONLY ONE COMPONENT COOLING PUMP. ENSURE THE COMPONENT COOLING PUMP TO BE STARTED IS ENERGIZED FROM THE SAME VITAL Bus AS WAS THE CONTAINMENT SPRAY PUMP, SECURED FROM IN THE ABOVE STEP .
- 2.1 EQUIPMENT oN 1AC2A) VITAL Bus (POWERED BY 1AC2A) DIESEL/GENERATOR)
A. No. 11 COMPONENT CooLING PuMP SALEM UNIT l/UNIT 2
--"~--1--y-,-0------
2.2 EQUIPMENT oN 1CC2C) VITAL Bus (POWERED BY 1CC2C) DIESEL/GENERATOR)
A. No. 13(23) COMPONENT CooLING PuMP NQIE IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING Bu1LDING, START No. 11 &12<21 &22) FHB EXHAUST FANS.
3.0 OPEN 1H2DSW122 AND 12C22)SW122 TO SUPPLY SERVICE WATER TO COMPONENT COOLING.
II - FAILURE OF lA C2A> DIESEL GENERATOR 1.0 STOP THE FOLLOWING EQUIPMENT:
1.1 EQUIPMENT ON 1BC2B) VITAL Bus (POWERED BY 1BC2B) DIESEL/GENERATOR)
A. No. 11(21) CHARGING PUMP
- B. No. 12(22) OR No. 14(24) CONTAINMENT FAN CoIL UNIT
- c. No. 12<22) AUXILIARY BUILDING SUPPLY FAN 1.2 EQUIPMENT ON 1C(2C) VITAL Bus (POWERED BY 1CC2C) DIESEL/GENERATOR)
-- A. No. 12C22) CONTAINMENT SPRAY PuMP WHEN RWST Low-Low LEVEL ALARM ACTUATES.
2.0 START No. 12(22) COMPONENT COOLING PUMP AND OPEN 12(22)SW122 TO PROVIDE SERVICE WATER TO COMPONENT COOLING, NfilE IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING BUILDING, START No. 12(22) FHB EXHAUST FAN, 3.0 THE FOLLOWING SHOULD BE THE ALIGNMENT FOR COLD LEG RECIRCULATION, 3.1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
A. No. 12(22) RHR PuMP B. No. 12(22) CHARGING PUMP
- c. No. 12(22) SAFETY INJECTION PuMP 3.2 ~_LOSE VALVES 12(22lRH19 AND 12(22)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 12(22) CHARGING PUMP AND No. 12(22) SAFETY INJECTION PUMP SUCTIONS AND TO THE CONTAINMENT SPRAY HEADER THROUGH 12(22)CS36.
3.3 THE COLD LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
- A. No. 12(22) RHR PUMP TAKING sucTION oN THE CoNTAINMENT SUMP AND DISCHARGING TO THE sucnoNs OF No. 12(22) CHARGING PUMP AND No *. 12(22) SAFETY INJECTION PUMP THROUGH 12(22)SJ45, 12(22)SJ113, 11<2l)SJ33 AND 12<22)SJ33, AND TO THE CONTAINMENT SPRAY HEADER THRoiJGH 12<22lCM ~oo;lOl~lllT~=~J rm:~~\f SALEM UNIT l/UNIT 2 REV. g
I-4.6 B. No. 12(22) CHARGING PUMP DISCHARGE THROUGH THE BORON INJECTION TANK TO ALL FOUR COLD LEGS I
- c. No. 12(22) SAFETY INJECTION PUMP DISCHARGE THROUGH 12(22)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS, III - FAILURE OF 1BC2B) DIESEL GENERATORS 1.0 STOP THE FOLLOWING EQUIPMENT:
1.1 EQUIPMENT ON 1A(2A) VITAL Bus (POWERED BY 1A(2A) DIESEL GENERATOR)
A, No. 11(21) CONTAINMENT SPRAY PUMP 1.2 EQUIPMENT ON 1C<2C) VITAL Bus (POWERED BY 1C(2C) DIESEL GENERATOR)
A, No. 12(22) CONTAINMENT SPRAY PUMP B. No. 12(22) SAFETY INJECTION PuMP 2.0 START No. 13(23) COMPONENT COOLING PUMP AND OPEN 11(2l)SW122 TO PROVIDE SERVICE WATER TO COMPONENT COOLING, tillIE IF IRRADIATED FUEL IS STORED IN THE FUEL HANDLING Bu1LDINGJ START No. 12(22) FHB EXHAUST FAN.
3.0 THE FOLLOWING SHOULD BE THE ALIGNMENT FOR COLD LEG RECIRCULATION:
3.1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
A. No. 11(21) RHR PuMP B, No. 12(22) CHARGING PUMP
- c. No. 11(21) SAFETY INJECTION PuMP 3.2 CLOSE VALVES 11(21)RH19 .AND 11(2l)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 12(22) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP SUCTIONS AND TO THE CONTAINMENT SPRAY HEADER THROUGH 11(2l)CS36, 3.3 THE COLD LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
A, No, 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO THE sucTIONS OF No. 12(22) CHARGING PUMP AND No. 11(21) SAFETY INJECTION PUMP THROUGH ~1(21)SJ45J _11(21)SJ113J 11(21)SJ33 AND 12(22)SJ33J AND TO .THE CONTAIN-MENT SPRAY HEADER THROUGH 11(2l)CS36.
No. 12(22) CHARGING PUMP DISCHARGING THROUGH THE BoRON INJECTION TANK TO ALL fOUR Colr> LEGS.
- c. No. 11(21) SAFETY INJECTION PUMP DISCHARGING THROUGH 11(2l)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS, SALEM UNIT l/UNIT 2 REV. 9
I-4.6 IV - FAILURE OF 1CC2C2 DIESEL GENERATOR 1.0 STOP THE FOLLOWING EQUIPMENT:
1.1 EQUIPMENT ON 1AC2A) VITAL Bus (POWERED BY 1AC2A2 DIESEL/GENERATOR)
A. No. 11(21) CONTAINMENT SPRAY PUMP WHEN RWST Low-Low LEVEL ALARM ACTUATES B. No, 11(21) AUXILIARY fEEDWATER PUMP 1.2 EQUIPMENT ON 1BC2B) VITAL Bus (POWERED BY 1BC2B2 DIESEL/GENERATOR)
A. No. 12(22) RHR PUMP 2.0 START No, 12(22) COMPONENT COOLING PUMP AND OPEN 11(2l)SW122 TO PROVIDE S~RVICE WATER TO COMPONENT COOLING, .*
N.QIE IF IRRADIATED FUEL. IS STORED IN THE FUEL HANDLING BUILDING, START No. 11AND12(21 & 22) FHB EXHAUST FANS.
3,0 THE FOLLOWING SHOULD BE THE ALIGNMENT FOR COLD LEG RECIRCULATION:
- 3,1 THE FOLLOWING PUMPS SHOULD BE RUNNING:
A.
B.
c.
No. 11(21) RHR PUMP No. 11(21) CHARGING PUMP No. 11(21) SAFETY INJECTION PuMP 3.2 CLOSE VALVES 11(2l)RH19 AND 11C2l)SJ49 TO PREVENT FLOW TO THE COLD LEGS AND TO INSURE ADEQUATE FLOW TO No. 11(21) CHARGING PUMP AND No, 12(22) SAFETY INJECTION PUMP SUCTIONS AND TO THE CONTAINMENT SPRAY HEADER THROUGH 11(2l)CS36.
3,3 THE (OLD LEG RECIRCULATION FLOW PATH WOULD BE AS FOLLOWS:
A, No, 11(21) RHR PUMP TAKING SUCTION ON THE CONTAINMENT SUMP AND DISCHARGING TO SUCTIONS OF No. 11<21) CHA~GING PUMP AND No. 11(21) SAFETY INJECTION PuMP ~HROUGH 11(2l)SJ45, 11(2l)SJ113, 12(22)SJ113, 11(2l)SJ33, AND 12(22)SJ33, AND TO THE CONTAINMENT SPRAY HEADER THROUGH 11(2l)CS36.
B, No. 11(21) {HARGING PUMP DISCHARGING THROUGH THE BORON INJECTION TANK TO ALL FOUR COLD LEGS, C, No. 12(22) SAFETY INJECTION PUMP DISCHARGING THROUGH 12(22)SJ134 AND 1(2)SJ135 TO ALL FOUR COLD LEGS.
4.0 TRANSFER THE SECURITY SYSTEM TO THE EMERGENCY POWER SUPPLY ON lA 230V VITAL Bus.
SALEM UNIT l/UNIT 2
I-4.6 APPENDIX 2 DETERMINATION OF ACTUAL PRESSURIZER AND STEAM GENERATOR LEVELS To DETERMINE ACTUAL PRESSURIZER OR STEAM GENERATOR LEVELS) UTILIZE THE ATTACHED TABLES AS DESCRIBED BELOW:
TABLES 1-5 ARE TO BE USED FOR THE STEAM GENERATORS TABLES 6-11 ARE TO BE USED FOR THE PRESSURIZER
- 1. OBTAIN THE AVERAGE CONTAINMENT TEMPERATURE FROM COMPUTER POINT Ul304.
- 2. REFER TO THE APPROPRIATE TABLE FOR PRESSURE IN THE STEAM GENERATOR AND PRESSURIZER,
- 3. LOCATE THE DESIRED ACTUAL LEVEL UNDER THE COLUMN FOR THE AVERAGE CONTAINMENT TEMPERATURE
- 4. FROM THE COLUMN. HEADED "INDICATED LEVEL (%)" DETERMINE THE INDICATED LEVEL WHICH SHOULD BE MAINTAINED TO ENSURE THE ACTUAL LEVEL IS MAINTAINED AT OR ABOVE THE DESIRED VALUE, tiOI£ IF THE COMPUTER IS UNAVAILABLE) MAINTAIN INDICATED LEVEL 35% ABOVE THE DESIRED ACTUAL LEVEL.
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I-4.7 EMERGENCY INSTRUCTION 1-4.7 STEAM GENERATOR TUBE FAILURE 1.0 PURPOSE l,l THIS INSTRUCTION COVERS THE SYMPTOMS, AUTOMATIC ACTIONS AND MANUAL ACTIONS FOR A STEAM GENERATOR TUBE LEAK AND A STEAM GENERATOR TUBE RUPTURE, EITHER OF THESE CONDITIONS RESULT IN LEAKAGE OF REACTOR.COOLANT INTO THE SECONDARY SYSTEM, 1.2 OPERATOR ACTION IS REQUIRED, IN ACCORDANCE WITH THE ACCIDENT ANALYSIS IN THE FSAR, IN ORDER TO IDENTIFY AND ISOLATE THE FAULTED STEAM GENERATOR ON A TUBE RUPTURE, REACTOR COOLANT SYSTEM PRESSURE MUST BE REDUCED TO LESS THAN 1000 PSI WITHIN 30 MINUTE~ IN ORDER TO PREVENT LIFTING OF THE STEAM GENERATOR SAFETIES AND POWER OPERATED REUIEF VA~VE ON THE AFFECTE~ STEAM GENERATOR, THIS WILL MINIMIZE THE RADIOACTIVE RELEASE TO THE ATMOSPHERE AND.ENSURE COMPLIANCE WITH THE LIMITS SPECIFIED IN 10CFR100.
1.3 THIS INSTRUCTION IS DIVIDED INTO TWO PARTS:
PART I - STEAM GENERATOR TUBE LEAK, WHICH DEALS WITH LEhKS SMALL ENOUGH WHERE SAFETY INJECTION IS NOT ACTUATED, PART II - STEAM GENERATOR TUBE RUPTURE, WHICH DEALS WITH LEAKS OF A MAGNITUDE WHERE SAFETY INJECTION IS INITIATED.
PART I STEAM GENERATOR TUBE LEAK 2.0 INITIAL CONDITIONS 2.1 ANY OF THE FOLLOWING HIGH RADIATION ALARMS, 11(21) STEAM GENERATOR SLOWDOWN 1(2)Rl9A 12(22) STEAM GENERATOR BLOWDOWN 1(2)Rl9B 13(23) STEAM GENERATOR BLOWDOWN 1(2)Rl9C 14(24) STEAM GENERATOR BLOWDOWN 1(2)Rl9D.
CONDENSER AIR EJECTOR 1(2)Rl5 SG SLOWDOWN FILTER DISCHARGE 1(2)R35 CONDENSATE PoLISHI.NG FILTER 1(2)R40 2.2 CHARGING PUMP SPEED AND CHARGING FLOW INCREASE TO MAINTAIN PRESSURIZER LEVEL NORMAL, 3.0 IMMEDIATE ACTIONS 3,1 AUTOMATIC 3.1.1 CHARGING FLOW INCREASING 3.1.2 AUTOMATIC MAKEUP TO VCT SALEM UNIT l/UNIT 2 . REV. 6
I-4.7 3.1.3 WARNING ALARM ON RMS CHANNEL Rl9 ISOLATES 12(22) S/G BD TANK VALVES 11, 12, 13 AND 14 (21, 22, 23 AND 24)GB10 AND 1(2)GB50.
3.1.4 HIGH ALARM ON THE STEAM GENERATOR BLOWDOWN RADIATION MONITORS (Rl9) WILL ISOLATE THE FOLLOWING:
A) UNIT 1 - ALARM ON ANY CHANNEL, 1Rl9A-D, WILL TRIP CLOSED 11, 12, 13 AND 14GB4 STEAM GENERATOR BLOWDOWN lsOLAT!ON VALVES, B) UNIT 2* - 2Rl9A WILL TRIP CLOSED 21GB4, STEAM GE~ERATOR BLOWDOWN ISOLATION VALVE 2Rl9B WILL TRIP CLOSED 22GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE, 2Rl9C WILL TRIP CLOSED 23GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE 2Rl9D WILL TRIP CLOSED 24GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE, 3.1.5 HIGH ALARM ON THE BLOWDOWN FILTER RADIATION MONITOR, 1(2)R35, SHIFTS 3-WAY VALVES 1(2)GB74 AND 1(2)GB112 TO DISCHARGE TO THE WASTE MONITOR HOLDUP TANKS, 3.2 MANUAL
- 3.2.1 3.2.2 VERIFY AUTOMATIC ACTIONS, INITIATE ANY THAT DID NOT OCCUR, ON A HIGH RADIATION ALARM ON THE CONDENSATE POLISHING FILTER, 1(2)R40, BYPASS THE CONDENSATE POLISHING SYSTEM.
OPEN ll-13(21~23)CN108, CONDENSATE POLISHING BYPASS VALVES CLOSE 1(2)CN109, CONDENSATE POLISHING INLET VALVE 3.2.3 ON A HIGH RADIATION ALARM ON 1Rl9A-D:
OPEN 1WD900, BLOWDOWN SAMPLE DISCHARGE TO WASTE HEADER CLOSE 1WD901, BLOWDOWN SAMPLE DISCHARGE TO NON-RADIOACTIVE WASTE.
3.2.4 NOTIFY PERFORMANCE DEPARTMENT OF POSSIBLE STEAM GENERATOR TUBE LEAK.
4.0 SUBSEQUENT ACTIONS COMMENTS 4.1 DETERMINE PRIMARY TO SECONDARY LEAK RATE, 4.1 TECH SPEC 3,4,6.2.
4.2 DETERMINE WHICH STEAM GENERATOR IS LEAKING 4.2 STEAM GENERATOR SAMPLE LINES BY SAMPLE ANALYSIS AND OBSERVING READINGS AND RADIATION MONITORS ARE NOT ON. STEAM GENERATOR SAMPLE. RADIATION MONITORS, ISOLATED BY THE HIGH RADIATION DETERMINE SECONDARY ACTIVITY, SIGNAL, TECH SPEC 3.7.1.4 4.3 MONITOR CHARGING PUMP FLOW FOR ANY INCREASE AND THE STEAM GENERATOR SAMPLE RADIATION MONITORS FOR INCREASED READINGS WHICH INDICATE HIGHER LEAKAGE, REV' 6 SALEM UNIT l/UNIT 2
1-4.7 4.4 SHUTDOWN THE PLANT WHEN TECHNICAL SPECIFICATION 4.4 THE FAULTY STEAM GENERATOR LEAKAGE LIMITS OR SECONDARY ACTIVITY LIMITS ARE SHOULD NOT BE STEAMED DURING REACHED IAW 01 I-3.4, "POWER OPERATION", I-3.5, SUBSEQUENT COOLDOWN, COOLDOWN "MINIMUM LOAD TO Hor STANDBY", AND I-3.6, "Hor SHOULD BE ACCOMPLISHED BY USING STANDBY TO COLD SHUTDOWN", THE ATMOSPHERIC STEAM RELEIF VALVES (MS-10) FOR THE UNAFFECTED STEAM GENERATORS, REV. 6 SALEM UNIT l/UNIT 2
PART II l-4.7 II. STEAM GENERATOR TUBE RUPTURE*
2.0 INITIAL CONDITIONS 2.1 SAFETY INJECTION HAS BEEN INITIATED AND IT HAS BEEN DETERMINED BY USE OF SECTION 5,0, "IDENTIFICATION OF FoLLOWUP AcTioNs" OF EI 1-4.0, "SAFETY INJECTION INITIATION", THAT A STEAM GENERATOR TUBE RUPTURE HAS OCCURRED, 3.0 IMMEDIATE ACTIONS 3,1 AUTOMATIC 3.1.1 WARNING ALARM ON RMS CHANNEL Rl9 ISOLATES 12(22) S/G BD TANK VALVES 11, 12, 13 AND 14(21, 22, 23 AND 24)GB10 AND 1(2)GB50, .
3.1.2 HIGH AL~RM ON THE STEAM GENERATOR BLOWDOWN RADIATION MONITORS (Rl9) WILL ISOLATE THE FOLLOWING:
A) UNIT 1 - ALARM ON ANY CHANNEL, 1Rl9A-D, WILL TRIP CLOSED 11, 12, 13 AND 14GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES,
..._ B) UNIT 2 - 2R19A WILL TRIP CLOSED 21GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE 2Rl9B WILL TRIP CLOSED*22GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE 2Rl9C WILL TRIP CLOSED 23GB4, STEAM GENERATO~ BLOWDOWN ISOLATION VALVE 2Rl9D WILL TRIP CLOSED 23GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVE 3.1.3 HIGH ALARM ON THE BLOWDOWN FILTER RADIATION MONITOR 1(2)R35, SHIFTS 3-WAY VALVES 1(2)BG74 AND 1C2)BF112 TO DISCHARGE TO THE WASTE MONITOR HOLDUP TANKS I 3.2 MANUAL 3.2.l VERIFY THAT ALL IMMEDIATE AND SUBSEQUENT ACTIONS DESCRIBED IN El 1-4,0, "SAFETY INJECTION INITIATION"~ HAVE BEEN PERFORMED, COMPLETE ANY ACTIONS WHICH HAVE NOT BEEN PREVIOUSLY COMPL£TED, 3.2.2 IF A WARNING ALARM HAS BEEN REACHED ON ANY OF THE R-19 CHANNELS, VERIFY THE FOLLOWING ARE CLOSED:
ll-14(21-24)GB10, No, 12(22) BLOWDOWN TANK INLET VALVES H2)GB50, No. 12(22) BLOWDOWN TANK INLET CoNTROL VALVE 3.2.3 IF A HIGH ALARM HAS BEEN REACHED ON AN R-19 CHANNEL, VERIFY THE FOLLOWING ARE CLOSED:
UNIT 1 14GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES UNIT 2 - 2R19A - TRIPS 21GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES 2R19B - TRIPS 22GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES 2Rl9C - TRIPS 23GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES 2R19D - TRIPS 24GB4, STEAM GENERATOR BLOWDOWN ISOLATION VALVES SALEM UNIT l/UNIT 2
1-4.7 3.2.4 ON A HIGH RADIATION ALARM ON THE CONDENSATE POLISHING FILTER, 1(2)R40, BYPASS THE CONDENSATE POLISHING SYSTEM, OPEN OPEN ll-13(21-23)CN108, CONDENSATE POLISHING BYPASS VALVES CLOSE 1(2)CN109, CONDENSATE POLISHING INLET VALVE 3.2.5 ON A HIGH RADIATION ALARM ON 1Rl9A-D:
OPEN 1WD900, BLOWDOWN SAMPLE DISCHARGE TO WASTE HEADER CLOSE 1WD90L BLOWDOWN SAMPLE DISCHARGE TO NoN-RAD I OACT I VE WASTE, 4.0 SUBSEQUENT ACTIONS COMMENTS 4,1 IF NOT ALREADY IDENTIFIED, IDENTIFY THE FAULTED STEAM GENERATOR BY:
4.1.1 lsOLAT~*AUXILIARY FEEDWATER FLOW TO 4.1.1 CLOSE THE AFll &2l's, THE ALL STEAM GENERATORS AND OBSERVE THE Aux. FEED PUMPS WILL AUTO-LEVELS AS INDICATED ON THE NARROW RANGE MATICALLY RESTART IF LEVEL LEVEL INDICATORS, THE STEAM GENERATOR IS <J.8%,
THAT HAS AN INCREASING LEVEL IS THE FAULTY UNIT, 4.1.2 COMPARE RADIATION READINGS ON THE 4.1.2 SAMPLE LINES AND RADIATION STEAM GENERATOR BLOWDOWN SAMPLE MONITORS HAVE BEEN ISOLATED RADIATION MONITORS, THE ONE WITH BY PHASE nAn ISOLATION AND THE HIGHER READING IS THE FAULTY MAY NOT SHOW ANY INCREASE UNIT I IN RADIATION LEVELS, 4,2 RE-ESTABLISH AUXILIARY FEEDWATER FLOW TO 4,2 Do NOT FEED THE FAULTED STEAM THE UNAFFECTED STEAM GENERATORS AND CON- GENERATOR, TROL THE LEVEL AT ~33% IN THE NARROW RANGE, 4.3 CLOSE THE STEAM GENERATOR STOP VALVE, MS167, 4.3 THE MAIN STEAM ISOLATION PUSH-BYPASS VALVE, MS-18, AND DRAIN VALVE, MS7, BUTTON(s) ON THE SAFEGUARDS ON THE AFFECTED STEAM GENERATOR, BEZEL(s) MAY BE USED, IF ANY OF THESE VALVES ON THE FAULTED ISOLATION OF NON-FAULTED STEAM STEAM GENERATOR WILL
. NOT CLOSE,
. CLOSE. THE GENERATORS WILL RESULT IN VALVES ON ALL UNAFFECTED STEAM GENERATORS, ISOLATION OF THE FAULTED STEAM GENERATOR, 4.4 IF THE_ RCP's ARE *IN SERVICE, COMPLETE STEPS
.4.5 AND 4.6. IF THE RCP's ARE liQI IN SERVICE, CO~PLETE STEPS 4,7 A~~ 4*:8.
4.*5 REDUCE RCS TEMPERATURE TO <S00°f AS QUICKLY
- AS. POSSIBLE.
4.5.1 IF THE CONDENSER IS AVAILABLE:
SALEM UNIT l/UNIT 2 REV. 6
I .
1-4.7
- 1. SHIFT THE STEAM DUMP TO PRESS 1. . APPROXIMATELY SATURATION 0
CONT AND REDUCE THE SETPOINT TO PRESSURE FOR 5QQ f,
"-660 PSIG,
- 2. WHEN TAVG DECREASES TO BELOW THE 2. STEAM DUMP SHOULD MAINTAIN Low-Low TAVG INTERLOCK RE-ESTABLISH RCS TEMP, "-5QQ 0 f, STEAM DUMP BY DEPRESSING THE BYPASS IF THE CONTROLLER HAS SATURATED TAVG PUSHBUTTONS ON THE STEAM DUMP AND THE DEMAND REMAINS HIGH, GO INTERLOCK TRAIN "A" OR "B" BEZELS, TO MANUAL AND REDUCE THE DE-MAND AND THEN GO BACK TO AUTO.
4.5.2 IF THE CONDENSER IS NOT AVAILABLE, 4,5,2 IlQ. liQI. STEAM THE AFFECTED OR THE NON-FAULTED STEAM GENERATORS STEAM GENERATOR, ARE ISOLATED, REDUCE THE SETPOINT TO IF THE CONTROLLERS HAYE SAT-
"-660 PSIG ON THE ATMOSPHERIC STEAM URATED AND THE DEMAND REMAINS RELIEF VALVES, MS-10 FOR THE UNAFFECTED HIGH AS PRESSURE APPROACHES STEAM GENERATORS, 660 PSIG GO TO MANUAL AND REDUCl THE DEMAND AND THEN GO BACK TO AUTO.
4,6 REDUCE RCS PRESSURE TO APPROXIMATELY THE 4,6 MAINTAIN AT LEAST 50°f SUB-PRESSURE OF THE FAULTED STEAM GENERATOR COOLING, BY FULLY OPENING ONE PRESSURIZER SPRAY THE RCP MUST BE RUN~ING-iN ORDER VALVE CPSl OR 3). TO GET SPRAY FLOW, THE CRITERIA FOR TRIPPING ALL RCP's AT 1500 PSIG DOES NOT APPLY, 4.6.1 TERMINATE THE PRESSURE REDUCTION BY 4.6.1 PREVENT PRESSURIZER FROM CLOSING tHE SPRAY VALVE WHEN EITHER: BECOMING WATER SOLID.
RCS PRESSURE IS EQUAL TO THE FAULTED STEAM GENERATORS, OR, PRESSURIZER LEVEL INCREASES TO 50%.
4.7 IF THE RCP's ARE fiQI IN SERVICE, PROCEED 4.7 THE REDUCTION IN RCS TEMP.
AS FOLLOWS TO REDUCE RCS TEMPERATURE TO AND PRESS, MUST BE DONE QUICKLY
~00°f As QUICKLY As poss1LBE. TO MINIMIZE THE RELEASE TO THE ATMOSPHERE FROM THE AFFECTED SIG.
4,7,l fULLY OPEN THE ATMOSPHERIC STEAM RELIEF VALVES, MS-10, ON THE UN-AFFECTED STEAM GENERATORS.
4.7.2 REDUCE RCS TEMPERATURE TO ~OO~F AS 4.7.2 TAVG IS NOT VALID WITH NO INDICATED BY THE INCORE THERMOCOUPLES RCP's IN SERVICE.
- o~ TH IN THE ~NAFFECT~ Loops. REFER TO. THE
... . .PRESSURE-TEMPERATURE
.. - . . .. . . CURVE DETERMlNE THE REQUIRED STEAM GENERATOR PRESSURE, TO SIG Tc.
PRESS IS DETERMINED BY SALEM UNIT llUNIT 2
(!}) 'l /"! nR,~,
lWLJDib'U' 6 I
I-4,7 REQUIRED S/G PRESS IS DE-TERMINED BY AMOUNT OF DECAY HEAT AS INDICATED BY ~T.
EXAMPLE:
~T IS 50°F To GET 500°F TH, Tc MUST BE 450°F.
STEAM PRESS SHOULD BE ~ 410 PSIG, 4.8 REDUCE RCS PRESSURE TO APPROXIMATELY THE 4.8 MAINTAIN AT LEAST 50°F SUB-PRESSURE OF THE FAULTED STEAM GENERATOR COOLI NG I BY OPENING ONE PRESSURIZER POWER OPERATED POWER OPERATED RELIEF VALVE RELIEF VALVE, .CPRl OR 2), BLOCK VALVE CPR6 OR 7) MUST BE OPEN, 4.8.1 TERMINATE THE PRESSURE REDUCTION BY 4.8.1 PREVENT PRESSURIZER FROM THE POWER OPERATED RELIEF WHEN EITHER: BECOMING WATER SOLID, RCS PRESSURE IS EQUAL TO THE FAULTED STEAM GENERATOR, OR, PRESSURIZER LEVEL INCREASES TO 50%,
- 4.9 IF THE FAULTED STEAM GENERATOR IS IDENTIFIED AS EITHER 11 OR 13(21 OR 23) Allil No, 11 &12 (21 &22) AUXILIARY FEEDWATER PUMPS ARE SUPPLYING WATER TO THE NON-FAULTED STEAM GENERATORS, STOP No. 13(23) Aux. FEED PUMP, 4.9 No. 13(23) Aux. FEED PUMP TURBINE EXHAUSTS TO ATMOSPHERE, 4.10 STOP THE RESIDUAL HEAT REMOVAL PUMP AS 4.10 THE RHR PUMPS SHOULD NOT BE FOLLOWS: ALLOWED TO RUN ON RECIRC FOR MORE THAN ~30 MINUTES SINCE THERE IS NO COMPONENT COOLING TO THE RHR HEAT EXCHANGERS.
4.10.1 RESET SAFETY INJECTION BY DEPRESSING 4.10,l AUTOMATIC ACTUATION OF BOTH TRAIN "A" & "B" SI RESET PUSH- SAFETY INJECTION WILL NO BUTTONS ON THE SAFEGUARDS ACTUATION LONGER BE AVAILABLE, BEZELS ON THE CONTROL CONSOLE, ANY SUBSEQUENT ACTUATION MUST BE ACCOMPLISHED MAN-UALLY BE INSERTING THE SAFEGUARDS KEY INTO EITHER TRAIN "A" OR "B" OPERATE ON THE SAFEGUARDS ACTUATION BEZEL AND TURN THE KEY, SALEM UNIT l/LiNIT 2 REV, 6
I-4.7 IF AT ANY TIME AFTER SAFETY INJECTION IS RESET) A BLACKOUT SIGNAL IS RECEIVED) THE VITAL BLISSES WOULD BE STRIPPED AND THE BLACKOUT LOADS WOULD BE SE-QUENCED ON BY THE SEC. THE SAFETY INJECTION PUMPS WILL NOT BE RESTARTED, THEY MUST BE MANUALLY STARTED AFTER THE LOADING SEQUENCE IS COMPLETE AS INDICATED BY THE LOADING COMPLETE LIGHTS ON THE lA) lB AND 1C(2A) 2B AND 2C) DIESEL GENERATOR BEZELS, THIS IS TO BE ACCOMPLISHED IN SUCH A MANNER AS TO PREVENT OVERLOADING THE DIESELS, THE LOADS SHOULD BE APPLIED AT
~10 SEC, INTERVALS, D.Q. NQ.l RESTART THE PUMPS BY MANUALLY INITIATING SAFETY
- 4.10.2 RESET THE SAFEGUARDS LOADING SEQUENCE BY DEPRESSING EMERGENCY LOADING RESET PUSH-INJECTION AS THIS WILL ALSO START THE RHR PUMPS.
BUTTONS ON THE CONTROL CONSOLE FOR lA) lB AND 1C(2A) 2B AND 2C) DIESEL GENERATORS.
4.10.3 STOP BOTH RHR PUMPS.
4.11 WHEN THE FOLLOWING CONDITIONS EXIST:
REACTOR COOLANT PRESSURE INCREASES BY INJECTION FLOW IS GREATER 200 PSIG AFTER THE CONTROLLED DEPRES- THAN LEAK FLOW, SURIZATION (STEP 4.6 OR 4.8) filID PRESSURIZER LEVEL IS INCREASING ON 2/3
-CHANNELS, REACTOR
. . COOLANT SYSTEM
. TEMPERATURE IS MORE IF TEMPERATURE REMAINS BELOW THAN 50°F SUBCOOLED AS INDICATED BY EITHER THE TsAT -50°F CURVE ON THE THE WIDE RANGE TH _INDICATORS ON THE NON- PRESSURE-TEMPERATURE CURVE)
FAULTED LOOPS OR THE INCORE THERMOCOUPLES, S0°F SUBCOOLING IS ASSURED.
SALEM UNIT l/LiNIT 2
1-4.7 4.11.1 STOP No. 11 &12(21 &22) SAFETY IN-JECTION PUMPS I 4.11.2 IF No, 13(23) CHARGING PUMP IS RUNNING)
STOP No, 11 &12(21 &22) CHARGING PuMPs. IF No. 13(23) CHARGING PUMP Is NQl RUNNING) STOP EITHER No, 11 OR 12 (21 OR 22) CHARGING PUMP.
4.12 ESTABLISH NORMAL CHARGING AND LETDOWN IAW OI II-3.3.L "ESTABLISHING CHARGING) LET-DOWN AND SEAL INJECTION FLOW",
4.12.1 CONTROL PRESSURIZER LEVEL AT ~22%.
4.12.2 OPERATE THE PRESSURIZER HtATERS AS REQUIRED TO MAINTAIN REACTOR COOLANT PRESSURE DURING THE SUBSEQUENT COOL-DOWN, 4.13 IF PRESSURIZER LEVEL CANNOT BE MAINTAINED 4.13 CONTINUE TO MONITOR FOR THESE
- 4.14
>17%J QRJ RCS SUBCOOLING CANNOT BE MAINTAINED
>50°FJ TI:i.ENJ RESTART No, 11 AND/OR 12 (21 AND/OR 22) SAFETY INJECTION PuMP(s).
IF No. 11AND12(21 AND 22) SAFETY INJECTION PUMPS ARE RUNNING AND EITHER PRESSURIZER LEVEL 4.14 CONDITIONS THROUGHOUT THE SUBSEQUENT COOLDOWN, CONTINUE TO MONITOR FOR THESE CONDITIONS THROUGHOUT THE OR SUBCOOLING CANNOT BE MAINTAINED) MANUALLY SUBSEQUENT COOLDOWN, REINITIATE SAFETY INJECTION BY tNSERTING THE SAFEGUARDS KE~ INTO EITHER TRAIN "A" OR "B" SAFETY INJECTION OPERATE BEZEL AND TURN THE KEY, RETURN TO STEP 4.6 OF THIS INSTRUCTION AND PROCEED FROM THERE, 4.15 WHEN CONDITIONS PERMIT) RETURN THE 4KV VITAL BLISSES TO NORMAL BY:
4.15.1 STOP THE EMERGENCY DIESEL GENERATORS IAW 01 IV-16.3.lJ "EMERGENCY POWER - DIESEL OpERATION".
4,15.2 START OR STOP VITAL BUS LOAD AS NECESSARY,
- 4.16 REFER TO EI I-4.2J "RECOVERY FROM SAFETY INJECTION" FOR GUID~NCE
~ . . . IN ~~T~RNING SYSTEMS TO NORMAL OPERATION IN PREPERATION FOR COOLDOWN, 4.16 DuE TO ABNORMAL PLANT CONDI-TIONS) SOME STEPS MAY NOT BE APPROPRIATE AND SOME EQUIPMENT SALEM UNIT l/UN!T 2
1-4.7 4.17 IF NO REACTOR COOLANT PUMPS ARE IN OPERATION, 4.17 RUNNING No. 13C23)RCP GIVES START ONE PUMP IN AN UNAFFECTED LOOP, THE BEST PRESSURE CONTROL, No, 11(2l)RCP WOULD BE THE SECOND CHOICE, 4.18 COMMENCE A COOLDOWN AND DEPRESSURIZATION OF THE REACTOR COOLANT SYSTE~ AS DESCRIBED BELOW, OBSERVE THE FOLLOWIN~ PRECAUTIONS, 4.18,l Do NOT ATTEMPT TO COOLDOWN WITHOUT AT LEAST ONE RCP IN OPERATION, IF AN RCP CANNOT BE STARTED, MAIN- 4.18.1 THE FAULTED STEAM GENERATOR TAIN _PRESSURIZER LEVEL AND THE IS AN INTEGRAL PART OF THE FAULTED STEAM GENERATOR LEVEL BY RCS. THE LEVEL WILL BE CONTROhLING CHARGING FLOW AND CONTROLLED BY THE PRESSURE PRESSURIZER PRESSURE, IN THE RCS.
4.18.2 MAINTAIN LEVEL IN THE FAULTED STEAM 4,18.2 A SUPERHEATED STEAM BUBBLE GENERATOR IN THE NARROW RANGE. MAY EXIST IN THE FAULTED STEAM GENERATOR, IF THIS IS ALLOWED TO COME IN CON-TACT WITH THE SUBCOOLED TUBES A RAPID DEPRESSURIZATION OF THAT STEAM GENERATOR WILL RESULT IN A LARGE OUTFLOW OF WATER FROM THE RCS AMD A RESULTANT DROP IN PRESSURIZER LEVEL.
4.18.3 IT IS PREFERRED TO DEPRESSURIZE THE 4.18.3 ALL POTENTIAL RELEASES FAULTED STEAM GENERATOR BY ALLOWING FROM THE STEAM GENERATOR IT TO DRAIN BACK TO THE RCS. IF TO THE ATMOSPHE-RE MUST BE FOR SOME REASON THIS IS NOT POSSIBLE, CALCULATED BEFORE THE THE FAULTED STEAM GENERATOR WILL RELEASE, THE RELEASES HAVE TO BE DEPRESSURIZED BY BLEEDING MUST BE LESS THAN THAT OF STEAM BY ONE OF THE FOLLOWING: ALLOWED BY 10CFR20.
- 1. OPEN THE MAIN STEAM STOP BYPASS ALL RELEASES MUST BE YALVE!'MS18, AND BLEED STEAM TO PREVIOUSLY APPROVED BY THE THE CONDENSER, OR, SENIOR SHIFT SUPERVISOR,
- 2. BRIEFLY OPEN THE STEAM GENERATOR POWER OPERATED RELIEF VALVE, MS-10, APPROXIMATELY 10%,
- 4 .19 REFER TO 01 1-3. 6, "Hor STANDBY TO COLD SHUTDOWN" FOR DIRECTION AS TO THE OPERATION OF SUPPORT SYSTEMS DURING THE cooLDOWN.
ff))
f'@~h mNr"'<<l\f°f]ffi/K\ ~\in ""\~n IJ.U.\lu \Uli.il!U'\JUim UU~u'\.I
@lliHL~
SALEM UNIT l/UNIT 2 REV, 6
I-4.7 4.20 SAMPLE THE RCS FOR BORON.
4.20.l BORATE THE RCS AS NECESSARY TO 4.20.l REFER TO REACTOR ENGINEER-INSURE SHUTDOWN MARGIN WILL BE ING MANUALJ FIGURE 20A.
MAINTAINED WHEN COLD SHUTDOWN IS ACHIEVED, 4.20.2 PERIODICALLY SAMPLE THE RCS DURING 4.20.2 THE RCS BORON CONCENTRATION COOLDOWN TO INSURE SHUTDOWN MARGIN MAY DECREASE AS THE FAULTED IS MAINTAINED, STEAM GENERATOR DRAINS BACK TO THE RCS.
4.21 DUMP STEAM FROM THE UNAFFECTED STEAM 4.21 USE EITHER STEAM DUMP TO THE GENERATORS AND ESTABLISH A COOLDOWN CONDENSER OR THE MS-lQ's, RATE OF <5Q°F/H~.
4.21.l MAINTAIN THE LEVEL IN THE UNAFFECTED STEAM GENERATORS ~33%,
4.21.2 MAINTAIN PRESSURIZER PRESSURE IAW THE PRESSURE TEMPERATURE CURVE.
4.21.3 WHEN RCS PRESSURE DECREASES TO 4.21.3 RELEASE THE TAGS AND ENERGIZE
<1000 PSIGJ ISOLATE THE SAFETY THE VALVES, ONCE VALVES INJECTION ACCUMULATORS BY CLOSING ARE CLOSEDJ OPEN THE BREAKERS THE ACCUMULATOR ISOLATION VALVESJ AND TAG FOR THE SHIFT SUPER-ll-14C21-14)SJ54. VISOR, 4.21.4 WHEN RCS TEMPERATURE IN THE UN-AFFECTED LOOPS IS DECREASED TO
<350°F AND RCS PRESSURE IS I
<400 PSIGJ PLACE THE RHR SYSTEM IN OPERATION IAW DI II-6.3.2J "INITIATING RESIDUAL HEAT RE-MOVAL".
4.21.5 CONTINUE THE COOLDOWN TO COLD SHUTDOWN CONDITIONS, PREPARED BY _ _ _ _ _ _ _ _ _ _ _ _ __
MANAGER - SALEM GENRATING STATON
.EVIEWED BY SORC MEETING No. _ _ _ _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 REV. 6
1-4.9 EMERGENCY INSTRUCTION I-4.9 BLACKOUT 1.0 PURPOSE THIS INSTRUCTION PROVIDES THE STEPS REQUIRED TO RECOVER THE STATION FOLLOWING A "BLACKOUT",
1.1 A "BLACKOUT", Loss OF POWER TO THE 4KV GROUP BLISSES, WILL RESULT IN A REACTOR TRIP, TURBINE TRIP, AND A LOSS OF STATION POWER TO BOTH UNIT 1 AND UNIT 2,* THE 4KV VITAL BLISSES WILL BE AUTOMATICALLY ENERGIZED FROM THE EMERGENCY DI~SEL GENERATORS, THE 4KV GROUP BussES CAN BE MANUALLY ENERGIZED FROM THE GAS TURBINE GENERATOR.
1.2 SINCE A BLACKOUT WILL RESULT IN A LOSS OF FORCED FLOW THROUGH THE REACTOR, DECAY HEAT WILL BE REMOVED BY NATURAL CIRUCLATION, THIS INSTRUCTION PROVIDES THE GUIDELINES TO BE FOLLOWED TO VERIFY NATURAL CIRCULATION, 2.0 INITIAL CONDITIONS 2.1 GENERAL LOSS OF ELECTRICAL POWER, IMMEDIATE ACTIONS
- .o 3.1 AUTOMATIC 3.1.1 REACTOR TRIP - TURBINE TRIP 3.1.2 4KV VITAL Bus LOADS STRIPPED.
3.1,3 DIESEL GENERATOR START AND LOAD IN THE BLACKOUT MODE, 3.1.4 THE 13(23) TURBINE DRIVEN AUXILIARY FEED PUMP STARTS 3.1,5 THE EQUIPMENT LISTED IN TABLE I WILL SEQUENCE ON THE BUS, 3.1,6 THE FOLLOWING DC OIL PUMPS WILL START AS HEADER OIL PRESSURE DECREASES:
- 1) 11 &12 (21 &22) STEAM GENERATOR FEED PUMP TURBINE EMERGENCY OIL PUMPS,
- 2) 1 &2 TURBINE GENERATOR EMERGENCY BEARING OIL PUMPS
- 3) 1 &2 EMERGENCY SEAL OIL PUMPS.
3.2 MANUAL
- 3,2,l VERIFY THAT A REACTOR TRIP HAS TAKEN PLACE:
- 1) CHECK THAT ALL FULL LENGTH RODS ARE FULLY INSERTED BY CHECKING INDIVIDUAL ROD POSITION INDICATORS AND ROD BOTTOM LIGHTS, SALEM UNIT l/UNIT 2 W~~ ~OOFllll~IJDf!/l]~<l ral;¥J!Uv. io
I-4.9
- 2) IF ALL FULL LENGTH CONTROL RODS ARE NOT FULLY INSERTED, RAPID BORATE BY 150 PPM FOR EACH ROD NOT FULLY INSERTED AS FOLLOW:
A, SHIFT ONE OR BOTH BORIC ACID TRANSFER PUMPS TO FAST SPEED, B. OPEN 1(2)CV75, RAPID BORATION STOP VALVE.
C. BORATE FOR AT LEAST 8 MINUTES FOR EACH ROD NOT FULLY INSERTED (4 MINUTES WITH BOTH PUMPS IN FAST),
3.2.2 VERIFY TURBINE TRIP B\ CHECKING THE FOLLOWING:
- 1) UNIT TRIP LIGHT ON E/H CONSOLE ILLUMINATED.
- 2) TURBINE STOP VALVES, GOVERNOR VALVES, INTERCEPTOR VALVES AND REHEAT STOP VALVES CLOSED,
- 3) TURBINE SPEED DECREASING, IF THE TURBINE HAS NOT T~JPPED, PROCEED AS FOLLOWS UNTIL STEAM FLOW FROM THE STEAM GENERATORS JS TERMINATED.
- 4) INITIATE A MANUAL TRIP WITH THE HANDLE ON THE CONSOLE
- 5) TRIP CLOSED THE MAIN STEAM ISOLATION VALVES, ll-14C21-24)MS167 FROM EITHER THE SAFEGUARDS BEZELS OR MAIN STEAM BEZELS, IF THE UNCONTROLLED STEAM FLOW HAS CAUSED REACTOR COOLANT SYSTEM PRESSURE TO DECREASE TO <1765#, INSURE SAFETY INJECTION IS ACTUATED, IF SAFETY INJECTION IS NOT ACTUATED, INITIATE IT MANUALLY BY INSERTING THE SAFEGUARDS KEY INTO EITHER TRAIN "A" OR "B" SAFETY INJECTION OPERATE BEZEL AND TURN THE KEY, PROCEED TO EI I-4.0, "SAFETY INJECTION INITIATION",
3,2,3 VERIFY THAT RCS WIDE RANGE Tc JS DECREASING TOWARD OR IS BEING MAINTAINED AT 547°F BY ATMOSPHERIC STEAM RELIEF, 3.2.4 ANNOUNCE OVER THE PLANT PA SYSTEM TWICE: "UNIT NO. 1(2) REACTOR TRIP",
4.0 SUBSEQUENT ACTIONS COMMENTS 4.1 VERIFY AUXILIARY FEEDWATER FLOW JS ESTABLISHED TO AT LEAST TWO STEAM GENERATORS BY CHECKING THE AUXILIARY FEEDWATER FLOW INDICATORS ON THE CONTROL CONSOLE, 4,1,l IF FLOW HAS NOT BEEN ESTABLISHED, PROCEED AS FOLLOWS:
- 1) CHECK THE DISCHARGE PRESSURE ON THE*
MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS (11 &12, 21 & 22) WHICH ARE RUNNING IT SHOULD INDICATE:_ RI m~n:@~~~1 ~~w lm~~w SALEM UNIT l/UNIT 2 Ri:v. 10
I-4.9
- 2) lF PRESSURE IS LOW (<1350#) DEPRESS 2) THIS WILL REMOVE THE PUMP THE PRESS OVERRIDE DEFEAT PUSHBUTTON RUNOUT PROTECTION, ON THE CONSOLE BEZEL FOR EACH Aux. THE DISCHARGE PRESSURE TRANS-FEEDWATER PUMP WITH A LOW PRESSURE. MITTER MAY BE FAILED LOW PREVENTING THE DISCHARGE VALVES FROM OPENING,
- 3) l F PRESSURE IS ~350# CHECK THE 3) A FAILURE IN THE PUMP RUNOUT VALVE DEMAND SET AT ~95% FOR PROTECTION CIRCUITRY MAY ll-14(21-24)AF21 ON THE CONSOLE PREVENT THE DISCHARGE VALVES BEZEL. ALSOJ DEPRESS THE PRESS FROM OPENING, OVERRIDE DEFEAT PUSHBUTTON ON No. 11(21) FEEDS No. 13 &
THE CONSOLE BEZEL FOR EACH 14(21&24) STEAM GENERATORS, AUXILIARY FEEDWATER PUMP FOR No. 12C22) FEEDS No. 11 &
WH~CH THERE IS NO FLOW, 12(21 & 22) STEAM GENERATORS.
- 4) IF EXCESSIVE FLOW IS INDICATED TO ONE OR MORE STEAM GENERATORS)
RE-ESTABLISH THE PUMP RUNOUT PROTECTION BY DEPRESSING THE PRESS OVERRIDE NORMAL PUSH-BUTTON ON THE CONSOLE FOR THE
- " AFFECTED AUXILIARY FEEDWATER PUMP(s). PROCEED ro EI I-4.6J nLoss OF SECONDAY COOLANT",
- 5) START) IF NOT ALREADY RUNNING) No.
13(23) AUXILIARY fEEDWATER PUMP AND VERIFY ll-14(21-24)Afll ARE OPEN.
4.2 VERIFY DECAY HEAT REMOVAL BY NATURAL CIRCUATION 4.2 IT MAY TAKE SEVERAL MINUTES BY OBSERVING THE FOLLOWING: TO ESTABLISH NATURAL CIRCU-LATION INDICATIONS DUE TO 4.2.1 REACTOR CooLANT Loop 6T ~62°F ON ONE INCREASED LOOP TRANSIT TIMES, OR MORE LOOPS, 4.2.2 JNCORE THERMOCOUPLES AND LOOP WIDE RANGE TH ARE STABLE OR SLOWLY DECREASING,
- 4.2.3 STEAM GENERATOR PRESSURE IS ~1000 PSIG FOR ALL STEAM GENERATORS FOR WHICH LOOP 6T IS <62°f, 4.3 [STABLISH OR MAINTAIN THE FOLLOWING CONDITIONS TO ENSURE MAXIMUM NATURAL CIRCULATION IS MAIN-TAINED IN THE REACTOR COOLANT SYSTEM FOR DECAY HEAT REMOVAL.
SALEM UNIT l/LiNIT 2
I I-4.9 4.3.1 REACTOR COOLANT PRESSURE ~ 2000 PSIG, 4.3.2 PRESSURIZER LEVEL~ 50%.
4.3.3 STEAM GENERATOR LEVEL~ 10% IN THE NARROW RANGE ON AT LEAST ONE STEAM GENERATOR, AND IF POSSIBLE, ALL FOUR, 4.4 VERIFY BOTH MAIN FEED PUMPS ARE TRIPPED, 4.4 TURBINE EXHAUST TO No, 11(21)
IF EITHER IS NOT TRIPPED, THE TRIP PUSH- CONDENSER MAY OVERPRESSURE THE BUTTON ON THE APPROPRIATE CONTROL CONSOLE CONDENSER SHELL, BEZEL, 4.5 MAINTAIN THE UNIT IN A Hor STANDBY 4,5 IT IS PREFERRED TO MAINTAIN CONDITION AS FOLLOWS UNTIL OFF-SITE POWER THE UNIT IN Hor STANDBY.
IS RESTORED, IF NECESSARY, PLACE THE PLANT IN COLD SHUTDOWN AS DIRECTED BY APPENDIX 1.
4,5,l MAINTAIN STEAM GENERATOR PRESSURE BY 4,5,l fOR CONDITIONS WHERE A HIGH ADJUSTING THE SETPOINT FOR THE ATMOS- DEGREE OF DECAY HEAT IS PRESENT, PHERE STEAM RELIEF VALVES, MS-lO's THE 6T INDICATED WILL APPROACH TO MAINTAIN THE .L.Q\ifR OF FOLLOWING THE FULL LOAD 6T, SINCE THE COND !TI ONS; STEAM GENERATOR PRESSURE IS INDICATIVE OF TC CONDITIONS,
- 2) INCORE THERMOCUPLE TEMPERATURES FOR A STEAM GENERATOR PRESSURE
<600°F. OF 1000 PSIG, THEREFORE A REDUCTION IN STEAM GENERATOR PRESSURE MAY BE REQUIRED, 4.5.2 IF ADJUSTMENTS IN STEAM GENERATOR 4,5.2 RESPONSES IN TEMPERATURE ARE PRESSURE ARE REQUIRED, MAKE THE SEEN SLOWLY DUE TO LONG LOOP ADJUSTMENTS SLOWLY, TRANSIENT TIMES, 4.5.3 REFER TO THE PRESSURE-TEMPERATURE 4.5.3 SAMPLE CALCULATION:
CURVE TO CALCULATE THE STEAM PRESSURE 6T IS 62°F, STEAM PRESSURE REQUIRED TO MAINTAIN THE DESIRED 1000#, Tc IS 547; so TH IS REACTOR COOLANT TEMPERATURE. 609°F.
To REDUCE TH BY 10°F, Tc MUST BE REDUCED BY 10°F SINCE 6T IS CONSTANT.
REDUCE STEAM GENERATOR PRES-SURE TO ~950 PSIG, 4.5.4 MAINTAIN STEAM GENERATOR LEVELS AT
- _,,. 11 _ _ ~
~33% BY CONTROLLING THE AF-11 AND AF-21 FOR EACH STEAM GENERATOR J.IJ ___ r\
~ALEM UNIT itUNl I ~
1-4.9 CAUTION: IF THE LEVEL IN ANY STEAM THE FEED RING DRAINS SLOWLY GENERATOR HAS BEEN <10% IN THROUGH THE LOOSE FIT CONN-THE NARROW RANGE FOR MORE ECTION TO THE FEED INLET THAN 5 MINUTES AND ALL FEED- PIPING.
WATER FLOW HAS BEEN ISOLATED IF CONDITIONS REQUIRE MAXIMUM FOR MORE THAN 5 MINUTES, FLOW FLOW FOR DECAY HEAT REMOVAL MUST BE LIMITED TO <lxl0 5 CONSIDERATIONS, THIS TAKES LBM/HR. TO THAI STEAM GEN- PRECEDENCE OVER THE WATER ERATOR UNTIL"' THE LEVEL IS HAMMER CONSIDERATION, RETURNED TO >10% IN THE NARROW RANGE, 4.6 DETERMINE WHETHER THE BLACKOUT IS DUE 4.6 CALL THE LOAD DISPA~CHER.
IO A LOCAL MALFUNCTION OR A FAILURE OF THE NEW FREE-DOM AND KEENEY LINES.
4.7 OPEN OR VERIFY OPEN THE FOLLOWING:
BREAKERS AND DISCONNECTS, 4.7.1 500 KV BREAKERS, 1-5, 5-6, 2-6 1-8, 2-8, 2-10, 9-10, 1-9,
- - 4.7.2 4.7.3 500 KV DISCONNECTS - 1T60, 2T60.
13 KV BREAKERS 2, 2-3, 3-4, 4-5, 5-6, 1-6.
CAUTION: Do NOT OPEN 13 *KV DISCONNECTS INTERLOCKS REQUIRE GAS TURBINE 1T50 AND 2T50. BREAKER AND 13KV BREAKERS OPEN TO CLOSE THESE, 4.8 STRIP ALL LOADS FROM THE 4KV GROUP BUSES 4,8 To INSURE LOADS DO NOT IN-FOR UNIT 1 AND UNIT 2. OPEN OR CHECK ADVERTENTLY START WHEN BUS OPEN THE FOLLOWING INFEED BREAKERS TO FEED IS SUBSEQUENTLY CLOSED.
THE GROUP BussEs.
lH - llHSD &lAFHGD 2H - 21HSD &2AHGD lE - llESD &lAEGD 2E - 21ESD &2AEGD lF - 12FSD &lBFGD 2F - 21FSD &2BFGD lG - 12GSD &2BGGD 2G - 22GSD &2BGGD 4.9 START THE GAS TURBINE IAW DI V-13.3.3, "DEAD Bus OPERATION BoorsrRAP STARTUP".
4.9.1 WHEN THE GAS TURBINE IS IN OPERATION RETURN TO THIS INSTRUCTION AND COMPLETE THE APPROPRIATE SUBSEQUENT AcnoNs.
4.9.2 IF THE GAS TURBINE FAILS TO START, PROCEED TO STEP 4.16, REV. 10 SALEM UNIT l/UNIT 2
4.10 COORDINATE THE CLOSURE OF THE FOLLOWING 4.10 To ENERGIZE No, 11, 12, 21 13KV BREAKERS WITH THE LOAD DISPATCHER: & 22 STATION POWER TRANS-3-4, 4-5, 2-3, 5-6, PROCEED AS FOLLOWS FORMERS, FOR EACH BREAKER, 4.10.l DEPRESS THE LOCAL PUSHBUTTON ON THE APPROPRIATE BEZEL, 4.10.2 SELECT THE DESIRED BREAKER ON THE MIMIC Bus.
4.10.3 DEPRESS SYNC POT ON FOR THE DESIRED BREAKER, 4.10.4 CLOSE THE BREAKER, 4.10.5 DEPRESS SYNC POT OFF.
4.11 CLOSE THE FOLLOWING BREAKERS TO ENERGIZE 4.11 RECOVERY MAY PROCEED WHILE THE 4KV GROUP BusES. As EACH BUS IS ANY INVESTIGATIONS ARE CON-ENERGIZED CHECK THE BUS VOLTAGE ~4160 DUCTED I IF BUS VOLTAGE IS NOT AS EXPECTED, REOPEN THE FEEDER AND INVESTIGATE THE CAUSE, lH - llHSD 2H - 21HSD lE - llESD 2E - 21ESD lF - 12FSD 2E - 22FSD lG - 12GSD 2G - 22GSD 4.12 START THE FOLLOWING EQUIPMENT ON THE 4.12 THE EXACT COMPONENT DEPENDS GROUP BUSES, MONITOR THE GAS TURBINE ON PLANT CONDITIONS AND LOAD, VOLTAGE, FREQUENCY, ETC, FOR EQUIPMENT AVAILABILITY, NORMAL RESPONSE. IF ABNORMAL CONDI -
TIONS ARE OBSERVED, STOP THE PIECE OF EQUIPMENT AND INVESTIGATE, CAUTION: D.o. NQi ATTEMPT TO START A REACTOR COOLANT PUMP.
4.12.l 4KV LOADS'
- 1) ONE STATION AIR COMPRESSOR
- 2) ONE CONDENSATE PUMP
- 3) ONE TURBINE AUXILIARY COOLING PUMP .
SALEM UNIT l/LiNIT 2 REV 10 I
1-4.9
- ENERGIZE THE 460V BusES BY CLOSING 4.12.2 THE 460V AND 230V BREAKERS 4.12.2 THE INDICATED 4KV FEEDER. STOP DO NOT HAVE UNDERVOLTAGE ANY EQUIPMENT WHICH STARTS AND IS TRIPS AND WILL REMAIN CLOSED.
NOT DESIRED, ENERGIZE ONE AT A TIME AND
- 1) 1H30 TO LIGHTING BUS lHL AND STABILIZE LOAD, No. 1 500KV SWITCHYARD 280V/
120V Bus.
- 2) 1F3D TO LIGHTING Bus lFL.
- 3) 1E6D TO lE 460V Bus AND PRES-SURIZER HEATER Bus lEP.
- 4) 1G60 TO lG 460V Bus AND PRES-suRiZER HEATER BusEs lGP <CoN-TROL AND BACKUP HEATERS)
- 5) lHSD TO lH 460V Bus AND lH 230V Bus.
- 6) lFSD TO lF 460V Bus AND lF 230V Bus.
- 7) 2H3D TO LIGHTING BUS 2Hl AND No. 2 500KV SWITCHYARD 280V/
120V BUS,
- 8) 2F3D TO LIGHTING BUS 2Fl.
- 9) 2E6D TO 2E 460V Bus AND PRES-SURIZER HEATER Bus 2EP. '.
- 10) 2G6D TO 2G 460V Bus AND PRES-SURIZER HEATER BusES 2GP. ([ON-TROL AND BACKUP HEATERS)
- 11) 2H5D TO 2H 460V Bus AND 2H 230V Bus.
- 12) 2F5D TO 2F 460V Bus AND 2F 230V Bus.
START, IF NOT ALREADY RUNNING, THE 4.12.3 SHOULD HAVE STARTED IF IN 4.12.3 FOLLOWING PUMPS. AUTO.
- 1) ONE LUBE OIL PuMP ON No. 11, 12 21 AND 22 STEAM GENERATOR fEED PUMP.
R11 llJroJ.rffimi~JOO Lm~~w SALEM UNIT l/UNIT 2 REV 10 I
1-4.9
- 2) *AIR SIDE SEAL OIL PUMP.
- 3) AUXILIARY BEARING OIL PUMP,
- 4) BEARING LIFT PUMP.
- 5) HIGH PRESSURE SEAL OIL PUMP.
4.13 STOP THE FOLLOWING DC LUBE Or~ PuMPs:
4.13.1 11, 12, 21 AND 22 FEED PUMP EMER-GENCY LUBE OIL PUMP.
4.13.2 1 AND 2 EMERGENCY AIR SIDE SEAL OIL PUMP 4.13.3 1 AND 2 EMERGENCY BEARING OIL PUMP, 4.14 RESET THE SAFEGUARDS LOADING SEQUENCE BY DEPRESSING THE EMERGENCY LOADING RESET PUSHBUTTONS ON THE CONTROL CONSOLE FOR lA, lB, 1C(2A, 2B, 2C) DIESEL GENERATORS.
- -- 4.15 PLACE TURBINE GENERATOR ON TURNING GEAR, IF TURNING GEAR TRIPS, DO NOT ATTEMPT REPEATED STARTS, THEREAFTER, ATTEMPT TO PLACE TURNING GEAR IN OPERATION AT ONE HOUR INTERVALS, 4.16 IF UNABLE TO UTILIZE THE GAS TURBINE GENERATOR, PROCEED AS FOLLOWS:
4.16.1 BREAK CONDENSER VACUUM TO REDUCE TURBINE 4.16.l THE VALVES ARE MOTOR OPERATED, ROLL TIME BY MANUALLY OPENING 11, 12, 13 (21, 22, 23)AR65 VACUUM BREAKER VALVES, 4.16.2 THE DC EMERGENCY BEARING OIL PUMP SHOULD SUPPLY LUBRICATING OIL DURING THE ROLL DOWN TO ZERO SPEED AND FOR 1/2 HOUR THEREAFTER, 4.16.3 SUBSEQUENT OPERATION OF THE DC PUMP 4.16.3 THIS WILL EXTEND THE USE-SHOULD BE INTERMITTENT; OFF.FOR 45 FULNESS OF THE 250V BATTERY, MINUTES AND RUN FOR 15 MINUTES, TO AVOID DAMAGING BEARING BABBITT, 4.16.4 DURING OPERATION OF THE EMERGENCY OIL 4.16.4 THERE IS NO POWER TO THE PUMP, ATTEMPT TO OPERATE TURNING GEAR TURNING GEAR.
WITH AN AIR DRIVE ON GEAR EXTENSION SHAFT, SALEM UNIT l/UNIT L
1-4.9
- 4.16.5 REDUCE Hz PRESSURE IN THE MAIN GENERATOR TO < z PSIG IAW DI IV-Z.3.Z, "GENERATOR GAS SYSTEMS - NORMAL OPERATION", AS SOON AS POSSIBLE TO PREVENT Hz LEAKAGE, 4.16,6 ENERGIZE ONE GROUP OF PRESSURIZER 4.16.6 ENERGIZE THE BACKUP HEATERS BACKUP HEATERS FROM ITS EMERGENCY FROM THE DIESEL WITH THE VITAL SUPPLY AS DESCRIBED BY A, li LOWEST LOAD, QR ( BELOW: THE ARRANGEMENT FOR lEP AND ZEP ARE DIFFERENT, THE AR-A. ENERGIZE lEP PRESSURIZER RANGEMENT FOR lGP AND 2GP HEATERS FROM lA 460V VITAL ARE THE SAME, Bus.
- 1) **OPEN lEPX FROM THE PRESSURIZER BACKUP HEATER GROUP lZ BEZEL ON.THE CONTROL CONSOLE, Z) OPEN 1E6D, 4KV INFEED TO PRESSURIZER HEATER TRANS-FORMER, FROM THE CONTROL CON-SOLE,
- 3) RACK OUT 1E6D AND REMOVE 3) ON lE 4KV GROUP Bus IN THE KEY FROM INSIDE THE BREAKER, 64 FT, ELEVATION SWITCHGEAR CUBICLE FOR THE CORRECT KEY ROOM, INTERLOCK,
- 4) OPEN AND RACK OUT lEX 4) ON lE 460V GROUP Bus IN AND REMOVE THE KEY FOR THE 84 FT, ELEVATION SWITCHGEAR CORRECT KEY INTERLOCK, RooM.
- 5) VERIFY 1Al4X OPEN .. 5) ON lA 460V VITAL Bus IN 84 FT, ELEVATION SWITCHGEAR RooM.
- 6) OPEN ALL BUT THREE BREAKERS 6) IN 78 FT, ELEVATION ELECTRICAL FOR INDIV.IDUAL HEATERS ON THE PENETRATION AREA, lEP HEATER BUS, EMERGENCY FEED WILL TRIP IF
>Z50 KW OF HEATERS ARE CON-NECTED, THREE GROUPS IS ~ 207 KW,
- 7) REMOVE THE PADLOCK AND CLOSE THE MANUAL DISCONNECT SWITCH FOR THE EMERGENCY FEED TO lEP HEATER Bus.
- 7) ON COLUMN NEXT TO lEP HEATER BUS, No LOAD DISCONNECT SWITCH, SALEM UNIT l/UNIT 2 REV 10 I
1-4.9
- 8) INSERT THE KEYS FROM 1E6D AND lEX INTO 1Al4X AND CLOSE THE BREAKER,
- 9) 0PERA1E THE EP GROUP OF BACKUP HEATERS IN THE NORMAL MANNER.
- 10) OBSERVE THE LOAD ON lA DIESEL 10) 2000 HR. RATING, GENERATING AND VERIFY IT REMAINS <2750 KW, B. ENERGIZE 2EP PRESSURIZER HEATERS FROM 2A 460 V VITAL Bus.
- 1) -OPEN 2EPX FROM THE PRESSURIZER
. BACKUP HEATER GROUP 22. BEZEL ON (
THE CONTROL CONSOLE,
- 2) REMOVE THE KEY FROM THE BREAKER CUBICLE FOR 2EPX FOR THE CORRECT KEY INTERLOCK,
- 3) ON 2A 460V VITAL Bus IN 34
- 3) VERIFY 2Al4X OPEN.
FT, ELEVATION SWITCHGEAR ROOM,
- 4) OPEN ALL BUT THREE BREAKERS 4) IN 78 FT, ELEVATION ELECTRICAL FOR INDIVIDUAL HEATERS ON PENETRATION AREA, EMERGENCY THE 2EP HEATER BUS, FEED WILL TRIP !F >250 KW OF HEATERS ARE CONNECTED, THREE GROUPS JS ~207 KW,
- 5) REMOVE THE PADLOCK AND CLOSE 5) ON COLUMN NEXT TO 2EP HEATER THE MANUAL DISCONNECT SWITCH BUS, FOR THE EMERGENCY FEED TO 2EP No LOAD DISCONNECT SWITCH HEATER Bus.
- 6) INSERT THE KEY FROM 2EPX INTO BREAKER 2Al4X AND CLOSE THE BREAKER,
- 7) OPERATE THE 2EP GROUP OF BACKUP 7) THIS SCHEME BYPASSES THE HEATERS FROM THE CONTROL CONSOLE PRESSURIZER PRESSURE CONTROL BY DEPRESSING THE EMERG FEED ON SYSTEM, ENERGIZE THE HEATERS AND THE. CONTROL OF THE HEATER IS EMERG FEED OFF TO DE-ENERGIZE STRICTLY MANUAL.
THE HEATERS,
<2750 KW.
SALEM UNIT l/UNIT 2 REV' 10
I-4.9
- C, ENERGIZE 1GP(2GP) PRESSURIZER HEATERS FROM 1C(2() 460V VITAL Bus.
1). OPEN 1GPXC2GPX) FROM THE PRESSURIZER BACKUP HEATER GROUP 11(21) BEZEL ON THE CONTROL CONSOLE,
- 2) VERIFY BREAKER 1CPXC2CPX) 2) ON 1CC2C) 460V VITAL Bus IS CLOSED TO PROVIDE POWER IN 84 FT, ELEVATION SWITCH-TO THE 1C(2C) 460V VITAL GEAR RooM.
Bus EXTENSION.
POWER AVAILABLE LIGHT ON THE VITAL Bus EXTENSION IN 64 FT. ELEVATION SWITCHGEAR ROOM,
- 3) VERIFY 1C23X(2C23X) OPEN. 3) ON 1CC2C) 460 VITAL Bus EXT ENS ION, REQUIRES SPECIAL RACKING TOOL,
..._ 4) OPEN ALL BUT THREE BREAKERS 4) IN 78 FT, ELEVATION ELECTRICAL FOR INDIVIDUAL HEATERS ON PENETRATION AREA, THE 1GPC2GP) HEATER BUS. EMERGENCY FEED WILL TRIP IF >250 KW OF HEATERS ARE CONNECTED, THREE GROUPS IS ~207 KW.
- 5) RACK OUT 1GPXC2GPX) AND 5) IN 78 FT, ELEVATION ELECTRI-REMOVE THE KEY, CAL PENETRATION AREA,
- 6) REMOVE THE PADLOCK AND CLOSE 6) ON COLUMN NEXT TO 1GPC2GP)
THE MANUAL DISCONNECT SWITCH HEATER BUS, FOR THE EMERGENCY FEED TO No LOAD DISCONNECT SWITCH 1GP(2GP) HEATER BUS.
- 7) INSERT THE KEY FROM 1GPX(2GPX)
IN 1C23X(2C23X) AND CLOSE THE BREAKER,
- 8) OPERATE THE GP GROUP OF BACKUP 8) l~IS SCHEME BYPASSES THE HEATERS FROM THE CONTROL CONSOLE PRESSURIZER PRESSURE CONTROL BY DEPRESSING THE EMERG FEED ON SYSTEM, CONTROL OF THE HEATERS TO ENERGIZE THE HEATERS AND--THC______ -- -IS STRICTLY MANUAL, __
EMERG FEED OFF TO DE-ENERGIZE
- THE HEATERS, SALEM UNIT l/UNIT 2 REV' 10
I-4.9 9)_ OBSERVE THE LOAD ON 1C(2C) 9) 2000 HR, RATING, DIESEL GENERATOR AND VERIFY IT REMAINS <2750 KW, 4.16.7 WHEN OFF-SITE POWER IS AVAILABLE)
ESTABLISH STATION POWER IN COORDI-NATION WITH THE LOAD DISPATCHER AS FOLLOWS:
- 1) VERIFY THAT 5023 AND/OR 5024 AND/OR 5015 LINES ARE ENER-GIZED,
- 2) CLOSE THE FOLLOWING BREAKERS FOR THE LINES WHICH ARE ENER-GIZED:
5023 8 AND 2-8 5024 6 5015 10 PROCEED AS FOLLOWS FOR EACH BREAKER,
- A)
B)
DEPRESS THE LOCAL PUSH-BUTTON, SELECT THE DESIRED BREAKER oN THE MIMIC Bus.
c) DEPRESS SYNC POT ON.
D) CLOSE THE BREAKER E) DEPRESS THE SYNC POT OFF.
- 3) CLOSE CIRCUIT SWITCHES 1T60 AND 2T60,
- 4) CLOSE THE FOLLOWING 13KV BREAKERS TO ENERGIZE THE No. 11) 12) 21 AND 22 STATION TRANSFORMERS:
SALEM UNIT l/LJNIT 2 REV, 10
1-4.9
- 5) CLOSE THE FOLLOWING BREAKERS TO
- ENERGIZE THE 4KV GROUP BLISSES:
lH - llHSD lE - llESD lF - 12FSD 2H 2E 2F 21HSD
- 21ESD 22FSD lG - 12GSD 2G - 22GSD
. COORDINATE LOADING OF THE BLISSES WITH THE LOADING DISPATCHER,
"EMERGENCY POWER - DIESEL OPERATION",
CAUTION: IN THE EVENT ONE OF THE DIESEL HAS FAILED TO ENERGIZE ITS VITAL Bus) THAT VITAL Bus MUST BE RETURNED TO OFF-SI TE POWER FIRST IN ORDER TO MAINTAIN MINIMUM OPERABLE SAFEGUARDS EQUIPMENT, 4.17 IF THE GAS TURBINE GENERATOR WAS STARTED IN STEP 4.9) CONTINUE OPERATION UNTIL 5023 AND/OR 5024 AND/OR 5015 - 500KV LINES ARE ENERGIZED TO SALEM FROM NEW FREEDOM OR KEENEY, PROCEED AS FOLLOWS IN COORDINATION WITH THE LOAD DISPATCHER TO RESUME NORMAL STATION POWER:
4.17.1 VERIFY THAT 5023 AND/OR 5024 AND/OR 5015 500KV LINES ARE ENERGIZED, CAUTION: Two OFF-SITE POWER SUPPLIES 4.17.1 THE USE OF TWO LINES PREVENTS MUST BE AVAILABLE BEFORE SYN- THE GAS TURBINE FROM ATTEMPT-CHRONIZING #3 GENERATOR WITH ING TO SUPPLY A 500KV LINE THE 500KV INFEED LINES) SO THAT IF THE INFEED AT KEENEY OR VAR RATING OF THE #3 GENERATOR NEW FREEDOM OPENS UP, IS NOT EXCEEDED, 4.17.2 CHECK TH~TiT60 CIRCUIT SWITCH IS OPEN, 4.17,3 CLOSE 2160 CIRCUIT SWITCH TO ENERGIZE SODKV BUS SECTION 1.
4.17.4 CLOSE THE FOLLOWING BREAKERS FOR THE LINES WHICH ARE ENERGIZED TO ENERGIZE 500KV BUS SECTION 2.
5023 8 5024 6 5015 10 SALEM UNIT l/UNIT 2 REV' 10
. l-4. 9 CAUTION: WHILE No. 3 GENERATOR IS SYNCHRONIZED TO TWO 500KV LINES 5023 (OR 5024) (OR 5015) THE THREE BREAKERS ASSOCIATED AT NEW FREEDOM
- OR KEENEY WITH EACH LINE MUST BE CLOSED, VERIFY WITH LOAD DISPATCHER.
5023 - NEW F.REEDOM BREAKERS 20X, 21X, 22X.
5024 - NEW FREEDOM BREAKERS 30X, 31X, 32X.
5015 - KEENEY BREAKERS 503 OR 504 PROCEED AS FOLLOWS FOR EACH BREAKER:
A) DEPRESS THE LOCAL PUSHBUTTON.
B) SELECT THE DESIRED BREAKER ON THE MIMIC Bus c) DEPRESS SYN POT ON D) CLOSE THE BREAKER E) DEPRESS THE SYNC POT OFF 4.17.5 lF THE 5023 LINE IS NOT AVAILABLE, 4.17.5 THIS WILL ALLOW 500KV OPEN THE LINE DISCONNECT 21X5Q AND BREAKER 1-8 TO BE USED TO THEN CLOSE 500KV BREAKER 2-8 AS PARALLEL BUS SECTION 1 AND 2.
DESCRIBED IN STEP 4.17.4, 4.17.6 CLOSE 1T60 CIRCUIT SWITCH TO ENERGIZE 13KV Bus SECTION 1.
4.18 PARALLEL ACROSS AND CLOSE 500KV BREAKER 1-8 AS FOLLOWS:
4.18.1 SWITCH THE GAS TURBINE FROM ISOLATED 4.18.l THE GAS TURBINE MAY BE PRECISE TO PARALLEL CAUTION. GAS OPERATING IN EITHER LOCAL TURBINE FREQUENCY MAY DECREASE AT A OR REMOTE, AnJUSMENTS CAN RATE Of ~i CYCLE/5 SECONDS TO~ 57.5 BE MADE IN EITHER MODE.
HZ. To CORRECT, SELECT MANUAL ON THE GOVERNOR CONTROL AND RE-ADJUST THE FREQUENCY TO 60 HZ.
4*, 18 2 DEPRESS THE LOCAL PUSHBUTTON I I 4.18.3 DEPRESS BREAKER 1-8 ON THE MIMIC Bus .
- 4*,18.4 DEPRESS SYNC POT ON.
SALEM UNIT l/UNIT 2 REV I 10
I-4.9
- 4.18.5 OBSERVE THE SYNCHROSCOPE AND THE RUNNING AND INCOMING VOLTAGE METERS ON THE CONTROL CONSOLE, IF THE SYNCHROSCOPE IS NOT ROTATING SLOWLY IN THE FAST DIRECTION) SELECT MANUAL ON THE GOVERNOR CONTROL AND ADJUST 4.18.5 THE GAS TURBINE MAY BE OPERATING IN EITHER LOCAL OR REMOTE. ADJUSTMENTS CAN BE MADE IN EITHER MODE, THE GAS TURBINE SPEED AS NECESSARY, 4.18.6 WHEN THE SYNCHROSCOPE IS 1-2 MINUTES BEFORE THE VERTICLEJ CLOSE THE BREAKER, 4.18.7 DEPRESS THE SYNC POT OFF.
4.19 OPERATE THE GAS TURBINE AS DIRECTED BY THE LOAD DISPATCHER, 4.20 RETURN THE 4KV VITAL BUSES TO NO~MAL OPERATION IAW DI IV-16.3.lJ "EMERGENCY POWER - DIESEL OPERATION",
CAUTION: IN THE EVENT ONE OF THE DIESELS
.- FAILED TO ENERGIZE ITS VITAL BUSJ
~
THAT BUS MUST BE RETURNED TO OFFSITE POWER FIRST IN ORDER TO MAINTAIN MINIMUM SAFEGUARDS EQUIP-MENT, 4.21 As CONDITIONS DICTATE) OPERATE !AW ONE OF THE FOLLOWING Ol's:
4.21.1 DI I-3.8J "MAINTAINING Hor STANDBY" 4.21.2 DI I-3.3J "Hor STANDBY To MINIMUM LOAD"
- 4. 21. 3 DI I-3, 6J "Hor STANDBY ro CoLD SHUTDOWN" PREPARED BY _ _ __..J. . . __....BA.....l.. .,L....E.. ._y_ _ _ _ _' - - _
MANAGER - SALEM GENERATING STATION REVIEWED BY .I. ZupKO SORC MEETING No. DATE _ _ _ _ _ _ _ _ __
SALEM UNIT l/UNIT 2 REV I 10
I-4.9 TABLE I BLACKOUT LOADING SEQUENCE
- 11 (21) U2 (22) 13 (23)
DIESEL GENERATOR DIESEL GENERATOR DIESEL GENERATOR 240/480V Breaker 240/480V Breaker 240/480V Breaker 11(21) Component Cooling Pump 11(21) Charging Pump 12(22) Charging Pump 11(21) Auxiliary Feed Pump 12(22) Component Cooling Pump 13(23) Component Cooling Pump 15(21) Service Water Pump 12(22) Auxiliary Feed Pump 11(25) Service Water Pump or* or*
16(22) Service Water Pump 14(24) Service Water Pump 12(26) Service Water Pump or*
11(21) Auxiliary Building
- 13 (23) Service Water Pump Emergency Air Compressc Exhaust Fan 11(21) Reactor Shield Vent Fan 12(22) Auxiliary Building 11(21) Auxiliary Build-Supply Fan ing Supply Fan 11(21) Reactor Nozzle Support 12(22) Auxiliary Building 13(23) Auxiliary Build-Vent Fan Exhaust Fan ing Exhaust Fan 11 (21) Chiller 12(22) Reactor Shield Vent 13(23) Reactor Nozzle Fan Support Vent Fan 12(22) Reactor Nozzle Support 14(24) Reactor Nozzle Vent Fan Support Vent Fan 12(22) Chiller 13 (23) Chiller
, 11(21) Electrical Equipment Room 12(22) Electrical Equipment Room 13(23) Electrical Main Supply Fan Main Supply Fan Equipment Room Main Supply Fan
- NOTE: Only the lead Service Water Pump will start, if the lead pump fails to start the backup pump breaker will close .
- TABLE I Page l of l Salem Unit l/Salem Unit 2 Rev.IO
I-4.9 APPENDIX 1 1.0 PURPOSE 1.1 To PROVIDE THE INSTRUCTIONS NECESSARY TO PLACE THE PLANT IN A COLD SHUTDOWN CONDITION WHILE ON NATURAL CIRCULATION FOLLOWING A STATION BLACKOUT, 2.0 INITIAL CONDITIONS 2.1 THE UNIT IS BEING MAINTAINED IN Hor STANDBY CONDITION ON NATURAL CIRCULATION.
2.2 NORMAL CHARGING AND LETDOWN ARE ESTABLISHED.
2.3 PRESSURIZER HEATERS ARE ENERGIZED AND AVAILABLE TO MAINTAIN PRESSURIZER PRESSURE, 3.0 PRECAUTIONS 3.1 LIMIT THE COOLDOWN RATE TO ~20-25°F/HR.
3.2 HOLD TEMPERATURE AT ~350°F FOR AT LEAST FOUR HOURS TO ALLOW STORED HEAT IN THE REACTOR VESSEL HEAD TO DISSIPATE .
3.3 MAINTAIN RCS PRESSURE AS HIGH AS ALLOWED BY THE PRESSURE TEMPERATURE CURVE.
3.4 MAINTAIN RCS SUBCOOLING AT LEAST 50°F.
4.0 PROCEDURE COMMENTS 4.1 SAMPLE THE RCS TO DETERMINE BORON CONCENTRATION, SAMPLE THE FOLLOWING POINTS:
4.1.1 RCS HOT LEGS 4.1.2 LETDOWN LINE 4.1.3 PRESSURIZER LIQUID SPACE 4.2 BORATE THE RCS IAW OI-II-3.3.6) 4.2 REFER TO REACTOR ENGINEERING "BORON CONCENTRATtbN CONTROL." INCREASE MANUAL FIGURE 20A FOR THE COLD THE CONCENTRATION IN THE RCS HOT LEGS SHUTDOWN CONCENTRATION, AND LETDOWN LINE TO AT LEAST 100 PPM EXCESS BORATION OF THE ACTIVE GREATER THAN THAT REQUIRED TO ACHIEVE PORTIONS OF THE RCS IS REQUIRED COLD SHUTDOWN. SINCE THE PRESSURIZER CANNOT BE BORATED .
SALEM UNIT l/LiNIT 2 PAGE 1 OF 3
I-4,9 4.3 SET THE BLENDER UP FOR AUTO WITH A BORON CONCENTRATION EQUAL TO OR GREATER THAN THE CONCENTRATION ESTABLISHED ABOVE, 4,4 COMMENCE A CONTROLLED COOLDOWN OF THE RCS AS FOLLOWS:
4,4,l SLOWLY OPEN THE ATMOSPHERIC STEAM 4.4,l EITHER DECREASE THE AUTO SET-RELIEF VALVES, ll-14C21-24)MS10, POINTS OR PLACE THE VALVES IN MANUAL AND OPEN THEM, 4.4,2 ESTABLISH A COOLDOWN RATE OF < 25°F, 4,4,2 MONITOR THE CORE EXIT THERMO-CUPLES AND WIDE RANGE TH, 4,4,3 MAINTAIN PRESSURIZER PRESSURE AS HIGH A~ ALLOWABLE JAW THE PRESSURE-TEMPERATURE CURVE BY OPERATION OF THE PRESSURIZER HEATERS AND Aux1-LIARY SPARY VALVE, 1(2)CV75.
CAUTION NORMAL CHARGING AND LETDOWN MUST REMAIN IN OPERATION WHEN USING AUXILIARY SPRAY, 4.4.4 REFER TO OI I-3,6, "HoT STANDBY TO 4,4,4 SOME SYSTEMS MAY NOT BE COLD SHUTDOWN" FOR GUIDANCE IN AVAILABLE DUE TO LOSS OF POWER.
THE OPERATION OF SUPPORT SYSTEMS DURING THE COOLDOWN, 4.4.5 WHEN RCS TEMPERATURE REACHES ~350°F.
TERMINATE THE COOLDOWN AND STABILIZE THE PLANT, 4,4,6 MAINTAIN THE PLANT AT ~350°F WITH 4.4,6 ALLOW ALL PORTIONS OF THE PRESSURE AS HIGH AS ALLOWABLE FOR RCS TO SOAK AND EQUALIZE AT LEAST FOUR HOURS, TEMPERATURES, 4,4,7 AFTER THE FOUR HOUR SOAK, REDUCE RCS PRESSURE SLOWLY USING THE AUXILIARY SPRAY VALVE, 1(2)CV75 .
- U\~uu UU\Ju WuuUl) u.,
11 .~, u U*-'uu u ~
- \JI IWUULb LJ SALEM UNIT l/UNIT 2 PAGE 2 OF 3 REV, 10
I-4.9
- 4.4.8 CLOSELY MONITOR PRESSURIZER LEVEL. IF 4.4.8 RAPID CHANGES IN PRESSURIZER UNEXPLAINED FLUCTUATIONS ARE EXPERIENCED LEVEL INDICATE VOIDING IN THE TERMINATE THE DEPRESSURIZATION AND RCS, PROBABLY IN THE HEAD AREA.
REPRESSURIZE THE RCS TO THE ORIGINAL VALUE, MAINTAIN THAT PRESSURE FOR AT LEAST AN ADDITIONAL TWO HOURS BEFORE ATTEMPTING TO DEPRESSURIZE AGAIN.
4.4,9 PLACE THE RESIDUAL HEAT REMOVAL SYSTEM IN OPERATION IAW OJ II-6.3.2, "INITIATING RESIDUAL HEAT REMOVAL,"
4,4.10 (ONTINUE THE COOLDOW~ TO COLD SHUTDOWN CONDITIONS, SALEM UNIT l/UNIT 2 PAGE 3 OF 3 REV. 10
I-4.12 EMERGENCY INSTRUCTION I-4.12 LOSS OF FEEDWATER 1.0 PURPOSE 1.1 This instruction describes the actions required to stabilize the plant following a partial or complete loss of feedwater flow.
1.2 A loss of feedwater flow mayoe caused by any of the following:
1.2.l Loss of Main Feed Pump(s) l.2.2 Loss of Condensa~e Pumpisl 1.2.3 Loss of.-Heater Drain Pump(s) 1.2.~ Malfunction of a feedwater control valve l.2.5 Malfunction of the Condensate Polishing System 1.2.6 Feed or Condensate System leak or rupture upstream of the Feedwater Header Isolation Valves, 11-14 (21-24)BF22 .
- 1.3 1.4 A Feedwater System leak or rupture downstream of the Feedwater Header Isolation Valves, ll-14(21-24)BF22 is treated as a loss of secondary coolant in EI I-4.6.
The primary consideration on a partial loss of flow is the reduction of steam flow to less than the available feedwater flow to avoid a reactor trip if possible.
2.0 INITIAL CONDITIONS Steam flow and/or feed flow deviation alarms (F s > F w and/or F w > F s l on one or more 2.1 Steam Generators.
2.2 Erratic Steam Generator level indication.
2.3 Stearn Generator level deviation alarm.
2.4 Low Feedwater header pressure.
2.5 Main Feed Pump trip.
2.6 Condensate Pump trip.
2.7 Heater D~ain Pump trip.
2.8 Condensate Polishing System Trouble Alarm.
Rev. 3 Salem Unit l/Unit 2
I-4.12 IMMEDIATE ACTIONS 3.1 Automatic 3.1.1 Feedwater Heater Bypass Valve 1(2)CN47 opens when the pressure at the suction of the Main Feed Pumps decreases to 265 psig.
3.1.2 Main Feed Pumps trip at 215 psig decreasing suction pressure. This will result in No. 11 & 12(21 & 22) Auxiliary Feedwater Pumps starting. As Steam Generator levels decrease, a Reactor Trip will occur as a result of one of the following:
a) Steam Flow > Feed Flow in coindidence with Low Level, or b) Low-Low Steam Generator Level.
3.2 Manual 3.2.1 Reduce steam flow to a value less than the existing feedwater flow.
3.2.2 Place feedwater control in MANUAL for the affected Steam Generators and attempt to stabilize the levels, if necessary.
3.2.3 If a feed line rupture is indicated, proceed as follows:
a) Trip both Main Feed Pumps from the control console bezel for each pump.
b) Close ll-14(21-24)BF13 c) Initiate a manual Reactor Trip and refer to EI I-4.3, "Reactor Trip".
d) Verify 11 & 12(21 & 22) Auxiliary Feedwater Pumps have started. Start them if necessary.
4.0 SUBSEQUENT ACTIONS COMMENTS 4.1 If both Main Feed Pumps have tripped, insure 4.1 Flow is required to at least No. 11 & 12(21 & 22) Auxiliary Feedwater two Steam Generators.
Pumps have started and are delivering flow to the Steam Generators by check-ing the Auxiliary Feedwater Flow Inidicators on the control console.
4.1.1 If flow has not been established, proceed as.follows:
- 1) Check the Discharge pressure on the Motor Driven Auxiliary Feed-water Pumps (11 & 12, 21 & 22) which are running. It should be >1350lt.
- 2) If the pressure is <1350#, 2) This will remove the pump run-depress the PRESS OVERRIDE DEFEAT out protection.
S~le~ Unit l(Vnit 2 :Rev. 3
I-4.12
- 2) If the pressure is <1350j, 2) This will remove the pump run-depress the PRESS OVERRIDE out protection.
DEFEAT pushbutton on the console bezel for each Auxiliary Feed- The discharge pressure trans-water pump with a low pressure. mitter may be failed low pre-venting the discharge valves from opening.
- 3) If the pressure is >1350# check .the 3) A failure in the pump runout valve demand set at ~95% for 11-14 *protection circuitry may pre-(21-24)AF21 on the console bezel. vent the discharge valves.from Also, depress the PRESS OVERRIDE opening. No. 11(21) F~eds No.
bEFEAT--pushbutton on the console 13 & 14(23 & 24) Steam Genera-for each Auxiliary Feedwater tors.
Pump, for which there is no flow. No. 12(22~ Feeds No. 11 & 12 (21 & 22) Steam Generators.
- 4) If excessive flow is indicated to one or more Steam Generator, re-establish the pump runout protection by depressing the PRESS OVERRIDE NORMAL pushbutton on the console for the affected Auxiliary Feedwater Pump(s).
Proceed to EI I-4.6, "Loss of Secondary Coolant".
- 5) Start, if not already running, No. 13 (23) Auxiliary Feedwater Pump and verify ll-14(21-24)AF11 are open.
CAUTION: If the Level in any The feed ring drains slowly Steam Generator has been <10% through the loose fit connec-in the Narrow Range from more tion to the fe.ed inlet piping.
than 5 minutes and all feedwater has been isolated to that Steam If conditions require maximum Generator f.or more than 5 minutes, flow for decay heat removal 5 considerations, this takes flow must be limited to <l x 10 lbm/hr to that Steam Generator precedence over the water until the level is returned to hammer considerations.
>10% in the Narrow Range.
4.2 'If the loss of feedwater flow is due to 4.2 Power can be returned to full a malfunction of the Steam Generator load.
Water Level Control System, maintain the feedwater flow control in MANUAL until necessary repairs can be made.
Salem Unit l/Unit 2 Rev. 3
4.3 Feed Pump <55%
I-4.12 4.3 If the loss of flow is due to a loss of a Main Feed Pump, Condensate Pump Condensate Pump <70%
or Heater Drain Pump, maintain the Heater Drain Pump <85%
power level consistent with the avail-able feedwater flow.
4.4 If the loss of flow is due to a Condensate 4.4 Power can be returned to full Polishi_ng System malfunction, bypass the load.
Condensate Polishing System as follows:
4.4.1 Open ll-13(21-23)CN108, Condensate Polishing System Bypass Valves.
4.4.2 Close 1(2)CN109, Condensate Polishi~g System Inlet Valve 4.4.3 Notify the Performance Department 4.4.3 Operation with the Condensate that the Condensate Polishing Unit Unit bypassed should be is bypassed. minimized.
Prepared by~~~-J_a~y;;...._Ba~_i_l_e~y~~~~~~~- ~
Manager - Salem Generating Station Reviewed by~~~-Chr.:;;;.;=..::i~s:.......::Co~nn~o~r=--~~~~~~~
SORC Meeting No.~8_0_-_1~7~~~~~~~~~~~
Date _ _ _,,~~0,c....;.A.;....~/
....../f._c_-_ __
Rev. 3 Salem Unit l/Unit 2 I-4.15
- 1.0 PURPOSE EMERGENCY INSTRUCTION 1-4.15 LOSS OF COMPONENT COOLING 1.1 THIS INSTRUCITON PROVIDES GUIDELINES FOR PLANT OPERATION DURING AND FOLLOWING A FAILURE IN THE COMPONENT COOLING SYSTEM, EITHER DUE TO A LOSS OF FLOW, A PIPE RUPTURE, OR IN-LEAKAGE FROM ANOTHER SYSTEM, 1.2 SINCE THE COMPONENT COOLING SYSTEM IS AN ENGINEERED SAFEGUARDS SYSTEM AND IS ESSENTIAL TO ALL PHASES OF PLANT OPERATION, THIS INSTRUCTION DEALS WITH THE NECESSARY COURSE OF ACTION TO BE TAKEN TO PLACE THE PLANT IN A SAFE CONDITION JAW TECHNICAL SPECIFICATION 3,7,3,l, 2.0 INITIAL CONDITIONS .
2.1 THE FOLLOWING WOULD BE INDICATIVE OF OUT-LEAKAGE FROM THE COMPONENT COOLING SYSTEM:
2.1.1 DECREASING CCW HEADER PRESSURE, 2.1.2 INCREASING PUMP AMPS ON THE RUNNING CCW PUMPS.
2.1.3 DECREASING COMPONENT COOLING SURGE TANK LEVEL, 2.2 INCREASING TEMPERATURES ON COMPONENTS SUPPLIED CCW IS INDICATIVE OF A DECREASE IN FLOW DUE TO A FLOW OBSTRUCTION, FOULING OF HEAT EXCHANGER TUBES, RUPTURE UPSTREAM GF THE COMPONENT, OR A LOSS OF PUMPS, 2.3 THE FOLLOWING WOULD BE INDICATIVE OF INLEAKAGE TO THE CCW SYSTEM:
2.3,l INCREASING ACTIVITY LEVEL ON EITHER HEADER, 2.3,2 INCREASING COMPONENT COOLING SURGE TANK LEVEL, 3.0 IMMEDIATE ACTIONS 3.1 AUTOMATIC 3.1.1 THE CW SURGE TANK VENT VALVE 1(2)CC149, WILL CLOSE ON HIGH ACTIVITY ON EITHER RMS CHANNEL Rl7A OR Rl7B.
3.1.2 THE STANDBY COMPONENT COOLING WATER PUMP WILL START AT 70 PSIG, IF IN AUTO, 4.0 SUBSEQUENT ACTIONS COMMENTS 4,1 lF A LOSS OF FLOW TO AN INDIVIDUAL COMPONENT IS INDICATED, PROCEED AS FOLLOWS:
SALEM UNIT l/UNIT 2 REv. 5
1-4.15 4.1.1 VERIFY ANY AUTOMATIC FLOW CONTROL 4,1,l LETDOWN HEAT EXCHANGER, WASTE VALVES ASSOCIATED WITH THE AFFECTED EVAPORATOR) BORIC ACID EVAP-EQUIPMENT ARE FUNCTIONING PROPERLY, ORATOR.
TAKE MANUAL CONTROL IF NECESSARY TO CONTROL TEMPERATURES, 4.1.2 PLACE REDUNDANT EQUIPMENT IN SERVICE WHERE AVAILABLE AND REMOVE THE AFFECTED EQUIPMENT FROM SERVICE IN ACCORDANCE NQIE: IF THE LETDOWN HEAT EXCHANGER
. IS ISOLATED) CHARGING MUST ALSO BE SECURED, 4.1,3 REFER TO THE TECH SPECS FOR ANY EQUIP- 4.1.3 TECH SPEC 3.1.2.1, 3.1.2.2)
MENT REMOVED FROM AN OPERABLE STATUS 3.1.2.3J 3.1.2.4, 3.4.1.l, AND COMPLY WITH ALL REQUIREMENTS OF 3.5.2J 3,5,3, OR 3,9,8, THAT TECH SPEC SECT ION I
- 4.2 IF A REDUCTION IN FLOW IS INDICATED DUE TO 4.2 AT LEAST ONE PUMP IS STILL IN A LOSS OF ONE OR TWO COMPONENT COOLING PUMPS SERVICE, PROCEED AS FOLLOWS:
-- 4,2,1 ATTEMPT TO START ADDITIONAL COMPONENT COOLING PUMPS IAW DI II-7.3.2J "COM-PONENT COOLING SYSTEM - NORMAL OPERA-TION",
4,2,2 IF ADDITIONAL-PUMPS CANNOT BE STARTED) 4,2,2 PROCEED UNTIL PRESS: ~E CAN BE ISOLATE SYSTEMS OR COMPONENTS IN THE MAINTAINED ON THE SAFEGUARDS FOLLOWING ORDER TO MAINTAIN FLOW TO HEADERS AND ALL COMPONENT THE SAFEGUARDS HEADERS, CLOSE MANUAL ISOLATION
- 1. WASTE EVAPORATOR IAW DI Il-11.3.3) VALVES AS REQUIRED, "WASTE EVAPORATOR - NORMAL DPERAT ION" I INSURE THE VALVE DEVIATION
- 2. BORIC ACID EVAPORATOR IAW DI II-3.3.17, LIST IS UPDATED AS REQUIRED, "BoRrc Acrn EVAPORATOR - NORMAL OPERATION",
- 3. EXCESS LETDOWN !AW 01 11-3.3.3)
"EXCESS LETDOWN FLOW",
4, SECURE CHARGING AND LETDOWN JAW 4, Do NOT SECURE SEAL INJECTION.
01 Il-3,3,3J "ExCESS LETDOWN PRESSURIZER LEVEL SHOULD BE fLOW"J AND ISOLATE THE LETDOWN INCREASING UNDER THE INFLUENCE HEAT EXCHANGER BY TAKING MANUAL OF SEAL INJECTION, CONTROL OF 1(2)CC71 AND CLOSING THE VALVE, SALEM UNIT l/UNIT 2 ~
r\n~I u.ulb EV, 1
1-4.15 5, IF FLOW CANNOT BE MAINTAINED TO THE SAFEGUARDS HEADERS AND THE REMAINING EQUIPMENT, IT WILL BE REQUIRED TO PLACE THE UNIT IN COLD SHUTDOWN. PROCEED IAW THE FOLLOWING Ol's AS APPLICABLE:
1-3.4, "POWER OPERATION" 1-3.5, "MINIMUM LOAD To Hor STANDBY" 1-3.6, "Hor STANDBY TO COLD SHUTDOWN" 4.3 IF A TOTAL LOSS OF FLOW IS INDICATED AND NO COMPONENT COOLING PUMPS CAN BE STARTED, PROCEED AS FOLLOWS:
4,3,l MANUALLY TRIP *THE REACTOR BY THE USE OF EITHER MANUAL TRIP HANDLE ON THE CONTROL CONSOLE AND BEFER "ro EI 1-4. 3 "REACTOR TRIP".
4,3,2 WITHIN FIVE MINUTES TRIP ALL REACTOR COOLANT PUMPS, OR IF ANY MOTOR BEARING TEMPERATURE EXCEEDS 175°F.
4.3.3 VERIFY DECAY HEAT IS BEING REMOVED 4,3.3. lT MAY TAKE SEVERAL MINUTES BY NATURAL CIRCULATION AS FOLLOWS: TO ESTABLISH NATURAL CIRCU-LATION DUE TO INCREASED LOOP TRANSIT TIME,
- 1. REACTOR CooLANT Loop ~T <62°F ON ONE OR MORE LOOP,
- 3. STEAM GENERATOR PRESSURE IS
~1000 PSIG FOR ALL STEAM GEN-ERATORS FOR WHICH LOOP ~T IS
<62°F I
- 4.3.4 SECURE CHARGING AND LETDOWN IAW 4.3.4 Do NOT SECURE SEAL INJECTION.
01 11-3.3.3, "EXCESS LETDOWN FLOW". PRESSURIZER LEVEL SHOULD BE INCREASING UNDER THE INFLUENCE OF SEAL INJECTION,
- REV' 5 SALEM UNIT l/UNIT 2
1-4.lL., -----
4,3,5 SECURE THE FOLLOWING SYSTEMS IF THEY ARE IN OPERATION:
- 1. BORIC ACID EVAPORATOR IAW 01 11-3.3.17, "BoRIC Acrn EVAP-ORATOR - NoR~AL OPERATION",
- 2. WASTE EVAPORATOR IAW 01 11-11.3.3, "WASTE EVAPORATOR -
NORMAL OPERATION""'*
- 3. EXCESS LETDOWN IAW 01 11-3.3.3, "EXCESS LETDOWN FLOW".
4, WASTE GAS COMPRESSORS, 4,3,6 ESTABLiSH OR MAINTAIN TH; FOLLOWING CONDITIONS TO ENSURE MAXIMUM NATURAL CIRCULATION IS MAINTAINED IN THE REACTOR COOLANT SYSTEM FOR DECAY HEAT REMOVAL, l, REACTOR COOLANT PRESSURE ~
2000 PSIG,
- 2. STEAM GENERATOR LEVEL ;:_10% IN THE NARROW RANGE ON AT LEAST ONE STEAM GENERATOR, AND IF POSSIBLE ALL FOUR, 3, PRESSURIZER LEVEL >17%. lF . 3. LEVEL SHOULD BE SLOWLY IN-IT IS NECESSARY TO RAISE PRESS- CREASING UNDER THE INFLUENCE URIZER LEVEL, OPEN THE BORON OF SEAL INJECTION, 1(2)CV55 INJECTION TANK BYPASS VALVE, WILL PASS MINIMUM FLOW, 1(2)SJ71, OR INCREASE SEAL INJECTION FLOW TO 13 GPM PER PUMP.
4.3.7 MAINTAIN
. . STEAM GENERATOR PRESSURE
. . BY 4.3.7 fOR CONDITIONS WHERE A HIGH ADJUSTI'NG THE SETPOl'NT FOR THE ATMOS- DEGREE OF DECAY HEAT IS PHERE STEAM RELIEF VALVES, MS-lO's PRESENT THE ~T INDICATED OR STEAM D~~~ 7 PRi~iuRE Co~~Ro~~ER WILL APPROACH THE FULL TO_MAINTAlN THE J..m1ER. OF FOLLOWING LOAD ~T. SINCE THE STEAM CONDI.TIONS: GENERATOR PRESSURE IS INDI-CATIVE OF Tc CONDITIONS,
- 1. STEAM PREssuRE ~looo PsIG oR, TH MAY BE AS HIGH AS ~610°F FOR A STEAM GENERATOR PRESSURE
- 2. INCORE THERMOCOUPLE TEMPERATURES OF 1000 PSIG. THEREFORE, A
< 600°f, ~>>-,lfft!Tr IN STEAM GENERATOR
~§'MM MAY BE REQUIRED I SALEM UNIT l/UNIT 2 -lj- REV. 5
1-4 .-i-s- ------
4,3,8 IF ADJUSTMENTS IN STEAM GENERATOR 4,3,8 RESPONSES IN TEMPERATURE ARE PRESSURE ARE REQUIRED, MAKE THE SEEN SLOWLY DUE TO LONG ADJUSTMENTS SLOWLY, LOOP TRANSIT TIMES. Loop TRANSIT TIMES MAY BE 10 MIN OR MORE, 4.3.9 REFER TO THE PRESSURE-TEMPERATURE 4,3.9 SAMPLE CALCULATION:
CURVE TO CALCULATE THE STEAM PRESSURE ~T IS 62°f, STEAM PRESSURE REQUIRED TO MAINTAIN THE DESIRED 1000#, Tc 1s 547; so TH 1s REACTOR COOLANT TEMPERATURE. 609°F.
To REDUCE TH BY l0°F, Tc MUST BE REDUCED BY 10°f, SINCE ~T IS CONSTANT, REDUCE STEAM GENERATOR PRES-SURE TO ~950 PSIG.
4.3.10 MAINTAI°N THE UNIT IN Hor STANDBY 4,3,10 Jr IS PREFERRED TO REMAIN IN UNTIL COMPONENT COOLING IS RETURNED TO Hor STANDBY.
SERVICE, lF NECESSARY, PLACE THE PLANT IN COLD SHUTDOWN AS DIRECTED BY APPENDIX 1.
... 4,4 IF LEAKAGE FROM THE COMPONENT COOLING SYSTEM IS INDICATED BY A DECREASING SURGE TANK LEVEL, PROCEED AS FOLLOWS:
CAUTION: ANY LEAKAGE FROM THE COMPONENT 4,4 INSURE THE VALVE DEVIATION LIST IS UPDATED AS REQUIRED, COOLING SYSTEM WILL BE COLLECTED IN THE JN-SERVI CE WASTE HOLDUP .
TANK, SINCE THIS WATER CONTAINS CHROMATES, IT CANNOT BE DISCHARGED DIRECTLY TO THE RIVER, WHEN ALL LEAKAGE HAS BEEN COLLECTED, THE WASTE HOLDUP TANK MUST BE REMOVED FROM SERVICE AND AN ALTERNATE METHOD OF DISPOSAL WILL BE REQUIRED, 4.4.1 INITIATE MAKEUP TO THE SURGE TANK AS FOLLOWS AND RETURN THE LEVEL TO NORMAL,.
- 1. UNIT 1 - OPEN 1CC145 FROM THE l, MANUAL VALVES, PRIMARY WATER SYSTEM OR 1CC146 FROM THE DEMINERALIZED WATER SYSTEM,
- 2. UNIT 2 - OPEN 2DR107 FROM 2. REMOTE OPERATED VALVE, DEMINERALIZED WATER SYSTEM FROM THE CONTROL CONSOLE, SALEM UNIT l/UNIT 2
1-4.15 IF DM WATER IS UNAVAILABLE, OPEN 2, MANUAL VALVE, 2CC145 FROM THE PRIMARY WATER SYSTEM.
4.4.2 LOCATE AND ISOLATE THE LEAK AS QUICKLY AS POSSIBLE, 4.4.3 lF THE LEAK IS ON ONE OF THE SAFE-GUARDS HEADERS, RETURN THE INOPERABLE LOOP TO AN OPERABLE STATUS WITHIN THE TIME ALLOWED BY TECH SPEC 3.7.3.1 OR PROCEED TO COLD SHUTDOWN IAW THE FOLLOWING INSTRUCTIONS:
01 1-3.4, "Po~ER OPERATION" 01 1-3.S, "MINIMUM LoAD To Hor STANDBY" 01 1-3.6, "Hor STANDBY TO COLD SHUTDOWN" 4.4.4 CLOSELY MONITOR ALL RUNNING CCW. PUMPS FOR CAVITATION (ABNORMAL FLUCTUATIONS IN PUMP AMPS AND DISCHARGE PRESSURE),
AND THE SURGE TANK LEVEL. IF .CAVITA-TION IS INDICATED, OR THE SURGE TANK LEVEL DECREASES TO 0%, PROCEED AS FOLLOWS:
l, TRIP ALL CCW PUMPS,
- 2. REFER TO STEP 4.3 OF THIS 2. NATURAL CIRCULATION INSTRUCTION I 4.4.5 IF THE LEAK IS ON THE NaN-SAFEGUARDS HEADER, PROCEED AS FOLLOWS:
- 1. IF THE ENTIRE HEADER IS ISOLATED 1. NATURAL CIRCULATION, REFER TO STEP 4.3 OF THIS INSTRUC-TION,
- 2. IF FLOW IS ISOLATED TO THE REACTOR 2. COMPLETE ONLY THE PORTiONS COOLANT PUMPS REFER TO STEP 4.3 OF OF 4.3.4 AND 4.3.5 FOR WHICH THIS INSTRUCTION, THE AFFECTED COMPONENT IS ISOLATED,
- 4. 5 lF I NLEAKAGE TO THE COMPONENT Coo LI NG SYSTEM 4,5 INSURE THE VALVE DEVIATION IS INDICATED
.. . BY . AN INCREASE IN THE SURGE TANK LIST IS UPDATED AS REQUIRED, LEVEL, PROCEED AS FOLLOWS:
NQIE: ISOLATE ONE COMPONENT AT A TIME AND ALLOW
. SUFFICIENT
. TIME FOR THE SYSTEM TO STABILIZE. RETURN EACH COMPONENT TO SERVICE BEFORE PROCEEDING, REV. 5 SALEM UNIT l/UNIT 2
~----_-**
1-4.15 4,5,l IF SURGE TANK LEVEL IS INCREASING WITH NO INCREASE IN ACTIVITY ON 1(2)Rl7A OR B, PROCEED AS FOLLOWS:
- 1. ISOLATE MAKEUP FROM DEMINERALIZED WATER BY CLOSING 1(2)DR10 AND 1<2)CC146.
- 2. ISOLATE MAKEUP FROM PRIMARY WATER BY CLOSING 1(2)WR14 AND 1(2)CC145,
- 3. I so LATE THE CoMPONENT Coou NG HEAT EXCHANGERS AS FOLLOWS:
A.
- VERIFY 1(2)CC30 AND 1(2)CC31 A, CROSS CONNECTS TO SUPPLY NoN-OPEN, SAFEGUARDS HEADER, B. CLOSE 11(2l)SW122 *To ISOLATE B. CONTROL SWITCH BY HEAT EXCHANG-SERVICE WATER TO 11(21) COM- ERS.
PONENT COOLING HEAT EXHANGER.
C, CLOSE 12(22)SW122 TO ISOLATE SERVICE WATER TO 12(22) COM-PONENT COOLING HEAT EXCHANGER, D, WHEN THE FAULTY HEAT EXCHANGER D. MANUAL VALVE, IS IDENTIFIED, CLOSE THE APPRO-PRIATE COMPONENT COOLING INLET AND OUTLET ISOLATION VALVE, CC6 AND CC8.
4.5.2 IF THE SURGE TANK LEVEL IS INCREASING WITH AN INCREASE IN ACTIVITY ON 1(2)
Rl7A OR B, PROCEED AS FOLLOWS:
- 1. IF THE HI ALARM IS REACHED ON 1. AUTOMATIC EITHER 1(2)Rl7A OR B, VERIFY THE SURGE TANK VENT, 1(2)CC149 IS CLOSED,
- 2. ISOLATE No, 11<21) RHR HEAT Ex- 2. TECH SPEC 3.5.2 OR 3.5.3.
CHANGER.
A. VERIFY No. 12<22) RHR PUMP OR A. TECH SPEC 3.4.1.1 AT LEAST ONE RCP IS IN OPERATION .
- B. STOP No. 11(21)
SALEM UNIT l/UNIT 2 REV I 5
I-4 ,15 * ----
- c. CLOSE 11(2l)RH14, 11<2l)RH17 c. CLOSING 11(2l)CC11 ISOLATES 11C2l)RH18, 11C2l)CC11, 11(21) COOLING TO ll(Ll) RHR PUMP CC16. SEAL,
- 3. IsoLATE No. 12(22) RHR HEAT Ex- 3. TECH SPEC 3.5.2 OR 3.5.3.
CHANGER A. VERIFY No. 11(21) RHR PUMP OR A. TECH SPEC 3.4.1.1 AT LEAST ONE RCP IS IN OPERA-TION.
B. SroP No. 12(22) RHR PUMP.
- c. CLOSE 12(22)RH14, 12C22)RH17, C, *CLOSE 12(22)CC11 ISOLATES 12C22)RH18, 12(22)CC11, 12C22) COOLING TO 12(22) RHR PUMP "CC16 I SEAL.
- 4. ISOLATE THE EXCESS LETDOWN HEAT EXCHANGER, A, SECURE EXCESS LETDOWN IF IN OPERATION IAW DI II-3.3.3, "EXCESS LETDOWN FLOW".
B, CHECK CLOSED 1(2)CV278, 1(2)
CV131, 1C2)CV132, 1(2)CC113, 1<2)CC215.
- 5. ISOLATE THE LETDOWN HEAT EXCHANGER 5. Do NOT ISOLATE SEAL INJECTION.
A. SECURE CHARGING AND LETDOWN IAW DI II-3.3.1, "ESTABLISHING CHARG-ING, LETDOWN AND SEAL INJECTION",
B. CLOSE 1(2)CC66 AND 1(2)CC72.
6, ISOLATE iNDIVIDUAL REACTOR COOLANT 6. RCP CAN OPERATE WITH Nb ccw PUMP THERMAL BARRIER FLOWS, TO THERMAL BARRIER IF SEAL INJECTION IS MAINTAINED, A. CLQSE ll-14(21-24)CC13D ONE AT A, I SOLA TES THERMAL BARR I ER A TIME UNTIL THE FAULTY PUMP IS RETURN, IDENTIFIED, B, REOPEN ll-14(21-24)CC13D FOR UN-AFFECTED PUMPS,
~@lm ~OOJlQJ~llilklrn]!Nl mn~w I
- c. PROCEED TO Hor STANDBY IAW DI l-3,4, "POWER OPERATION" AND DI 1-3. 5, "MINIMUM LOAD TO Hor STANBY",
SALEM UNIT l/UNIT 2 REV. 5
1-4.15 D, STOP TH E AFFECTED RCP IS <10%. WHEN POWER PREPARED ~y ~~~j~*c......Q.B~A~IL!EiY~~~
MANAGER - SALEM GENERATING STATION.
REVIEWED BY _~~~J~,~Z~U~P~KO~~~~~~-* --
SORC MEETING No. DATE - - - -
1-4.15
~ APPENDIX 1 1.0 PURPOSE 1.1 To PROVIDE THE INSTRUCTIONS NECESSARY TO PLACE THE PLANT IN A COLD SHUTDOWN CONDITION WHILE ON NATURAL CIRCULATION AS A RESULT OF LOSS OF FORCED FLOW DUE TO A LOSS OF COMPONENT COOLING, 2.0 INITIAL CONDITIONS 2.1 THE UNIT IS BEING MAINTAINED IN Hor STANDBY CONDITION ON NATURAL CIRCULATION.
2.2 NORMAL CHARGING AND LETDOWN WILL BE SECURED IF THE NON-SAFEGUARDS HEADER IS ISOLATED, 2.3 PRESSURIZER HEATERS ARE ENERGIZED AND AVAILABLE TO MAINTAIN PRESSURIZER PRESSURE.
3.0 PRECAUTIONS 3.1 LIMIT THE COOLDOWN RATE TO ~20-25°F/HR, 3.2 HOLD TEMPERATURE AT ~350°F FOR AT LEAST FOUR HOURS TO ALLOW STORED HEAT IN THE REACTOR VESSEL HEAD TO DISSIPATE, 3.3 MAINTAIN RCS PRESSURE AS HIGH AS ALLOWED BY THE PRESSURE-TEMPERATURE CURVE.
3.4 MAINTAIN RCS SUBCOOLING AT LEAST 50°F.
4.0 PROCEDURE COMMENTS 4.1 SAMPLE THE RCS TO DETERMINE BORON CONCENTRATION. SAMPLE THE FOLLOWING POINTS:
4.1.1 RCS HOT LEGS 4.1.2 LETDOWN LINE 4.1.3 PRESSURIZER LIQUID SPACE 4.2 BORATE THE RCS IAW 01-11-3.3.6, 4.2 REFER TO REACTOR ENGINEERING "BORON CONCENTRATION CONTROL." INCREASE MANUAL FIGURE 20A FOR THE (OLD HE CONCENTRATION IN THE RCS HOT LEGS SHUTDOWN CONCENTRATION, AND LETDOWN LINE TO AT LEAST 100 PPM EXCESS BORATION OF THE ACTIVE GREATER THAN THAT REQUIRED TO ACHIEVE PORTIONS OF THE RCS IS REQUIRED COLD SHUTDOWN. SINCE THE PRESSURIZER CANNOT. BE BORATED.
SALEM UNIT l/UNIT 2 PAGE 1 OF 3 REV. 5
I-4.15 4.3 SET THE BLENDER UP FOR AUTO WITH A BORON CONCENTRATION EQUAL TO OR GREATER THAN THE CONCENTRATION ESTABLISHED ABOVE.
4.4 COMMENCE A CONTROLLED COOLDOWN OF THE RCS AS FOLLOWS:
4.4.1 DUMP STEAM FROM ALL FOUR STEAM GENERATORS BY ONE OF < THE FOLLOWING:
A. SLOWLY OPEN THE ATMOSPHERIC A. EITHER DECREASE THE AUTO SETPOINT STEAM RELIEF VALVES, 11-14 OR PLACE THE VALVES IN MANUAL AND
<21-24) MSlO. OPEN THEM.
B. SLOWLY OPEN THE STEAM DUMP B. EITHER DECREASE THE AUTO SETPOINT VALVES. OR PLACE THE STEAM PRESSURE CON-TROLLER IN MANUAL AND OPEN THE VALVES.
4.4.2 ESTABLISH A COOLDOWN RATE OF < 25°F, 4,4,2 MONITOR THE CORE EXIT THERMO-MAINTAIN THE CONTROL ROD DRIVE COOLING CUPLES AND WIDE RANGE TH.
FANS IN OPERATION, IF POSSIBLE. CONTROL ROD DRIVE COOLING FANS WILL HELP COOL THE REACTOR VESSEL HEAD, 4,4,3 MAINTAIN PRESSURIZER PRESSURE AS HIGH 4-:-4~3-NeRMAL_S_PRAY IS NOT AVAILABLE.
AS ALLOWABLE !AW THE PRESSURE-TEMPERATURE (URVE BY OPERATION OF THE PRESSURIZER USE AUXILIARY SPRAY IF AVAIL-HEATERS AND EITHER OF THE FOLLOWING: ABLE.
A. CYCLE ONE POWER OPERATED RELIEF VALVE, 1(2) PR 1 OR 2, IF AUXILIARY SPRAY IS NOT AVAILABLE, OR, B. CYCLE THE AUXILIARY SPRAY VALVE, 1(2) CV 75, IF NORMAL CHARGING AND LETDOWN ARE IN OPERATION, CAUTION NORMAL CHARGING AND LETDOWN MUST REMAIN IN OPERATION WHEN USING AUXILIARY SPRAY.
4.4.4 REFER TO DI l-3.6, "HoT STANDBY TO 4.4.4 SOME SYSTEMS MAY NOT BE (OLD SHUTDOWN" FOR GUIDANCE IN AVAILABLE DUE TO LOSS OF THE OPERATION OF SUPPORT SYSTEMS COMPONENT COOLING, DURING THE COOLDOWN, SALEM UNIT l/UNIT 2
1-4.15 4.4.5 WHEN RCS TEMPERATURE REACHES ~350°F
- 4,4,6 TERMINATE THE COOLDOWN AND STABILIZE THE PLANT, MAINTAIN THE PLANT AT ~350°F WITH PRESSURE.AS HIGH AS ALLOWABLE FOR 4,4,6 ALLOW ALL PORTIONS OF THE RCS TO SOAK AND EQUALIZE AT LEAST FOUR HOURS, TEMPERATURES, 4,4,7 AFTER THE FOUR HOUR S'QAK, REDUCE RCS 4,4,7 NORMAL SPRAY IS NOT AVAILABLE, PRESSURE SLOWLY USING ONE OF THE FOLLOWING: USE AUXILIARY SPRAY IF AVAIL-ABLE I A. CYCLE ONE POWER OPERATED RELIEF VALVE, 1(2)PR1 OR 2, IF AUXILIARY SPRAY IS NOT AVAILABLE, OR, B. CYCLE THE 'AUXILIARY SPRAY VALVE~
1(2)CV75, IF NORMAL CHARGING AND LETDOWN ARE IN OPERATION, CAUTION NORMAL CHARGING AND LETDOWN MUST 1--------~R~E;M~A~IN~_IN OPERATION WHEN USING A~ILIA~-~MYT,--------------------------
4,4,8 CLOSELY MONITOR PRESSURIZER LEVEL, IF 4,4,8 RAPID CHANGES IN PRESSURIZER UNEXPLAINED FLUCTUATIONS ARE EXPERIENCED LEVEL INDICATE AVOIDING IN THE TERMINATE THE DEPRESSURIZATION AND RCS, PROBABLY IN THE HEAD AREA, REPRESSURIZE THE RCS TO THE ORIGINAL VALUE, MAINTAIN THAT PRESSURE FOR AT LEAST AN ADDITIONAL TWO HOURS BEFORE ATTEMPTING TO DEPRESSURIZE AGAIN, 4,4,9 PLACE THE RESIDUAL HEAT REMOVAL SYSTEM IN OPERATION IAW 01 11-6.3.2, "INITIATING RESIDUAL HEAT REMOVAL."
4,4,10 CONTINUE THE COOLDOWN TO COLD SHUTDOWN CONDITIONS, SALEM UNIT l/UNIT 2 PAGE 3 OF 3 REV, 5