ML20094C098
| ML20094C098 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/05/1984 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20094C092 | List: |
| References | |
| OS1300, NUDOCS 8408070365 | |
| Download: ML20094C098 (25) | |
Text
Coda Syap ten /
Title:
Procedure No.
4 Ravisica No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 A. PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a reactor trip or safety injection, to assess plant conditions, and to identify the appropriate recovery procedure.
B. SYMPTOMS OR ENTRY CONDITIONS
- 1. Any symptom that requires a manual reactor trip listed in ATTACHMENT A, if one has not occurred.
- 2. The following are symptoms of a reactor trip:
- a. Any reactor trip annunciator lit.
- b. Rapid decrease in neutron level indicated by nuclear instrumen-tation.
- c. All shutdown and control rods are fully inserted. Rod bottom i lights are lit.
- 3. Any symptom that requires a manual reactor trip and safety injection listed in ATTACHMENT B, if one has not occurred.
- 4. The following are symptoms of a reactor trip and safety injecItion:
- a. Any SI annunciator or status lamp lit.
- b. ECCS pumps in service.
I l
i 1 of 25 A
8070365 g40739 p ADOCK 05000443 PDR
(E-0)
OPERATOR ACTION
SUMMARY
FOR E-0 SERIES PROCEDURES
- AND -
RCS Subcooling - LESS THAN 30'F e Phase B containment isolation (loss of PCCW) e RCP seal AP - LESS THAN 220 PSID e RCP #1 seal leakoff flow - LESS THAN 0.2 GPM
- 2. ECCS ACTUATION CRITERIA Actuate SI and go to E-0, REACTOR TRIP OR SAFETY INJECTION, Step 1, if EITHER condition listed below occurs:
e RCS subcooling - LESS THAN 30'F
- OR -
e Pressurizer level - CANNOT BE MAINTAINED GREATER THAN 5%
[(50)% FOR ADVERSE CONTAINMENT)
- 4. RED PATH
SUMMARY
- ATTACHMENT F
- 5. KEY CAUTIONS e If offsite power is lost af ter SI reset, manual action may be required to restart safeguard equipment.
e RCS pressure should be menitored. If RCS pressure drops below 200 PSIC, RHR pumps must be manually restarted to supply water to RCS.
t
/6 .
Cods: Syapton/ Title Precsdura No.
Revision No./Date E- 0 REACTOR TRIP OR SAFETY INJECTION OS1300 Re v. 1 0 / 06/05/84 l ST;P l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l
[
NOTE e Steps 1 through 14 are IMMEDIATE ACTION steps.
o Initiate monitoring of critical safety function status trees at Step 27 Ojt if exiting from this procedure.
e Review OPERATOR ACTION
SUMMARY
periodically.
1 Verify Reactor Trip Manually trip reactor. Ij[
reactor will NOT trip, THEN go e Rod bottom lights - LIT to FR-S.1, RESPONSE.TO NUCLEAR POWER GENERATION /ATWS, Step 1.
- Reactor trip and bypass breakers - OPEN e Neutron flux - DECREASING 2 Verify Turbine Trip:
- a. All turbine stop valves - a. Manually trip turbine. IJ[
CLOSED turbine will NOT trip, THEN close MSIVs and open generator breaker.
3 Verify Power To AC Emergency Busses:
- a. AC emergency busses - a. Try to restore power to at AT LEAST ONE ENERGIZED least one 'c emergency bus.
IJ[ power can NOT be re-e E-5 Voltmeter stored to at least one ac emergency bus, THEN go to e E-6 Voltmeter ECA-0.0, LOSS OF ALL AC POWER, Step 1.
- b. AC emergenc'y busses - b. Try to restore power to ALL ENERGIZED deenergized ac emergency busses.
l 2 of 25 m
Csda Symp tem / Title s Procedure No.
Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 4 Check If SI Is Actuated: Check if SI is required.
SI IS REQUIRED IF:
e SI Annuncia tor - TRAIN A
- OR - 1) Pressurizer pressure - LESS e SI Annunciator - TRAIN B THAN 1850 PSIG AND DECREASING
- OR -
MANUALLY ACTUATE SI IF ANY 2) Containment pressure -
TRAIN UNACTUATED GREATER TRAN 4.0 PSIG
- OR -
- 3) Steamline pressure - LESS THAN 585 PSIG AND DECREASING
- OR -
- 4) RCS subcooling - LESS THAN 30'F
- OR -
- 5) Pressurizer level - LESS THAN 5% DECREASING Il[ SI is required, THEN manually actuate.
E SI is NOT required, THEN go to ES-0.1, REACTOR TRIP RESPONSE, Step 1.
5 Verify Feedwater Isola tion: Manually close valves or trip main feedwater pumps as necessary.
- a. Check feed regula ting -
valves - CLOSED
- b. Check feed regulating bypass valves - CLOSED
- c. Check feedwater isolation ,
valves - CLOSED
- d. Check main feedwater pump turbines - TRIPPED
- e. Check main feedwater pump discharge valves - CLOSED 3 of 25 k .
C:d2: Sy ptsa/ Titles l Prcesdure No.
Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE } l RESPONSE NOT OBTAINED l 6 Verify Containment Isolation Phase A Actuation:
- a. Phase A components - ALL a. Manually actuate 'T' signal STATUS PANEL LIGHTS LIT for BOTH trains. Align equipment as necessary by e TRAIN A status panels.
e TRAIN B 7 Verify EFW Pumps Running:
- a. Mo tor-driven pump - RUNNING a. Manually start pump.
- b. Turbine-driven pump - b. Manually open at least one RUNNING steam supply valve or reset trip valve as necessary.
e MS-V127 - OPEN e MS-V128 - OPEN e TRIP VALVE MS-V129 -
OPEN i
- 8 Verify ECCS Pumps Running
- Manually start pumps.
l l e CCPs - TRAIN A AND B e SI pumps - TRAIN A AND B e RHR pumps - TRAIN A AND B l
I 9 Verify PCCW Pumps - RUNNING: Manually start pumps.
- s. Loop A - ONE PUMP RUNNING
- b. Loop B - ONE PUMP RUNNING
- c. Thermal barrier cooling pumps - AT LEAST ONE PUMP RUNNING f
I 4 of 25 E.
/7)
Cida: Sysp tem /
Title:
Procedure No.
R2visicn No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 10 Verify Ultimate Heat Sink Manually start SW pumps or Opera tion s actuate TA as necessary.
- a. Train A - RUNNING e One SW pump
- OR -
e One CT pump AND CT fan in TA mode
- b. Train B - RUNNING e One SW pump
- OR -
e One CT pump AND CT fan in TA mode 11 Verify SW Cooling To DCCW:
l a. Train A cooling established:
- 1) SW-V16 - OPEN 1) Manually or locally open-SW-V16.
- 2) Flow indicated - GREATER THAN 1700 GPM
- b. Train B cooling established:
- 1) SW-V18 - OPEN 1) Manually or locally open SW-V18.
- 2) Flow indicated - GREATER THAN 1700 GPM l 5 of 25 20
Codos Syrptsc/Ti tle: Procsdure No. !
Ravision No./Da ta s l l
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 12 Verify Containment Enclosure Cooling And Exhausts
- a. Verify at least one containment a. Start at least one cooling enclosure cooling fan - RUNNING unit.
e FN-SA e FN-58
- b. Verify containment enclosure b. Adjust enclosure pressure as negative pressure - BETWEEN necessary to keep it negative.
(-)0.15 AND (-)0.35 INCHES W.C. _IF_ static pressure controllers do NOT control pressure in range, THEN place modulating dampers to open position.
e DP-29A OPEN e DP-29B OPEN i
) 13 Check If Main Steamlines Should Be Isolated:
- a. Steam line isolation is a. Go to Step 14.
REQJIRED IF:
e Any steamline - LESS THAN OR EQUAL TO 585 PSIG WITHOUT PRIOR P-11 BLOCK
- OR -
e Containment pressure is -
l GREATER TRAN OR EQUAL TO 4.3 PSIC
- OR -
e Main steamline pressure i negative rate bistable
- i. trip light (s) - LIT i
i valves - CLOSED I 6 of 25 h i
J2/
l
T Cod 2: Sysp ton /
Title:
Procedure No.
R2 vision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 4
l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 14 Check Containment Pressure - IF pressure has exceeded 18 PSIG, HAS REMAINED LESS THAN 18 PSIG TEIEN:
BY PRESSURE RECORDING
- a. Verify containment spray initiated:
- 1) Train A in operation:
o CBS Pump A - RUNNING l
e CBS-Vll - OPEN e CBS Pump A discharge pressure - LESS THAN 290 PSIG e Miniflows - CLOSED
- 2) Train B in operation:
I e CBS Pump B - RUNNING e CBS-V17 - OPEN e CBS Pump B discharge pressure - LESS THAN 290 PSIG e Miniflows - CLOSED
- 3) SAT outlet valves -
AT LEAST ONE OPEN e CBS-V38 e CBS-V43
! IjP NOT initiated, THEN manually initiate.
- a. HOLD BOTH manual activa te switches in a train AND place to ACTUATE.
l
- b. Verify containment Phase B
('P' signal) actuated.
l i 1) All Phase B status lights - LIT l
e TRAIN A AND e TRAIN B Manually align valves and equipment as necessary.
~
, c. Stop ALL RCPs.
7 of 25
- c22
Coda: Synp ton /
Title:
Procsdure No.
Revision No./Date:
l E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 1 Re v. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 15 Verify ECCS Flow:
- a. CCP flow indicator - a. Manually start pumps and CHECK FOR FLOW THROUGH align valves.
BIT PATH
- b. RCS pressure - LESS TRAN b. Go to Step 16.
1450 PSIG
- c. SI pump flow indicators - c. Manually start pumps and CHECK FOR FLOW align valves.
e TRAI!; A e TRAIN B
- d. RCS pressure - LESS THAN d. Go to Step 16.
130 PSIG
- e. RHR pump flow indicators - e. Manually start pumps and CHECK FOR FLOW align valves.
e TRAIN A e TRAIN B 8 of 25 h
C3das Symptoc/
Title:
Prcesdure No.
Revisien No./Date:
- E- 0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84
[ STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 16 Verify EFW Flow - GREATER TRAN Manually start pumps. IJ[ proper 470 GPM TOTAL COMBINED FLOW TO flow can NOT be established, THEN AT LEAST TWO SGs go to FR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, STEP 1.
NOTE High EFW flow to a faulted SG will cause automatic closure of that SG's EFW flow control valves.
17 Verify EFW Valve Alignment - Manually align valves as PROPER EMERGENCY ALIGNMENT necessary.
NORMAL IJ[ valves to a SG are closed, SG VALVE NOMENCLATURE POSITION THEN verify that the SG is faulted. Djl NOT reopen valves A FV-4214A, FLOW CONTROL OPEN to a faulted SG.
TV-4214B, FLOW CONTROL OPEN IF SG is NOT faulted, THEN check j that EFW line is intact before B FV-4224A, FLOW CONTROL OPEN reestablishing EFW flow to that l
FV-4224B, FLOW CONTROL OPEN SG.
C FV-4234A, FLOW CONTROL OPEN FV-4234B, FLOW CONTROL OPEN l
D FV-4244A, FLOW CONTROL OPEN FV-4244B, FLOW CONTROL OPEN l
i l
l*
I 9 of 25
C;d): Sy:p tim / Tit 12: Precedure No.
Ravisica No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 18 Verify ECCS Valve Alignment - Manually align valves as PROPER EMERGENCY ALIGNMENT necessary. ECCS valve align-INDICATED ON STATUS PANELS ment checklists are provided as ATTACHMENTS C, D and E.
e TRAIN A - COLD LEG INJECTION e TRAIN B - COLD LEG INJECTION l 19 Check RCS Temperature - STABLE IF temperature less than 557'F AT OR TRENDING TO 557'F and decreasing, THEN:
e WR LOOP COLD LEG TEMPERATURE a. Stop dumping steam.
RECORDERS
- OR - e Condenser e TAVG RECORDER IF RCPs RUNNING e Atmosphere
- b. Check MS to MSRs isolated.
LEVEL ABOVE SG U-TUBES ADVERSE CONTM NORMAL CONTM l
I NARROW RANGE NARROW RANGE LEVEL GREATER LEVEL GREATER THAN 35% THAN 5%
i
IF temperature greater than 357'F and increasing, THEN:
e Reset low-low Tavg interlock if necessary, and dump steam
,- to condenser.
- OR -
1 i e Dump steam with SG ASDVs.
10 of 25
Cod): Sy ptra/
Title:
Precedurs No.
Revisica No./Da te:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84
[ STEP l [ ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 20 Check PRZR PORVs And Spray Valves:
- a. PORVs - CLOSED a. IF PRZR pressure less than 1385 psig or LTOP setpoint, LTOP SETPOINT THEN manually close PORVs.
CURVE FIGURE IIPany valve can NOT be E-0-1 *'Tosed, c THEN manually close its block valve. IF block valve can NOT be cTosed, THEN go tot 1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. Normal PRZR spray valves - b. Il[ PRZR pressure less than CLOSED 2260 psig, THEN manually close valves. IF valves can NOT be closed, THEN stop RCP(s) supplying failed spray valve (s).
I e PCV-455A - RC-P-1C e PCV-455B - RC-P-1A NOTE Seal injection flow should be maintained to all RCPs.
21 Check If RCPs Should Be Stopped:
- a. High Head ECCS Pumps - AT a. Go to Step 22.
LEAST ONE RUNNING e CCP
-OR-e SI Pump,'
- b. RCS subcooling - LESS b. Go to Step 22.
THAN 30'F
- c. Stop all RCPs 11 of 25 b
Cod 3: Sycp tsn/
Title:
Precoduro No.
Revision No./ Dates E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 22 Check If SG Pressure Boundary Is Intact:
- a. Check pressures in all a. Go to E-2, FAULTED STEAM SGs - GENERATOR ISOLATION, Step 1.
e NO SG PRESSURE DECREASING IN AN UNCONTROLLED KANNER
- OR -
e NO SG COMPLETELY DEPRESSURIZED 23 Check If SG U-Tubes Are Intact: Go to E-3, STEAM GENERATOR
, TUBE RUPTURE, Step 1.
, o Main steamline radiation -
NORMAL ON EACH LINE e Condenser effluent radiation - NORMAL 24 Check If RCS Is Intact: Go to E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
o Containment radiation -
NORMAL e Containment pressure -
NORMAL e Containment building level - NORMAL l
12 of 25
Codas Synp tem /
Title:
Prccedure No.
Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 25 Check If ECCS Flow Should Be Reduced:
c THAN 30'F I b. Secondary heat sinks b.
l Il[ neither condition satis-
! fied, THEN DO NOT STOP CENTRIFUGAL CHARGING PUMPS e Total EFW flow to intact OR SI PUMPS. Go to Step 27.
SGs - GREATER THAN 470 GPM TOTAL COMBINED FLOW
- OR -
e NR level in at least one j ' intact SG - GREATER THAN l 5%.
l l
i
- d. PRZR level - GREATER THAN d. DO NOT STOP ECCS PUMPS. Try 5% to stabilize RCS pressure with normal spray. Return to Step 25a.
26 Go To ES-1.1, SI TERMINATION, Step 1 27 Initiate Monitoring Of Critical Safety Function Status Trees
' 13 of 25
Coda: Symp tsa/Titlo s Procedura No.
Ravision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 i
l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 4
CAUTION CST makeup should commence as early as possible to avoid low inventory problems.
28 Check SG Levels:
- a. NR level - GREATER a. Maintain EFW flow greater TRAN 5% than 470 GPM to intact SGs until NR level greater than 5% in at least one SG.
- b. Control EFW flow to b. IF, NR level in any SG maintain NR level - continues to increase in an BETWEEN 5% AND 50% uncontrolled manner, THEN go to E-3, STEAM GENERATOR TUBE RUPTURE, Step 1.
l r l l
29 Check Secondary Radiation - Go to E-3, STEAM GENERATOR NORMAL USING RDMS: TUBE RUPTURE, Step 1.
l e Main steamline radiation -
NORMAL ON EACH LINE ,
l e Condenser effluent i radiation - NORMAL l l
l l
14 of 25
Coda Syap ton /
Title:
Precedure No.
Ravision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 5
l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l 30 Check Auxiliary Building Evaluate cause of abnormal Radiation - NORMAL USING conditions. IF the cause is a RDHS loss of RCS inventory outside containment, THEN go to ECA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
31 Check PRT Conditions - Evaluate cause of abnormal NORMAL conditions.
e PORV OR SAFETY valve o Pressurizer PORV's and safeties tailpipe temperature -
LESS THAN 140'F e RHR relief valves e Pressure - BETWEEN 2 PSIG e Letdown relief valve AND 4 PSIG e Seal return header relief e Level - BETWEEN 50% AND 86% valve o Temperature - LESS THAN 120'F e Reactor vessel head vent i
1 CAUTION If offsite power is lost af ter SI reset, manua l action may be required to res tart safeguard equipment.
32 Reset SI 33 Reset Containment Isola tion Phase 'A' AND Phase 'B' 15 of 25 Y
Cod 2: Sy:ptem/
Title:
Precedura No.
Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Re v. 1 0 / 06/05/84
.i l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l NOTE If a LOP has occurred, reset EPS-kMO.
34 Reestablish Instrument Air Supplies:
- a. Restore service air a. Open fire water cooling to compressor operation service air compressors as follows: and start at least one service air compressor as
- 1) Open SW isolation valves necessary.
to SCCW e SW-V4 e SW-V5 E on CT, OPEN SW-V74 AND SW-V76, CLOSE SW-V75
- 2) Verify at least one
, SCCW pump - RUNNING k 3) Start at least one service air compressor, if necessary
- b. Restore containment air b. IJ[ phase B isolation has
,- compressor operation previously occurred, AND as follows: a compressor can NOT be restarted, THEN continue
- 1) Open PCCW containment with this procedure.
isolation valves TRAIN A, LOOP A TRAIN B, LOOP B l
CC-V168 CC-V175 CC-V57 CC-V176 CC-V122 CC-V257 ,
CC-V121 CC-V256 l
- 2) Start one containment air com, pressor, if necessary e IA-C-4A (Loop A cooled) e IA-C-4B (Loop B cooled) 16 of 25 _y t.?
o 3/)
Codas Sympten/Titist Procedure No.
R2 vision No./ Data:
E-0 REACTOR TRIP OR SAFETY INJECTION 0S1300 Rev. 1 0 / 06/05/84 l STEP l l ACTION / EXPECTED RESPONSE l l RESPONSE NOT OBTAINED l l
CAUTION RCS pressure should be monitored. If RCS pressure drops below 270 PSIG, RHR pumps must be manually restarted to supply water to RCS.
35 Check If RHR Pumps Should Be Stopped:
- a. Check RCS pressure:
- 2) Pressure - STABLE OR 2) Go to Step 36.
INCREASING l b. Stop RHR pumps and place in l s tandby l
! 36 Check If Emergency Diesel Generators Should Be Stopped:
- a. Verify AC emergency busses - a. Try to restore offsite ENERGIZED BY UATs OR RATS power to AC emergency busses. IF offsite power can NOT be restored, THEN RESET EPS - RMO.
i 1) Go to Step 37
- b. Stop emergency diesel -
generators and reset for i AUTO START
- 1) Stop diesel generator
- 2) Reset diesel generator
- 3) Isolate SW to DCCV l
37 Re turn To Step 19
- END -
I l 17 of 25 l
l f~
C:ds: Symptom /
Title:
Procedure No.
Revision No./Date:
'E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 I.
FIGURE E-0-1
,LTOP SETPOINT CURVE
{ l i , ,
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' f I 'P kJh J n. t I !
i A *=B A .,B" ,r' . w.,,
l FIVEM EL i3\F e , i s. s m m. w .s 'v si
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m2385 QR ! -
1 i iis i ! i t i i
- "" I t i 4 fl 6 i i . i e i i 6
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f 4l 6 6 I J l ' 4 I 3I t i i j ,f '
e i i g '
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- f I
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__ t i / i _
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- 6 ,
6 . / I i I i ! 6 6 ,
i 6 6 a 6
/ . . . 6 . s 2 . ,
.s , ,l .
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2E 1000--- / , l
X s 4 4 mn e
' /' ! I Il ! I y I 3M %I m
I I I /
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i 4 i{ j
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3 I i e a re i e i 1 6 4 . i , i
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100 .
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. 200 250 300 350 400 l
lLTOP RCS TEMPERATURE (*F) ARMING POINT l 350' F l
I M
16 of 25 n
Coda Syrp ten / Tit 12: Prccedure No.
navisien No./ Data:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Re v. 1 0 / 06/05/84 i-ATTACHMENT A The following are symptoms that require a reactor trip, if one has not occurred:
FUNCTIONAL UNIT TRIP SETPOINT A. POWER RANGE NEUTRON FLUX:
- 2) HIGH SETPOINT . . . ....... j[ 109% OF RTP B. POWER RANGE, NEUTRON . . ....... j[ 5% OF RTP WITH A FLUX, HIGH POSITIVE TIME CONSTANT j; 2 RATE SECONDS C. POWER RANGE, NEUTRON . . . . . . .... < 5% OF RTP WITH A FLUX, HIGH NEGATIVE TIME CONSTANT > 2 RATE SECONDS D. INIERMEDIATE RANGE, . . . ....... ;[ 25% OF RTP NEUTRON FLUX E. SOURCE RANGE, NEUTRON . . ....... j[ 105 CPS FLUX F. OVERTEMPERATURE AT . . . . ....... j[ 109.95% -t PENALTIES G. OVERPOWER AT . . . . . . . ....... j[ 109% - PENALTIES H. PRESSURIZER PRESSURE -- . ....... ),1945 PSIG LOW I. PRESSURIZER PRESSURE -- . ....... j[ 2385 PSIC HIGH J. PRESSURIZER WATER . . . . ....... ;i 92% OF INSTRUMENT LEVEL--HIGH SPAN K. LOSS OF FLOW .l . . . . . ....... JL 90% OF LOOP DESIGN FLOW 19 of 25 d
' Cod 3: Syrp tra/ Title t Precedure No.
Rsvisica No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 ATTACHMENT A (cont. )
The following are symptoms that require a reactor trip, if one has not occurred:
FUNCTIONAL UNIT TRIP SETPOINT L. STEAM GENERATOR WATER . . . . ..... > 18.1% OF NARROW LEVEL.- LOW-LOW IANGE INSTRUMENT SPAN M. UNDERVOLTAGE - REACTOR . ....... > 70% OF NOMINAL BUS COOLANT PUMPS ' VOLTAGE N. UNDERFREQUENCY - .. . . ....... ),55.4 Hz REACTOR COOLANT PUMPS P. TURBINE TRIP
- 2) TURBINE STOP . . ....... > 1% OPEN VALVE CLOSURE Q. SAFETY INJECTION .. . . ....... NA INPUT FROM ESF R. GENERAL WARNING . . . . . ....... NA l
\ -
l l
20 of 25 l %
Cods: Syrp tsa/
Title:
Precedure No.
! R2 vision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 ATTACHMENT B The following are symptoms that require a reactor trip and safety injec-tion, if one has not occurred:
AUTOMATIC ACTUATION FUNCTIONAL UNIT SI SETPOINT A. PRESSURIZER PRESSURE - .. ...... < 1850 PSIG
~~
l LOW 1 B. 00NTAINMENT PRESSURE - .... .... > 4.3 PSIG HIGH C. STEAMLINE PRESSURE . . . ...... < 585 PSIG LOW i
MANUAL ACTUATION A. RCS SUBC00 LING - LESS THAN 30'F B. PRESSURIZER LEVEL - LESS THAN 5%
I 21 of 25 N
3C
Cod 3: Sy ptss/ Tit 10 Precedure Ns.
Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION 0S1303 Re v. 1 0 / 06/05/84 ATTACHMENT C ECCS VALVE ALIGNMENT - CCP VIA BIT TO RCS COLD LEGS VALVE NOMENCLATURE POSITION CS-V142 CHARGING ISOL. CLOSED CS-V143 CHARGING ISOL. CLOSED CS-LCV-112B CVCT OUTLET CLOSED CS-LCV-112C CVCT OUTLET CLOSED CS-LCV-112D RWST OUTLET OPEN CS-LCV-112E RWST OUTLET , OPEN I
CS-V844 BIT INLET OPEN
, CS-V65 BIT INLET OPEN l CS-V845 BIT INLET OPEN CS-V66 BIT INLET OPEN CS-V846 BIT BYPASS CLOSED l'
I CS-V847 BIT BYPASS CLOSED CS-V165 BIT RECIRC. PUMP DISCHG. CLOSED i CS-V173 BIT RECIRC. ISOL. CLOSED I
CS-V174 BIT RECIRC. ISOL. CLOSED l SI-V138 BIT OUTLET TO RCS OPEN SI-V139 BIT OUTLET TO RCS OPEN 1
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~
Coda: Synptsa/ Titles Prcesdure No.
Ravision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 ATTACHMENT D
- ECCS VALVE ALIGNMENT - SIP -
TO RCS COLD LEGS VALVE NOMENCLATURE POSITION CBS-V47 SI PUMP A SUCTION FROM RWST OPEN CBS-V49 SI PUMP A SUCTION FROM RWST OPEN SI-V90 SI PUMP A MIN FLOW TO RWST OPEN ,
SI-V102 SI TO HOT LEGS CLOSED SI-V112 SI TO COLD LEGS OPEN SI-V114 SI TO COLD LEGS OPEN CS-V460 SI PUMP A SUCTION CROSSOVER CLOSED l
l . CS-V461 S1 PUMP A SUCTION CROSSOVER CLOSED i
CS-V475 SI PUMP A SUCTION CROSSOVER OPEN CBS-V51 S1 PUMP B SUCTION FROM RWST OPEN CBS-V53 SI PUMP B SUCTION FROM RWST OPEN SI-V89 SI PUMP B MIN FLOW TO RWST OPEN SI-V93 SI PUMP A & B MIN FLOW TO RWST OPEN SI-Vill SI TO COLD LEGS OPEN SI-V77 SI TO HOT LEGS CLOSED 1
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- ~
F.
Cod 3: Sy;p toa/
Title:
Prcesdurs No.
Revision No./D:sta E-O' REACTOR TRIP OR SAFETY INJECTION OS1300 Rev. 1 0 / 06/05/84 ATTACHMENT E
- ECCS VALVE ALIGNMENT - RHR -
PUMP TO RCS COLD LEGS VALVE NOMENCLATURE POSITION CBS-V8 CONTM SUMP TO RHR PUMP A & CBS PUMP A CLOSED CBS-V2 RWST TO CBS PUMP A & RHR PUMP A OPEN RC-V23 RHR SUCTION FROM RCS CLOSED RC-V88 RHR SUCTION FROM RCS CLOSED RC-V87 RHR SUCTION FROM RCS CLOSED RC-V22 RHR SUCTION FROM RCS CLOSED CBS-V5 RWST TO CBS PUMP B & RHR PUMP B OPEN CBS-V14 CONTM SUMP TO RHR PUMP B & CBS PUMP B CLOSED RH-V36 RHR TRAIN B TO SUCTION OF SI PUMP B CLOSED RH-V35 RHR TRAIN A TO SUCTION OF S1 PUMP A CLOSED RH-V21 RHR SYSTEM B TO HOT LEGS OPEN RH-V32 RHR A/B TO HOT LEGS CLOSED RH-V26 RHR TRAIN B TO COLD LEGS OPEN RH-V22 RHR SYSTEM A TO HOT LEGS OPEN I RH-V70 RHR A/B TO HOT LEGS CLOSED RH-V14 RHR TRAIN A TO COLD LEGS OPEN l
l l
24 of 25 ,.
Coda: Procedure No.
Sy;p tfg/Titic s Revision No./Date:
E-0 REACTOR TRIP OR SAFETY INJECTION OS1300 Re v. 1 0 / 06/05/84 ATTACHMENT F RED PATH
SUMMARY
SUBCRITICALITY - Neutron flux greater than 5% RTP CORE COOLING - Core exit TCs greater than 1200'F
- OR -
! Core exit TCs greater than 700'F AND RVLIS less than 40% with no RCPs running HEAT SINK - SG inventory less than required in table AND EFW flow capability less than 470 GPM total combined flow NORMAL ADVERSE CONTAINMENT CONTAINMENT 5% NR 35% NR INTEGRITY - Cold leg temperature decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 250'F CONTAINMENT - Containment pressure greater than 52.0 psig 1
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