ML17249A735
| ML17249A735 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/03/1979 |
| From: | Bodine J, Noon J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17249A732 | List: |
| References | |
| E-1.2, NUDOCS 8003060616 | |
| Download: ML17249A735 (33) | |
Text
ROC.="S':-R GAS.-'2lQ::-C RT.C COBZCR TZGN GWLb)A S)..~T".Oi't COiVHOW COPY Z~H""R PROCWUR=. '.lO.
E-1.2 NO.
18 LOSS OF REACTOR COOLANT
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E-l.2 LOSS OF REACIOR CCOLAÃl 1.0 SYMPIQNS
'.0 2.1 3.0 Refer to Section 1.0 of E-l.l if not already performed.
IMMEDIATE OPERATOR ACTIONS:
Refer to section 2.0 of E-l.l if not already performed.
SUBSEQUENT OPERA'IOR ACIIONS:
CAUTION:
%he diesels should rat be operated at idle or minimum load for extended periods of time. If the diesels are shut down, they should be prepared for restart.
3.0.1 Monitor HWST level closely.
If RNST level decreases rapidly such that the HNST low level alarm appears inminent, go directly to step 3.6.
CAUTION:
Eo not rely upon S/G or Pressurizer level indication after any event &ere a high energy line break has occurred inside of containment.
An erroneous level indication will be caused by reference leg heatup and possible boiling as a result of increased CV temperature and/or changes in S/G pressurizer pressures.
Basis for this is shown in tables 1-4 and figures 1-4, attached.
If S/G and pressurizer levels are maintained between 85% and 25%,
this will ensure an actual water level is present.
NOTE:
At a CV temperature of 300'F, CV pressure will be over 52 psig.
The following tables show the maximums and minimun levels at graduated levels of temperature during post accident conditions which will ensure an actual water level exists scmewhere between the level taps.
PRESSURIZER S/G (NARRA RANGE)
Min. Level
% of Span 10%
14%
19%
24%
30%
37%
Max. Level
% of Span 85%
85%
85%
85%
85't 85%
C.V.
TEMPERATURE (oF) 150 200 250 300 350 400 Min. Level 0 of Span 5%
10%
13%
17'2%
27%
i~hx. Level 0 of Span 95%
95%
95%
95%
95%
95%
E-1.2:2 NCTE:
The process variables referred to in this Instruction are typically monitored by more than one instrumentation channel.
The redurdant channels should be checked for consistency while performing the steps of this Instruction.
NOTE The pressurizer water level irdication should always be used in conjunction with other specified reactor coolant system indications to evaluate system corditions ard to irdicate manual operator actions.
3.1 As the water in the refueling water storage tank decreases under the action of the safeguards
- pumps, check that sump "B" water level instrumentation indicates an increase in water level in the sump.
If a sump "B" water level increase is not evident then a re-evaluation of the symptans in E-l.l must be conducted unless step 3.2 below applies.
3.2 Regulate the auxiliary feedwater flow to the stean generators to restore and/or maintain an indicated narrow range water level. If narrow range water level increases in an unexplained manner in one steam generator verify other potential S/G Tube Leak Symptans, if valid go to E-1.4, Steam Generator Tube Rupture.
MZE:
Monitor the primary water supply (Cordensate Storage Tank) for the auxiliary feedwater pumps ard upon, reaching a low level, switch over to an alternate water supply source.
(procedure T-41E).
3.3 Close all pressurizer power operated relief valves and backup isolation valves.
3.4 Check for SI termination criteria by:
CAUTION:
Ensure that containment isolation is maintained, i.e., not reset until such time as manual action is required on necessary process streams.
3.4.1 IF reactor ccolant pressure is above the shutoff head of the safety injection pumps 3.4.2 3.4.3 AND safety injection flow to the Reactor Ccolant System is zero
~ attempt to reestablish the reactor coolant pressure to greater than 2000 psig and pressurizer water level to greater than 50% of span 3.4.3.1 BY Resettirg safety injection, ard 3.4.3.2 Establishing full charging flow.
CAUTION:
Subsequent to this Step, should loss of offsite power occur manual safety injection initiation will be required to load the safeguards equipnent onto the diesel powered emergency busses.
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VQ E-l.2:3 Q:"I.4.4 3.4.4.1 3.4.4.2 3.4.4.3 Safety Injection can be terminated IF:
Reactor coolant pressure is greater than 2000 psig and increasing, AND t
Pressurizer water level is greater than 50% of span, AND The reactor ccolant indicated subcooling is greater than 50'F ger subcooling meters AND NOTE:
As a backup to the subcooling meters, the average of:
thermocouples (points ll, 15, 18, 19 6 20) may be used with pressurizer pressure and the attached saturation curve to verify 50'F subccoling.
3.4.4.4 Water level in at least one Steam Generator 25% in the narrow range to assure that the U-tubes are covered.
'1NEN:
3.4.4.5 Stop all SI and RHR pumps 3.4.5 Following termination of safety injection place all safety injection pumps in standby mode and maintain operable safety injection flowpaths.
CAUTION:
If reactor ccolant pressure drops below the low pressurizer pressure setgoint for safety injection or pressurizer water level drops below 20% of span following termination of safety injection flow or the reactor ccolant systen is < 50'5 sutcooled, VIEN NaNEALLY REINITIATE safety injection to ensure core ccoling.
Go to Section 3.0 fo E-l.l to reevaluate the event.
3.4.6 Reset containment isolation by gerforming the following:
3.4.6.1 Place CV Sumo A pumps in pull-stop position 3.4.6.2 Place all containment isolation (T signal) valve switched in the closed position and manually reset contairment isolation by use of key switch.
(Refer to Autcmatic Actions in Section 4 of E-l.l for Containment Isolation Valve numbers) 3.4.6.3 If outside gower has been lost, close bus tie breaker 14 to 13 and/or 16 to 15 ard restart instrument Air Containment Ccmpressors as necessary.
3.4.6.4 Open the Instrument Air Containment Isolation valve.
3.4e7 Reestablish normal makeup ard letdown (if letdown is unaffected) to maintain pressurizer water level in the normal operating range and to maintain reactor coolant pressure at values reached when safety injection is terminated.
Ensure that water edition during this process does not result in dilution of the reactor coolant system boron concentration.
Reestablish operation of the pressurizer heaters (refer to 0-8.1, "Restoration of Pressurizer Heaters to bhintain Natural Circulation at HSD,"
if no RCP's are running).
When reactor ccolant pressure can be controlled by pressurizer heaters alone, return makeup ard letdown to pressurizer water level control.
3.4.9 Verify that RCS temp is > 50'F subcooled per subcooling meters.
MZE:
As a backup to the subccoling meters the average of thermocouples (points 11,15gl8g19
& 20) may be used with pressure pressure and the attached saturation curve to verify 50'F subcooling.
3.4.9.1 If 50'F indicated subcooling is not present then attempt to establish 50'F indicated subcooling by steam dumo frcm the steam generators to the condenser or the atmosphere.
CAUTION:
If steam dump is necessary, reduce the steam generator pressure 200 psi below the lowest steam safety valve setpoint ard maintain a reactor coolant cooldown rate of no more.than 50'F/HR, consistent with plant make-up capability.
3.4.9.2 If 50'F indicated subcooling cannot be established or maintained, then manuall reinitiate safet injection.
Go to Section 3.0 of E-l.l to re-evaluate the event.
3.4.10 Perform a controlled cooldown to cold shutdown conditions using Normal Cooldown Procedures if required to effect repairs.
Maintain subcooled conditions (at least 50'F indicated subcooling) in the reactor coolant system.
If subcooled conditions cannot be maintained, go to step 3.5.
.3.5 If the conditions for terminating safety injection in Step 3.4 are not met start or maintain necessary safety injection pumps operating.
If any safeguards equignent is not operating, attempt to operate the equipment from the control rocm or locally.
Effect repairs if necessary.
If reactor ccolant pressure is above the low head safety injection pump shut-off head, manually reset safety injection so that safeguards equipment can be controlled by manual action.
Stop the low head safety injection pcs and place in the standby mode.
CAUTION:
Nhenever the reactor coolant pressure decreases below the low head safety injection shutoff head, the low hea3 safety injection pumps must be manually restarted to deliver fluid to the reactor coolant system.
3.6 Stop AU'eactor Coolant Pumps after the high head safety injection pmp operation has been verified ard when the narrow range reactor coolant pressure is
< 1715 psig.
CAUTION:
If reactor ccolant pumps are stopped, the seal injection flow should be maintained.
NZE:
The conditions given above for stopping reactor coolant pumps should be continuously monitore3 throughout this instruction:
3.7 In the case of a break characterized by reactor coolant pressure quickly decreasing below stean generator
- pressure, go to step 3.8.
In case of a break characterized by a slowly decreasing reactor coolant pressure or stabilized reactor coolant systen pressure above the lowest steam system safety valve setpoint, (1085) psig, the following a3ditional manual actions should be taken to aid the cooldown ard depressurization of the reactor coolant system:
E-1. 2:5
( 'l.7.1 If the main cordenser is in service, open at least one main steamline isolation valves or bypass valves and transfer the steam dump control to steam header pressure control and dump stean to the condenser to lower the reactor ccolant temperature and consequently the reactor ccolant pressure.
3.7.2 If the main condenser is not in service, dump steam to the atmosphere with the steam relief valves to lower the reactor ccolant temperature and consequently the reactor coolant pressure.
CAUTION Reduce the steam generator pressure 200 psi below the lowest stem system safety valve setpoint ard maintain a reactor coolant ccoldown rate of no more than 50'F/HR, consistent with plant make-up capability.
NCTE:
If RUST low level alarm is not imminent, then consideration should be given to performing a preliminary evaluation of the plant status in Steps 3.10 and 3.11.
3.8 Perform the following:
3.8.1 Check for break in high head safety injection line by cbserving flow on F.I.
924 (A pump to B loop) and F.I. 925 (B pump to A loop). If a break has occurred in a high head injection line, the flow meter reading in the correspondirg header may be constant ard substantially higher than in the other.
PRECAUTION:
Stopping flow to the high Q.ow rate line may not be wise,
- however, because the same irdication of unbalanced flow could be caused by a check valve failing to open ccmpletely.
Therefore, no action should be taken unless the operator is firmly convinced that his actions will not aggravate the accident condition.
3.8.1.1 With no flow on FI 924 and ra pressure on PI 922 secure "A" SI pump and close MOV-871A.
3.8.1.2 With no flow on FI 925 and rn pressure on PI 923 secure "B" SI pump and close MOV-871B.
3.8.2 Check for break in Low Head Safety Injection by observing flow on F.I. 626.
A flow reading above 200 gpn when the reactor coolant system is above 170 psig, may be an indication of a leak in one of the tm Low Head Injection Lines or the RHR Return Line to the Loop either inside or outside containment.
If large leaks are cbserved in the RHR or SI systems outside contairment, action should be taken to provide core delivery and minimize radiation exposure.
In the case of the two low head injection line inside
'contairment it may be difficult to detect if one line is spillirg to containment without getting to the vessel; so unless the operator is firmly convinced that a realigrment is necessary to provide core delivery and his action will not aggrevate the accident condition he should rat realign the systems.
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E-l.2:6 NOZE:
By exercising HCV-624, and HCV-625, ard by watching the corresponding indication on FI-626, the operator could detect failure location, isolate it, ard use an alternate path for recirculation.
Reset SI signal when either K)V-825A or MOV-825B, Safety Injection Pumps suction frcm EST, is open.
PRECAUTION: If loss of off-site pomr occurs during the INJECZION PHASE of SI after the SI signal has been reset, manually push SI button again to restart the required engineered safeguards equipment on the Emergency Diesel Generators.
When the refueling water storage tank low level alarm is actuated at 31%,
stop one safety injection pump arrl one contairment spray pump.
Stop auxiliary feedwater flow to the steam generators when the level has increased to 40%.
If a charcoal filter high temperature alarm is actuated, open the charcoal filter dousing valves 875A, B or 876A, B.
Restore Service Water Flow to both ccmponent ccoling water heat exchangers, if lost, by opening b1CV 4616 and 4735 for "A" Hx, and NN 4615 and 4734 for "B" Hx, and start both ccmponent cooling water pumps..
Ensure that the ccmponent cooling'ystem's supply ard return lines associated with containment users are isolated frcm the outside portion of the system by closing or ensuring closed the following remote operated C.I. valves.
Close supply lines MOV 817 (Common CC supply to Containment)
MOV 749A (CC supply to "A" RCP)
MOV 749B (CC supply to "B" RCP)
MOV 813 (CC supply to Reactor Support Coolers).
E-1.2:7 3.8.7.3 3.8.8 3.8.9 Close return lines MOV 759A (CC return from "A" RCP)
MOV 759B (CC return frcm "B" RCP)
AOV 745 (CC return fran Excess Letdown Heat Exchanger)
MOV 814 (CC return from Reactor Support Cooler)
NOTE:
Valves 813 and 814 isolate automatically Ensure that ccmponent cooling flow is established to the residual heat exchangers by opening MOV-738A and MOV 738B CCW frcm RHR Heat Exchanger.
Verify that ccmponent cooling low flow alarms to the residual heat removal, containment spray and safety injection pumps are not actuated.
3.8.9.1 Alarm A-9 RHR Pmp Cooling Water Outlet low flow.
3.8.9.2 Alarm A-14 Safety Injection Pumps Gooling Water Outlet low flow.
3.8.9.3 Alarm A-6 Containment Spray Pumps Water Outlet low flow.
3.8.10 3.8.11 3.8.12 3.8.13 Determine by PR-420 if reactor ccolant system pressure will permit recirculation without the use of a high head injection peep (systen pressure below 140 psig).
If spray additive has been actuated during the injection phase and spray additive tank level is higher than 40% or if contairment pressure is > 30 psig, prepare to initiate recirculation with containment spray.
At 10% in WST, stop the operatic safety injection, contairment spray and residual heat removal pumps, proceed to the recirculation phase.
Recirculation Phase Important:
KiE SWITCHOVER SHOULD BE CCMPLETED AS RAPIDLY AS POSSIBLE (WITHIN 5 MINVZES), SINCE DURING THIS TZK THE CORE IS NOZ RECEIVING ANY ADDITIONALEMERGENCY COOLING WATER.
3.8.14 PRECAUTION: If at any time during the Recirculation Phase of the accident offsite ~wer is lost, start at the beginning of the Recirculation Phase of this procedure ard reverify ard start equipnent as necessary after Bnergency Diesel Generators tie into their respective buses.
Verify the valve status and align valves as follows for recirculation using the RHR pumps.
VERIFY THAT THE FOLLOWING M)V VALVES ARE CLOSED:
826A 826B 826C Boric Acid Storage Tank to Safety Injection Pcs Boric Acid Storage Tank to Safety Injection Pumps Boric Acid Storage Tank to Safety Injection Pumps
826D 857A 857B 857C 1813A 18138 700 701'20 721 E-1.2:8 Boric Acid Storage Tank to Safety Injection Pumps RHR Pumps to Safety Injection Pumps G Containment Spray Pumps RHR Pumps to Safety Injection Pumps a Contaianent Spray Pumps RHR Pumps to Safety Injection Pumps 6 Containment Spray Pumps RCOZ Pump Suction frcm Sump B RCOZ Pump Suction free Sump B
RCS to RHR pump suction RCS to RHR pump suction RHR Discharge to RCS RHR Discharge to RCS CLOSE THE FOLLOWING lGV'S AND AOV'S
- 896A, B FNST to SI Pumps MZE:
%897
- 898
- 704A
- 704B To close 896 A or B the D.C. power hold switch labeled 896A or B "KEY SYI'ICH" must be placed in the "ON" position.
After placing valve in proper position return key switch to "OFF".,
SI Pumps Recirculation to RfST SI Pumps Recirculation to EST
'RHR Pump "A" Suction Cross-Tie RHR Pump "B" Suction Cross-Tie VERIFY THAT THE FOLLOWING K)V VALVES ARE OPEN:
852A 852B 878B 878D 851A 851B 1815A 1815B 825A 825B RHR Discharge to Reactor Vessel RHR Discharge to Reactor Discharge Safety Injection Pump Discharge Zaop B Cold Leg Safety Injection Punp Discharge Locp A Cold Leg RHR Pump Suction frcm Sump B Inside Containment RHR Pump 'Suction fran Sump B Inside Contairment 1C Safety Injection Pump Suction Valve lC Safety Injection Pump Suction Valve Safety Injection Pumps Suction fram RWST Safety Injection Pumps Suction from RWST 3.8.15 "OPEN THE FOLLGvING K)V:
3.8.15.1 850A and 850B RHR Pump Suction From Sump B Outside Containment 3.8.16 Low Head Recirculation 3.8.16.1 Start lA and 1B residual heat removal pumps.
3.8.16.2 Check flow meter FI-626 to ensure that low head recirculation is adequate.
If FI reading is not at least 400 gpn, switch to high head recirculation.
Refer to Step 3.8.18.
3.8.16.3 Close HOV 856, FWST to RHR Suction.
To operate K)V 856, AC power must be restored at the motor control center (breaker 10C MCC 1C).
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E-1.2:9 The following could be indications of passive failure in the low head recirculation path:
Abnormal flow on FI-626.
Flow on FI-931A or FI-931B.
High water level alarm in auxiliary buildirg sump.
High radiation level alarms in the auxiliary building.
NZE By exercising HCV-624, and HCV-625, ard by watchirg the corresponding indications on FI-626, FI-931A and FI-931B, the operator should detect the failure location, isolate it, ard use an alternate path for recirculation.
3.8.16.5 Within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, line up one safety injection pump to recirculation flow as follows:
3.8.16.5.1 3.8.16.5.2 Open valves 857B and C if lA RHR Pump is running or 857A if 1B RHR Pump is running ~
Start one SI pump 1A or 1B or lC to establish recirculation flow to the loop through MOV 878Bor D, safety injection to Loop A or B cold legs.
3.8.16.5.3 Check the recirculation flow on FI924 and FI925.
3.8.16.5.4 Place all containment isolation (T signal) valve switches in the "closed"
- position, and place CV A Sump Pumps in Pull stop position and manually reset containment isolation by use of key switch.
(Refer to E-l.l, "Safety Injection System Actuation," for containment Isolation Valve numbers).
3.8.17 3.8.17.1 3.8.17.2 3.8;17.3 3.8.17.4 Weekly, sample recirculation lcop fluid by opening AOV-959 to determine solution boron concentration and pH and make necessary adjustments.
Low Head Recirculation with S ra Note:
Start 1A and lB residual heat renoval pump.
'pen valves MOV-857B and MOV-857C if the 1A residual heat removal pump is running or open MOV-857A if the lB residual heat removal pump is running.
Start one spray pump and verify K)V discharge valves are open.
Close MOV 856, H/ST to RHR suction.
Vo operate MOV 856, AC gower must be restored at the rotor control center (breaker 10C MCC 1C).
3.8.17.5 Verify that HCV-836A or HCV-836B NaOH addition to Contaiment Spray Pump Disharges are open.
'Ihere should be at least a 5 gpn reading on FI-930.
NOZE:
If low head recirculation with contairxnent spray pump(s) is necessary, do rat also run the safety injection purop(s).
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E-1.2:10 1VZE:
When the spray additive tank level reaches 40$ ard containment pressure is less than 30 psig, HCV-836A and 836B may be closed and the containment spray pump(s) may be stopped.
Spray should be regulated during recirculation to ensure tht diverting recirculation flow to spray will not deprive the ECCS of sufficient flow to ensure core flocding.
'Lhis can be done by monitoring FI-626 (at least 400 ggm) ard regulating valves 860 A,B,C,D.
3.8.17.7 NOTE:
Spray must be resumed if containment pressure at any time approaches 30 psig with all available fan coolers in operation.
Within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, start one safety injection pump 1A or 1B or 1C to establish recirculation flow to the loop through NN 878B or D, safety injection to Loop A or B cold legs.
3.8.17.7.1 Check the recirculation flow on FI 924 ard FI 925.
3.8.17.7.2 Place all containment isolation (T signal) valve switches in the "closed" position, ard place CV A Sunp Pumps in Pull Stop gosition ard manually reset containment isolation by use of key switch.
(Refer to E-l.l, "Safety Injection System Actuation," for Contairraent Isolation Valve numbers).
hUZE:
Weekly, sample recirculation loop fluid by opening AOV-959 RHR sample to determine solution boron concentration ard pH, make necessary adjustments.
3.8.18 3.8.18.1 Hi h Head Recirculation Flow th usin the residual heat removal s.
Ogen valves tGV-857 A,B,C RHR to Safety Injection ard Containment spray suctions.
3.8. 18. 2 Start. residual heat renoval pumps ard safety injection pumps, lA and 1B, to establish recirculation flow to both lcops through valve 51OV-878B, ard BGV-878D, Safety Injection to Loop A and Loop B Gold Legs.
3.8.18.3 3.8.18.4 Check the recirculation flow on FI-924 ard FI-925.
Close bGV 856, PAST to RHR suction.
Kb cperate K)V 856, AC gower must be restored at the motor control center (breaker 10C HCC 1C).
3.8.18.5 Place all containment isolation (T signal) valve switches in the "closed" gosition, ard place CV A Sunp Pungs in Pull Stop position,-manually reset containment isolation by use of key switch.
(Refer to E-l.l "Safety Injection System Actuation," for Containment Isolation Valve numbers).
3.8. 18. 6 Within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, the RCS should be depressurized to the goint that the RHR low head flow path could be used for recirculation.
NOTE:
U n loss of instrument air operation of the pressurizer PORV's using the RCS overpressurxzation Nitrogen system can be achieved if 1).
RCS pressure is > 435 psig and 2).
There is > 200 psig of Nitrogen available frcm averpressurization storage tanks (normally at aproximately 700 psig) are satisfied.
CAUTION:
One operator will have to be on the back of the board turning
~ke switches as instructed below while another operator is watching pressure indication frcm the front of the control board.
To open PCV 431C:
1).
Turn "PC 431 SV8619B" to Arm 2).
Turn "Surge ZC V802B SV8616B" to open To o n PCV 430:
(i.
1).
Turn "PC430 SV8619A" to Arm.
2).
Turn "Surge 'IK V802A SV8616A" to open.
These steps will open respective PORV until 1 of the 2 valves in the train is closed.
If Nitrogen supply runs low, tanks can be refilled using procedure S29.2.
This will require reset of CV isolation.
3.8.18.7 When low head recirculation has been established, stop all but one safety injection pump.
3.8.19 MZE:
Weekly, sample recirculation loop fluid by opening AOV-959 to determine solution boron concentration ard pH and make necessary adjustments.
Daily, 'sample H2 to ensure that no dangerous
(>
4 volume percent) buildup occurs as a result of the LOCA.
3.9 If containment spray has been actuated, and if the containment pressure is reduced to ncminal operation containment pressure, reset contairnent spray.
Spray pumps should be shut-off and placed in the standby mode'with operable flow paths.
3.9.1 A water head equivalent to 25 psi above containment pressure should be maintained above the A a B Contairxnent Spray Pump Discharge Check Valves 862A and 862B.
Pressure is indicated by PI933A and PI933B located in vicinity of the pumps.
MZE:
If you are not sure of the above water head and do rut want to send operator to check, perform the following step to filllines.
3.9.1.1 To ensure that this water head remains during the design basis accident (D.B.A), the containment spray pump discharge MOV valves are to be maintained closed if the pumps are not in service.
A Spray Pump B Spray Pump MOV 860A MOV 860B NK 860C MOV 860D tVZE:
In the event that fluid must be made uo to either of these lines during the recirculation phase of the D.B.A. it will be necessary to align the RHR Pump Discharge to the ccmmon suction line for the spray pumps.
A RHR Pump B RHR Pump MOV 857B MOV 857C YiCV 857A If the "A" Spray Header needs fluid open, then close MOV 860A or lDV 860B.
If the "B" Spray Header needs fluid open, then close MOV 860C or MOV 860D.
Momentarily opening either of the parallel pump discharge valves for the spray header of concern will restore the fluid hea3 above the check valves.
3.10 Pericdically check auxiliary building area radition monitors for detection of leakage frcm ECCS during recirculation.
If significant leakage has been identified in the ECCS, attempt to isolate the leakage.
The operator must maintain recirculation flow to the RCS at all times.
E-l.2:13 While the plant is in the recirculation mcde, plant operators should make provisions. for an evaluation of equipnent in the plant.
'Ihis evaluation should include the primary safeguards equipnent e.g.,
RCS pumps ard valves, emergency diesels, continment fan ccolers, etc.
and support ecpipment e.g.,
ECCS HVAC eguignent, diesel fuel supply, diesel start air supply, samplirg of RCS for boron concentration and fuel damage, sampling of containment atmosphere, samplirg of recirculation sunp, etc.
Adjust recirculation sump pH, if recpired.
3.12 Continue to implement the recirculation mode of ccoling.
Recovery prccedures for the particular event must be developed ard implemented to effect plant return to service.
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