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$tephen E..eace 3-31-87 87-12 ToTai Approvsd by Station Supsrintendent Effective Date ETC Mtg. No.
STATION PROCEDURE COVER SHEET A.
, IDENTIFICATION lI Nder: E0P 35 ECA-3.1 Rev.
2 j
Title:
SGTR WITH LOSS OF_ REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED Prepared By: A.W. HORTON B.
REVIEW t
I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE f
-__G_,/r te-DEPARTMENT HEAD r
i C.
SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REOUiRED:
I
~
Modifies intent of procedure and changes operation of systems as described in design documents.
YES ( )
NO [4 j
(If yes, perform written USQ determination and Safety I
Evaluation, and contact Manager, Safety Analysis Branch to
[
determine need for Integrated Safety Evaluation.)
O l
ENVIRONMENTAL REVIEW REQUIRED l
(Adverse environmental impact)
YES ( ]
NO [6 D.
SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response.
YES ( )
NO (4 (If yes, perform written Saf ety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
E.
INTEGRATED SAFETY EVALUATION REQUIRED YES ( )
NO (4 F.
PROCEDURE REQUIRES SORC REVIEW (In addition to review, ite ith a YES response must be documented in the R SORC meeting minutes.)
YES (d NO ( )
G.
50RC APPROVAL
/50RC Meeting Ne er 3 -- MF-/o 3 H.
APPROVAL AND IMPLEMENTATION The attached by approved, and effective on the date below:
W
_/-/f.JY O
Station / Service / Unit Superintendent Eftective Date 8810260454 001007 SF 301 PDR ADOCK 05000213 Rev. 9 P
PDR Page 1 of 1
E0P 35 ECA-3.1 Page 1 Rev. 2
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O l
STEAM GENERATOR TUBE Rt!PTURE WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED Page No.
Ef f. Ren 1 - 24 2
Attachment A 2
l 4
O 1
O
SGTR WITH LOSS OF REACTOR COOLANT -
E0P35ECA-I.1 Pag 2 2 SUBC00 LED RECOVERY DESIRED Rev. 2 m
i A.
PURPOSE This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory
(
and voiding in the RCS.
t B.
ENTRY CONDITIONS l
This procedure was written for Modes 1, 2 and 3 assuming RHR is not in service. Using this procedure when not in thesa modes requires a step by step ovaluation to determine if the required action is still i
applicable to current plant conditions.
L l
This procedure is enteritd from l
1)
E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 3, if a ruptured l
SO cannot be isolated from any intact SG.
2)
E0P 35 E-3, STEM GEhTRATOR TUBE RUPTURE, Step 5, if PZR PORV cannot be isolated by closing its block valve.
3)
E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 13, if the j
O ruptured SG pressure is less than low steamline pressure SI setpoint.
4)
E0P 35 E-3, STEM GENERATOR TU~i RUPTURE, Step 14, if no intact SG is available for RCS cooldown.
5)
E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 15, if a ruptured SG pressure continues to decrease following RCS cooldown.
6)
E0P 35 E-3, STEM GENERATOR TUBE RUPTURE, Step 16, if RCS i
subcooling is less than required.
i 7)
E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 19, if RCS pressure does not increase after closing PZR PORY and block l
1 valve.
8)
E0P 35 E-3, STEM GENERATOR TUBE RUPTURE, Step 20, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 7, if SI can not i
be terminated.
)
9)
E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 25, and ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, Step 11, if SI flow l
is required.
4 4
l 1
1 OPS 06&2 3 64 l
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Paga 3 SUBC00 LED KF.COVERY DESIRED Rev. 2 l
I I
- 10) E0P 35 ES-3.1, POST-SGTR C00LD0b'N USING BACKFILL, Step 2. E0P 35 i
ES-3.2, POST-SGTR C00LDOWN USING BLOWDOWN, Step 2 and E0P 35 ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 2 if SI j
i accumulators should not be isolated.
- 11) E0P 35 ES-3.1 POST-SGTR COOLDOWN USING BACKFILL, Step 5. E0P 35 i
ES-3.2 POST-SGTR C00LDOWN USING BLOWDOWN, Step 5 and Step 14, and E0P 35 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP, Step 5 l
and Step 14, if a non-ruptured SG is not available for
~
RCS cooldown.
1 r
1 I
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1
=
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t e
i t
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C#SM4-2 344 1
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SGTR WITH LOSS OF DI.'.0 TOR COOLANT -
E0P 35 ECA 3.1 Pass 4 SUBC00 LED RECOVERY DESIRi9 Rev. 2 t
i f
I star Mmon/espectes neapones neapones not oatswee t
i i
i j
CAtTTION i
l ll 1.
If RWST level decreases to < 520,000 gallons, l
l j
the ECCS System should be aligned for cold leg l
recirculation using E0P 35 ES-1.3, TRANSFER TO COLD j
LEO RECIRCULA110N.
l 2.
If offsite power is lost after SI reset, manual i
action may be required to restart safeguards t
equipment.
NOTE 6
Foldout page should be open.
6 r
4 i
l i
1 1
RESET SI t
2 RESET Containment Isolation
)
Phase A and Phase B 1
i 3
Instrument Air to Containment Establish Instrument Air j
1
- ESTABLISHED to Costainment.
t
{
a.
One instrument air
[
compressor - RUNNING j
l b.
Open instrument air f
containment isolation l
valve
}
i j
4 Verify All AC Busses -
Try to restore offsite power.
d ENERGIZED BY OFFSITE E necessary, THEN manually POWER load the following equipment on the ac emergency busses
[
a.
PZR heaters
{
i
)
b.
Shutdown air compressor or instrument air 4
j compressor 1
c.
Fuel pool cooling pump j
)
d.
Fuel building filter system f
e.
Energize MCC 32-3T and i
j verify it supplying J
I inverter 6.
l ors:es t w i
3 i
o SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Pag 2 5 SUBC00 LED RECOVERY DESIRED Rev. 2
[^'i O
sisP ACTIOM;txPECTED AESPONet !
RESPONSE NOT QBTAINED J
Check If Coutainment Spray Should Be Stopped a.
Spray pumps - RUNNING a.
Go to Step 6.
b.
Containmer.t pressure b.
Continue with Step 6.
< 13.0 psia VMEN containment pressure is < 13.0 psia, THIN do Steps 5c and d.
c.
RESET CDA.4gnal d.
STOP containment spray pumps and place in AUTO.
- 1) STOP quenc' spray pumps CLOSE spray header valves and CAT valves
- 2) STOP containment racire spray pumps (s
x.
CAUTION RCS pressure should be monitored.
If RCS pressure decreases to < 300 psia (450 psia FOR ADVERSE CONTAINMENT),
j the RHR pumps must be manually restarted to supply water to the RCS.
6 Check If RHR Pumps Should Be Stopped a.
Check RCS pressure a.
Go to Step 7.
- 1) Pressure > 300 psia (450 pria FOR ADVERSE CONTAINMENT)
- 2) Pressu e - STA*T.I OR INCREASING b.
STOP RHR pumps and place in AUTO.
-s k
C#K66 ' F84
SGIR WITH LOSS OF REAC'l0R COOLANT -
E0P 35 ECA-3.1 Pag? 6 SUBCOOLED RECOVERY DESIRED Rev. 2 T's
(
)
STEP ACTION,5XPECTED ME SPON05 RESPONSE NOT OSTAINED N'
7 Initiate Evaluation Of Plant Status a.
Check ESF building a.
Try to identify and radiation - NORMAL isolate leakage
- 1) If the radiation monitoring Computer is NOT available.
THEN have the HP technician locally verify radiation levels - NORMAL b.
Check Aux Building (charging / letdown) using radiation monitor - NORMAL c,
Obtain samples
- 2) RCS activity
- 3) SG activity
- 4) Containment hydrogen
- 6) Containment sump activity d.
Evaluate plant equipment for continued usage capabilities
- 1) Evaluate secondary plant status and realign equipment as necessary
- 2) Place BTRS to 0FF
- 3) Evaluate vaste building equipment and realign as
(-
necessary CPSMS-t 3 44
i e
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Pass 7 SUBC00 LED RECOVERY DESIRED Rev. 2 l
o_..
t e.
Start additional plant
[
equipment as needed i
"or plant recovary
)
t
- 1) N2 '*DI"
I L
- 2) Water treating
[
system j
- 3) Radwaste Systems f
i 8
Check If SGs Are Not Taulted i
a.
Check pressures in a.
Verify all faulted SGs all SGs -
isolated unless needed t
d for RCS cooldown f
- 1. NO SG PRESSURE e
DECREASING IN AN
- 1. Main Steam Line I
f l
UNCONTROLLED MANNER isolation and I
bypass valves
- 2. NO SG COMPLETELY DEPRESSURIZED
- 2. Main feed line isolation and O
bypass valves t
3 i
- 3. Chemical feedlines j
- 4. Slowdown and Sampling lines 1
i
- 5. Auxiliary Teed Lines
- 6. Steam supply to TDAW l
Pump
}
i j
- 7. SG atmospheric dump J
valves
{
l
- 8. Main steamline low t
point drains l
)
- 9. TDATW pump low point drains Ir NOT, THEN 3o to E0P
{
35 E-2 FAULTED STEAM GENERATOR ISOLATION, Step 1.
oPkles 1 344
SGTR WITM LOSS OF REA OR COOLANT -
~
E0P 35 ECA 3.1 Pass 8 SURC00 LED RECOVERY DESIRED Rev. 2 I
i Os efse ACTH>wespectes maapones naapones NOT oefsesse CAUTION The CST can be used as an alternate water source for the AFW pumps if DWST level decreases to < 80,000 gal.
l 9
Check intact SG Levels l
a.
Narrow ranse level a.
Maintain total feed i
> 4% (34% TOR flow > $25 spa until ADVERSE CONTAINMENT) narrow range level CONTAINMENT)
> 4% (34% TOR ADVERSE CONTAINMENT) in at least one SG.
I b.
Control feed flow
- .o b.
IF, narrow range level in maintain r ' row range any intact SG continues l
1evel between 4%
to increase in an l
(34% TOR ADVERSE uncontrolled mancer, THEN l
CONTAINMENT) and 501 go to E0P 35 E-3. STEAM l
GENERATOR TURE RUPTURE, Step 1 l
O I
I L
o SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Peg 2 9 SUBC00 LED RECOVERY DESIRED Rev. 2
]
STEP ACTION /f RPECTED RESPONlt RESPONlt NOT OtTAINED NOTE 1.
Shutdown margin should be maintained during RCS cooldown.
2.
Low steamline pressure SI signal should be blocked when PZR pressure decreases to < 2000 psia.
l 10 Initiate RCS Cooldown To Cold 3hutdown a.
Maintain cooldown rate in RCS cold legs l
< 100'F/HR b.
Use RRR System if in service 93 c.
Dump steam to condenser c.
Dump steam from intact from intact SG(s)
SG(s) to atmosphere IF no intact SG
(N available THEN perform
(_,)
the following
~
- 2) If necessary use ruptured SG after consulting with Director of Station Emergency Organtration (DSEO) and performance l
of offsite release calculations 11 Check RCS Subsooling On to step 26.
Based On Core Exit TCs > 30*F (90*F FOR l
ADVERSE CONTAINMENT) 1 i
l I
i UN l
OPKeet 3H 1
l
SGTR WITH LOSS OF REACTOR COOLANT -
EOP 35 ECA-3.1 Page 10 SUBC00 LED RECOVERY DESIRED Rev. 2 I
4 STEP ACTION /EXPECTEJ RESPONSE RECPONSE NOT 08TAINED l
NOTE Step 12 applies for the remainder of this procedure.
12 Check If Subcooled Recovery Is Appropriate a.
Check RWST level a.
Refer to OPS FORM E0P
> 791,000 gal.
35 ECA-3.1-1 to determine expected containment sump level.
IF containment sump level less than expected, THEN go to E0P 35 ECA-3.2, SGTR WITil LOSS LOSS OF REACTOR COOLANT -
SATUR/:TED RECOVERY DESIRED, Step 1 b.
Check ruptured SG b.
Consult Director of narrow range level Station Emergency
< 92% (77% FOR ADVERSE Organization (DSEO) to CONTAINMENT) determine if recovery l
should be completed using E0P 35 CA-3.2,
}
SGTR WITH LOSS OF RZACTOR COOLANT -
SATURATED RECOVERY DESIRED.
13 Check If ECCS Is In Go to Step 22.
Se rvice a.
Cht,rging Pump iu Reactor Cold Legs Isol, tion Valves - OPEN OR c.
RHR pumps - ANY RUNNING IN SI MODE 14 Place All PZR Heater
~
Switches In OFF Position O
OPS 0041 3-44
.N---
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 11
~
SUBC00 LED RECOVERY DESIRED Rev. 2 i
d SMP ACTION / EXPECTED RESPONSE RASPONSE NOT OSTAINED CAUTION Voiding may occur in the RCS during RCS l
depressurization. This will result in a rapidly increasing PZR level.
15 Depressurize RCS To Refill PZR a.
Use normal PZR spray a.
Use one PZR PORV.
I_F no PORV available, THEN use auxiliary spray b.
PZR level > 17%
b.
Cont.inue with Step 16.'
(50% FOR ADVERSE WHEN level > 17% (50%
CONTAINMENT)
FOR ADVERSE CONTAINMENT),
THEN do Step 15c.
i c.
Stop RCS depressurization O
1 t
I O
OPSOH 1 3 44
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 12 SUBC00 LED RECOVERY DESIRED Rev. 2 O
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT C STAINED CAUTION If seal injection had previously been lost, the affected RCP(s) should not be started prior to a status evaluation.
'~
NOTE RCPs should be run in order of priority (RCP 2,1 THEN 3 or 4) to provide normal PZR spray.
3 Check If An RCP Should l
Be Started l
a.
All RCPs - STOPPED a.
STOP all but one RCP..
Go to Step 17.
b.
RCS subcooling b.
Go to Step 26.
based on core exit
]
TCs > 30*F (90'F l
l FOR ADVERSE CONTAINMENT)
)
e.
PZR level > 17%
c.
Return to Step 15.
l (50% FOR ADVERSE CONTAINMENT) d.
Try to start an RCP I
- 1) Establish conditions for starting an RCP l
- a. RPCCW to RCP r
thermal barrier -
1 ALIGNED
- b. #1 Seal leak off fled >.2 gpm
- c. #1 Seal AP >
210 paid
- 2) START one RCP j
1 1
G C/
i OP5044-1 3-H i
.SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 13 SUBC00 LED RECOVERY DESIRED Rev. 2 l
~-
STEP ACTIONalXPECTED RESPON' E MESPONSE NOT OETAINED NOTE 1.
After stopping any Charging or SI pump, RCS pressure should be allowed to stabilize or increase before stopping another Charging or SI pump.
2.
The charging pumps and SI pumps should be stopped on alternate ECCS trains when possible.
17 Check If One Charging Pump Should Be Stopped a.
Two Charging Pumps a.
Go to Step 18.
- RUNNING b.
Determine required RCS subcooling from table RCS SUBC00 LING (*F)
SI PUMP STATUS ANY RCP RUNNING NO RCP RUNNING __
NONE NORMAL ADVERSE NORMAL ADVERSE RUNNING 89'F 191*F 103*F 195'F O-ONE RUNNING 52*F 155'F 54'F 157'F TWO RUNNING 44*F 151'F 55'F 153*F c.
RCS subcooling based c.
IF RCS hot leg temperav:res on core exit TCs >
> 370*F (345'F FOR REQUIRED SUBC00 LING ADVERSE CONTAINMENT)
THEN go to Step 26.
IF RCS hot leg temperatures
< 370*F (345'F FOR ADVERSE CONTAINMENT)
THEN START one RHR pump if none running.
IF at least one RHR pump can NOT,be operated, THEN go to Step 26.
d.
PZR level > 17% (50%
d.
DO NOT STOP CHARGING FOR ADVERSE CONTAINMENT)
PUMP.
Return to Step 15.
e.
STOP one charging pump rm OP%$41 344
o F
j Sbin WITH LOSS OF REACIOR C00LANI -
E0P 35 ECA-3.1 Paga 14 SUBC00 LED RECOVERY DESIRED Rev. 2
,e N
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STEP ACTION / EXPECTED RESPONSE RESPONFE NOT OSTAINED 18 Check If One SI Pump Should Be Stopped a.
Any SI pump -
a.
Go to Step 19.
RUNNING b.
Determine required RCS subcooling frcm table RCS SUBCOOLING ('F)
SI ONE CHARGING PUMP RUNNING NO CHARGING PUMP RUNNING PUMP ANY RCP RUNNING NO RCP RUNNING ANY RCP RUNNING NO RCP RUNNING STATUS NORMAL ADVERSE NORMAL ADVERSE NORMAL ADVERSE NORMAL ADVERSE ONE RUNNING 142 239 154 239 WO RUNNING 42 134 47 136 55 158 64 160 c.
RCS subcooling c.
IF RCS hot leg temperatures based on core
> 370'F (345'F FOR exit TCs >
ADVERSE CONTAINMENT) THEN f-g REQUIRED SUBC00 LING go to Step 26.
Q' IF RCS hot leg temperatures
< 370*F (345'F FOR ADVERSE CONTAINMENT) THEN START one RER pump if none running.
IF at least one RHR pump can NOT be operated, THEN go to Step 26.
d.
PZR level > 17%
d.
DO NOT STOP SI PUMP.
(50% FOR ADVERSE Return to Step 15.
CONTAINMENT) e.
STOP one SI pump f.
Return to Step 18a
[v cexes t a s4
7 SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 15 SUBC00 LED RECOVERY DESIRED Rev. 2 (V
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 19 Check If Normal Charging Should Be Established a.
Check the following a.
Go to Step 26.
- 1) SI pumps - STOPPED AND
- 2) Charging pumps -
ALL BUT ONE STOPPED b.
RCS subcooling b.
IF RCS hot leg temperature based on core exit
> 370'F (345*F FOR TCs > 30*F (94*F ADVERSE CONTAINMENT) THEN FOR ADVERSE CONTAINMENT go to Step 26.
IF RCS hot leg temperatures
< 370*F (345'F FOR ADVERSE CONTAINMENT) THEN START one RHR pump if none running.
IF at least one RHR pump can NOT be operated, THEN go to Step 26.
c.
PZR level > 17% (50%
c.
Depressurize RCS to FOR ADVERSE CONTAINMENT) refill PZR level to
> 17% level and return to step 19b 20 Establish Normal Charging Pump Injection Flow Path a.
IF two charging pump cold leg injection valves are open, THEN CLOSE one valve b.
Eatablish 60 gpm normal charging path c.
CLOSE the Charging Pump miniflow isolations to l
the RWST (3CHS*MV8511A/B)
I d.
CLOSE a Charging Pump Cold Leg Injection valve 21 OPEN the Charging Pump
)
Recire Isolations l
t
- O cexes.1 344 l
l L
O 4
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 16 SUBCOOLED RECOVERY DESIRED Rev. 2 step AcTiowaxPeciso mesPONSE RESPONSE NOT OSTAINED 22 Check if Charging Flow should be controlled to maintain PZR Level a.
Check RHR Pumps - NONE a.
Go to Step 26 RUNNING IN SI MODE r
b.
Control charging flow to maintain PZR level i
f f
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e SCTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 17 SUBC00 LED RECOVERY DESIRED Rev. 2 O)
.(V step ACTioA /'escTao nesPoNSE ntsPONSE NOT OSTAINEO CAUTION If seal injection had previously been lost, the affected RCP(s) should rot be started prior to a status evaluatico.
NOTE RCPs should be run in order of priority (RCP 2,1 THEN 3 or 4) to provide normal PZR spray.
23 Check RCP Status a.
RCPs - AT LEAST a.
Try*to start one RCP ONE RUNNING
- 1) Establish conditions for starting an RCP a.
RPCCW supplied to RCP thermal O
barrier b.
- 1 Seal leak off
>.2 gpm c.
- 1 Seal AP >,
210 psid
- 2) START one RCP. E RCP can NOT be started, THEN refer to ATTACHMENT A to verify natural circulation.
IF natural circulation NOT verified, ThEN increar,e dumping l
steam.
b.
STOP all but one RCP lO 4
5 OP$0N 1 3-84
(.
g SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 18 SUBC00 LED RECOVERY DESIRED Rev. 2 4
STEP ACTION /EXPECTCO RESPONS3 RESPONSE NOT OSTAINED CAUTION Voiding may occur in the RCS during RCS depressurization.
This will result in an rapidly increasing PZR level.
l 24 Depressurize RCS To Minimize RCS Subcooling a.
Use notaal PZR spray a.
Use one PZR PORV.
IF no PORV available, TNEN use auxiliary spray.
b.
Control PZR heaters e
as necessary c.
Depressurize RCS until EITHER of the following conditions satisfied
- 1) PZR level > 73%
l (50% FOR ADVERSE I
CONTAINMENT)
-0R-
- 2) RCS subcooling based l
on core exit TCs < 40'F (100'F FOR ADVERSE CONTAINMENT)
CAUTION Dilution of RCS boron concentration may occur on transfer of secondary water into the RCS.
25 Verify Adequate Shutdown Margin l
a.
Sample RCS b.
b.
Borate as necessary ADEQUATE OPi0641 3H s
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 19 SUBC00 LED RECOVERY DESIRED Rev. 2 I
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT 08T#,1NEO g
26 Verify ECCS Flow Not Required a.
RCS subcooling a.
Manually operate ECCS based on core pumps as necessary.
exit TCs > 30*F Go to Step 27.
(90*F FOR ADVERSE CONTAINMENT) b.
PZR level > 7%
b.
Manually operate ECCS (50% FOR ADVERSE pumps as necessary.
CONTAINMENT)
Return to Step 15.
27 Check If SI Accumulators Should Be Isolated a.
LCS subcooling based a.
IF at least two RCS hot on core exit TCs >
leg temperatures > 375'F, 30*F (90'F FOR THENego to Step 27c.
ADVERSE CONTAINMENT)
IF NOT, THEN go to Step 28.
b.
PZR Levels > 7%
b.
Return to Step 15.
(50% for ADVERSE CONTAINMENT) c.
Restore power to isolation valves (32-2R-RSF, 32-2W-R3J,
?2-2R-F4M, 32-2W-F4M) d.
CLOSE all SI d.
Vent any unisolated accumulator isolation accumulators valves e.
Remove power to isolation valves 28 Check If Diesel Generators Should Be Stopped a.
Verify ac emergency a.
Try to restore offsite busses - ENERGIZED BY power to ac emergency 0FFSITE POWER busses.
b.
Reset any LOP, SIS, or CDA signal at MS2.
i c.
Stop any unloaded i
diesel generator and place in standby
, O OPS 0641 3 44
.)
r e
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 20 SUBC00 LED RECOVERY DESIRED Rev. 2 (O
STEP ACTION /EMPECTED RESPONSE RESPONSE NOT OSTAINEO d.
RESET station LOP at both sequencer panels.
e.
RESET, then turn on each Diesel Sequencer Automatic Tester toggle switch.
f.
CLOSE Feeder Breakers to Emergency Generator Distribution Panels 3EGS*PNLIA at 32-1T-3H and 3EGS*PNL1B at 32-1U-3H 29 Minimize Secondary System Contamination a.
Shut condensate reject to Condensate Surge Tank b.
Remove all but two condensate demin from service c.
Consider starting up Auxiliary Boiler system to supply steam loads to limit the spread of contamination 30 Check RCP Cooling a.
RPCCW to RCP thermal a.
Refer to OP 3330A, barrier - ALIGNED REACTOR PLANT COMPONENT COOLING WATER b.
RCP seal injection b.
Refer to OP 3304A flow CHARGING AND LETDOW
- 1) Check flow between 8-13 gpm
- 2) Check VCT temperature
< 135'F i
- 3) Check RCS pressure
> 115 psia O
l ornes i 344
6 SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 21 SUBC00 LED RECOVERY DESIRED Rev. 2 i
L STEP ACTION /EIPECTED RESPONSE RESPONSE NOT OSTAINEO 31 Check If RCP Seal Return Flow should be established a.
RPCCW flow available a.
Go to Step 32.
to seal water heat exchanger b.
OPEN Leakoff header containment isolation valves - FLOW ESTABLISHED 32 Check If Source Range Detectors Should Be Energized a.
Check intermediate a.
Continue with Step 33.
range flux < 10E-10 WHEN flux < 10E-10 amps e
amps on Post Accident Nuetron Monttor, THEN do Steps 32b and c.
b.
Verify source range b.
Manually energize detectors - ENERGIZED source range detectors.
c.
Transfer nuclear O
recorders to source range scale 33 Shutdown Unnecessary Plant Equipment a.
All but one condensate Pump b.
All but one circulating l
water pump per bay c.
Moisture separator drain pumpa I
d.
4th point hester
{
drain pumps l
OP6006 t 344
r SGTR WITM LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 22 SUBC00 LED RECOVERY DES 1 RED Rev. 2 p
STEP ACTeON/ EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION Feed flow should NOT be established to any ruptured SG which is also faulted unless needed for RCS cooldown.
NOTE In the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow range level and then refill it to a high narrow range level rather than continuously feeding the ruptured SG to control level.
34 Check Ruptured SG(s)
Refill ruptured SG to 82%
Narrow Range Level (61% FOR ADVERSE CONTAIN-
> 4% (34% FOR ADVERSE MENT) using feed flow.
IF CONTAINMENT) either of the following j
conditions occurs, THEN stop feed flow to the ruptured SG unless needed for RCS O
cooldown and go to Step 36 a.
Ruptured SG pressure decreases in an uncontrolled manner.
-OR-b.
Ruptured SG pressure increaers to 1100 psig.
35 Check Status of Steam Ceterators a.
Two Steam GeJerators 4.
With less than tve intact intact steam ?,ener-ators consult with the D4: actor of Station Emergency Organization (DSEO) on advisability of isolating the ruptured steam generators by closing the appropriate loop stop valves.
O OPM401 3H
r
.SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 23
~
SUBCOOLED RECOVERY DESIRED Rev. 2 O
STEP ACTION /EEPkCTED RESMNSE RESPONSE NOT 08TAINEO b.
No RCP's operating
- b. If operating RCP in and plant verified an intact steam in natural circulation generator loop then l
in accordance with go to Step 35c.
Attachment A.
01 If operating RCP in a I
ruptured steam generator loop go to l
Step 36.
c.
Consult Director of A
Station Emergency Organization (DSEO)
[
to close ruptured steam generator (s) loop isolation valves.
36 Check If RCPs Must Be Stopped a.
Check the following a.
Go to Step 37.
- 1. Number 1 seal differential pressure < 210 i
psid r
OR I
t
- 2. Number 1 seal return flow <.2 gpm b.
STOP affected RCP(s)
L l
l l
t 1
NOTE At 425*r RCS temperature, OP 3208 PLANT C00LD0WN should I
be used (in parallel with the followins steps) with steps l
being evaluated for applicability based on plant conditions.
(
i i
i 37 Cooldown RCS by dumping If condenser not available steam to condenser and dump steam to 4tmosphere block low steamline using an intact steam SI signal.
generator.
1 I
OPS (es 1 3-44 e
i
-we-
SGTR WITH LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 24 SUBC00 LED RECOVERY DESIRED Rev. 2 0
STkP ACTION / EXPECTED RESPONSE RESPONSE NOT 09TAINEO 1
38 Check If RHR System Can Be'Placed In Service a.
Check the following a.
Go to Step 39.
- 1. RCS temperatures
< 350*F
- 2. RCS pressure < 390 psia b.
Consult Director of Station Emergency Organization (DSEO) to determine if RHR System should be l
placed in service 39 Check RCS Temperatures AND Return to Step 9.
RVLMS Head TC's < 200*F 40 Evaluate Long Term Plant j
Status a.
Maintain cold shutdown conditions b.
Consult Director of Station Emergency Organization (DSEO)
-FINAL-O OP90061 3-a4
r-SGTR WITil LOSS OF REACTOR COOLANT -
E0P 35 ECA-3.1 Page 1 ef 1 SUBC00 LED RECOVERY DESIRED Rev. 2 i
)
s.s ATTACIDfENT A The following conditions support or indicate natural circulation flow 1.
RCS subcooling based on core exit TCs > 30*F (90*F FOR ADVERSE CONTAINMENT) 2.
SG pressures - STABLE OR DECPIASING 3.
RCS hot leg temperatures - STABLE OR DECREASING 4.
Core exit TCs - STABLE OR DECREASING 5.
RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE (O
^ \\
m CP N I 344
7
~
LJ FOLDOUT FAR E0P 35 ECA-3.1 l'ROCEDURE 1.
SI REINITIATION CRITERIA Manually operate SI pumps as necessary E EITHER condition listed below occurs a.
RCS subcooling based on core exit TCs < 30'F (90*F FOR ADVERSE CONTAINMENT)
OR b.
PZR level - CAN NOT BE MAINTAINED > 7% (50% FOR ADVERSE i
I CONTAINMENT) l 2.
RED PATH
SUMMARY
a.
SUBCRITICALITY - Nuclear power > 5%
b.
CORE COOLING - Core exit TCs > 1200'F 1
l c.
HEAT SINX - Narrow range level in all SGs < 4% (3t# FOR ADVERSE l
CONTAINMENT) AND total feedwater flow < 525 gpa 1
1 l
d.
INTEGRITY - Cold leg temperature decrease > 100*F in last 60 l
l minutes AND RCS cold leg temperature < 252*F e.
CONTAINMENT - Containment pressure > 60 psia 3.
SECONDARY INTEGRITY CRITERIA Go to E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1, E EITHER condition listed below occurs (UNLESS needed for RCS cooldown) a.
Any SG pressure is decreasing in an uncontrolled manner, AND has NOT been isolated, b.
Any SG has completely depressurized. AND has NOT been isolated.
4.
COLD LEG REdIRCULATION SWITCHOVER CRITERION Go to IWMTS-1.3, TRANSFER TO COLD llG RECIRCULATION, Step 1, E
~ ~~
RWST level decreases to < 520,000 gal.
E.
AFW SUPPLY SWITCHOVER CRITERION Establish We CTt AEV water supply E DWST level decreases to <
80,000 gal.
O
6 -s = Y 3-87-20,
FORM APPROVE 0 BY UNIT 3 SUPERINTENDENT EFFECTIVE DATE PORC MTG NO.
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OPS Form E0P 35 ECA-3.1-1 Rev. O Page 1 of 1 I