ML20062L687

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Public Version of Emergency Instruction I-4.2,Revision 9, Recovery from Safety Injection
ML20062L687
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/15/1981
From:
Public Service Enterprise Group
To:
Shared Package
ML18085A819 List:
References
I-4.2-01, I-4.2-1, NUDOCS 8102170384
Download: ML20062L687 (20)


Text

"

1-4.2 E?.ERGENCY INSTRUCTION

, 1-4.2 V , RECO'JERY FROM SAFETY INJECTION 1.0 PURPOSF ,

1.1 IO DELINEATE THE STEPS REQUI9ED 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 RECulRED OR DESIRABLE.

2.1.1 El 1-4.0, " SAFETY INJECTION INITIATION" 2.1.2 El I-4.4, " LOSS OF CCOLANT" 2.1.3 E! I-4.6, " LOSS OF SECONDARY COOLANT" 2.1.4 El I-4.7, " STEAM GENERATOR IUBE RUPTURE" 3.0 IP GIATE ACTIONS

~

3.1 NCNE 4.0 SUESECUENT f.CT!ONS COVENTS v'

4.1 IHE SENIOR SHIFT SUPERVISOR / SHIFT SUPERVISOR 4.1 ONCE SAFETY INJECTION IS RESET SHALL VERI,FY THAT THE INITIA'_ CONDITIONS IT WILL NOT AUTOMATICALLY RE-DESCRIBED IN STEP 2.1 ABOVE ARE SATISFIED INITIATE UNTIL AFTER THE REACTOR I THE OPERATOR SHALL THEN PRCCEED AS FOLLOWS: IRIP 3REAKERS HAVE BEEN RESET.

4.1.1 REFER TO IABLE I. IF ANY OF THE CRITERIA LISTED UNDER THE COLU'?N " SAFETY INJEC-T!ON REINITIATION CRI*ERIA" FOR THE APPROPRI ATE ACCIDENT EXIST AT ANY TIME AFTER SAFETY INJECT 10'l IS RESET, MANUALLY REINITIATE SAFETY INJECTION BY INSERTING .

THE SAFEGUARDS KEY IN'O EITHER IRAIN A OR 3 SAFETY INJECTION OPERATE BEZEL AND TURN THE KEY.

4.1.2 MAINTAIN SAFETY INJEC 10N IN OPERATION UNTIL THE CRITERIA L1?TED UNDER THE COLUMN " ACTIONS REQUlcED AFTER RE-INITIATION" FOR THE A2PROPRIATE ACCIDENT ARE SATISFIED.

s-1021703 %

=C -

SALEM UNIT 1/ UNIT 2 REY. 9 1 0F 20

  • l-4.2 4.2 CONTROL AUXILIARY FEEDWATER FLOW TO MAINTAIN 4.2 REFER TO APPENDIX 1 TO DETER-AN ACTUAL LEVEL 0F ~33% IN T*E NARROW RANGE MINE INDICATED LEVEL WHICH WILL ASSURE $33% ACTUAL LEVEL.

Q IN ALL UNAFFECTED STEAM GENERATORS.

4.2.1 IF AuxlLIARY FEEDWATFR FLOW HAS BEEN 4.2.1 IHIS APPLIES THOQUGHCUT THE ,

INTERRUPTED *TO ANY STIAM 6ENERATOR FOR RECOVERY.

MORE THAN 5 MINUTES A';D THE LEVEL HAS COINCIDENTALLY BEEN <10% IN THE NARROW

  • RANGE FOR MORE THAN E MINUTES, FLOW MUST BE MAINTAINED < 10 x 10' lam /H9 UNTIL THE LEVEL IS >10%.

4.3 ' RESET THE FOLLOWING SIGNALS: 4.3 IT IS NOT NECESSARY AT THl3 TIME TO RESET CONTAINMENT VEN-TILATION OR FEEDWATER ISQLATION.

4.3.1 DEPRESS THE IRAIN "A" AND IRAIN "3" SI RESEI PUSHBUTTONS, ON'THE CONTROL CONSOLE TO RESET THE 3AFETY INJECTION SIGNAL.

4.3.2 DEPRESS THE TRAIN "A" AND IRAIN "B" 4.3.2 THE STATUS 1.lGHTS ASSOCIATED CONIISOLgARESETPUSHBUT1CNS,ON WITHkAONRP-4SHoutDGOCuT.

THE CONTROL CONSOLE, 70 RESET THE CONTA!NMENT PHASE A I3OLATION S!G-NAL.

4.3.3 DEPRESS THE E".ER3ENCY LOADING RESET 4.3.3 THE STATUS LIGHTS ON RP-4 PUSHBUTTONS, ON THE CONTROL CONSOLE, ASS.0CIATED WITH THE SEC LOADING FOR 1A, 1B AND 1C(2A, 23, AND 2C) SHouLD Go OuT.

DIESEL 6ENERATORS TO '.ESET THE SAFE-GUARDS LOADING SEQUEN:E.

4.3.4 DEPRESS THE 230V CONT:0L CENTER 4.3.4 THE 230V CONTROL CENTERS MAY RESET ON THE CONTROL :ONSOLE FOR ALREADY BE RESET IF THE 20 1A, 13 AND IC(2A, 2B, AND 2C) MINUTE TIMER HAS TIMED QUT.

DIESEL GENERATORS.

4.4 OPEN THE CONTAINMENT CONTROL AIR HEADER 1(2)A 1(2)B ISOLATION VALVES.

11(21)CA330 12(22)CA330 4.5 RETURN THE CHARGING PUMPS TC THEIR NCRMAL 4.5 INSURE NO.13(23) CHARGING LINEUP 1AW 01 11-3.3.2, "0PERATING THE PUMP IS IN SERVICE BEFORE STOP-CHARGING PUMPS", AND RE-ESTA3LISH CHARGING PING NO. 11 & 12(21 1 22)

AND LETDOWN FLOW IAW 01 11-!.3.1, "ESTAB- CHARGING PUMPS.

LISHING CHARGING, LETDOWN AN: SEAL INJEC-l TION FLOW".

SALEM UN!T 1/ UNIT 2 2 0F 20 REY. 9 i i - - - -- -_ _

1

I-4.2 4.5.1 CONTROL ACTUAL PRESSUR!!ER LEVEL ~ 4.5.1 REFER TO APPEND!x 1 TO DE-AT S227. TERMINE INDICATED LEVE1. WHICH b ,

ASSURES $22% ACTUAL LEVEL.

4.6 IF THE REACTOR COOLANT PUMPS ARE NOT 4.6 IT IS PREFERRED TO START NO.13 .

RUNNING, START AT LE'AST ONE PUMP 1AW (23) RCP INCE THIS LOOP HAS 01 11-1.3.1, "RCP OPERATION", IN AN BOTH PRESSURIZER SURGE AND UNAFFECTED LOOP. SPRAY. IF NO.13(23) IS NOT AVAILABLE, START NO. 11(21).

4.7 OPEN THE CENTRIFUGAL CHARGING PUMP 4.7 INSURE A DISCHARGE FLOW PATH.

MINI-FLOW VALVES, 1(2)CV139 1 140 THEN STOP THE FLOW THRU THE SCRON INJECT,10N IANK BY CLOSING INLET VALVES 1(2)SJ4 AND 1(2)SJ5. STOP THE CENTRIFUGAL CHARGING pumps .

WHICH ARE NOT BEING USED FOR NORMAL CHARGING.

4.8 STOP THE RHR PUMPS AND SAFETY INJECTION 4.8 THE PUMPS ARE RUNNING ON RECIRC.

PUMPS.

4.9 RETURN THE SERVICE WATER SYSTEM TO NORMAL LINEUP IAW 01 V-1.3.1, " SERVICE i WATER - NORMAL OPERATION".

4.10 RETURN DIESEL GENERATORS 1A, 13 AND 1C (2A, 23, ANb 2C) TO NORMAL OPERATION LAW 01 IV-16.3.1, " EMERGENCY PowEF - DIESEL OPERATION".

'4.11 RETURN THE CONTAINMENT VENTILATION SYSTEM TO NORMAL OPERATION IAW 01 11-16.3.1, " CONTAINMENT VENTILATION OPERATION".

4.12 RETURN THE Aux!LIARY BUILDING VENTILATION SYSTEM TO NORMAL OPERATION lA', 01 Il-17.3.1, Aux!LIARY 3UILDING VENTILATION OPERATION".

4.13 RETURN THE CONTROL ROOM VENTILATION SYSTEM TO NORMAL OPERATION IAW 01 11-17 3.2, " CONTROL ROOM VENTILATION OPERATION".

4.14 VERIFY THE EMERGENCY CONTROL AIR C3MPRESSOR

! STOPS WHEN CONTROL AIR PRESSURE IS NORMAL

! AND RETURN THE CONTROL AIR Sy: TEM TO NORMAL r

OPERATION LAW 01 V-5.3.1, "CCreTROL AIR SYS-TEM OPERATION".

l .

! SALEM UNIT 1/ UNIT 2 '3LCF 20 REv. 9

1-4.2 4.15 RETURN THE FEEDWATER SYSTEM TO THE DESIRED 4.15 THE AUXILIARY FEED PUMPS MAY BE' MODE OF OPERATION LAW 01 111-9.3.2, " FEED USED TO MAINTAIN STEAM GENERATOR p PUMP OPERATION", AND SECURE THE Aux!LIARY LEVELS.

FEED PUMPS.

1) REFILL THE Aux 1LIARY FEEDWATER STORAGE INE CONDENSATE PUMPS MAY BE TANK AS NECESSARY. STOPPED IF DESIRED.
2) REALIGN THE AUXILIARY FEED SYSTEM FOR POWER OPERATION LAW 01 ill-10.3.1,

" AUXILIARY FEEDWATER SYSTEM OPERATION".

4.15 RETURN THE STEAM GENERATOR D'tAINS AND 3 LOWDOWN SYSTEM TO NORMAL OPERATION Ia.W 01 III-13.3.2,

" STEAM 6ENERATOR 3LOWCOWN - NORMAL OPERATION".

4.17 RETURN THE CONTAINMENT / PUNY VENT RADIATION MONITOR TO NORMAL OPERATION IAV THE FOLLOWING Ol'S:

1) UNIT 1 - 01 IV-11.3.4, "CPERATION OF THE CONTAINMENT / PLANT VENT SmPLER (R11/R12)". .
2) UNIT 2 - 01 IV-11.3.2, "CPERATION OF RADIA-TION MONITOR SYSTEM SAf9: ERS".

4.18 RETURN THE INLET VALVES TO wE GAS ANALYZER, FROM THE REACTOR COOLANT DR';N IANK AND PRESSURIZER RELIEF IANK, TO NORMAL BY CPENING THE FOLLOWING VALVE!:

1(2)WL96 1(2)WL97 1(2)PR18 1(2)PR17 4.19 DRAIN AND REFILL 3ORON INJECTION IANK FROM 4.19 DQ E I, REMOVE THE POWER FROM THE BORIC ACID. TANKS IAW OI 11-4.3.5, 1(2)SJ4, 5, 12, 13 AS THl3

" FLUSHING AND DRAINING THE 30RON INJECTION WILL MAKE THE 3ORON INJECTION IANK". TANK INOPERABLE.

CaVTION: DO NOT ISCLATE THE 30RON INJECTION EXPEDITE BECAUSE 3II BORON IANK DURING THE RE~lLLING PROCESS CONCENTRATION IS BELOW THE OR DURING THE SUB!ICUENT SAMPLING IECH SPEC LIMIT.

TO INSURE THE FLOh DATH THRU THE BIT IS OPERABLE.

4.20 RETURN THE SAFETY INJECTION 3YSTEM TO NORMAL 4.20 RWST AND 3AT LEVELS MAY BE LOW.

IAW 01 11-4.3.1, " SAFETY INJECTION SYSTEM -

NORMAL OPERATION".

l SALEM UNIT 1/ UNIT 2 4 0F 20 REv. 9

I-4.2

~

1 4.21 MAKE A VISUAL INSPECTION WITHIN THE CONTAIN-MENT WHEN ENTRY IS PERMISS!!LE.

U 4.22 AFTER THE PLANT HAS STABILIZED, SAMPLE THE REACTOR COOLANT SYSTEM FOR BORON CONCENTRA-

  • TION AND H .

01!!-3.3.b,"ADau'STBORONASNECESSARYIAW BORON CONCENTFATION CONTROL" FOR THE DESIRED PLANT CONDITIONS. DEGAS THE RCS AS NECESSARY LAW 01 11-!.3.11, " VOLUME CONTROL IANK DEGASSIFICATI0t.".

4.23 CALCULATE THE SHUTDOWN MARGIN IAW THE REACTOR ENGINEER'S MANUAL TO ENSURE THAT THE REACTOR IS SHUTDOWN BY >1.6% AK/K.

4.24 AS rNDICATED BY ~ PLANT CONDITIONS PROCEED AS FOLLOWS:

IAKE THE UNIT TO COLD SHuTDCwN IAW 01 I-3.6

" HOT STANDBY TO COLD SHUTDOWN", OR AS AUTHORIZED BY AP-5, WITH RAW THE SHUTDOWN 3ANKS AS FOLLOWS:

1) RESET THE FLUX RATE TRIP BY MCMENTARILY 1) MUST BE RESET FOLLCWING ANY TAKING THE RATE MODE SW:TCHES, ON EACH REACTOR TRIP FROM POWER.

NIS POWER RANGE A DRAWEF, TO THE RESET POSITION.

2) DEPRESS THE CLOSE~PUSHBUTTON, ON THE CON-TROL CONSOLE, FOR REACTCi TRIP 3KR A, VERI-FYING THE BREAKER DOES CLOSE.
3) CEPRESS THE Cl.0SE PUSHPUTTON, ON THE CON-SOLE, FOR REACTOR TRIP E 'R 3, VERIFYING THE BREAKER DOES CLOSE.
4) DEPRESS THE STARTUP PUBH3UTTON, ON THE CON- 4) IF THE STARTUP PUSHBUTTON HAS TROL CONSOLE, AND VERIFY EACH SHUTDOWN AND BEEN PUSHED P8t!OR TO CLOSING CONTROL RCD STEP COUNTER 3 RESET TO ZERO. THE REACTOR IRIP 3REAKERS, A ROD URGEN ALARM CONDITIONS WILL BE PRESENT. THIS CAN BE CLEARED BY PUSHING EITHER THE STARTUP PUSHBUTTON OR THE ALARM RESET PUSHBUTTON.

SALEM UNIT 1/ UNIT 2 5 0F 20 REV._ 9

I-4.2

5) COMMENCE WITHDRAWING SH'JTDOWN 3ANK A, B, C AND D, IN THAT ORDER, To THEIR FULLY IQ WITHDRAWN POSITION.

4.25 COMPLETE ATTACHMENT No. 1 AND ATTACH IT To THE .

OPERATING INCIDENf REPORT, AP-6.

PREPARED BY J. 3AILEY / 2_1_J MAhAGER - SALEM 6ENERATING STAT!cN gEVIEWED BY

,, G. CoNNoR SCRC MEETING No. 74-go DATE f// [*

SALEM UNIT 1/ UNIT 2 6 op 20 REV. 9

l-4.2 i ATTACHMENT NO 1 i POST SAFETY INJECTION DATA V '

INITIAL PRESSURIZER LEVEL I -

FINAt. PRESSURIZER LEVEL I INITIAL PRESSURIZER PRESSURE PSIG  ;

FINAL PRESSURIZER PRESSURE PSIG INITIAL IAVG 'F FINAL IAVG *F RWST TEMPERATURE (T0650A) *F DURATION OF SAFETY INJECTION MIN.

I

~ \

RECORDED BY DATE REVIEWED BY DATE SENIOR SHIFT SUPERVISOR / SHIFT SUPERVISOR l s

I i

i i

SALEMllNIT1/hMIT2 7 0F 20 REv. o

f I-4.2 THE I -

SAFETY INJECTION SAFETY INJECTION ACTIONS REQUIRED V FETY INJECTION ACTUATION TERMINATION CRITERIA (1) REINITIATION CRITERIA (2) AFTER REINITIAT10N(1)

1. SPURIOUS SI El-4.0 1. RCS PRESS >2000 PSIG 1. RCS <1765 PSIG 1. RETURN TO El-4.0 .

AND RE-EVALUATE.

2. PRZ LEVEL >22% 2. PRZ LEVEL <101 2. INCREASE SUSCCOLING

, To 65'F.

OR INCREASE RCS PRESS.

To 2200 PSIG.

3. StBCocuNC >50*F 3. SUBCOOLING <50*F 4

) 4. AFW 42x1C LB/HR OR S/G LEVEL 15% NARROW RANGE (IS/G)

2. SMALL LOCA 1. RCS PRESS >2000 PSIG 1. RCS <1765 PSIG 1. RETURN TO El-4.0 El 4.4 2. PRZ Lvt >E:: 2. PRI LVL <20% AND RE-EVALUATE.

l 3. SuBCocLINc ,>50*F 3. SUBCCOLING <50*F 2. INCREASE SuBCOOLING

4. AFW >42x1C' LB/HR *To 65'F OR OR S/G LVL 15". NARROW INCREASE RCS PRESS RANGE (IS/G) To 2200 PSIG.

a 6

3. LOSS oF SECONDARY
l. RCS PRESS '700 PSIG 1. RCS PRESS OROPS BY ll 1. RETURN To El-4.0 A CcotANT - ONE I H 2. PRZ Lvt >21 BY 200 PSIG RE-EVALUATE.

<350'P El-4.6 3. SuBCo0 LINS $50*F 2. PRZ LVL DROPS BY 10: 2. INCREASE SUBCCOLING T L

4. AFW >42x10' LB/aR 3. SuBCoct!NG <50*F 65'F BY CCCLDOWN i OR 3. RETURN RCS PRESS. To S/G Lvl 15~. NARROW THE VALUE AT TERMI-RA::GE(IS/G) NATICN.
4. LOSS OF SECONDARY 1. RCS PRESS >2000 PSIG 1. RCS PRESS DROPS BY 1. RETURN TO El-4.0 AND CoCLANT - ALL T H 2. PRZ LVL >20% 200 PSIG RE-EVALUATE.

i

>350*F El-4.6 3. SUBCOOuNG >50*F 2. PRZ LVL DRCPS BY 10 2. INCREASE SuBC00 LING T 4

4. AFW >42x10 LB/HR 3. SuBCocuNG <50*F 65'F BY CCOLDOWN OR 3. RETURN RCS PRESS. TO S/G LVL ISS NARROW THE VALUE AT TERMI-RA:.sE(IS/G) NATICN.

(1) ALL CRITERIA MUST BE MET (2) ANY CF THE CONDITIONS REQUIRE REINITIATION S

SALEM UNIT 1/ UNIT 2 8 0F 20 REV. 9

I-4.2 1

APPENDIX 1 DETERMINATION OF ACTUAL PRESSURIZER AND STEAM GENRATOR LEVELS

%)

IO DETERMINE ACTUAL PRESSURIZE,R OR STEAP GENERATOR LEVELS, UTILIZE THE ATTACHED TABLES AS DESCRIBED BELOW.

IABLES 1-5 ARE TO BE USED FOR THE STEAM 6ENERATORS IABLES 5-11 ARE TO BE USED FOR THE PRESSURIZER L

1. OBTAIN THE AVERAGE CONTAINMENT TEMPERATURE FROM COMPUTER POINT U1304.
2. REFER TO THE APPROPRIATE IABLE FOR THE PRESSURE IN THE STEAM GENERATOR AND PRES 3URIZER.
3. LOCATE THE DESIRED ACTUAL LEVEL UNDER THE COLUMN FOR THE AVERAGE CONTAINMENT TEMPERATURES. l
4. FROM THE COLUMN HEADED " INDICATED, LEVEL '(I)" DETERMINE THE INDICATED LEVEL WHICH SHOULD BE MAINTAINED To ENSURE THE ACTUAL LEVEL IS MAINTAINED AT OR ABOVE THE DESIRED VALUE.

l W '

IF THE COMPUTER 13 UNAVAILABLE, MAINTAIN INDICATED LEVEL %33% ABOVE THE DESIRED ACTUAL LEVEL. [

t

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1 l

SALEM UNIT 1/ UNIT 2 9 0F 20 REv. 9

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70 nr 70

1-4.3 i

REACTOR TRIP SETPOINT COINCIDENCE

. INTERLOCK V 8. Low REACTOR 18E5 estG 2/4 P-7 C00uNT PRESSURE

9. HIGH REACTOR 2385 PS!G 2/4 NONE C00uNT PRESSURE  !
10. HIGH pressurizer 92: LEVEL 2/3 P-7 l
11. Low REACTOR 90: OF NORMAL Flow 2/3/ LOOP P-7 & P-3 L C00uNT Plow
12. REACTOR C00uNT PUMP 75: OF NOR.tAL VOLTAGE WITH A 2 IAKEN P-7 I UNDER VOLTAGE, 0.2 SEC. TIME DELAY Tw!CE
13. REACTOR C00unT PUMP 56.5 HERTZ wlTH A 0.1 SECOND 1/2 IAKEN P-7 UNace FRCOUENCY TIME DELAY IWICE .
14. REACTOR C00 u MT PUMP 10; owr. 2 [ '4. OPEN 1/ PUMP P-7 & P-8 3REAKER OPEN 36 UwR. 1 3KA. OPEN
15. Low FEEDwATER PLCa' l.4 x 10' STM. Flow GREATER THAN 1/2 Ftow NONE FEE ..ATER Flow & 25; S/G LEVEL P.!sxATCH, IN

,q CCINCIDENC w!TH 1/2 Low

, WTR LEVEL, PER LOOP.

16. low-low STEAM 18: .EVEL PER S/G 2/3 PER S/G N:NE GENE *ATOR WTR. LYL
17. TURBINE-6ENERATOR 45 P71G AUTO STOP 0:t PRESSURE 2/3 P-7 TRIP OR A.L FOUR STOP VALVES CLOSED 4/4
18. SAFETY INJECTION 1. fANUAL 1/2 NONE (ACTUATION) 2. IRESSURl!ER AT 1765 PSIG 2/3 NONE
3. CONTAINMENT AT 4.7 PSIG 2/3 HIGH CON- NONE TAINMENT PRES $URE
4. ANY ONE S/G 100 PstG lower 1/2 STEAM PRES
  • NONE THAN ANY OTHER Two S/6's SURE ON ANY S/6 LowtR THAN 3/2 STEAn PREFSURES ON 2/3 0F THE QTHER LOOPS.

SALEM UNIT 1/U:17 2 2 0F 10 REv. 5,

~

I-4.3 REACTOR TRIP SETPOINT COINCIDENCE INTERLOCK U 5. VAIRABLE: STEAM LINE FLCw 1/2 HIGH STEAM NONE 1.4 x 10' #/HR. 0-20 LOAD FLOW 2/4 STEAM

. !NCREASING TO 4.0 x 10' s/HR. GEN '!*3 COINCIDENCE AT 100% PWR. IN ColNCEDENCE WITH 2/4 LOW TAVG dlTH LOW TAVG 543'F CR LCW On 2/4 Low STEAM

. 37M. PRESS 500 PSIG. LINE PRESSURE.

19. GENERAL ALARM Lool: TRAIN "A" & IRAIN "3" !N NCr:E TEST $1MULTANECUSLY.

E: IHE GENERAL ALARM TRIP IS NOT ALARMED ON THE FIRST CUT ANNUNCIATCR.

20. TalP 3YPASS BKRS. RACK:NG.lN, OR ATTEMPTING To RACK NCnE IN, 30TH REACTCR IRIP 3YPASS 3KRS.

AT Td! SAME TIME.

6: IHE 3YPASS 3REAKER TRIP 15 NOT ,

ALARMED ON THE FIRST CUT ANNUN-CIATCR.

1- 3.0 P'ESI ATE AU10NS 3.1 Autenic 3.1.1 REACTOR TRIP 3.1.2 TURBINE IRIP 3.1.3 GENERATOR IRIP 3.2 MANUAL 3.2.1 IF AN AUTOMATIC REACTOR TRIP E E OCCURRED AS INDICATED BY REACTOR PCWER REMAINING HIGH AND/CK MULTIPLE CCNTRCL RODS FAILING TO INSERT, TH1515 IDEN-TIFIED AS AN "ANTICIFATED IRANSIENT WITHOUT A IRIP" EVENT (AIMI [ VENT). PROCEED AS FOLLOWS UNTIL THE REACTCR is SUCESSFULLY TRIPPED:

1) ' INITIATE A MANUAL REACTOR TRIP WITH EITHER HANDLE CN THE CONTROL CONSOLE.
2) INITIATE A MANUAL TURBINE TRIP WITH THE HANDLE ON THE CONTROL CONSCLE.
3) OPEN THE REACTOR IRIP 3tEAKERS MANUALLY FRCM THE CONTRCL CONSOLE 3Y OEPRESSING )

. OPEN PUSHBUTTCNS ON BOTH REACTCR IRIP 3REAKER A 13 3E2ELS. l SALEM UNIT 1/ UNIT 2 3 er 10 Rev. 6

I-4.3

4) MANUALLY INITIATE SAFETY INJECTICN BY INSERTING THE SAFEGUARD KEY INTO EITHER IRAIN A OR B 3AFETY INJECTION OPERATE BEZEL AND TURN THE KEY.

b/'

5) MANUALLY TRIP BCTH REACTOR IRIP 3REAKERS LOCALLY AT THEIR CUBICLE IN THE 84 FT. ELEVATION Sw1TCHGEAR Rt0M. .
6) MANUALLY TRIP BOTH CONTROL rcd M3 SETS AT THEIR CONTROL PANELS IN THE 84 FT.

ELEVATION SWITCHGEAR ROOM.

3.2.2 IF AN AUTOMATIC REAC OR TRIP Bd10CCURRED, PRCCEED AS FOLLOWS:

1) CMECK THAT ALL FULL LENGTH RODS ARE FULLY INSERTED BY CHECKING INDIVIDUAL RCD PCSITION INDICATORS AND ROD BOTTOM LIGHTS.
2) IF ANY FULL LENC~H CONTROL RCD DOES NOT INDICATE FULLY INSERTED, MANUALLY INITIATE A REAC:?R TRIP.
3) IF ALL FULL LENGTS CONTROL RCDS ARE r.0T THEN FULLY INSERTED, RAPlL 30 RAT 3 BY 153 PPM FOR EA:H RCD NOT INSERTED AS FCLLows:

A) SHIFT ONE OR BOTH 3CRic ACID TRANSFER PUMPS TO FAST SPEED.

B) OPEN 1(2)CV15. RAPID 3CRAT!CN STOP VALVE.

s,,

C) 3 ORATE FOR A LEAST 8 MINUTES FOR EACH RCD NOT FULLY INSERTED (4 MINUTES WITH 30TH PUMPS IN FAST).

3.2.3 VERIFY IURBINE TRIP SY CHECKING THE FOLLCWING:

e

1) UNIT TRIP LIGHT IN E/H CONSOLE !LLUMINATED.~
2) TURBlNE STOP VAL /ES, 60VERNOR VALVES, INTERCEPTCR VALVES AND REHEAT STOP VALVES CLOSED.
3) TURBINE SPEED DE REASfNG.

IF THE TURBINE Bd1 E21 TRIPPED, PROCEED AS FOLLOWS UNTIL STEAM FLOW FROM THE STEAM GENERATORS 15 *ERMINATED.

4) INITI ATE A MANUA'. TRUBINE TRIP WITH THE HANDLE ON THE CONTRCL CONSOLE.

- 5) MANUALLY CPEN THE GENERATOR Output 3REAKERS, 1-5 1 5-6 (1-9 8 9-10).

6) TRIP CLOSED THE MAIN STEAM ISOLATION VALVES, ll-14(21-24)M3167 FRCM EITHER THE SAFEGUARD BE;ELS OR MAIN STEAM BE ELS.

IF THE UNCONTROLLE: 37EAM FLOW HAS CAUSED REACTCR COOLANT SYSTEM PRESSURE TO

'~' OECREASE TO *1765#, :sSURE SAFETY INJECTION IS ACTUATED. IF SAFETY INJECTION IS NOT ACTUATED, INITIATE IT MANUALLY BY INSERTING THE SAFEGUARDS KEY INTO EITHER TRAIN A OR 3 SAFETY INJECTION OPERATE 3E2EL AND TURN THE KEY. ERCCEED TO El 1-4.0, "SAFTEY INJECTICN INITIAT:0N".

Satt- UN d.1/ UNIT 2

  • 4 CF 10 Rzv., 6

1-4.3 3.2.4 VERIFY I gyg IS DECREAS:NG TOWARD OR !$ BEING MAINTAINED AT 547'F BY EITHER STEAM DUMP OR ATMOSPHERIC S. TEAM RELIEF.

3.2.5 VERIFY THAT FEEDWATER ISOLATICH TAKES PLACE WHEN Igyg DECREASES TO 554*F. ,

3.2.6 VERIFY Aux!LIARY FEEDWATER FLOW IS ESTABLISHED TO ALL FouR STEAM GENERATORS IF ANY STEAM 6EN.,RATOR LEVEL !! <l8%.

3.2.7 ANNCUNCE OVER THE PLANT PA SYSTEM TWICE: UNii NO.1(2) REACTOR TRIP.  ;

4.0 SUBSEQUENT ACTIONS COTENTS 4.1 IF SAFETY INJECT!CN WAS MANUA.LY INITIATED UTILIZE REDUNDANT INDICATIONS WHERE IN STEP 3.2.1, PROCEED TO El-i-4.0, PCSSIBLE TO CONFIRM EVALUATICNS AND

" SAFETY INJECT!DN INITIATION" ACTIONS.

4.2 VERIFY ALL !MMEDIATE ACTICNS ARE COMPLETE, ACC0hPLISH ANY WHICH ARE NOT.

4.3 VERIFY THE GENERATOR OUTPUT E:EaKERS, 4.3 SHOULD CPEN -30 SECCNOS AFTER 1-5 & 5-6(1-9 8 9-10) ARE OPE' THE TURBINE Ti!P, IF THEY DO NOT OPEN, CPEN MANJALLY BY DEPRESSING THE OPE': PuSHBU TON ON THE BEZEL FOR EACH BREAKER ON THE CONTROL CONSOLE.

4.4 CHECK THAT NUCLEAR PCWER IS CICREASING BY CBSERV!NG THE NUCLEAR INSTRUMINTATION.

4.4.1 CHECK THAT THE $9URCE 5ANGE HIGH 4.4.1 SHOULD OCCUR IN 15-13 MINUTES v0LTAGEy$ REIND 'TED 3ELOW FOLLOWING TmE TRIP.

5 x 10- 4MPS ON _ m INTER-MEDIATE RANGE (HANNELS

1) IF THE SOUACE RAr HIGH VOLTAGE DOES NOT ENERGIZh AUTOMATICALLY, MANUALLY DEPRESS TuE RESET SOURCE

. PANGE "A" AND RESET SOURCE RANGE "3" PUSHBUTTONS CN THE CONTROL CONSOLE.

4.4.2 3 WITCH THE NUCLEAR POWIR RECCRDER (NR-45)

TO READ ONE INTERMEDIA E $ANGE CHANNEL AND CNE 3CURCE RANGE CHANN!;..

i 4.4.3 NOTIFY THE PERFCRMANCE DEP' 'NT THAT 4.4.3 IHl3 SHOULD SE ACC0".PLISHED AS l

( A REACTCR TRIP HAS OCC'.1RL THAT SCCN AS PRACTICAL TO INSURE THE COMPENSATING VOLTA 3E ON s' INTER- PRCPER INTERMEDIATE RANGE MEDIATE RANGE DETECTCFS Sh0ULI. 1E AD- INDICATION.

JUSTED.

1-4.3

4. 5 VERIFY THAT THE PRES $URIZER PRESSURE AND LEVEL 4. 5 TAKE MANUAL CONTROL AS NECESSARY.

ARE WITHIN LIMITS, AND UNDER CON, TROL.

4.6 VERIFY THAT THE 4160V group 3USSES HAVE TRANS-FERRED FROM THE NQ.1(2) Au.<!LI ARY POWER IRANS-FORMER TO NO.'11(21) & NO. 12(22) STATION POWER IRANSFORMERS.

4.6.1 CHEC. THAT THE F0LL04tNG 4160V BREAKERS 4.6.1 OPEN MANUALLY AS NECESSARY.

HAVE OPENED AND ACKNOWLEDGE THEM ON THE APPROPRIATE CONTROL CONSOLE SEZELJ 1(2)BGGD 1(2)BFGD 1(2)AEGD 1(2)AHGD 4.6.2 CHECK THAT THE FOLLOWING 4150V 3REAKERS 4.6.2 CLOSE MANUALLY AS NECESSARY.

HAVE CLOSED AND ACKN*.WLEDGE TnEM ON THE APPROPRIATE CONTROL CONSOLE BEZEL:

12(22)GSD 12(22)FSD ~

11(21)ESD 11(21)CSD v 4.7 VERIFY THAT T3yg IS BE!NG Pl.!NTAINED AT 4.7 CHECK STEAM DUMP VALVE POSITION 547'F DuE 10 iTEAM DU"# CPE?aTION.

INDICATING LIGHTS AND T-E STEAM DUMP DEMAND INDICATOR.

4.7.1 ENSURE THE MAIN STEAM FRES$URE SET- 4.7.1 CHECK THE SETTING FIRST TO PolNT IS SET TO MAIN AIN STEAM PREVENT ANY UNWANTED STEAM 6ENERATOR PRESSURE A- s1005 PSIG, DUMP OPERATION.

THEN TRANSFER THE Stim DUMP CON-TROL TO MAIN STEAM E* ESSURE CONTROL.

4.7.2 IF CONDENSER STEAM D ?P IS NOT ' VAIL-ABLE, UTILIZE THE A nOSPHERIC STEAM RELIEF VALVES, 11-14: 21-24)MS10 TO MAINTAIN STEAM GENERATOR PRESSURE AT s1005 PSIG.

4.3 VERIFY THAT FEEDWATER ISOLA 10N HAS TAKEN PLACE DUE TO THE REACTOR TRIP IN ColNCIDENCE WITH LOW T gyg W N.

4.3.1 CHECK THAT THE FOLLok!NG VALVES HAVE CLOSED BY OBSERVING THEIR A'*ROPRIATE BE EL INDI-g CATION:

11(21)BF19 FEEDWATER CONTRCL VALVE 12(22)BF19 FEEDWATER CONTRCL VALVE C".EM UNIT 1/ UNIT 2 6 0F 10 REv. 6

o .

1-4.3 13(23)BF19 FEEDWATER CONTROL VALVE 14(24}BF19 FEEDWATER CCNTROL VALVE V 11(21)BF40 FEEDWATER 2 PASS VALVE 12(22)BF40 FEEDWATER BYPASS VALVE

.13(23)BF40 FEEDWATER 3YPASS VALVE - -

14(24)BF40'FEEDWATER 3YPASS VALVE 4.9 TERMINATE ANY RCS DILUTION dHICH IS IN 4.9 FRCVENT ANY INADVERTENT RE-PROGRESS. DUCTION IN 3MUTDOWN M RGIN.

4.9.1 DEPRESS THE STOP PUS *3UTTON ON THE MAKEUP MODE SELECTOR BEIEL AND ALIGN THE BLENDE; FOR AUTO MAKEUP IAW UI 11-3.3 5, "BCRON CONCENTRATICH CONTRCL".

4. 9.2 BYPASS THE DEBCRATING DEMINERALIZERS BY ALIGNING 1(2)CV27 TO THE VCI.

4.10 RETURN THE LEVELS IN THE STCAM GENERATCRS TO 4.10 THE FEED RING DRAINS SLOWLY NCRMAL ($33%) AS FOLLOWS: THRCUGH THE LOCSE FIT CON-NECTION TO THE FEED INLET PtrtNG.

CAUTION: IF THE l! VEL IN AiY STEAM 6ENERATCR HAS BEEN *10 ON THE NARROW RANGE FOR MCRE IF CONDITIONS REQUIRE MAXIMUM THAN 5 MINUTES AND ALL FEEDwATER FLOW MAS FLOW FOR DECAY HEAT REMOVAL BEEN ISOLATED FOR MCRE THAN 3 MINUTE;, CONSIDERATIONS, THIS TAKES FLOW MUST BE LIMITED TO < IC x 10' lam /HR. ?RECEDENCE OVER THE WATER TO THAT STEAM 6ENERATOR UNTI'. THE LEVEL MAMMER CONSIDERATIC;dS.

IS RETURNED TO >10 IN THE tARRCW RANGE.

CAUTIOf!: h h 1 STCP 11 OR 12(21 CR 22) IF EITHER MOTOR DRIVEN PUMP Aux. FEED FUMP WHILE ANY STEAM GENERATOR IS STorPED WHILE A STEAM GEN-IS *18%. ERATOR LEVEL IS *18%, THE PUMP Mur BE STARTED LCCALLY FROM TH. dCT $NUTDOWN FANEL, OR THE 125 VDC CONTROL PCWER MUST BE CYCLED TO START'THE PUMPS FROM THE CONTROL RCOM. IF THE LEVEL INCREASES 70 >l3% THE PUMPS MAY BE RESTARTED NCRMALLY.

4.10.1 CONTROL FLOW TO THE $7EAM GENRATORS AS REculRED BY CONTRC'. LING THE FCLLOWING VALVES:

I 1) 11-14(21-24)AF11 ;F NO. 13(23) i AUX. FEEDWATER Fu = !$ IN OPERATICN.

SALEMUNITh0 NIT 2 7 0F 10 *~
  • l l

1-4.3

2) 11-14(21-24)AF21 IF NO. 11 1 12 Aux FEEDWATER F;MPS ARE IN OPERAT10N.

4.11 ESTABLISM AND mal'ITAIN THE HOT STANDBY CONDITION IAW 01 1-3.5, " MINIMUM LOAt 70 HOT STANDBY", AND 01 1-3.8, " MAINTAINING HOT 37ANDBY".

4.12 IF RX TRIP WAS FRon >157, Rx POWER, HAVE THE 4.12 TECH SPEC 3.4.3 TABLE 4.4 CHEM DEPT. PERFORM AN l , I ,I ISOTOPIC ANALYSIS BETWEEN 2 AND E Hour.

FOLLOWING THE RX IRIP.

4.13 OBTAIN A SAMPLE OF THE REACTOR COOLANT SYSTEM AND DETERMINE, BORON CONCENTRATION. ADauST BORON CONCENTRATION'AS REcu! RED IAW 01 !!-3.3.6, "3ORON CONCENTRATION CONTRC.".

4.14 AS PER ADMIN!iTRATIVE PROCE uRE NO. 5:

4.1L.1 NCTIFY THE STATION C8ERATING ENGINEER OR CHIEF ENG!hEER OF THE REACTOR TR!P AND; 4.14.2 INITIATE AN OPERATIONAL INCIDENT REPORT IAW AP-6 AND FORWAR IT TO THE STATION OP,ERATING ENG!NEER.

4.15 IF, AT THl! TIME, IT BECOME1 NECESSARY, TAKE 4.15 IF ANY OF THE AUTOMATIC FUNCTION THE PLANT TO THE COLD SHuTO'WN CONDITION LAW REQu! RED (1.E. REACTOR TR!P, 01 1-3.6, " HOT STANDBY TO C. a SHUTDOWN". TuRBlKE TRIP, AUXILIARY FEED-WATER INITIATION) HAVE FAILED TO ACTUATE, IT WILL BE NECESSARY TO PROCEED TO C00 SHUTDOWN LAW IECH 3PE; 3.0.3.

4.16 AS AUTHORl!ED BY AP-5, wlTH:4AW THE SHUTDOWN 3ANKS AS FOLLOWS:

4.16.1 RESET THE FLUX RATE ~ RIP BY MOMENTARILY 4.16.1 ANY REACTOR TRIP FROM POWER TAKING THE RATE MODE SWITCHES, ON EACH WILL GENERATE A NEGATIVE NIS POWER RANGE A DRAWER, > THE RESET RATE TRIP SIGNAL WHICH SEALS POSITION. IN AND MuST BE MANUALLY RESET.

4.16.2 DEPRESS THE Cl.0SE Pu.wBuTTON, ON THE CONTROL CONSOLE, FOR REACTCR TRIP BKR

' A, VERIFYING THE BRE u!R DCES CLOSE.

SALEM UNIT 1/ UNIT 2 8 0F 10 REv. 6

. 1-4.3 4.16.3 DEPRESS THE CLOSE PussBuTTON, ON THE

[ CONTROL CONSOLE, FOR REACTOR TRIP BKR h 3, VERIFYING THE BREAKER DGES CLOSE.

4.16.4 DEPRESS THE STARTUP PUSHBUTTON, ON THE 4.16.4 IF THE STARTUP PUSNBUTTON .

CONTROL CONSOLE, AND VERIFY EACH SHUT- HAS BEEN PUSHED PRIOR 70 DOWN AND CONTROL RCD STEP COUNTER RESETS CLOSING THE REACTOR TRIP TO ZERO. 3REAKERS, A Rc0 URGENT ALARM CONDITION WILL BE PRESENT. TH13 CAN BE CLEARED BY PUSHING EITHER THE STARTUP PUSHBUTTCN CR THE ALARM RESET PUSMBUTTON.

4.16.5 COMENCE WITHDRAWING SMUTDOWN 3ANK A, 3, C AND 3, IN THAT CFDER, TO THEIR FULLY WITHDRAWN POSITION.

4.17 WHEN THE CAUSE OF THE TRIP HAS BEEN DETER-MINED AND CORRECTED, OBTAIN ~HE PERMISSION OF THE STATION OPERATING enc:NEER OR THE CHIEF ENGINEER, IAW AP-3, TC TAKE THE

  • REACTOR CRITICAL.

y 0.13 WITH STEAM GENERATOR LEVELS GTHIN THEIR NORMAL OPERATING BANDS AND J')3T PRICR TO CCMMENCING THE RECOVERY, STATTUP, PERFORM THE FOLLOWING: ,

4.18.1 PLACE THE STEAM GENER *.TCR FEEDWATER CONTROLS IN .".ANUAL AN: RUN THE VALVE DEMAND TO ZERO.

4.18.2 RESET THE FEEDWATER ISCLATION SIGNAL BY DEPRESSING THE IRAIN "A" AND IRAIN "3" FEEDWATER ISOLATION RESET PUSMBUTTONS ON THE CONTROL CONSOLE.

4.18.3 MAINTAIN STEAM GENERATCR LEVELS WITHIN THEIR NORMAL CPERATlh'. 3 ANDS BY MANUALLY CONTROLLING FEEDWATER BYPASS VALV'ES 11, 12, 13 AND 14(21, 22, 23 AnD 14)3F40.

4.18.4 RETURN THE AUXILIARY ~EEDWATER SYSTEM 4.18.4 AFW STORAGE IANK LEVEL PJY SE TO ITS NCRMAL AT PCWE9 LINEUP IAW 01 Lcw.

111-10.3.1, "AuxlLIArv FEEDwATER j SYSTEM OPERATICN".

SALEM UNIT 1/ UNIT 2 4 0F 10 REY. 6

, o O

l-4.3 4.19 RETURN To POWER OPERATION IF4 01 1-3.3, " hot l STANDBY TO MIN! MUM LOAD", AlD 01 1-3.4, "P0 wen y

OPERATION .

  • r PREPARED BY J. BAILEY g[

REv!EWED BY G. CONNOR SORC MEETING NO. 74-80 DATE .

/f O

e C.,so . ? tt ' . . 9

-