ML20113G619
| ML20113G619 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/16/1989 |
| From: | Butterworth H GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092F288 | List:
|
| References | |
| CON-IIT05-273-001-90, CON-IIT5-273-1-90, RTR-NUREG-1410 17009-1, NUDOCS 9202240410 | |
| Download: ML20113G619 (33) | |
Text
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ProcIdure No.
Vogtle Electric Generating Plani 17009-1
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NUCLEAR OPERATIONS Repon No 1
Georgia Power en."t of 33 Unit T -/(> -/9
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1 ANNUNCIATOR RESPONSE PROCEDjJRES FOR ALB-09 ON PANEL ICl,0N MCE r?\\/
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PURPOSE E d}i jit.
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These procedures describe alarm conditions annunciated on Annunciator Light Board (ALB) 09 located on the Main Control Board.
They apply to Unit 1 operation only to provide guidance for specific operator responses to given alarms and may not be appropriate for all plant conditions.
Alarms on this panel should not be acknowledged until the operator is aware of the first to occur.
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PROCEDURE NO.
REVISION PAGE NO.
VEGP 17009-1 4
2 of 33
(!)
(2)
(3)
(4)
(5)
(6)
I STH CEN LOOP 1 STM CEN 1 PR2R PRESS NIS HI FLUI UNDERVOLTAGE
^
LO.LO LEVEL HI-HI LEVEL SI SOURCE RANCE RCP BU5/P7 REACTOR TRIP TURBINE TRIP RI TRIP REACTOR TRIP REACTOR TRIP STM CEN LOOP 2 STM CEN 2 FRZR LO NIS HI PLUX UNDERTREQUENCY B
LO-LO LEVEL HI-HI LEVEL PRESS /P 7 IR RCP BUS /P7 REACTOR TRIP TURBINE TRIP REACTOR TRIP REACTOR TRIP REACTOR TRIP STM CEN LOOP 3 STM CEN 3 PR2R HI PRESS FIS HI FLUI TURBINE LO-LO LEVEL HI-HI LEVEL REACTOR TRIP LO SET POINT TRIP /P9 RE. ACTOR TRIP TURBINE TRIP PWR RNG RX TRP REACTOR TRIP S
CD WOP 4 SW CM 4 mR HI MS HI M I HI C M PRESS D
LO-LO LEVEL HI-III LEVEL LEVEL /P 7 RATE PWR RANCE SI RX TRIP REACTOR TRIP TURBINE TRIa*
REACTOR TRIP REACTOR TRIP AD/2RSE CNMT MANUAL TURBINE TRIP LOW FLOW /RCP/P7 OVERTEMP A T NIS HI PLUI g
REACTOR TRIP DUE TO PERMISSIVE REACTOR TRIP HI SET POINT REACTOR TRIP REACTOR TRIP PWR RNC RI TRP MANUAL LO STM LOW PLOW /RCP/P8 OVERPOWER AT p
SAFETT INJ PRESS SLI PERMISSIVE REACTOR TRIP REACTOR TRIP SI-RI TRIP REACTOR TRIP
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PROCEDURE NO.
REVISION PAGE NO VEGP 17009-1 4
3 of 33 ANNUNCIATOR RESPONSE INDEX ANNUNCIATOR WINDOW NO, TITLE PAGE A01 STM GEN LOOP 1 LO-LO LEVEL REACTOR 5
TRIP A02 STM GEN 1 HI-HI LEVEL TURBINE TRIP 6
A03 A04 PRZR PRESS SI RX TRIP 7
-A05 NIS HI FLUX SOURCE RANGE REACTOR TRIP 8
A06 UNDERVOLTAGE RCP BUS /P7 REACTOR TRIP 9
B01 STM GEN LOOP 2 LO-LO LEVEL REACTOR 10 TRIP B02 STM GEN 2 HI-HI LEVEL TURBINE TRIP 11 B03
-B04 PRZR LO PRESS /P7 REACTOR TRIP 12 B05 NIS HI FLUX IR REACTOR TRIP 13 B06 UNDERFREQUENCY RCP BUS /P7 REACTOR 14-TRIP C01 STM GEN LOOP 3 LO-LO LEVEL REACTOR 15 TRIP CO2 STM GEN 3 HI-HI LEVEL TURBINE TRIP 16 C03 C04 PRZR HI PRESS REACTOR TRlP 17 C05 NIS HI FLUX LO SET POINT FWR RNG RX 18 TRP C06 TURBINE TRIP /P9 REACTOR TRIP 19
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PQOCEDU REVISION PAGE NO, ANNUNCIATOR WINDOW NO.
TITLE PAGE D01 STM CEN LOOP 4 LO-LO LEVEL REACTOR 20 TRIP D02 STM GEN 4 HI-HI LEVEL TURBINE TRIP 21 D03 D04 PRZR HI LEVEL /P7 REACTOR TRIP 22 DOS NIS HI FLUX RATE PWR RANGE REACTOR 23 TRIP D06 HI CNMT PRESS SI RX TRIP ADVERSE 24 CNMT E01 MANUAL REACTOR TRIP 25 E02 TURBINE TRIP DUE TO REACTOR TRIP 26 E03 LOW FLOW /RCP/P7 PERMISSIVE REACTOR 27 TRIP E04 OVERTEMP AT REACTOR TRIP 28 E05 NIS HI FLUX HI SET POINT PWR RNG RX 29 TRP-E06 F01 MANUAL SAFEIT INJ REACTOR TRIP 30 F02 LO STM PRESS SLI SI-RX TRIP 31 F03 LOW FLOW /RCP/P8 FERMISSIVE REACTOR 32 TRIP F04 OVERPOWER AT REACTOR TRIP 33 F05 F06 703445
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PROCEDURE No.
REVISION PAGE NO.
VEGP-17009-1 4
5 of 33 VINDOW A01 ORIGIN SETPOINT STM GEN LOOP 1 Any'two of the 18.5% on narrow LO-LO LEVEL following:
range REACTOR TRIP a.
1~LT-0551 b.
1-LT-0517 c.
1-LT-0518 d.
1-LT-0519 1.0 PROBABLE CAUSE 1.
Feedwater Regulator or Bypass Valve malfunctions.
2.
Steam Generator Level Control System malfunction.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Auxiliary Feedwater Initiation.
4.
Feedwater Isolation if Tavg is less than 564*F.
5.
Steam Dump Armed.
6.
Steam Generators Blowdown Isolation and Sample Line Valves Close.
3.0-INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE-END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.,
Technical Specifications Section 2.2.1
9 L'
PHoCEDURE No.
REVISION PAGE No.
VEGP 17009-1 4
6 of 33 WINDOW A02 ORIGIN SETPOINT STM GEN 1 Any two of the 78% on narrow HI-HI LEVEL following:
range TURBINE TRIP a.
1-LT-0551 b.
1-LT-0517 c.
1-LT-0518 d.
1-LT-0519 1.0 PROBABLE CAUSE 1.-
Feedwater Regulator or Bypass Valve malfunction.
2.
Steam Generator Level Control System malfunction.
2.0 AUTOMATIC AC'fIONS 1.
2.
Reactor Trip if above P-9.
3.
Main Feedwater Pumps Trip.
4.
Feedwater Isolation.
5.
Auxiliary Feedwater Initiation.
3.0 INITIAL OPERATOR ACTIONS 1.
If less than 50% Reactor Power Go to 18011-C,
" Turbine Trip.Below P-9".
2.
If greater than 50% Reactor Power GO to 19000-C, "E-O Reactor Trip _ Or Safety Inj ection".
4,0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE RFFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.
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PMoCEDUMkGP 17009 4 7 of 33 No.
REVISloN PAGE No, V
1 WINDOW A04 ORIGIN SETPOINT PRZR PRESS.
'Any two of the 1870 psig SI followingr RX TRIP a,
1-PT-0455 Db.
.1-PT-0456 4
c.
1-PT-0457 d.
1-PT-0456 1.0 PROBABLE CAUSE-1.
Loss of coolant accident or 3ceam Generator tube rupture.
2.
Pressurizer Pressure Control System malfunction.
2.0 AUTOMATIC ACTIONS NOTE This function la r.anually
-blocked below P-ll permissive.
1.
-2..
3.
Safety Injection Signals Actuation.
~
3.0
, INITIAL OPERATOR ACTIONS GO to'19000-C, "E-0 Reactor Trip _Or Safety Injection".
4.0=
SUBSEQUENT UPERATOR ACTIONS NONE~
2 5.0-COMPENSATORY OPERATdR ACTIONS NONE
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END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-230, P.L.S.,
Technical Specifications Section 3.3.2 Wh 3
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c PRoCEDU'.E No.
REVISloN PAGE NC.
VEGP 17009-1 4
8 of 33 WINDOW A05 ORIGIN SETPOINT NIS HI FLUX 5
N 10 counts /sec SOURCE RANGE N-32 REACTOR TRIP 1.0
, PROBABLE CAUSE 1.
One or both source range channels reaching high flux level.
2.
Loss of control power to one or both Source Range Cabinets.
2.0 AUTOMATIC ACTIONS NOTE This trip function blocked above P-6, 1.
2.
Turbine Trin.
3.
Feedwater Isolation if Tava is less than 564*F.
4.
Steam Dump Armed.
3.0' INITIAL OPERATOR ACTIONS GO to.19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACT_ IONS NONE k
END'0F SUB-PROCEDURE l
REFERENCES:
FSAR Section 7.2, 1X6AS01-154, 1X6AA02-227, P.L.S.
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PROCEDURE No.
REVISloN PAGE No.
VEGP 17009-1 4
9 of 33
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VlNDOW A06 ORIGIN SETPOINT UNDERVOLTAGE f2.of 4 RCP 70% of bus RCP BUS /P7 Busses Under-voltage REACTOR TRIP voltage (27)
Relays when above P7 1.0 PROBABLE CAUSE Loss of power to 13.8kV bus 1NAA and/or bus 1 NAB.
2.0 AUTOMATIC ACTIONS NOTE This reactor trip is blocked below the P-7 permissive.
-1, Reactor Trip.
2.
3.
Feedwater Isolation if Tavg is less than 564*F.
4 Steam Dump Armed.
3.0 1NITIAL OPERATOR-ACTIONS Go to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0-COMPEN3ATORY OPERATOR ACTIONF NONE 4
G END OF S~UB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-229, 1X3D-BD-B01N, 1X3D-BD-B01P, 1X3D-BD-B0lX, 1X3D-BD-B01Y, P.L.S.
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a PROCEDURE No.-
REVISloN PAGE No.
VEGPL
-17009-1 4
10 of 33 WINDOW B01-O_RIGIN SETPOINT STM GEN LOOP 2 Any tvo of the 18.5%-on narrow LO-LO LEVEL following:
range REACTOR TRIP a.
1-LT-0552 b.
1-LT-0527 c.
1-LT-0528 d.
1-LT-0529 1.0 PROBABLE CAUSE 1.
Feedwater Regulator or Bypass Valve malfunction.
2.
Steam Generator Level Control System malfunction.
2.0 AUTOMATIC ACTIONS, 1.
2.
3.
Auxiliary Feedwater Initiation.
4.
Feedwater isolation if Tavg is less than 564 *F.
5..
Steam Dump Armed.
6..
Steam Generators Blowdown Isolation and Sample Line Valves.Cicse.
3.0 INITIAL ~ OPERATOR ACTIONS L
GO to-19000-C, "E-0 Reactor Trip or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE' END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.,
Technical Specifications Section 2.2.1 l
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PROCEDURE NO.
REVISION PAGE NO VEGP 17009-1 4
11aof 33 WINDOW B02 ORIGIN SETPOINT STM GEN 2 Any two of the 78% on narrow HI-H1 LEVEL following:
range TURBINE TRIP a.
1-LT-0552 b.
1-LT-0527 c.
1-LT-0528 d.
1-LT-0529-1.0 PROBABLE CAUSE 1-Feedwater Regulator or Bypass Valve malfunctions.
2.
Steam Generator Level Control System malfunction.
2.0 AUTOMAT,IC ACTIONS 1.
2.
Reactor Trip if above P-9.
3.
Main _Feedwater Pumps Trip.
4.
Feedwater Isolation.
5.
Auxiliary Feedwater Initiation.
3.0 INITIAL OPERATOR ACTIONS 1.
If less than 50% Reactor Power GO to 18011-C,
" Turbine Trip Below P-9".
2.
If greater than 50% Go to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS
?
NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.
P40CEDURE NO.
REVIStoN PAGE NO, VEGP-17009-1.
4 12 of 33
. WINDOW B04 ORIGIN' SETPOINT PRZR LO Any two of the 1960 psig PRESS /P7
-following:
REACTOR TRIP a.
1-PT-0455 b.
1-PT-0456 c.
1-PT-0457 d.
.1-PT-0458 1.0 PROBABLE CAUSE 1.
Loss of coolant accident or Steam Generator tube rupture.
2.
Pressurizer Spray malfunction.
3.
Pressurizer Pressure Contre' System malfunction.
2.0 AUTOMATIC ACTIONS NOTE This trip function is blocked below the P-7 permissive.
1.
2.
3.
Feedwater Isolation if Tavg is less than 564'F, 4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS Go to,19000-C, E-O Reactor Trip Or Safety. Inj ection".
-4. 0 -
SUBSEQUENT OPERATOR ACTIONS NONE,-
5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-230, P.L.S.
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f PWcEDURE NO.
REVistoN FAGE 900~
VEGP 17009-1 4
13 of 33J WINDOW BOS ORIGIN SETPOINT NIS HI FLUX N-35 Current equivalent IR-N-36 to 25% of full REACTOR TRIP power 1.0 PROBABLE CAUSE 1.
One or both intermediate range channels reaching.
high flux level.
2.
Loss of control power to one or both Intermediate -
Range Cabinets.
2.0 AUTOMATIC ACTIONS 1.
2.-
3.
Feedwater Isolation if Tavg is less than 564*F.
'4 Steam Dump Armed.
3.0
'_NITIAL OPERATOR ACTIONS I
00 to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS N0iiE 5.0 COMPENSATORY OPERATOR ACTIONS NONE o
1 END OF SUB-PROCEDURE
REFERENCES:
_FSAR Section 7.2, 1X6AS01-154, 1X6AA02-227, P.L.S.
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1 PROCEDUf;E NO.
REVISION PAG!! NO.
VEGP 17009 4 14 of 33 WINDOW B06 ORIGIN SETPOINT UNDERPREQUENCY
-2 of 4 RCP Buses 57.3 H, RCP BUS /P7 Underfrequency REACTOR TRIP (81) Relays when above P7 1.0 PROBABLE CAUSE Underfrequency condition on 13.8kV bus 1NAA or INAB.
2.0 AUTOMATIC ACTIONS' gg{E This reactor trip is blocked below the P-7 permissive.
1.
2.
3.
Feedwater Isolation if Tavg is less than 564*F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Inj ection".
- 4. 0-SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE l-l l
l l
END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-229, 1X3D-BD-B01N, 1X3D-BD-B0lP, IX3D-BD-B0lX, 1X3D-BD-B0lY, P.L.S.
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PHoCEDURE 94o. -
19EVISioN
?kGE NO.
'17009-1 4
15 of 33-WINDOW C01 ORIGIN SETPOINT i'
STM GEN LOOP 3 Any two of the 18.5% on narrow LO-LO LEVEL following:
range REACTOR THIP a.
1-LT-0553 b.
1-LT-0537 c.
1-LT-0538 d-1-LT-0539 1.0 PROBABLE CAUSE 1.
Feedwater Regulator or Bypass Valve malfunctions.
2.
Steen Concr:ter Lcycl Control Systcc calfunctica, 2.0 A_UTOMATIC ACTIONS 1.
2.
3.
Auxiliary Feedwater Initiation.
4.
Feedwater Isolation if Tavs is less than 564'F.
5.
Steam Dump Armed.
6.
Steam Generators Blowdown Isolation and Sample Line Valves Close.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS
}K)}UE 5.0 COMPENSATORY OPERATOR ACTIONS NONE' END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA07-231, P.L.S.,
Technical Specifications Section 2.2.1
~
PQOCEDUREWO.
RE%SIOh PAGE No.
VEGP 17009-1 4
16 of 33 WINDOW CO2 ORIGIN SETPOINT STM-GEN 3
'Any-two of the.
78% on-narrow HI-HI LEVEL-following :
range TURBINE-TRIP s.
1-LT-0553 b.
1-LT-0537 c.
1-LT-0538 d.
1-LT-0539 1.0 PROBABLE _CAUSE L
1.
Feedwater Regulator or Bypass Valve malfunctions, t
2.
Steam Generator IcVel Control System mm.1 function.
2.0 AUTOMATIC ACTIONS 1.
2.
Reactor Trip if above P-9.
3.
Main Feedwater Pumps Trip.
l 4
Feedvater Isolation.
l S.
Auxiliary Feedwater Initiation.
l 3.0 INITIAL OPERATOR ACTIONS 1.
If less than 50% 1X) to 18011-C, " Turbine Trip Below P-9".
2.
If greater thaa 50% Go to 19000-C, "E-O Reactor Trip Or Safety Injection".
-4.0 pyBSEQUEN_T OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE E
i END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, IX6AA02-231, P.L.S.
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FROCEDURE NO.
REVCoN PAGE No.
VEGP 17009-1 4
17 of 33 WINDOW C04 ORIGIN-SETPOINT
~
PR2R HI PRESS Any two of the 2385 psig REACTOR TRIP following:
a, 1-PT-0455 b.
1-PT-0456 c.
1-PT-0457 d.
1-PT-0458 1.0 PROBABLE CAUSE 1.
Pressurizer Pressure Control System malfunction.
2.
Load rejection.
- 2.0 AUTOMATIC ACTIONS 1.
2.
3.
Feedwater isolation if Tavg is less than 564'F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-230, P.L.S.
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~
PROCEDUR* MO.
REVIMoN CDAGE No.
VEGP 17009-1 4
18 of 33 ORIGIN SETPOINT
~
~~
NIS HI FLUX
'Any-two of the' 252 of full power LO SET POINT following:
PWR RNG RX TRP a,
N-41 b.
N-42 c.
N-43 d.
N-44 1.0 PROBABLE CAUSE 1.
High flux (low setpoint) on at least 2 out of 4 Power Range Channels.
2.
Loss of control power to at least 2 out of 4 Power Range Monitors.
2.0 AUTOMATIC ACTIONS NOTE This trip is normally manually blocked after the P-10 permissive.
1.
2.
3.
Feedwater Isolation if Tavg is less than 564*F.
4.
Steam Dump _ Armed.
3.0 INITIAL OPERATOR ACTIONS-GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTION 4 NONE
- 5.0 COMPtNSATORY OPERATOR ACTIONS NONE-l END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AS01-154, 1X6AA02-227, P.L.S.
~
DCEDURE NO.
REVISloN PAGE No.
VEGP 17009-1 4
19 of 33 WINDOW C06 ORIGIN SETPOINT
~~
TURBINE Any.two of the 580 psig TRIP /P9 following:
REACTOR TRIP a.
1-PT-6161 b.
1-PT-6162 c.
1-PT-6163 OR all four Steam
.Etcp Valves less than 96.7% open 1.0 PROBABLE CAUSE Turbine Trip above P>9.
2.0 AUTOMATIC ACTIONS 1.
2.
Reactor Trip, if greater than 50% Reactor Power.
3.
Feedwater Isolation if Tavg is less than 564*F.-
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-0 Reactor Trip Or Safety Inj ection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE-
-5. 0 COMPENSATORY OPERATOR ACTIONS NONE.
END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-240, 1X4DB194, P.L.S.,
Technical Specifications Section 2.2.1
- m..s.
PROCEDURE No.
HEVtSloN PAGE NO VEGP 17009-1 4
20 of 33 WINDOW D01 ORIGIN SETPOINT
~
STM GEN LOOP 4 Any two of the 18,5 % on narrow LO-LO LEVEL following:
range REACTOR TRIF a.
1-LT-0554 b.
1-LT-0547 c.
1-LT-0548 d,
1-LT-0549 1.0 PROBABLE CAUSE 1.
Feedwater Regulator or Bypass Valve malfunctions.
2.
Steam Generator Level Control Sys tem malfunction.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Auxiliary Feedwater Initiation, 4.
Feedwater Isolation if Tavg is less than 564*F, 5.
Steam Dump Armed, 6.
Steam Generators Blowdown Isolation and Sample Line Valves Close.
3,0 INITIAL OPERATOR ACTI0h]
GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 S_UBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PPOCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.,
Technical j
Specifications Section 2.2.1
-_______--__A
FRoCEDURENo.
REVISioW PAGE No.
VEGP 17009-1 4
21 of 33 WINDOW D02 ORIGIN SETPOINT STM GEN 4 Any two of the 78% on narrow HI-HI LEVEL following range TURBINE TRIP a.
1-LT-0554 b.
1-LT-0547 c.
1-LT-0548 d.
1-LT-0549 1.0 PROBABLE CAUSE 1.
Feedwater Regulator or Bypass Valve malfunctions.
2.
Stehm Generator Level Control.
l 2.0 AUTOMATIC ACTIONS 1.
2.
Reactor Trip if above P-9.
3.
Mair. Feedwater Pumpa Trip.
f 4
Feedwater Isolation.
5.
Auxiliary Feedwater Initiation.
3.0 INITIAL OPERATOR ACTIONS 1.
If less than 50% Go to 180ll-C, " Turbine Trip Below P-9".
2.
If greater than 50%_GO to 19000-C, " E-0 Reactor Trip Or Safety Inj ection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.
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PRoCEDLCE No.
REVISloN PAGE No-VEGP-17009-1 4
22-of 33 WINDOW D04 ORIGIN SETPOINT PRZR HI Any'two of the 92% of span LEVEL /P7 following:
REACTOR TRIP a.
1-LT-0459 b.
1-LT-0460 c.
1-LT-0461 1.0 PROBABLE CAUSE 1.
Pressurizer Level Control System malfunction.
2.
Charging Flow Valve 1-FV-121 failed open.
2.0 AUTOMATIC ACTIONS NOTE This trip function is blocked below the P-7 permissive.
1.
2.-
3.
Feedwater Isolation if Tavg is less than 564*F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS L
Go to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 S_UBSEQUENT OPERATOR ACTIONS NONE I
5.0 COMPENSATORY OPERATOR ACTIONS l
NONE.
l.
i-i END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-230, P.L.S.
l
m
, ~.. _.
-)
-C PROCEDURE No.-
REVIStoN PAGE No,
- VEGP-17009-1 4
23 of 33 WINDOW DOS-s ORIGIN SETPOINT NIS HI FLUX Any two of-the i.5% of full power RATE PWR RANGE following:
per 2 seconds REACTOR TRIP a.
N-41 b.
N-42 c.
N-43 d.
N-44 1.0 PROBABLE CAUSE 1.
High positive power rate due to ejected rod.
2.
High negative power rate due to one or more dropped rods.
3.
Loss of control power to at least 2 out of 4 Power Range Detectors.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Feedvater Isolation if Tavg is less than 564'F.
4.
Steam _ Dump Armed.
3,0 INITIAL OPER/d'OR ACTIONS y
GO to 19000-C, "E-0 Reactor Trip Or Safety Injection". _
i 4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS g
NONE.
END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AS01-154, 1X6AA02-227, P.L.S.
,,g.
i.
PROCEDUQE NO.
REVISION PAC E NO.
VEGP 17009-1 4
24 of 33 t
WINDOW D06 ORIGIN SETPOINT HI CNMT PRESS
'Anv two of the 3.8 psig SI RX TRIP following:
ADVERSE CNMT a.
1-PT-0934 b.
1-PT-0935 c.
1-PT-0936 1.0 PROBABLE CAUSE Containment Hi pressure from either a Reactor Coolant System or secondary system pipe break, 2.0 AUTOMATIC ACTIONS 1.
2.
3.
Safety Injection Signals Actuation.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-0 Reactor. Trip Or Safety Injectioti "
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-232, P.L.S.
~
mm.
~
~
PROCEDURE No.
REVIStoN PAGE NO, VEGP 17009-1 4
25 of 33 WINDOW E01 ORIGIN SETPOINT
~ '
MANUAL 1-HS-40002 Not Applicable REACTOR TRIP or 1-HS-40007 1.0-PROBABLE CAUSE Reactor tripped manually.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Feedwater Isolation if Tavg is less than 564*P.
4 Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C,_ "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X3D-BD-UO1C i
l'
.~
. ~.
i PROCEDURL NO, REVISION PAGE NO.
VEGP' 17009 4 26 of 33 WINDOW E02 ORIGIN-SETPOINT
-~
'The following Not Applicable DUE TO Reactor Trip REACTOR TRIP Breakers Open:
RTA, BYA RTB, BYB 1.0 PROBABLE CAUSE Turbine Trip caused by Reactor Trip.
2.0 AUTOMATIC ACTIONS 1.
2.
Steam Dump Armed.
3.
Feedwater Isolation if Tavg is less than 564*F.
l 3.0 INITIAi. OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection",
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR-ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-240, P.L.S.
~
.. m u.
4..
PROCEDURE NO.
REVIStoN PAGE No.
VEGP.
17009-1 4
7 of 33 WINDOW E03 ORIGIN SETPOINT
-- ~ -
LOW FLOW /RCP/P7 2 of 4 RCP Loops 90% of normal flow PERMISSIVE 1
Low Flow when REACTOR TRIP above-P7 1.0
-PROBABLE CAUSE 1.
Loss of 13.8kV bus 1NAA or 1 NAB.
2.
Two or.more Reactor Coolant Pump Breakers tripped.
2.0 AUTOMATIC ACTIONS NOTE This trip function is blocked below the P-7 permissiva.
1.
2.
3.
Feedwater Isolation if Tavg is less than 564*F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS Go to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COP.PENSATORY_ OPERATOR ACTIONS NONE l
l END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-229, P.L.S.
l l
sw
' PROCEDURE No.
REVISloN PAGE No VEGP 17009-1 4
28 of 33 WINDOW E04
_0RIGIN SETPOINT OVERTEMP AT Any two of the Variable REACTOR TRAP following a.
1-TI-0411 b.
1-TI-0421 c.
1-TI-0431 d.
1-TI-0441 1.0 PROBABLE CAUSE Overtemperature T caused by a combination of:
pressurner pressure, Tavg, and neutron flux.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Feedwater Isolation if Tavg is less than 564*F, 4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS Go to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 C_0MPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-229, P.L.S.
1 m"'
4 '
l
.4 PROCEDURE No.
NVISloN PAGE No.
VEGP 17009-1 4
29.of 33 I
WINDOW E05 ORIGIN SETPOINT NIS HI FLUX
.'Any.two of the 109% of full power HI SET POINT following:
PWR RNG RX TRP a.
N-41 b.
N-42 c.
N-43 d.
N-44 1.0 PROBABLE CAUSE 1.
High-flux range (high setpoint) on at least 2 out of 4 Power Range Monitors.
2.
Loss of control power to at least 2 out of 4 Fower Range Monitors.
2.0 AUTOMATIC ACTIONS
.1.
Reactor. Trip.
2.
3.
Feedwater Isolation if Tavg is less-than 564*F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0
. SUBSEQUENT OPERATOR ACTIONS, NONE 5.0 COMPENSATORY OPERATOR ACTIONS.
NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AS01-154, 1X6AA02-227, P.L.S.
e n -
s-PROCEDURE NO.
REVISION PAGE NO, VEGP 17009-1 4
30 of 33 WINDOW F01 ORIGIN SETPOINT j
MANUAL
- 1-HS-40003 or Not Applicable SAFETY INJ 1-HS-40008 REACTOR TRIP 1.0 PROBABLE CAUSE Manual Safety Injection.
2.0 AUTOMATIC ACTIONS 1.
2.
3.
Safety Injection Signals Actuation 3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X3D-BD-U01C M448
n-4.
PRoCEDU@E No, REVISION PAGE Wo.
l VEGP.
17009-1 4
31 of 33 1
WINDOW F02 ORIGIN SETPOINT LO STM 585 psig PRESS SLI 1 of 4 Steamlines Low Pressure SI-RX TRIP when above P-ll 1.0 PROBABLE CAUSE
-Low steamline pressure due to a system rupture.
2.0 AUTOMATIC ACTIONS NOTE t
This function is manually blocked below the P-ll permissive.
1.
Reactor Trip, i
2.
3.
Safety Injection Signals Actuation.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection",
- 4. 0 SUBSEQUENT OPERATOR ACTIONS NONE
.5.0 COMPENSATORY OPERATOR ACTIONS NONE t!
1
(
i END OF SUS-PROCEDURE
REFERENCES:
FSAR Section 7.2, 1X6AA02-231, P.L.S.
$344$ '
o pc
- 1 PROCEDURE No.
REVIStoN PAGE No.
~]
VEGP 17009-1 4
32 of 33 WINDOW F03 ORIGIN SETPOINT
~~~'
LOW FLOW /RCP/F8
.1 of 4 RCP Loops 90*4 of normal flow PERMISSIVE Low Flow when REACTOR TRIP above P-8 1.0 PROBABLE CAU$6 Loss of power to one or more Reactor Coolant Pumps-or one or more Reactor Coolant Pump Breakers tripped.
2.0 AUTOMATIC ACTIONS E:'TE This trip function is blocked below the P 8 permissive.
1.
2.
3.
Feedwater Isolation if Tavg is less than 564*F.
4.
Steam Dump Armed.
3.0 INITIAL OPERATOR AC7;[ONS GO to 19000-C, "E-0 Reactor Trip Or Safety Injection".
4.0 SUBSEQUENT OPERATOR, ACTIONS NONE 5.0 COMPENSATORY OPERATCR ACTIONS NONE END OF SUB-PROCEDURE
REFERENCES:
FSAR Section 7.2,
.Z6AA02-229, P.L.S.
)
m
!s FGoCEDURE No.
REVIStoN PAGL No.
VEGP 17009-1 4
33 of 33 WINDOW F04.
ORIGIN SETPOINT
~
OVERPOWER AT-Any two of the Variable REACTOR TRIP following:
a.
1-TI-0411 b.
1-TI-0421 c.
1-TI-0431 d.
1-TI-0441 1.0 PROBABLE CAUSE Overpower T caused by a combination of:
Tavg and neutron flux.
20 AUTOMATIC AC'i10NS 1.-
2.
3.
Feedwater Isolation if Tavg is less than 564'F.
4 Steam Dump Armed.
3.0 INITIAL OPERATOR ACTIONS GO to 19000-C, "E-O Reactor Trip Or Safety Injection".
4.0-SUBSEQUENT OPERATOR ACTIONS NONE 5.0 COMPENSATORY OPERATOR ACTIONS NONE END OF PROCEDURE TEXT
REFERENCES:
FSAR Section 7.2, 1X6AA02-229, P.L.S.
7o