ML083190217
| ML083190217 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/06/2008 |
| From: | Caruso J Operations Branch I |
| To: | Hunter J Exelon Generation Co |
| Hansell S | |
| Shared Package | |
| ML081060533 | List: |
| References | |
| 50-352/08-301, 50-353/08-301, ES-D-1, TAC U01745 50-352/08-301, 50-353/08-301 | |
| Download: ML083190217 (88) | |
Text
Form E S - W -
Appendix D Scenario Outline Facility: Limerick 1 & 2 Scenario No.: 1 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
100% power, EOL, Unit 2 in refueling, OPCON 5 Turnover:
1A Drywell Chiller 00s for oil replacement, expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. D12 Diesel Generator running unloaded at rated speed for run-in following cylinder liner replacement.
Synchronize and load D12 Diesel Generator per RT-6-092-312-1, D l 2 Diesel Generator Run-In, beginning at Step 4.5.28.
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Event E
14 Malf. No.
NIA NIA MHP450 M C N 0 7 8 C MRR507A MPR020B MRDOIGF MRP029C MRP407C MSLl98A MSLl96B MSL196C MEHI 048 OR Bkrs MRC4578 Event Type*
N-BOP R-RO C-BOP, TS-SRO C-RO, TS-SRO I-RO TSOSRO M
M I-BOP
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Event
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Description Perform Loaded Run-In on D12 Diesel Generator 100 MWe Load Reduction For Transmission Line Problem HPCl Inadvertent Startup Condensate Pump C Trips, RRP A Fails to Runback APRM Channel 2 Fails to 96%
2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Power, B & C SLC Squib Valves Fail to Open
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Main Turbine Trip, Transfer Failure of Unit Aux Buses 11 and 12 RClC Flow Controller Fails Low in Automatic I *
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario # I - 2008 Limerick Operating Test Page 1 of 28
Scenario Summary and Administration Instructions SCENARIO
SUMMARY
The BOP will synchronize and load Diesel D12 to 700kW following a cylinder liner replacemont IAW RT-6-092-312-1, D12 Diesel Generator Run-In, beginning at Step 4.5.28.
After D12 load is stable at 650 to 700 kw, the Power System Director will call. Storms in the area have resulted in the loss of a grid transmission line. Unit 1 is requested to immediately reduce load by 100 MWe. The crew will lower power IAW GP-5, Steady State Operations,, Section 1 and OP-AB-300-1003, BWR Reactivity Maneuver Guidance.
HPCl will inadvertently start up after the plant is stable at the new lower power level. Power will rise but not to an automatic trip setpoint. Digital feedwater control system will reduce main feedwater flow to maintain RPV level. The crew will recognize the initiation signal is not valid and will isolate HPCl per S55.2.A, HPCl Shutdown From Automatic or Manual Initiation, Step 4.4. The SRO will determine HPCl is INOPERABLE and enter TS LCO 3.5.1.c. 1 Action c. 1 ( 14 days). HPCl Steam Line Outboard Isolation HV-55-1 F003 will fail as-is (closed) after isolation, such that HPCl cannot be unisolated by the crew later in the scenario.
Condensate Pump C will trip on motor overcurrent relay actuation, initiating a recirc pump runback to 42% speed on fail to runback. The RO will recognize the failure to runback and manually reduce RRP A speed. The SRO will identify operation outside of TS LCO 3.4.1.3.b and direct manual reduction of RRP A flow per TS LCO 3.4.1.3.b Action a to restore recirc loop flow mismatch to within limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3 condensate pumps running with feed flow > 80.3%. RRP A will APRM Channel 2 will fail upscale from current value to 96% over approximately 2 minutes. The crew will respond IAW alarm response procedures, determine the channel is failed and bypass the channel. The SRO will reference TS 3.3.1 and 3.3.6.
Two control rods will spuriously scram 2 minutes apart. The crew will respond per ON-104, Control Rod Problems, Section 2.3 and initiate a manual scram. A failure of RPS and ARI will prevent the scram. The crew will respond per T-101 and T-I 17 to lower reactor power. RO will insert rods. After some motion, rods will stop inserting due to a rod control system failure. The crew will lower reactor power by lowering RPV level to between minus (-)50 and minus (-) 186 inches (TAF is -161 inches).
When power is reduced by lowered RPV level, the main turbine will trip and both Unit Aux Buses 11 and 12 will fail to transfer to alternate power. Overrides on Unit Aux Bus alternate power breaker handswitches will prevent manually re-energizing these buses. The BOP will
- iatic, attempt to start RClC and determine the RClC speed controller has failed low in autot requiring flow control in manual.
Crew will determine unable to restore and maintain level > -1 86" and transition to T-I perform an emergency blowdown.
The scenario will be terminated when RPV pressure is 300 psig.
2 to NRC Scenario #I - 2008 Limerick Operating Test Page 2 of 28
Scenario Summary and Administration Instructions INITIAL SIMULATOR SETUP ITEM I MALFUNCTION / REMOTE FUNCTION I CONDITION Reset simulator to Scenario IC or IC-43 and perform the following:
100% Power A Drywell Chiller 00s D12 Diesel Generator running unloaded
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Apply Information Tags on the following components:
A Drvwell Chiller Take out of FREEZE and ensure the following:
Reactor Power is 100%
1 B Drywell Chiller is running.
With the exception of IA Drywell Chiller, all other equipment is OPERABLE.
Ensure materials for applicants:
Markup of RT-6-092-312-1, D12 Diesel Generator Run In (markup to Step 4.5.28, NA Step 4.5.30 for transferring safeguards buses.
Ensure the following malfunctions are loaded:
MSLl98A, active 1 minute after trigger 1 is activated.
MHP450, active after trigger 2 is activated.
MCN078C, active after trigger 3 is activated.
MPROZOB, active after trigger 4 is activated.
MRDO16F for 34-55, active after trigger 5 is activated.
MRDO16F for 18-35, active 2 minutes after trigger 5 is activated.
MEHIOB, active after trigger 7 is activated.
MRP029C, active immediately.
MRP407C, active immediately.
MSLl96B, active immediately.
MSLl96C, active immediately.
MRR507A, active immediately.
MRC457B, active immediately.
Ensure the following remote functions are loaded:
RSW397 at Target Value = YES RPC005 at Target Value = TRIP Ensure the following overrides are loaded:
252-10102/CS Aux Bus Feeder in OFF 252-101061CS Aux Bus Feeder in OFF 252-10202/CS Aux Bus Feeder in OFF NRC Scenario #I - 2008 Limerick Operating Test Page 3 of 28
Scenario Summary and Administration Instructions ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION 252-10206/CS Aux Bus Feeder in TRIP HS87-103A-2, 1A Drywell Chiller Disch Valve, GRN OFF, RED OFF HS87-103A-1, 1A Drywell Chiller Ind Lamps OFF I Ensure the following triggers are built:
Trigger 1 on SLC Pump 'A' RED Ind Light ON (ZSLLPAR)
I....
MRP407C MSL196B MSL196C MSL19rn MHP45U MCN078C MRR507A MPRO20B I MEH104B MRDOt6F MRD016F MRC457B BOTH ARCS OivisianrARl FailsloIntm4e SLC SquibValve 8 Fails l o Open SLC SquibValve C Fails ID Open SLC Pump 1A Loss 01 Conlrol Povm lnadverlenl HPCl S l a t Up Condensate Pump C Trips Rrcirc PumplAH1RunbackRlyE.21AFai's APRM Channel 2 Fails Io Selecled Value Turbine Goveiiwi Falls Low 34 55 Coniiol Rod Faiurs. Sciarnrned 18.35 Control Rod Failure. Scrammed RCIC Flow ControUer Fails Low
- o De-Eneigize 1,"s I,"%
True T l u a irus True T rue 96 T rue 1 rue TI"8 TlU.3 00 00 00 u0 0CI ou 00 00 WI 00 OD 00 00 00 00 00 00 00 00 00 00 00 00 00 00 00 w 00 00 w O[I ua ou oo 00 oo 00 u0 ou 00 00 ou mu1 no 00 00 00 00 00 00 00 00 00 wDoD0 00 00 00 00 00 00 00 02 00 WWO0 un 00 00 uouoo0 0
UUU00Cl u
U0UUOO u
00ou00 2
000000 3
000000 0 0000cQ 4
000000 7
000000 5
000000 5
oawoo 0
unooou i Delete All."d Pending Ti,',
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RSW397 ESW Loop B Service Wale, Isclated?
YES 000000 0000uo 0
RPCOO5 Diywell Chilie! A Manud Bleaker Coni801 TRIP o
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o o
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nooooo o
Override Siriirrimr 25210102/CS lOSU Busfeeder lo11 A\\uxBus10102ConliolSwitch CLOSE OFF oooooo oooooo o
!25210102/CS 1OSU BusFeadeitoll AuxBus 10102CantiolSwilch NACLUSE OFF 000000 000000 0
252101021CS lOSU BusFesd~r10 11 AuxBus 10102ControlSwitch NAlRlP 0 FF 000000 000000 0
25210102/CS lOSU BusFssdcrlo11 AuxB~~10102ConfiolSwiIch TRIP ON 000OOD 000000 0
25210106/C5 2OSU 8usFeedeiio11 AuxBus10106ConI~olSwiIch CLUSE OFF 000000 000000 0 252 10106/CS 20 SU Bus Feeder to 11 Aux Bur 10106 Control Switch NACLOSE 0 FF 0000oo 000000 0
252101061CS 20SU Bu;Feederloil AxBur10106ConliolSwilch NATRIP OFF 000000 000000 0 TRIP ON OOOUDO onrJoo0 0
252 101 06/CS 20 SU Bur Feeder Io 11 Aux Bur 10106 Conliol Switch 25210202/CS lOSU BusFesderlo12AuxBur10202Cont~olSw~lch CLUSE OFF Do0000 00uo00 0
L52 10202/CS 10 SU Bur Feeder lo l2Aux Bur 10202 Contiol Switch NACLOSE OFF 000000 000000 0
25210202/CS l 0 S U BurFeederlo12AuxBuil0202ConlialSwilch NATRIP OFF 000000 c100000 0
25210202/CS lOSU BusFeedarto12AuxBus10ZOZContiolSwilch TRIP ON uoouuo 00uouo 0
252 10206/CS 20 SU Bus Fesder IO l 2 A u ~
Bur 10206 Conlrol Swlch CLOSE OFF 000000 000000 0
252 10206/CS 20 SU Bus Feedei Io 12Aux Bus 10206 Conlrol Swilch NACLOSE OFF ouu000 00uo00 0 252 10206/CS 20 SU Bus Feeder lo 12 AUK Bus 10206 Cont!al Smleh NATRIP OFF uuouu0 000000 0
oou000 00OCIU0 0
25210206/CS LOSU Bur Feeder lo12A~.:Bus10206ConlioiS~Ich TRIP O P I HS87 1034 2 SV87 1024 l A Diywell Chiller Disci-Valve Ind Lainpr GREEN OFF 00uoo0 00000u 0
HS87 103a 2 SV87 1024 14 Drywell Chiller DirchV&e lnd Lamp, RED OFF 000000 000000 0 HS87 1034 1 Drywell Chill-[ 1AKl11 IndLamps ALLOFF 0000UU UU0000 0
Timer Pmsa lielare
-111 A l l Pending I Reset any annunciators that should not be present NRC Scenario #I
- 2008 Limerick Operating Test Page 4 of 28
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Scenario Summary and Administration Instructions J
INSTRUCTIONS FOR SIMULATOR OPERATOR MALFUNCTION / REMOTE FUNCTION / REPORT
.A Respond to request for assistance as appropriate.
Call as PSD. Storms in the area have resulted in the loss of a grid transmission line. Unit 1 is requested to immediately reduce load by 100 MWe.
ll 1
Activate Trigger 2.
II W Call back 5 minutes after help requested to inform "apparent relay failure, continuing to investigate".
Respond to request for assistance as appropriate.
II I
Activate Trigger 3 m Call back 5 minutes after help requested on condensate pump trip to inform "condensate pump has overcurrent trip relay actuated".
Call back 5 minutes after help requested on failure to runback to inform "apparent relay failure, continuing to investigate".
Respond to request for assistance as appropriate.
B Activate Trigger 4 EO reports.
If Channel is bypassed, then EO confirms "channel is bypassed" NRC Scenario #I
- 2008 Limerick Operating Test Page 5 of 28
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Scenario Summary and Administration Instructions MALFUNCTION I REMOTE FUNCTION I REPORT I
If Channel not bypassed, then EO reports "indicating 96%"
J rn If I&C contacted to investigate, acknowledge request.
W Respond to request for assistance as appropriate.
MALFUNCTION / REMOTE FUNCTION / REPORT H When SE-10 Floor Actions are called out, perform all SE-10 actions with Time Delays.
rn Respond to request for assistance as appropriate.
EVENT 6:
2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Power, B & C J
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MALFUNCTION / REMOTE FUNCTION / REPORT SLC Squib Valves Fail to Open MALFUNCTION I REMOTE FUNCTION I REPORT rn Activate Triggers 5 & 6.
When T-200's called out, perform T-270 remote with time delay and toggle T-221 to bypass after 1 I minutes.
rn Respond to request for assistance as appropriate.
rn If I&C contacted to investigate, acknowledge request.
H Respond to request for assistance as appropriate.
NRC Scenario #1 - 2008 Limerick Operating Test Page 6 of 28
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Scenario Summary andAdministration instructions CRITICAL TASKS
- 1. T-117.1 Standard:
- 2. T-117.7 Standard:
- 3. T-117.3 Standard:
Inhibit automatic ADS.
Prevent automatic initiation of ADS.
Terminate and prevent injection into the RPV.
RPV level lowered below -50 by Terminating and Preventing injection into the RPV per T-270.
Perform emergency blowdown per T-I 12.
When RPV level cannot be maintained above -186 inches and injection into the RPV (except from boron injection systems, CRD, and RCIC) has been terminated and prevented, 5 SRVs are opened.
NRC Scenario #I
- 2008 Limerick Operating Test Page 7 of 28
Form E S S Appendix D Required Operator Actions Op-Test No.: 2 Event
Description:
Time Posit ion SRO BOP BOP BOP BOP BOP Scenario No.:
1 Event No.: 2 Perform Loaded Run-In on D12 Diesel Generator e
Applicant's Actions or Behavior Direct BOP to continue with diesel generator run-in procedure.
Obtains CODV of RT-6-092-312-1, D l 2 Diesel Generator Run PLACE 125-1 1607/SS, DIESEL GEN 12, SYNC, to "ON," using Sync:
Switch handle.
VERIFY Synchroscope is rotating with both lights fully bright at 180" AND off at 0".
I NOTE Next two steps verify controls operating properly. Change in D/G frequency can be observed by change in Synchroscope (SYSTEM) speed. Change in DIG voltage can be observed by change in Synchronizing Incoming Voltmeter (INCOMING). (Ref 6.5)
OBSERVE change in D/G frequency by placing 165 BG501/CS, SPEED GOVERNOR, to "RAISE" AND to "LOWER."
OBSERVE change in D/G voltage by placing 170 BG502/CS, VOLTAGE REGULATOR, to "RAISE" AND to "LOWER."
NOTE Next step adjusts DIG frequency slightly faster than D12 Safeguard Bus frequency.
I I
I NRC Scenario #I
- 2008 Limerick Operating Test Page 8 of 28
Form E S E Appendix D Required Operator Actions 1
Op-Test No.: 1 BOP Event
Description:
I BOP oop 1 BOP 1 BOP Scenario No.:
1 Event No.: 2 Perform Loaded Run-In on D12 Diesel Generator Applicant's Actions or Behavior ADJUST 165-8(3501/CS, SPEED GOVERNOR, so Synchroscope is rotatina slowlv in FAST (CW) direction.
ADJUST 170-BG502/CS, VOLTAGE REGULATOR, SO INCOMING Voltaae is sliahtlv hiaher than RUNNING Voltaae.
e WARN I NG WHEN synchronizing, THEN extreme care is needed since excessive voltage/phase difference will cause equipment damage OR personnel WHEN Synchroscope is within 3 O before 12 ol'clock position rotating slowly in FAST (CW) direction, THEN CLOSE 152-1 1607, GENERATOR Bkr.
CAUTION KVAR's are to be maintained less than 75% KW to prevent generator winding overheating AND exceeding 0.8 rated power factor.
Immediately RAISE load to 200 - 300 KW by placing 165-BG501/CS, SPEED GOVERNOR, to "RAISE."
RAISE reactive load to 100 - 150 KVAR by placing 170-BG502/CS, VOLTAGE REGULATOR. to "RAISE."
PLACE 125-1 1607/SS, DIESEL GEN 12, SYNC, to "OFF."
IF performing other plant testing AND Safeguard Bus needs to be transferred, THEN PERFORM transfer of Safeguard Bus per S92.6.A, Transfer Of A 4kv Safeguard Bus From 101 Safeguard Feed To 201 Safeguard Feed And Vice Versa. [APPLICANT SHOULD NOT PERFORM THIS STEP.]
NRC Scenario #I - 2008 Limerick Operating Test Page 9 cf 28
Form E S m Appendix D Required Operator Actions Time Scenario No.: I Event No.:
Position BOP BOP BOP BOP Perform Loaded Run-In on D12 Diesel Generator Applicants Actions or Behavior CAUTION Rapid loading during testing will subject diesel generator to unnecessary stresses.
Gradually RAISE load at a rate of less than or equal to 350 KW/minLite to 650 - 750 KW (25% of Full Load) by adjusting 165-BG501/CS, SPEED GOVERNOR AND MAINTAIN reactive load (KVAR) less than or equal to 75% of KW, using 170-BG502/CS, VOLTAGE REGULATOR at Dane1 1 BC661.
WHEN 650 - 750 KW is obtained, THEN START stopwatch.
CAUTION II Hot water is present at vents. Appropriate personal protective equipment AND Tygon tubing must be used.
OPEN AND CLOSE 11-139OB, JACKET WATER HEAT EXCHANGER SHELL VENT, AND 92-1607B, AIR COOLER VENT, to ensure any trapped air is vented from the Jacket Water/Air Cooler Coolant Systems. [DIRECTS EO ACTION]
IF Jacket Water Expansion Tank Level is low, THEN OPEN 20-1 132B, Jacket Water Expansion Tank Manual Fill Valve, to fill tank to within 2 inches of top AND THEN CLOSE 20-1 132B. [DIRECTS 0 ACTION]
Examiner Note NRC Scenario #I
- 2008 Limerick Operating Test Page 10 of 28
Form E S G Appendix D Required Operator Actions Op-Test No.: 1 Event
Description:
Time Position SRO SRO SRO I RO SRO Scenario No.:
1 Event No.: 2 100 MWe Load Reduction For Transmission Line Problem
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Applicant's Actions or Behavior Refer to GP-5, Steady State Operations, Attachment 1, Planned I Intentional Rx Power Maneuvers Between 90% and 100%
Informs crew of PSD request and directs a power reduction of 1OOM6 IAW GP-5, Attachment I NOTES
- 1.
Power System Director should be notified of all Rx power changes. IF possible, THEN notification should be made prior to the change in Rx power.
A rapid reduction in Rx power may cause level swell in the Steam Seal Evaporator causing HV-07-*57, S.S.E. Cond MIU Shutoff Vlv (SUP}, to close. This valve will not reopen automatically.
Rx power reductions should be conducted in accordance with one of the following, unless directed otherwise by Reactor Engineering:
Reactor Maneuvering Shutdown Instructions 0
Reactor Maneuvering Special Instructions 2
3 OP-AB-300-1003, BWR Reactivity Maneuver Guidance
[RE not required]
CAUTION A Reactor Engineer must be present to monitor core performance during control rod manipulations, except during the following activities:
0 Reactor Maneuvering Shutdown Instructions 0
ST-6-1 07-760-*, Control Rod Exercise (CM-3)
As allowed by OP-AB-300-1003, BWR Reactivity Maneuver Guidance DETERMINE targeted Rx power level for intended drop in Rx power.
[Determines reactor power must be reduced approximately 1 O%.]
NOTIFY Power Team of power reduction and obtain E-DART Ticket number 803-6530 (61 0-765-6530)
NRC Scenario #I
- 2008 Limerick Operating Test Page 11 of 28
Form E S S
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Appendix D Required Operator Actions Op-Test No.: 1 Event
Description:
Scenario No.:
1 Event No.: 2 100 MWe Load Reduction For Transmission Line Problem Time Position SRO RO SRO I RO SRO BOP SRO BOP SRO Applicants Actions or Behavior REDUCE Rx power, as required, in accordance with one of the following, unless directed otherwise by Reactor Engineering Otherwise, MARK this step NIA.
0 Reactor Maneuvering Shutdown Instructions 0
0 Reactor Maneuvering Special Instructions OP-AB-300-1003, BWR Reactivity Maneuver Guidance
[Directs RO to reduce power using BWR Reactivity Maneuver Guidance]
Lowers Rx Recirc flow by reducing output of both RRP speed controllers, while maintaining On a continuing basis during Rx power reduction, OBSERVE the following:
0 APRMs - lowering 0
Recirc flow - lowering 0
Steam flow - lowering 0
RPV level - normal 0
FW flow - lowering
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MONITOR BOP [balance ofplant] during drop in Rx power.
ENSURE EHC Load Set is maintained greater than 100% as indicate on PMS computer point E*651.
REQUEST a new P-I edit.
NRC Scenario #I
- 2008 Limerick Operating Test Page 12 of 28
Form E§= -
Appendix D Required Operator Actions Op-Test No.: 1 Event
Description:
Scenario No.: I Event No.: 2 100 MWe Load Reduction For Transmission Line Problem Time Position SRO SRO Applicants Actions or Behavior VERIFY (APRM-%CTP) listed on the P-I edit are between -2.0 to 2 0.
IF any (APRM-%CTP) are not within these limits, THEN CHECK (APRM-%CTP) with either a new P-I OR an NSS03, Core Power And Flow Log.
IF (APRM-YoCTP) still outside prescribed limits, THEN PERFORM ST-6-1 07-887-*, APRM Gain Determination And Auto Adjustment OR ST-6-1 07-888-*, Manual APRM Gain Adjustment.
[Confirms A PRM-%CTP between limits.]
VERIFY scram margin is > 9.0%. IF scram margin is c 9.0%, THEN NOTIFY Reactor Engineering for rod pattern adjustment. [Confirms scram margin >9%]
Proceed to the next event Examiner Note NRC Scenario #I
- 2008 Limerick Operating Test Page 13 of 28
Form ES-P Appendix D Required Operator Actions Posit ion CREW RO SRO RO SRO SRO BOP Applicants Actions or Behavior The crew will observe annunciators :
(1 13 B-5) CORE SPRAY LINE INTERNAL BREAK (107 H-2) REACTOR HI / LO LEVEL Op-Test No.: 1 Scenario No.:
1 Event No.: 3 Event
Description:
HPCl Inadvertent Startup SRO Reports reactor power rising.
Maintain power < 90%.
Announces OT-I 04 entry.
Refer to alarm response procedures.
PER ARC-MCR-107-Ii2, REACTOR HllLO LEVEL :
- 1. IF Reactor water level is low and unexpected or unexplained, THEN enter OT-100, Reactor Low Level.
- 2. IF Reactor water level is high and unexpected or unexplained, THEN enter OT-110, Reactor High Level.
[SRO will enter OT-170.1
- 3. Refer to LGS Emergency Plan Annex, Table 3-1.
NRC Scenario #I
- 2008 Limerick Operating Test Page 14 of 28
Form E?= ~-
Appendix D Required Operator Actions Position SRO BOP BOP RO
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Applicants Actions or Behavior PER ARC-MCR-113-95, CORE SPRAY LINE INTERNAL BREAK : -
NOTE Alarm designed to indicate failure of one of the core spray loop pipirig between the vessel penetration AND the core shroud penetration.
Normal rated power shroud/annulus dP is 7.5 psid. A valid value of greater than +1.3 or less than -3.8 psid indicates a failure of the core spray piping outside the shroud. A value of greater than +7.5 psid or less than -10.0 psid indicates a failure of the core spray piping outside the vessel. A failure between the vessel AND containment would be measured by the containment leakage detection systems. This instrument loop is very noisy due to the condensation of steam inside the core spray piping AND also sensing pressures inside the shroud.
Spurious alarms that immediately clear should NOT be considered valid.
- 1. Inform Shift Supervision.
- 2. IF signal is valid AND dP is greater than + I.3 psid, THEN declare A Core Spray loop INOPERABLE due to a pipe break AND consider a normal plant shutdown per GP-3.
- 3. IF signal is valid AND dP is less than -3.8 psid, THEN declare B Core Spray loop INOPERABLE due to a pipe break AND consider a normal plant shutdown per GP-3.
- 4. IF containment parameters indicate a LOCA, THEN perform a rapid plant shutdown per GP-4.
- 5. Refer to Tech Spec 3.5.1.
- 6. Request I&C verify proper functioning of PDT-052-1 N056.
[BOP should inform SRO of alarm and refer to alarm response.
BOP and SRO will determine the alarm is due to HPCl pump running and NOT indicative of a pipe break.]
Recognize HPCl pump is running and injecting with no valid initiation sianal.
Should observe a small power rise.
NRC Scenario #I
- 2008 Limerick Operating Test Page 15 of 28
Form E S S Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
1 Event No.: 3 Event
Description:
HPCI Inadvertent Startup Position SRO SRO BOP BOP BOP Applicant's Actions or Behavior
[OT-770, Steps 3.7 thru 3.7 are not applicable to the situation.
SRO will utilize Step 3.12.5 of OT-104, shown below, to stop HPCI injection.]
IF inadvertently injecting, THEN ENSURE HPCl AND RClC not required for adequate core cooling.
- 1.
IF not required for adequate core cooling, THEN TRIP HPCl in accordance with S55.2.A, HPCl Shutdown From Automatic Or Manual Initiation AND RClC in accordance with S49.2.A, RClC Shutdown From Automatic Or Manual Initiation.
Order HPCl isolation per S55.2.A, HPCI Shutdown From Automatic or Manual Initiation.
[Procedure S55.2.A Actions :]
IF HPCl Initiation Signal is present as indicated by white SEAL IN light Lit AND can not be reset, THEN GO TO step 4.4.
Insert Malfunction MHP446B to fail HPCl Steam Line Outboard Isolation HV-55-1 F003 as-is (closed) after isolation, such that HPCl cannot be unisolated by the crew later in the scenario.
DEPRESS AND RELEASE HPCl Manual Isolation (ISOLATION)
Dushbutton.
VERIFY HV-55-*F003, "HPCI Steam Line Outboard Isolation" (OUTBOARD), closes.
VERIFY HPCl turbine comes to rest as indicated by SI 56 *61, "HPCI Turbine Speed" (S).
Booth Operator Note NRC Scenario #I - 2008 Limerick Operating Test Page 16 of 28
Appendix D Required Operator Actions Form E S G Time Op-Test No.: 2 Scenario No.:
1 Event No.: 3 Event
Description:
HPCl Inadvertent Startup Position BOP BOP BOP SRO SRO Applicant's Actions or Behavior COLLECT Turbine (*O-S211) reservoir oil sample per MAG CG-502-2, Lubrication Program Guide, after components come to rest, AND REQUEST Chemistry perform moisture analysis of oil sample. CM-"
[BOP will direct field activity to collect oil sample for Chemistry analysis. J ENSURE *OP216, "Barometric Condenser Vacuum Pump" (VACUUM P U M P), operating.
ENSURE *OP213, "Auxiliary Oil Pump" (AUX OIL PUMP), operating.
[No further steps can be performed in S55.2.A because initiation signal is not reset.]
Contact maintenance department to begin troubleshooting and repair.
Refers to Tech Specs. Announces HPCl INOPERABLE. Enters TS LCO 3.5.1.c.1 Action c.1 (14 days).
Examiner Note Proceed to the next event NRC Scenario #I
- 2008 Limerick Operating Test Page 17 of 28
Form E S - E Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
1 Event No.: 4 Event
Description:
Condensate Pump C Trips, RRP A Fails to Runback Time Position Crew BOP RO SRO RO SRO SRO SRO Applicant's Actions or Behavior Respond to numerous annunciators:
104 G I 104 G2 104 D4 107 D5 FWLCS TROUBLE 112 C4 Note to examiners: 11 1 C4, 1A RECIRC FLOW LIMIT should actuate on condensate pump trip but will not actuate because of concurrent failure of 1A auto runback.
CONDENSATE PUMP MOTOR OVERLOAD CONDENSATE PUMP BREAKER TRIP CONDENSATE PUMPS DISCHARGE HEADER LO PRESS 1B RECIRC FLOW LIMIT Report trip of 'C' Condensate Pump Report 1A Recirc Pump is not running back.
Place 1A Recirc Pump Speed Controller in MANUAL. Lower speed to 42%.
[per OP-LG-108-101-1001, "Simple Quick Acts / Transient Acts",
Transient Act 3.2.3 and 3.2.10 and per TS LCO 3.4. 1. 3. b, Action b]
Enters GP-5 Attachement 3, Unintentional Drop in Power. Checks mismatch in SteD 3.1.3.
Enters TS LCO 3.4.1.3.b Action b for restoring recirc loop flow mismatch to within limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Inform management and PSD of plant status.
Examiner Note:
Proceed to the next event NRC Scenario #I
- 2008 Limerick Operating Test Page 18 of 28
Form ES- --
Appendix D Required Operator Actions Position Crew RO RO BOP Applicant's Actions or Behavior Acknowledge numerous annunciators.
RO reports power, level, pressure stable.
Refer to alarm response procedures.
108 B-3 APRM UPSCALE TRIP I INOP
- 1. At APRM Operator Display Assemblies (ODAs) on Panel 1 OC603, determine APRM channel(s) causing Upscale TripllNOP condition as follows:
Message "TRIP (inverse video) appears in display header of each ODA whose associated channel has an active APRM HI-HIANOP OR OPRM Upscale Trip condition Message "INOP-CAL" OR "INOP-SET"(inverse video) appears in display header of each ODA whose associated chassis Key Lock Mode Switch is in "INOP" position "TRIP STATUS" screens display status of active trip outputs from associated channel (an "*'I indicates trip signal present)
Timely performance of Step 2 will reduce the likelihood of a full scram by eliminating a single point vulnerability exposure.
0 0
NOTE:
- 2.
IF one APRM channel has Upscale TripllNOP condition, THEN place APRM channel in "BYPASS" with SSV permission.
- 3.
IF all other APRhI channels are reading normal, THEN contact I&C to determine fault with APRM channel AND repair.
- 4.
IF Rx Power is rising, THEN refer to OT-104, Unexpected/
Unexplained Positive Or Negative Reactivity Insertion.
NRC Scenario #1 - 2008 Limerick Operating Test Page 19 of 28
Form E S B Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
1 Event No.:
Event
Description:
APRM Channel 2 Fails to 96%
Time Position RO BOP RO BOP SRO Applicant's Actions or Behavior Refer to alarm response procedures.
108 B-4 APRM UPSCALE
- 1. At APRM Operator Display Assemblies (ODAs) on Panel 10C603, determine APRM channel(s) causing Upscale Alarm condition as foIlows:~
Message "ALARM" (inverse video) appears in display header of each ODA whose associated channel has an active APRM HI OR OPRM Pre-Trip Alarm condition "TRIP STATUS" screens display status of active alarm outputs from associated channel (an "*I' indicates alarm signal present)
Timely performance of Step 2 will reduce the likelihood of a full scram by eliminating a single point vulnerability exposure.
IF one APRM channel has Upscale Alarm condition, THEN place upscale APRM channel in "BYPASS" with SSV permission.
IF all other APRM channels are reading normal, THEN contact I&C to determine fault with APRM channel AND repair.
IF Rx Power is rising, THEN refer to OT-104, Unexpected/
Unexplained Positive Or Negative Reactivity Insertion.
NOTE:
- 2.
- 3.
- 4.
Refer to alarm response procedures.
108 F-3 ROD OUT BLOCK
- 1. IF cause of Rod Block is RDCS INOP, THEN reset Rod Drive control cabinet per S73.0.F, Resetting the Rod Drive Control System.
- 2. Refer to S73.O.B, identifying rod block inputs to the Reactor Manual Control System.
Reference TS 3.3.1 and 3.3.6.
Examiner Note:
Proceed to the next event NRC Scenario #I - 2008 Limerick Operating Test Page 20 of 28
Form ES-D-2 Appendix D Required Operator Actions Position RO SRO RO RO SRO RO BOP RO SRO Scenario No.:
Event No.:
2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Power, B & C SLC Squib Valves Fail to Open Applicant's Actions or Behavior Observes 108 F-4 ROD DRIFT alarm. Notes 2 control rods scrammed 2 minutes apart. Informs SRO.
~
Enters ON-104, Control Rod Problems, Section 2.3.
IF more than one control rod inadvertently scrams, THEN manually SCRAM the reactor AND PLACE Mode Switch in "SHUTDOWN" OR T-I 01, as applicable.
Orders a reactor scram.
AND ENTER T-1 00, Depresses scram pushbuttons. Takes Mode Switch to Shutdown.
Reports reactor not scrammed.
Enters T-101, RPV Control, on "SCRAM condition with power above 4% or unknown". Directs 'TI Drocedure activities.
Manually initiates RRCS and ARI.
Ensures recirc runback to minimum (RC/Q-8).
Insert rods manually with the RWM bypassed (RCIQ-12)
Calls out procedures for electrical ATWS 215, T-216 (RCIQ-13).
Also directs T-209. T-214 and T-251.
NRC Scenario #I
- 2008 Limerick Operating Test Page 21 of 28
Form ES-D-2 Appendix D Required Operator Actions Position SRO RO Op-Test No.:
Scenario No.:
1 Event No.: 6 II
~-
Applicant's Actions or Behavior Attempts SLC injection. Determines SLC will not inject (RC/Q-16).
SRO directs T-212 (RCIQ-20).
- 1) Event
Description:
2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Powor, B & C SLC Squib Valves Fail to Open Inhibits auto ADS (RC/Q-19 or LQ-3).
BOP CRITICAL TASK (T-I 17.1)
Enters T-I 17, Level I Power Control (RC/L-2).
=-I----
NRC Scenario #I
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Form E S G Appendix D Required Operator Actions Op-Test NO.: 1 Event
Description:
Scenario No.:
1 Event No.: 6 2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Powcx, B & C SLC Squib Valves Fail to Open Time CT Position BOP Applicants Actions or Behavior Terminate and prevent per T-270, except Boron, RClC and CRD BOP: Ensures HPCl isolated, ensures LP ECCS is off, calls Field Supervisor to prevent auto start of ECCS.
4.1.I DISPATCH an operator to the Aux Equipment Room to perf0.m Section 4.7.
4.2.1 WHEN HV-55-1 F003, HPCI Main Steam Supply Outbrd PCI\\r (OUTBOARD), manipulation is required, THEN OBTAIN PA
- 2235 key.
4.2.2 IF HPCl initiation signal is present, AND can not be reset THEN SHUT DOWN 1 OS21 1 HPCI Turbine as follows:
- 1.
- 2.
4.2.3 IF HPCl initiation signal is not present, THEN SHUT DOWN 1 OS21 1, HPCI Turbine, as follows:
- 1.
(LQ-5).
DEPRESS AND RELEASE E41A-S32,Pushbutton for Manual Isolation (ISOLATION).
ENSURE HV-55-1 F003, HPCI Main Steam Supply Outbrd PCIV (OUTBOARD) closed.
Simultaneously DEPRESS AND HOLD HS-056-161, Pushbutton For HPCl Turbine Trip (E41A-519)
Main Steam Supply Outbrd PCIV (OUTBOARD).
VERIFY HV-55-1 F003, HPCI Main Steam Supply Outbrd PCIV (OUTBOARD), closed.
RELEASE HS-056-161, Pushbutton For HPCl Turbine Trip (E41A-SI9) (TURBINE TRIP).
(TURBINE TRIP) AND CLOSE HV-55-1 F003, HPCI
- 2.
- 3.
IF required, THEN ENSURE the following valves closed:
4.4.2 HV-52-1 F005 Core Spray Loop A Shutoff PCIV (OUTBOARD)
HV-52-1 F037 Core Spray B Loop Inboard Disch Vlv (INBOARD DISCHARGE) 0 CRITICAL TASK (T-I 17.7)
NRC Scenario #I - 2008 Limerick Operating Test Page 23 of 28
g -
Form E$-D-2 Appendix D Required Operator Actions Op-Test No.:
Event
Description:
Scenario No.:
1 Event No.: 6 2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Powrtr, B & C SLC Squib Valves Fail to Open Time Position BOP
~.-
-~
Applicants Actions or Behavior Terminate and prevent per T-270, except Boron, RClC and CRD 4.5.2 IF required, THEN ENSURE the following valves closed:
0 (LQ-5).
HV-51-1F017A, IA RHR LPCl lnj PCIV (OUTBOARE A)
HV-51-1 F017B, 1 B RHR LPCl lnj PCIV (OUTBOARD 6)
HV-51-1 F017C, 1 C RHR LPCl Inj PCIV (OUTBOARD C)
HV-51-1 F017D, 1 D RHR LPCl Inj PCIV (OUTBOARD D)
CRITICAL TASK (T-I 17.7)
NRC Scenario #I - 2008 Limerick Operating Test Page 24 of 28
Form E?=
Appendix D Required Operator Actions NOTE Op-Test No.: 1 Event
Description:
I Time Position RO BOP/RO Scenario No.:
1 Event No.: 6 2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Powr!r, B & C SLC Squib Valves Fail to Open Applicant's Actions or Behavior rerminate and prevent per T-270, except Boron, RClC and CRD LQ-5).
1.6 1.6.1 1.6.2 1.6.3 1.6.4 1.6.5 t.6.6 ERMINATION/PREVENTION OF CONDENSATE/FEEDWATER INJECTION (MAIN CONTROL ROOM)
ENSURE HV-06-138A, "IA RFP BPV" (BYPASS), closed at panel 1 OC651.
ENSURE LIC-06-138, "A Feedwtr Start-up Lvl Control" (LV, STARTUP BYPASS), in "Manual" (MAN) AND output demand at 0% at panel 1OC603.
ENSURE LIC-06-120, "Reactor Feedpumps Bypass Cont Vlv" (PUMP BYPASS) in "Manual" (MAN) AND output demand at 0% at panel 1OC603.
ENSURE FIC-MI -1 R601A,B,C, "A,B,C RFPT Speed Controller," in "Manual" (MAN) for all three RFPTs at panel 1 OC603.
DEPRESS EMERGENCY STOP pushbutton for all three RFPTs at panel 10C603.
WHEN EMERGENCY STOP light goes out, THEN DEPRESS AUTO START pushbutton for all three RFPTs at panel 1 OC603.
1 IF performing T-270 for emergency RPV depressurization, THEN steps 4.6.7 through 4.6.9 should be performed concurrently Otherwise, these steps may be performed in any order as desired.
2 Steps 4.6.7 through 4.6.9 are performed from panel 10C651 in Main Control Room.
1.6.7 CLOSE HV-06-108A, "IA RFP Discharge" (FEED DISCH A).
1.6.8 CLOSE HV-06-108B, "1 B RFP Discharge" (FEED DISCH 6).
1.6.9 CLOSE HV-06-108C, "1 C RFP Discharge" (FEED DISCH C).
- RITICAL TASK IT-I 17.7)
.ewer level and control - 60 to -100 inches (LQ-5).
JOTE: Crew may observe RClC failure (Event 8) here.
NRC Scenario #I
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Form ES-D-2 Appendix D Required Operator Actions Op-Test No.: 2 Event
Description:
Time Position BOP/RO BOP SRO Scenario No.:
1 Event No.:
2 Control Rods Scram, ATWS, 1A SLC Pump Loss of Control Powt:r, B & C SLC Squib Valves Fail to Open Applicants Actions or Behavior Lower level and control > - 186 inches (LQ-17).
[In T-1011:
Control RPV pressure 990 - 1096 with EHC (RC/P-4).
Directs T-221 to ensure MSlVs open (RC/P-9).
PROCEED TO THE NEXT EVENT WHEN LEVEL HAS REDUCED POWER AND T-221 AND T-270 ARE COMPLETE IN THE AUX EQUIPMENT ROOM.
11 (ensures crew must manually start LP ECCS pumps when needed for level control)
NRC Scenario #I
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Form ES-D-2 Appendix D Required Operator Actions Position I
Op-Test No.:
Scenario No.:
1 Event No.: 7 Applicant's Actions or Behavior Event
Description:
Main Turbine Trip, Transfer Failure of Unit Aux Buses 1 1 and 12 SRO Time Exit T-101, RClP leg only (EB-4).
Determine turbine has tripped and condenser is unavailable. Not -
t to feed with RClC (see next event).
Recognize unable to restore and maintain level =. - 186 inches. Enters T-I 12, Emergency Blowdown (T-I 17, LQ-19).
BOP CRITICAL TASK (T-I 17.3)
TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:
RPV PRESSURE IS q 300 PSIG RESTORING RPV LEVEL WITH LOW PRESSURE ECCS PUMPS POST-SCENARIO :
HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO.
NRC Scenario #I
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Form ESD-2 Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
1 Event No.: 8 Event
Description:
RClC Flow Controller Fails Low in Automatic Position Applicant's Actions or Behavior Observes RClC PUMP LO FLOW alarm (1 16 83) and RClC turbine riot running at normal speed. Identifies flow controller output at minimum in BOP 1
auto.
BOP I Places RClC flow controller in manual and raises flow.
TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:
II 0
RPV PRESSURE IS C 300 PSlG NRC Scenario #I
- 2008 Limerick Operating Test Page 28 of 28
Appendix D Scenario Outline Form ES-I)-1 1
2 3
4 6
Facility: Limerick 1 & 2 Scenario No.: 2 Op-Test No.: 1 Examiners:
Operators:
MRDOl6E NIA MCUI 95B MRP027B MRR433B MRR434B OR F023B MMS067 MRR440A MED261 MDG420A MED263C MHP447A MHP449 Initial Conditions:
Unit 1 at 90% power. Unit 2 is at 100% power.
Turnover:
1A Drywell Chiller 00s for oil replacement, expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Fuel handling is in progress in Unit 1 Spent Fuel Pool. Shift orders are to perform a rod pattern adjustment.
Event Type" C-RO TS-SRO R-RO C-RO C-BOP TS-SRO C-RO C-BOP M
M C-BOP Event Description I
Control Rod 38-47 Drifts Out Perform Rod Pattern Adjustment RPS Channel B Breaker Trip, RWCU Fails to Isolate RRP 1 B #I Seal Failure, Followed By #2 Seal Failure, RRP Suction Valve Fails As-Is Coolant Leak in Drywell Loss of Offsite Power, D11 Fails to Start and D13 Lockouts
~
~~
HPCl Aux Oil Pump Auto Start Failure and Turbine Trip Following Manual Start NRC Scenario #2 - 2008 Limerick Operating Test Page 1 of 28
Scenario Summary and Administration Instructions SCENARIO
SUMMARY
Control Rod 38-47 will drift out. The crew will respond IAW ON-104, Control Rod Problems, Section 2.2 and will fully insert the drifting rod. Reactor engineering will direct insertion of Control Rod 22-1 5 to maintain symmetry. The CRS will address Tech Specs.
RPS Channel B will lose power due to the trip of Breaker # I 3 on 120VAC Distribution Panel 1BY160. A half-scram and a half-NSSSS isolation will occur. The following valves will close 0
0 Loop B DW Chill Waterlsolations RRP Seal Cooling Valves HV13-I 08 &HV13-I 1 1 Division I I and IV CASS Valves PClG Compressor Suction Valve HV59-102 RWCU Isolation Valve HV44-1 F004 should close, however it will remain open due to failing as-is. The crew should respond per alarm response procedure. The crew will identify the failure of RWCU to isolate and will isolate RWCU by closing the other isolation valve, HV44-1 FOOI, GP-8 and GP-8.5 will be utilized to clear the isolation signals and restore instrument gas and drywell cooling. The CRS will determine affected TS LCOs (isolation actuation instrumentation, and PClV TS 3.6.3). Power will be restored when electricians replace the power supply breaker at 1 BY1 60 Distribution Panel. Following power restoration, systems (RWCU, RRP Seal Cooling) will be restored to normal.
RRP B # I seal will fail. The crew will respond IAW ARC-MCR-112-A1, identify the problem, determine the leak rate and refer to Leakage TS 3.4.3.2. After 5 minutes, the #2 seal will fail, resulting in approximately 60 gpm leakrate and increasing DW pressure and temperature (OT101 for high drywell pressure). The crew will commence a GP-4 shutdown and, if necessary, scram the reactor before reaching 1.68 psig in the drywell. The RRP should be stopped and isolated IAW S43.2.A, Shutdown of a Recirculation Pump. The RRP Suction Valve will fail as-is partially stroked closed. Drywell pressure and temperature will continue to increase. The crew will scram the reactor per OT-101, High Drywell Pressure. The leak gets larger after reactor shutdown.
Crew will enter T-101 on low RPV level. They will subsequently re-enter T-I 01 and enter T-I 02 on high drywell pressure at > 1.68 psig.
A loss of offsite power (E-I 020) occurs following RClC start and water level control. It results in a lockout on D13 Bus and a failure of auto start on D11 Diesel Generator. The BOP will start D11 Diesel and repower the bus. RClC and CRD can be started for injection. Division 2 RHR and Core Spray will be available on Diesel Generators. The crew will initiate suppression pool spray for pressure and temperature control. The leak will increase beyond RClC and CRD capacity. HPCl will fail to auto start and the turbine will trip shortly following manual startup. It cannot be recovered. A rapid depressurization will be required on PSP curve to inject with low pressure ECCS systems.
The scenario will be terminated when the reactor is depressurized and level is restored to between + I 2 5 and +54 inches and actions of T-102 have been performed to address containment control.
NRC Scenario #2 - 2008 Limerick Operating Test Page 2 of 28
~-
Scenario Summary and Administration Instructions INITIAL SIMULATOR SETUP ITEM I MALFUNCTION I REMOTE FUNCTION I CONDITION Reset simulator to Scenario IC or IC-44 and perform the following:
90% Power
'A' Drywell Chiller 00s Apply Information Tags on the following components:
'A' Drywell Chiller B Take out of FREEZE and ensure the following:
Reactor Power is 90%
"1 B" Drywell Chiller is running.
With the exception of "IA" Drywell Chiller, all other equipment is OPERABLE.
H Ensure the following malfunctions are loaded:
MRDOIGI, active 1 minute after trigger 1 is activated.
MRP027B, active after trigger 2 is activated.
MRR433B, active after trigger 3 is activated.
MRR434B, active 2 minutes after trigger 3 is activated.
MMS067 ramped to 40% over 2 minutes, active 2 minutes after trigger 3 is activated.
MED261, active after trigger 6 is activated.
MED263C, active after trigger 6 is activated.
MRR440A at 2%, active 15 minutes after trigger 7 is activated HP449, active after trigger 8 is activated.
MRDO16A for 38-47, active after trigger 9 is activated.
MCUl95B, active immediately.
MFW2516, active immediately.
MHP447A, active immediately.
MDG420A, active immediately.
H Ensure the following overrides are loaded:
HS43-FO236, RRP Pump '8' Suction Valve HS in PTS, active 10 seconds after trigger 5 is activated.
H Ensure the following triggers are built:
Trigger 5 on RRP 'B' Suction Valve HS to CLOSE (ZDIBl(3867))
Trigger 7 on Mode Switch to SHUTDOWN (ZRPSI SDN)
NRC Scenario #2 - 2008 Limerick Operating Test Page 3 of 28
~~
Scenario Summary and Administration Instructions ITEM / MALFUNCTION / REMOTE FUNCTION / CONDITION Feedwater SU Lsvsl Control Valve Ltyffi 138 ;ails [
HPCl Aux 011 Pump Fails lo Auto Slat Conliol Rod Failure Rod Drill Out Uncondilional Loss 01 Normd Power lo RPS Channel E Reciic Pump 18 Seal No 1 Faikrre Recirc Pump 18 Seal No 2 Felure Sleam Leak M DiyweU10 5000 gpm)
Loss of Oilrile Powei DasslGsnDll F&loAIXoSlail BusFaulton4KVSalaguardBusD13 Rscuculatm Loop A Ruplure HPfl lurhne Trip Conliol Rod Failure Dill In 38 47 38 47
- lased 1,"e T,"e Tlue 1 iue Tiue Tlue 40 True 1,"s T IW 2
True T l W 00 00 Do wwoo 00 00 00 00 00 00 00 00 00 00 00 00 00 02 00 00 00 00 00 DO 00 00 00 uo 00 15 00 WDDW 00 00 00 00 00 00 www 00 00 00 00 00 00 00 00 00 00 02 00 00 02 00 00 w 00 OD00 00 00 00 00 00 moo w OODO 00 0000 00 oo 00 00 00 DO 00 00 00 DO 00 00 30 on 00 00 w 00 00 0000 00 110 DO 00 00 00 00 00 00 00 00 00 w
DODO 00 00 00 0
0 1
2 3
3 3
6 0
6 7
8 9
I 1 Fiirilion,' T aiyrl I
CLOSE HS43 F0230 HV43 1F023B Reciic P u m ~
B Suction Valve OPEN OFF Do0010 000000 5
Reset any annunciators that should not be present INSTRUCTIONS FOR SIMULATOR OPERATOR EVENT 1: Control Rod 38-47 Drifts Out II J
I MALFUNCTION / REMOTE FUNCTION / REPORT Activate trigger 1.
Respond to request for assistance as appropriate.
When asked to close the 01 and 02 valves for CR 38-47, wait 2 minutes, then
- 1) remove MRDOIGI
- 2) activate trigger 9
- 3) report as EO that valves are closed 1
~
~-
When RE called for Rod 38-47 and Thermal Limit Guidance, wait 5 minutes and then call as RE to inform SRO that CR 22-15 should be fully inserted to maintain core symmetry.
NRC Scenario #2 - 2008 Limerick Operating Test Page 4 of 28
Scenario Summary and Administration I ns t ruct ions J
MALFUNCTION I; REMOTE FUNCTION / REPORT Activate trigger 2.
Respond to request for assistance as appropriate.
IC reports inadvertently bumped breaker. Breaker #13, 1BY160 is open but not damaged and should be fully functional.
EVENT 4: RRP 1B # I Seal Failure, Followed By #2 Seal Failure, RRP Suction Valve Fails AS-IS MALFUNCTION I REMOTE FUNCTION I REPORT 7
J Activate trigger 3.
Respond to request for assistance as appropriate.
EVENT 6:
Loss of Offsite Power, D11 Fails to Start and D13 Lockouts I1 J
I MALFUNCTION / REMOTE FUNCTION I REPORT Activate trigger 6.
When requested to perform SE-10 Floor Actions, load SE-10 actions with Time Delays.
Respond to request for assistance as appropriate.
II I
AFTER HPCl is running, activate trigger 8 to trip HPCl turbine.
ll When asked, load Remote Scenario SE-10 Floor Actions With Time Delay.
Respond to request for assistance as appropriate.
NRC Scenario #2 - 2008 Limerick Operating Test Page 5 of 28
Scenario Summary and Administration Instructions CRITICAL TASKS
- 1. ON-104.2 Standard :
- 2. T-102.2 Standard :
- 3. T-112.2 Standard:
Drifting control rod is fully inserted.
After it is determined that a control rod has drifted out from its original positiol-1, a continuous insert signal is applied until the control rod is at or beyond position.
Perform emergency blowdown per T-I 12.
When Suppression Pool Pressure cannot be maintained below the Pressure Suppression Pressure (PC/P-3) curve and before Drywell pressure exceeds 55 psig, open 5 SRVs.
Restore RPV level above -1 61 inches.
When Reactor pressure permits, inject with all available low pressure ECCS, to restore RPV level above -161.
NRC Scenario #2 - 2008 Limerick Operating Test Page 6 of 28
Scenario Summary and Administration Instructions Position RO RO SRO SRO Applicant's Actions or Behavior Acknowledge ROD DHIFT alarm. Informs SRO.
Refers to ARC-MCR-108-F4, ROD DRIFT:
Refer to ON-I 04, Control Rod Problems, OT-I 04, Unexpected/Unexplained Positive or Negative Reactivity Insertion, AND to Tech Spec 3.1.3.6 pertaining to control rod drive coupling for actions/limitations due to rod drift.
Enters OT-I 04.
2.0 IMMEDIATE OPERATOR ACTIONS 2.1 REDUCE Rx power in accordance with GP-5 Appendix 2, Planned Rx Maneuvering Without Shutdown, Section 3.1, Reducing Rx Power AND Reactor Maneuvering Shutdown Instructions, to maintain Rx power at OR below initial pre-transient level.
[SRO orders insertion of control rod.]
3.0 FOLLOW-UP ACTIONS NOTES Conditional IF... THEN steps that are not applicable AND steps to be skipped per direction of the IF... THEN step shall be marked N/A AND initialed.
3.1 IF all four Oscillation Power Range Monitor (OPRM) channels are inoperable due to common mode failure per TS Table 3.3.1.
1 ACTION 1 O.a, THEN PERFORM the following. Otherwise, MARK this step N/A.
[SRO marks this step MA]
NRC Scenario #2 - 2008 Limerick Operating Test Page 7 of 28
Scenario Summary and Administration Instructions Position SRO SRO RO SRO SRO Applicant's Actions or Behavior 1
NOTES Conditional IF... THEN steps that are not applicable AND steps to be skipped per direction of the IF... THEN step shall be marked N/A AND linitialed.
-- J 3.2 DETERMINE correct PowerlFlow Map for given plant conditions.
ATTACHMENT 2 (All Feedwater Heaters In Service)
ATTACHMENT 3 (Any Feedwater Heater Out Of Service)
[SRO chooses Attachment 21 3.3 DETERMINE Core Flow.
3.4 VERIFY plant is operating in an authorized region of Power/Flow M m.
CAUTION Restarting a Recirc Pump is not an acceptable means of raising flow.
3.5 3.6 3.7 3.8
[Steps are N/A]
IF RESTRICTED REGION... is entered...
IF operating in SLO...
IF MSL Monitor High alarm annunciates...
3.9 fSRO selects "Control Rod Position7 DETERMINE cause of positive OR negative reactivity insertion:
NRC Scenario #2 - 2008 Limerick Operating Test Page 8 of 28
Scenario Summary and Adm i n is t rat ion I nst ruct ions Posit ion SRO Op-Test No 2 Scenario No 2
Event No Event Description Control Rod 38-47 Drifts Out SRO SRO RO Applicants Actions or Behavior 3.12 3.12.1 PERFORM the following for an indication of positive reactivity insertion:
DEMAND a Control Rod Position Report AND REVIEW data for unexpected change in control rod position(s).
- 1. IF reactivity insertion was caused by control rod problems, THEN ENTER ON-104, Control Rod Problems AND EXECUTE concurrently.
3.12.9 DEMAND a P-I edit AND DETERMINE whether a Thermal Limit violation exists.
3.12.10 IF any Thermal Limit violations exist...
[SRO declares ON-104 entry and demands P-1 edi, no thermal violations exist]
Enters ON-I 04, Control Rod Problems 2.2 CONTROL ROD(S) DRIFT OUT 2.2.1 NOTIFY Shift Supervision.
NRC Scenario #2 - 2008 Limerick Operating Test Page 9 of 28
~
Scenario Summary and Adm i n is trat ion I nst ruct ions Position RO SRO RO BOP SRO BOP I-Applicants Actions or Behavior 2.2.2 2.2.3
- 1.
STOP all control rod motion demands.
APPLY continuous control rod insert signal to drifting rod until fully inserted.
IF control rod drifts out after fully inserted,THEN REAPPLY continuous control rod insert signal as necessary to maintain control rod fully inserted.
CRITICAL TASK (ON-104.2) 2.2.4 2.2.5 2.2.6 IF more than one control rod drifts out...
[Step is MA]
GO TO Flowchart on Attachment 2 AND CONSULT Tech Spec 3.1.3.1.
Reactor power > RWM low power setpt? [Answers YES]
2.2.12 Control rod going in [Answers YES]
2.2.19 Maintain continuous control rod insert signal to drifting rod as necessary to maintain rod full in. Isolate affected rod from its HCU as follows:
(A)
(B)
(C)
Release insert pushbutton. If affected rod begins to drift Close affected CRDs 47-*-01 valve Close affected CRDs 47-*-02 valve out while isolated then continue at step 2.2.1 4
[Maintains continuous insert signal and directs field to close valves, then releases insert pushbutton.]
2.2.20 Demand P-1 edit.
2.2.21 Any thermal limit > 1.O [Answers NO]
2.2.22 Return to ON-104, Step 2.2.25 NRC Scenario #2 - 2008 Limerick Operating Test Page 10 of 28
~-
Scenario Summarv and Administration Instructions Position SRO RO BOP SRO Scenario No :
2 Event No.: L Event
Description:
Control Rod 38-47 Drifts Out Applicant's Actions or Behavior 2.2.25 ISOLATION/MANUAL SCRAM OF ROD DRIFTING OUT
- 1.
ISOLATE the effected CRD from its HCU as follows after CR fully inserted:
- a.
CLOSE affected CRD's 47-*-01 valve.
- b.
CLOSE affected CRD's 47-*-02 valve AND RELEASE INSERT pushbutton.
IF control rod begins to drift while isolated, THEN quickly ENSURE control rod unisolated as follows...
IF not, GO TO step 2.2.25.9.
- 9.
DECLARE control rod inoperable, AND PERFORM actions required by Tech Spec 3.1.3.1.
- 11.
CONTACT Engineering Duty Manager.
- 2.
Refers to TS. Identifies applicable LCOs as:
LCO 3.1.3.1, Action b.2 0
LCO 3.1.3.5 Action a.1 PROCEED TO THE NEXT EVENT.
NRC Scenario #2 - 2008 Limerick Operating Test Page 11 of 28
Form ES-DX Appendix D Required Operator Actions Time Op-Test No.: 1 Scenario No.:
2 ll Position Applicant's Actions or Behavior Event No.: 2 Receives guidance from Reactor Engineering. Directs RO to perform rod pattern adjustment by fully inserting Control Rod 22-1 5.
4.2.1 Inserts Control Rod 22-15.
SRO RO PROCEED TO THE NEXT EVENT.
NRC Scenario #2 - 2008 Limerick Operating Test Page 12 of 28
Form ES4Z Appendix D Required Operator Actions Position CREW SRO BOP BOP Applicant's Actions or Behavior The crew will observe multiple annunciators on 107, 108, 1 I O, 112, 064 and 114 alarm boards.
Will probably enter E-I BY160 since many indications the entire bus is lost. Crew will later determine exact cause to be Bkr #I3 on 1BY160. _-
[Per E-lBY1601:
2.3 PERFORM the following to restore RECW flow to Recirc Pump seal AND motor oil coolers, at Panel 1OC655:
BYPASS, in "BYPASS."
2.3.2 OPEN HV-013-108 AND HV-013-111, by placing HS-013-108, SUPPLY/RETURN SEALSIOILS CLRS, in "OPEN."
2.3.3 PERFORM action described in Technical Specification (TS) 3.6.3 for an inoperable isolation valve.
2.3.1 PLACE HS-013-113, SEALS/OILS CLRS OUTBD ISOL
[Per E-1 BY 1 601 :
2.4 PERFORM the following to restore Drywell Cooling at Panel 10C681:
Key Lock Switch in "BYPASS."
2.4.2 ENSURE compliance with TS Action statement 3.6.3.a.
2.4.3 OPEN the following DWCW Isolation Valves as required:
0 0
2.4.4 REFER TO S87.1.A, Startup Of Drywell Chilled Water System AND START DWCW System.
2.4.1 PLACE HS-087-115, DIW CHILL WTR INBD ISOL BYPASS, HS-087-128, Loop A Drywell Inlet and Outlet HS-087-122, Loop B Drywell Inlet and Outlet NRC Scenario #2 - 2008 Limerick Operating Test Page 13 of 28
~~~
Form ES-13-2 Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Position BOP BOP Applicant's Actions or Behavior
[Per E - I BY1601:
2.5 2.5.1 2.5.2 2.5.3 2.5.4 2.5.5 PERFORM the following to restore PClG at Panel 1 OC601, I SO LATlO N :
PLACE HS-059-1298, "Instrument Gas Supply" (DRYWELL Bj, in "CLOSE."
PLACE HS-059-102, "Instrument Gas Suction (OUTBOARD),
in "CLOSE."
PLACE HSS-057-191 B, "Containment Isolation Bypass" (B), iri "BY PASS."
PLACE HS-059-129B, "Instrument Gas Supply" (DRYWELL Bj, in "AUTO."
PLACE HS-059-102, "Instrument Gas Suction" (OUTBOARD),
in "AUTO."
2.5.6 ENSURE compliance with TS Action Statement 3.6.3.a.
3.2 IF RWCU System required, THEN REFER TO S44.O.A, Operating RWCU To Meet Plant Conditions AND PLACE RWCU System back in service.
NRC Scenario #2 - 2008 Limerick Operating Test Page 14 of 28
Form ES-I>-2 Appendix D Required Operator Actions
~~
Op-Test No.: J-Scenario No.. 2 Event No.: 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Position SRO RO BOP SRO BOP SRO Applicants Actions or Behavior PER ARC-MCR-112-F4, RWCU SYSTEM ISOLATED
- 1. Verify RWCU system isolation.
[RO/BOP will determine required isolation did NOT occur and will manually close HV44-IF001 per E-IBYIGO.]
- 2. IF isolation IS unexpected, verify no SLC pump is operating.
- 3. IF SBLC is running THEN enter OT-I 04. [MA]
a flowpath to the reactor (HV-44-1 F042) exists to relieve CRD system pressure. [N/A]
- 5. Refer to S44.0.A AND GP-8 for isolation signals. [Refers fo GP-81
- 6. IF performing Rx Heat up/Cooldown ST re-evaluate temp data collection. [N/A]
- 7. Notify Chemistry to perform ST-5-041-810-1 as necessary to ensure Tech Spec compliance.
[Notifies chemsitry.]
~
~ ~- ~~-
~
PER ARC-MCR-114-G2(3), 1A (B) DRYWELL INSTR GAS TROUBLE :
- 1. Check adequate pressure (>96 psi) from IA(6) lnst Gas Compressor using PI-59-123A(B).
[RO/BOP will defermine PClG Compressor Suction Valve HV59-102 has closed.]
- 2. Dispatch Operator to check local control panel 1A(B)C217 to determine cause of compressor trip AND dryer overload.
- 3. IF low receiver pressure, THEN place HSS-059-11 lA(B) to ON to increase pressure OR locatelisolate leakage. [N/A]
- 4. IF compressor capacity is in doubt, THEN perform RT-6-059-310-1.
I N/A1 Could enters GP-8 and GP-8.5 to address inadvertent isolations if initially determines fault was not the loss of 1 BY160 and does not enter E-I BY160.
NRC Scenario #2 - 2008 Limerick Operating Test Page 15 of 28
Appendix D Required Operator Actions Form E S - D l Op-Test No.: 1 Scenario No.:
2 Event No.: 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Position SRO SRO SRO Applicant's Actions or Behavior GP-8, Primary And Secondary Containment Isolation Verification And Reset 3.1 WHEN an isolation signal is received, THEN ENSURE associated automatic equipment operation is verified as appropriate OR not appropriate.
3.2 3.2.1 Automatic Actuations by Isolation Signal IF the isolation signal is known, THEN USE GP-8.1 to identify the following:
- 1.
Equipment that automatically isolates
- 2.
Instrument channels
- 3.
Appropriate reset
- 4.
Applicable bypass 3.5 Isolation Bypass 3.5.1 WHEN Isolation Bypass is required, THEN REFER TO GP-8.4 for outlines of bypass procedures as identified in GP-8.1 AND GP-8.4 can be used to determine valves affected by each bypass.
NRC Scenario #2 - 2008 Limerick Operating Test Page 16 of 28
Appendix D Required Operator Actions Form ES-T)-2
~~~
~-
~
Op-Test No.: 2 Scenario No.:
2 Event No.. 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Posit ion SRO SRO SRO Applicants Actions or Behavior 3.6 3.6.1 Isolation Bypass of Crucial Systems WHEN Isolation Bypass of crucial systems is required THEN REFER TO GP-8.5 for outline of bypass procedure for systerr s crucial to plant operation.
NOTE GP-8.5 includes the following systems AND components:
0 Instrument Gas Drywell Chilled Water 0
Reactor Enclosure Cooling Water 0
0 H2/02 AnalyzersAND Post-LOCA Recombiners Bypass Barrier Block and Vent Valves 3.7 IF only the isolation group is known, THEN REFER TO for a mechanism to determine the cause of isolation AND how to reset.
SP-8.5, Isolation Bypass of Crucial Systems 3.0 PROCEDURE VOTE:
IF one OR more of the following conditions are met THEN bypassing of containment isolation interlocks may be performed;
- 1.
- 2.
- 3.
as directed by TRIP procedures To protect the health and safety of the public per 1 OCFR50.54(x).,
Per OM-L-3.2 AND OM-L-3.3, in the event of an emergency not covered by approved procedures, actions shall be taken to minimize personnel injury AND damage to the facility, and to protect the health and safety of the public.
IF an inadvertent isolation signal exists, THEN in accordance with Tech. Spec. 3.6.3 action statement, the automatic valve isolation capability is inoperable.
[Determines bypassing may be performed,]
- 4.
NRC Scenario #2 - 2008 Limerick Operating Test Page 17 of 28
Form ES-11 Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
2 Event No.: 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Position
~
~
~~~
Applicants Actions or Behavior 3.1 Instrument Gas Bypass (Group VllA - IsoI. Signals C, H, S) 3.2.1 Once bypass logic is completed, valve handswitches used to make up logic may be repositioned.
3.2.1 IF an Inboard Isolation has occurred...
[No inboard isolation]
3.1.3 IF an Outboard Isolation has occurred THEN perform the next step to bypass the isolation signals for HV-59-102 PClG Compressor Suction (OUTBOARD)
HV-59-129B PClG B Header Supply (DRYWELL B)
- 1.
Position switches as listed:
HSS-57-191 B BYPASS HV-59-102 CLOSE HV-59-1298 CLOSE
[Positions switches]
The following valves have also had their isolation signals bypassed:
0 HV-57-105 S/P Exhaust to REECE Filter (SUPP POOL EXH BYPASS (INBD))
e HV-57-111 DNV Exhaust to REECE Filter
- 2.
NRC Scenario #2 - 2008 Limerick Operating Test Page 18 of 28
Form ES-D-2 Appendix D Required Operator Actions
~
~
Op-Test No: 2 Scenario No.: 2 Event No.: 3 Event
Description:
RPS Channel B Breaker Trip, RWCU Fails to Isolate Time Position SRO BOP Crew SRO I
Applicant's Actions or Behavior 3.2 3.2.1 3.2.2 3.2.3 Drywell Chilled Water Bypass (Group VlllA - Isol. Signals C, H)
IF DWCW Head Tank HI/LO Alarm (PMS Point G532) is "NORMAL" OR DWCW Pump suction pressure is greater than 35 psig as read on PI-087-109A(B) (local PI at pumps)
THEN perform the following:
Otherwise do not bypass the isolation..
IF an Inboard Isolation has occurred THEN perform the next step to bypass the isolation signals for:
0 HV-87-128 A DMI Chilled Water Supply (LOOP A) 0 HV-87-129 A DMI Chilled Water Return (LOOP A) 0 HV-87-122 B DMI Chilled Water Supply (LOOP 8) 0 HV-87-123 B DIW Chilled Water Return (LOOP B)
[No inboard isolation]
- 1.
Position HS-87-115 in BYPASS.
- 2.
IF an Outboard Isolation has occurred THEN perform the next step to bypass the isolation signals for:
0 HV-87-120A A DMI Chilled Water Supply (LOOP A) 0 HV-87-121A A DMI Chilled Water Return (LOOP A) 0 HV-87-1208 B DMI Chilled Water Supply (LOOP B) 0 HV-87-121 B B D/W Chilled Water Return (LOOP B)
No other valves have had their isolation signals bypassed.
- 1.
Position HS-87-116 in BYPASS.
- 2.
[Positions switch]
No other valves have had their isolation signals bypassed.
Contacts maintenance to troubleshoot.
Refers to TS LCOs for isolation actuation instrumentation and PClVs for RECW, IG, RWCU and CW (3.6.3).
END OF EVENT 3. PROCEED TO THE NEXT EVENT.
NRC Scenario #2 - 2008 Limerick Operating Test Page 19 of 28
Form ES-P-2 Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
2 Event No.: 4 Event
Description:
RRP 1 B # I Seal Failure, Followed By #2 Seal Failure, RRP Suction Valve Fails As-Is Time Position SRO BOP RO SRO RO BOP SRO Applicant's Actions or Behavior Refers to ARC-MCR-112-A1, 1 B RECIRC PUMP SEAL STAGE HI/LOW FLOW:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
Check # I AND #2 seal cavity pressure.
Check both #I and #2 seal cavity temperatures.
Monitor seal pressure and temperatures on an increased frequency.
Monitor drywell pressure AND temperature.
Monitor Rx coolant leak detection instrumentation to quantify leakage.
Refer to T.S. 3.4.3.2 Rx Coolant system leakage.
Refers to ARC-MCR-112-A2, 1 B RECIRC PUMP SEAL LEAKAGE HI FLOW:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Check #I AND #2 seal cavity pressure.
Check # I and #2 seal cavity temperatures on an increased frequency AND refer to S43.0.D (Section 4.5).
Monitor seal pressure AND temperature.
Monitor drywell pressure AND temperature.
Monitor Rx coolant leak detection instrumentation to quantify leakage.
Refer to T.S. 3.4.3.2 Rx Coolant system leakage.
Check flow at FISH-43-101 B, located on El. 253, Area 16, Rm 402.
Enters OT-I 01, Hiah Drvwell Pressure NRC Scenario #2 - 2008 Limerick Operating Test Page 20 of 28
~~
~
Form ES-I13 Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
2 Event No.: 4 Event
Description:
RRP 16 # I Seal Failure, Followed By #2 Seal Failure, RRP Suction Valve Fails As-Is Time Position SRO SRO Applicants Actions or Behavior 2.0 IMMEDIATE OPERATOR ACTIONS 2.1 MAXIMIZE Drywell cooling.
TERMINATE Containment inerting. [N/A]
IF scram condition occurs, THEN ENTER T-101 AND T-102 AND EXECUTE concurrently.
3.0 3.1 3.4 3.5 FOLLOW-UP ACTIONS IF source of high Drywell pressure can not be eliminated through this procedure AND Drywell pressure is rising toward 1.68 psig, THEN PERFORM rapid plant shutdown per GP-4
[NIA].
IF a Recirc Pump seal is degraded, THEN:
MONITOR Recirc pump seal pressures and temperatures.
MONITOR D/W pressure & temperature.
MONITOR Containment leakage.
REFERENCE Tech Spec 3.4.3.2.
REVIEW EP-AA-I 008 MU Reactor Coolant System Leakage, along with the Fission Product Barrier Matrix.
IF both seals an a Recirc. Pump have failed, THEN:
3.5.1 TRIP applicable pump.
3.5.2 CLOSE pump discharge valve HV-43-*F031A(B),
DISCHARGE A(B).
3.5.3 CLOSE seal purge valve HV-46-*I 5A(B), SEAL PURGE.
3.5.4 CLOSE pump suction valve HV-43-*F023A( B),
SUCTION A( 6).
3.5.5 ENTER OT-I 12.
NRC Scenario #2 - 2008 Limerick Operating Test Page 21 of 28
Form ES-U Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
2 Event No.: 4 Event
Description:
RRP 1 B #I Seal Failure, Followed By #2 Seal Failure, RRP Suction Valve Fails As-Is Time Position SRO RO BOP SRO RO BOP Applicants Actions or Behavior
[OT-I 011 3.2 VERIFY automatic conditions [for 7.68 psig DWpressure]:
Scram HPCI Initiation Various NSSSS Isolation (PCIG, DWCW, RE HVAC, SGTS, RERS Isolation) 0 Cntmt Leak Detector
[OT-1011 3.5 THEN:
IF both seals on a Recirc. Pump have failed, 3.5.1 3.5.2 CLOSE pump discharge valve HV-43-*F 3 (B),
TRIP applicable pump. [Trips 7 8 RRP]
DISCHARGE A(B).CLOSE seal purge valve HV
- I 5A(B), SEAL PURGE. [Closes 775B seal purge]
3.5.3 CLOSE pump suction valve HV-43-*F023A(B),
SUCTlON A(B). [Closes F023B suction valve]
3.5.4 ENTER OT-I 12. [Enters OT-7721 END OF EVENT 4. PROCEED TO THE NEXT EVENT.
NRC Scenario #2 - 2008 Limerick Operating Test Page 22 of 28
Appendix D Required Operator Actions Form ES-D_I2 Position SRO SRO SRO RO BOP RO BOP SRO BOP BOP Applicant's Actions or Behavior Enters T-I 01 on "low RPV level below + I 2.5" or unknown" following manual reactor scram on GP-4 shutdown. Directs 'T' procedure activities.
Enters T-I 01 on "DW press above 1.68 psig".
Direct BOP to Unbypass DWCW, RECW and PClG Isolations when DW pressure > 1.68 Note : SRO may cancel direction based on scenario timing if/when DW temperature 145°F.
Ensure turbine trip and gen lockout (RC/Q-2).
Restore AND maintain RPV level between + I 2.5" AND +54" (RC/L-4).
Depressurize RPV within 1 OO"F/hr using ST-6-1 07-640-* bypassing PClG lsol logic per GP-8 as necessary (RC/P-16).
~
Enters T-I 02 on "DW press above 1.68 psig".
Spray Supp Pool per T-225 (PUP-5).
ENSURE HV-51-1 F004A(B), "IA(B) RHR Pump Suction PCIV,"
(SUCTION A(B)) open.
NRC Scenario #2 - 2008 Limerick Operating Test Page 23 of 28
Form ES-133 -
Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
2 Event No.: 5 Event
Description:
Coolant Leak in Drywell Time Position RO BOP BOP Applicant's Actions or Behavior Report that the 138 LVC is failed closed. Throttle RFP discharge valve (1 08's) as necessary to maintain level + I 2.5" to +54".
ENSURE the following valves closed:
0 HV-51-1FOOGA(B), "IA(B) RHR Pp SID Clg Suct Intertie Vlv" (SUCTION A@))
HV-51-1 F015A(B), "1 A( 6) Shutdown Clg injection PCIV' (OUTBOARD)
HV-51-1FOIGA(B), "IA(B) RHR Cntmt Spray Line Outboard PCIV' (OUTBOARD)
HV-51-1F017A(B), "IA(B) RHR LPCl Inj PCIV' (OUTBOARD A(B))
0 0
0 IF RHR pump not running THEN start 1A(B)P202 "RHR Pump" ENSURE the following valves open:
0 HV-51-1F047A(B), "IA(B) RHR Htx Shell Side Inlet Vlv" (INLET)
HV-51-1F003A(B), "IA(B) RHR Htx Shell Side Outlet Vlv" (OUTLET)
HV-C-51-1F048A(B), "IA(B) RHR Htx Shell Side Bypass Vlv" (HEAT EXCH BYPASS) 0 0
OPEN HV-51-1 F024A(B), "lA(B) RHR Pp Full Flow Test Return Vlv" (SUPP POOL CLG A@)) AND OBTAIN flow of 8,000 to 8,500 gpm as indicated on FI-51-1 R603A(B), FL.
(SUPP POOL SPRAY).
OPEN HV-51-1 F027A(B), "IA(E3) RHR Supp Pool Spray Line PCIV" NRC Scenario #2 - 2008 Limerick Operating Test Page 24 of 28
Form E S 4 U Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
2 Event No.: 5 Event
Description:
Coolant Leak in Drywell Time Position BOP SRO BOP Applicant's Actions or Behavior MONITOR the following:
0 PR-57-101. "Suppression Pool Pressure" (PX)
TR-57-1 I O. "Suppression Pool Air Space Temperature
(TP) AND TR-57-122, "Drywell Temperature" (TP)
FI-51-1R603A(B), "RHR System Flow" (FL) AND TI 127A(B), "RHR Htx Outlet" (TP)
PLACE RHR Service Water Pump for RHR Heat Exchanger to be used in service per S I 2.1.A, RHR Service Water System Startup.
Vlv" (HEAT EXCH BYPASS).
Flow Test line by throttling closed HV-51-1 F024A(B), "IA(B)
RHR Pp Full Flow Test Return Vlv" (SUPP POOL CLG A(B)).
CLOSE HV-C-51-1 F048A(B), "lA(B) RHR Htx Shell Side Bypass IF more spray flow is required, THEN REDUCE flow through Full Re-enter T-I 02 on "DW temp above 145°F".
When DWT is > 145"F, then, maximize DW cooling bypassing isol per GP-8 as necessary (DWfl-5).
PROCEED TO NEXT EVENT.
NRC Scenario #2 - 2008 Limerick Operating Test Page 25 of 28
Form ES-I=
Appendix D Required Operator Actions Op-Test No.: 2 Scenario No:
2 Event No:
Event
Description:
Loss of Offsite Power, D11 Fails to Start and D13 Lockouts i
Position I
Manually start D11 Diesel Generator.
[Will start after 3 minute time delay]
Applicant's Actions or Behavior Crew Recognizes loss of offsite power.
2.1 VERIFY Diesel Generators running AND Safeguard Switchgear eneraized.
BOP BOP 2.4 IF either Unit's condenser is not available, THEN CLOSE MSIV's for appropriate UNIT.
Closes MSlVs
---I--
BOP 1 Starts RClC IT-IO1, RCIL-4)
SRO WHEN safe side of Curve PCIP-3 CANNOT be maintained, THEN Enter T-I12 and execute concurrently (PUP-1 1/12).
Enters T-I 12 from T-I 02, PUP-1 2.
SRO Exit T-I 01, RC/P leg only (EB-4).
IF low press ECCS auto starts, THEN prevent injection from those Core Spray AND LPCl pumps NOT required for core cooling.
NRC Scenario #2 - 2008 Limerick Operating Test Page 26 of 28
Form E S - 0 2 -
Appendix D Required Operator Actions Op-Test No.:
Scenario No.:
2 Event No.: 6 Event
Description:
Loss of Offsite Power, D11 Fails to Start and D13 Lockouts
.- I Applicants Actions or Behavior Open all 5 ADS valves.
CRITICAL TASK (T-102.2)
Performs SE-10 actions on LOCA sianal.
Restores RPV level above -161 inches.
CRITICAL TASK (T-I 12.2)
I I
Controls LPCl injection flow to maintain level between +I 2.5 and +54 inches.
Examiner Note: Level may momentarily exceed +54 inches on the blowdown and injection, but applicant is expected to control flow to Drevent severe overfill.
TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:
0 RPV IS DEPRESSURIZED 0
LEVEL IS RESTORED TO BETWEEN + I 2 3 AND +54 INCHES 0
DRYWELL SPRAYS ARE IN SERVICE NRC Scenario #2 - 2008 Limerick Operating Test Page 27 of 28
Form ES-!>-2 Appendix D Required Operator Actions Time Position Applicants Actions or Behavior BOP Observes HPCI does not auto start on demand.
BOP Starts HPCl Aux Oil Pump Examiner Note: HPCl turbine will trip shortly after aux oil pump is started. It cannot be recovered.
BOP Observes HPCl turbine startup I
I TERMINATE THE SCENARIO WHEN ALL THE FOLLOWING ARE MET:
0 RPV IS DEPRESSURIZED 0
LEVEL IS RESTORED TO BETWEEN +12.5 AND +54 INCHES 0
DRYWELL SPRAYS ARE IN SERVICE POST-SCENARIO :
HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO.
NRC Scenario #2 - 2008 Limerick Operating Test Page 28 of 28
Form ES-DA Appendix D Scenario Outline Facility: Limerick 1 & 2 Scenario No.: 3 Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
Unit 1 at 58% power. C RFP has been running at 2300 prm for 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Unit 2 is at 100%
power.
Turnover:
1A Drywell Chiller 00s for oil replacement, expected to be returned in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Shift orders a*e to continue rod withdrawal per Sequence Step 32, Rod 54-39. GP-2 is complete through 3.5.33 Currently at Step 3.5.34. Raise power to > 6O%, place the C RFP in service per S06.1.C and then continue the startup to 75% power.
MRDOl6D 4
MED282C MAD1 49E Event Type*
R-RO C-RO TS-SRO N-BOP C-BOP TS-SRO C-BOP C-BOP C-RO M
M Event Description 1
Raise Power to 75%
Stuck Control Rod 06-23 Start C Reactor Feed Pump Loss of Div Ill DC Service Water Pump CTrtp An SRV Fails Open, Manual Reactor Scram Requires ARI Instrument Line Break in Drywell RHR Pump Suppression Pool Suction Line Rupture (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario #3 - 2008 Limerick Operating Test Page 1 of 32
Scenario Summary and Administration Instructions SCENARIO
SUMMARY
The crew has orders to raise power, start the third RFP and then continue to raise power to 75%. The RO will withdraw rods.
When power change has been observed, Control Rod 06-23 sticks. The crew will respond p w the alarm response procedures and S.73.1.A, Normal Operation Of The Reactor Manual Cortrol System. The rod will be able to move after CRD pressure is raised. The SRO will refer to Tesh Specs.
BOP will start up the C RFP IAW S06.1.C, Placing a Standby RFP in Service.
A loss of Division Ill DC will occur, impacting operability of RHR C, CS C, CR Chiller OA, DW Chiller A, CRD A and Div Ill Breakers. Crew will respond by swapping CRD pumps and CR Chillers IAW E-I FC. The CRS will address Tech Specs 3.5.1.a, 3.5.1.b, 3.8.2.1, and 3.8.3.1 (limiting 8 hr LCO).
The C Service Water Pump trips on motor overload. The BOP will start the standby service water pump per S I 0.6.A.
SRV 'N' fails open on mechanical drift of lift setpoint and then valve sticks open. The crew will respond IAW OT-I 14, Inadvertent Opening of a Relief Valve. The BOP will reduce pressure set to 900 psig to attempt SRV reseat. Actions will not reseat SRV. The crew will initiate suppression pool cooling and perform a GP-4 shutdown. Manual scram pushbuttons and mode switch will not shutdown reactor. Scram will be initiated per T-101 using ARI.
Immediately following the scram, an instrument line will break. Drywell pressure and temperature will increase. The crew will enter T-I 01 and T-102 and initiate a cooldown.
The 1 B RHR Pump suction line will rupture, resulting in pump room flooding from the suppression pool and lowering suppression pool level. The crew will stop RHR Pumps B and D and isolate the leak by closing RHR Pump 1 B Suction Valve F004B. Suppression pool spray will be initiated with the A loop of RHR per T-102.
The scenario will be terminated after the RHR suction line leak has been isolated and suppression pool sprays are in service from the other loop.
NRC Scenario #3 - 2008 Limerick Operating Test Page 2 of 32
~
~~~
~
Scenario Summary and Administration Instructions INITIAL SIMULATOR SETUP ITEM / MALFUNCTION I REMOTE FUNCTION I CONDITION Reset simulator to Scenario IC or IC-48 and perform the following:
58% Power
'A' Drywell Chiller 00s H Apply Information Tags on the following components:
'A' Drywell Chiller Take out of FREEZE and ensure the following:
Reactor Power is 58%
Ensure the following malfunctions are loaded:
MRDO16D for 06-23, active after trigger 1 is activated.
MSW488C, active after trigger 2 is activated.
MED282C, active after trigger 3 is activated.
MAD1 49E, active after trigger 4 is activated.
MMS067 ramped to 60% over 3 minutes, active after trigger 5 is activated.
MPC257 ramped to 1000 over 10 minutes, active after trigger 6 is activated.
"1 B" Drywell Chiller is running.
With the exception of "IA" Drywell Chiller, all other equipment is OPERABLE. --
Ensure the following triggers are built:
Trigger 5 on Mode Switch to Shutdown (ZRPSISDN)
Trigger 6 on (ZRHPPB(1))
I Cui,ml'/dur 1 TcnIirlVaiire 1 Rmpiimr 1 Aclime 1 O&e n r g -1 RPS Fails lo Scram Complete 1,"e 000000 000000 000000 0
T,ue 000000 000000 000000 1
Service Wale, Pump 1C Trip FaullanDCSaleguaid8us 1CD105 Relisl Valve fF013NI Fails [Fails O w
Mechant,all S l e m teak m Diywell [O 5000 gpmI teak Fionl Suppression Pool [I 100 000 gpml Reset any annunciators that should not be present Tl"e 000om 000000 000000 2
True u00000 ouu0uo 0oonuo 3
True 000000 000000 000000 4
60 000300 000000 000000 5
1 om 001000 000000 000000 6.
NRC Scenario #3 - 2008 Limerick Operating Test Page 3 of 32
Scenario Summary and Administration Instructions J
INSTRUCTIONS FOR SIMULATOR OPERATOR MALFUNCTION / REMOTE FUNCTION I REPORT J
MALFUNCTION / REMOTE FUNCTION I REPORT I
Respond to request for assistance as appropriate 1
m Respond to request for assistance as appropriate.
I J
MALFUNCTION I REMOTE FUNCTION I REPORT D Activate trigger 1.
U Remove MRDOl6D when drive water pressure is raised.
If RE contacted for multiple notch, RE will ask "did it notch past target position?". If answer is NO, then respond "no problem, rod is analyzed for a11 positions out to its target position."
Respond to request for assistance as appropriate.
- - ~
~- -
I Activate trigger 3 I1 If asked to investigate loss of Div I l l DC, wait 5 minutes and report the main bus fuse has blown. Electrical Maintenance is continuing to investigate.
Respond to request for assistance as appropriate.
ii II I
Activate trigger 2 II respond per S10.6.A (see Page 20, Applicant Actions, of this scenario guide)
If EO called to start the "IA" Service Water Pump, wait 5 minutes and then Respond to request for assistance as appropriate.
4 NRC Scenario #3 - 2008 Limerick Operating Test Page 4 of 32
Scenario Summary and Adm i n ist rat ion I nstr uct i ons J
MALFUNCTION I REMOTE FUNCTION I REPORT II I
Activate trigger 4 If requested to pull fuses for SRV IN', wait 5 minutes, then set RAD216 to OUT.
When RPV pressure reaches 600 psi, close the 'N' SRV.
Respond to request for assistance as appropriate.
1 After Mode Switch to SHUTDOWN, increase MMS067 to 300 gpm, ramped over 10 minutes.
AI Respond to request for assistance as appropriate.
II I W Respond to request for assistance as appropriate.
II ll W
If requested to verify sump pumps, report, "Yes, both sump pumps are running.
If called to investigate room flooding, wait 5 minutes, then report EO enters from 201 elevation and report 18 inches level, leak from 'B' RHR suction.
II I
When leak is isolated, if asked, report leak has stopped.
II H When HV-1 F004B, RHR Suction, is closed, delete MPC2577 m
I CRITICAL TASKS
- 1. T-101.7 Manually scram the reactor.
When any T-101 entry condition has been exceeded, the reactor is manually scrammed.
Standard:
- 2. T-103.4 Isolate systems discharging into area.
NRC Scenario #3 - 2008 Limerick Operating Test Page 5 of 32
Scenario Summary and Administration Instructions Standard:
After it is determined that Secondary Containment temperature, radiation, or water levels cannot be restored and maintained below MNO value of Table SCC-1, systems known to be discharging into the area are isolated before MSO value of Table SCC-2 is exceeded.
NRC Scenario #3 - 2008 Limerick Operating Test Page 6 of 32
Form ES-Dl3 Appendix D Required Operator Actions Position SRO RO Op-Test No 1 Scenario No 3
Event No 2 Event Description Raise Power to 75%
RO Applicant's Actions or Behavior lirects RO to commence rod withdrawal to raise power to 75%
2ommences rod withdrawal IAW S73.1.A, Normal Operation of the ieactor Manual Control System, Section 4.2 1.2.1 REVIEW Attachment 1 AND VERIFY the control rod to be withdrawn is not channel bow susceptible.
1.2.2 SELECT the control rod to be withdrawn at *O-C603, "Reactor Control Console."
1.2.3 VERIFY correct rod position is indicated on Four Rod Display.
1.2.4 ENSURE drive water pressure is 255 to 265 psid, as indicated on P D I
- R6 0 2, " Drive Water D iff e rent i a I Press u re I n d i ca t o r.
'I 1.2.5 PRESS WITHDRAW pushbutton at *O-C603.
NOTE WHEN WITHDRAW pushbutton is depressed,THEN the proper light sequence is:
- 1. INSERT light Lit AND THEN extinguishes after approximately 0.6 seconds.
- 2. WITHDRAW light Lit AND THEN extinguishes after approximately 1.5 seconds.
- 3. SETTLE light Lit AND THEN extinguishes after approximately 6.1 seconds.
1.2.6 VERIFY proper RDCS light sequence.
1.2.7 IF control rod fails to reposition, THEN GO TO Section 4.4.
1.2.8 VERIFY control rod has been withdrawn one notch position at Four Rod Display.
t.2.9 IF control rod is positioned to notch position 48, THEN PERFORM an over travel check per ST-6-107-730-*, Control Rod Coupling Check.
NRC Scenario #3 - 2008 Limerick Operating Test Page 7 of 32
Form ES-13-2 Appendix D Required Operator Actions Op-Test No.: A Scenario No.:
3 Event No.: 2 Control Rod 06-23 Op-Test No.: A Scenario No.:
3 Event No.: 2 Event
Description:
Stuck Control Rod 06-23 Time Position RO SRO SRO RO Time RO Position RO SRO SRO RO Applicants Actions or Behavior Identifies CR will not move. Informs SRO.
Directs RO to attempt to move rod IAW 53.73.1.A, Normal Operation Of The Reactor Manual Control System, Section 4.4, Failure of a Control Rod to Withdrawn (Non Channel Bow Rod)
Refers to TS 3.1.3.1 for inoDerable immovable rod.
Refers to S.73.1.A.
4.4.1 VERIFY no rod blocks exist.
4.4.2 NOTIFY Shift Supervision that control rod failed to move on a withdraw command.
NOTE The purpose of step 4.4.3 is to purge airOR crud from the control rod drive mechanism.
4.4.3 IF control rod is at notch position 00, THENDEPRESS AND HOLD the INSERT pushbutton far approximately 2 minutes OR until the insert flow stabilizes at the normal value.
4.4.4 ATTEMPT a single notch withdraw using WITHDRAW pushbutton.
NRC Scenario #3 - 2008 Limerick Operating Test Page 8 of 32
Appendix D Required Operator Actions Form ES-0-2 Position RO Applicant's Actions or Behavior 4.4.5 IF control rod fails to reposition in step 4.4.4, THEN PERFORM the following:
-1 NOTE The evaluation performed by Reactor Engineering must verify the triple notch will not violate any of the following:
0 Banked position withdraw sequence 0
Conservative approach to criticality OR the maintenance of a satisfactory reactor period
- 1. IF the control rod is capable of performing a triple notch THEN DIRECT Reactor Engineering to perform an evaluation of consequences of an inadvertent triple notch control rod withdrawal.
- 2. IF an inadvertent triple notch control rod withdrawal is permissible, OR IF control rod notch position is 46, THEN PERFORM the following:
- a. RAISE drive water pressure to 300 to 350 psid, as indicated on PDI-46-*R602, "Drive Water Differential Pressure Indicator."
- b. ATTEMPT a single notch withdraw using WITHDRAW pushbutton.
- c. IF control rod does not reposition, THEN ENTER ON-104, Control Rod Problems. Otherwise, CONTINUE.
- d. ENSURE drive water pressure is restored to 255 to 265 psid, as indicated on PDI-46-*R602.
VERIFY the control rod has moved one notch position at the Four Rod Display IF control rod is positioned to notch position 48, THEN PERFORM an over travel check per ST-6-107-730-*,
Control Rod Coupling Check.
Thermal limits.Rated core thermal power 4.4.6 4.4.7 PROCEED TO THE NEXT EVENT.
NRC Scenario #3 - 2008 Limerick Operating Test Page 9 of 32
Form ES:.
Appendix D Required Operator Actions Position SRO BOP Applicant's Actions or Behavior Directs BOP to place standby RFP I C in service IAW S06.1.C, Secticn 4.2.3, Placing Secondnhird RFP in Service [using FWLCS semi automatic sequences]
NOTE IF third RFP is being placed IN SERVICE, THEN a Reactor Operator must be stationed at panel 1 OC602, Recirc Pump Controls, in the event a Rx power reduction in accordance with OT-100, Reactor Low Level, is required.
CAUTION Operating below 25% power with more than one RFP IN SERVICE may cause severe RFP suction header piping movement.
I
- 1.
ENSURE the following:
NOTE RFPT is adequately warmed when either of the following conditions exist:
0 0
RFPT has been IN STANDBY for greater than 60 minutes AND lube oil cooler outlet temperature between 11 0 to 120 OF Following tripishutdown, RFPT has been on Turning Gear for less than two hours with steam seals applied AND lube oil cooler outlet temperature between 110 to 120 OF Oncoming RFPT has been adequately warmed.
HV-006-108A(B,C), "IA(B,C) RFP Disch Vlv" (FEED DISCH A(B,C)), is closed for oncoming RFP.
HlC-O06-~106A(B,C),
"A(B,C) RFP Min Flow Control" (FLOW), in "AUTO" for oncoming RFP.
0 0
0 NRC Scenario #3 - 2008 Limerick Operating Test Page 10 of 32
Form ES-0 Appendix D Required Operator Actions Position BOP BOP BOP BOP Applicant's Actions or Behavior
- 2.
IF third RFP is being placed IN SERVICE, THEN PERFORM the following:
- a.
REFER TO current P-I edit AND VERIFY FLLLP value is c 0.92.
- b.
ACCESS screen FWLC-01, Process Overview, at FWLCS Operator Station.
C.
SELECT blue bordered box next to "Reset" in FLLLP c 0.92 Dialog Box until it is outlined in white AND then release SELECT "Activate" (D4) Dialog Key (at bottom of screen)
AND VERIFY box next to "Reset" in FLLLP 0.92 Dialog Box turns solid blue with a white circle in center.
- d.
- 3.
PLACE FIC-MI -1 RGOIA(B,C), "A(B,C) RFPT Speed Controller" (FEED PUMP A(B, C), S), in "AUTO" for oncoming RFP.
- 4.
ENSURE LIC-006-138 "A FEEDWTR STARTUP LVL" (START UP BYPASS) in "AUTO".
NOTE Steps 4.2.3.5 through 4.2.3.8 initiate "Start A(B,C) RFP" sequence from FWLCS Operator Station.
I
- 5.
ACCESS screen FWLC-07, Automatic Sequences, at FWLCS Operator Station.
NRC Scenario #3 - 2008 Limerick Operating Test Page 11 of 32
Form E S
m 3
Appendix D Required Operator Actions Position BOP BOP BOP BOP Applicant's Actions or Behavior NOTE
- 1. Prerequisite conditions for "Start A(B,C) RFP" sequence are located in the uppermost text box of ATTACHMENT 1 (2,3).
- 2. All prerequisite conditions must be met for "READY" box to be solid green. SSV notification is required if prerequisite conditions can not be met.
- 6.
ENSURE "READY" box to left of "Start A(B,C) RFP" sequence is solid green.
- 7.
SELECT blue bordered box next to "Start A(B,C) RFP" sequence until it is outlined in white AND then release.
41
- 8.
SELECT "Start" (D4) Dialog Key (at bottom of screen).
- 9.
VERIFY the following on screen FWLC-07, Automatic Sequences, at FWLCS Operator Station:
0 Box next to "Start A(B,C) RFP" sequence turns solid blue.
Step Number AND Title appears next to blue box of "Start A(B.C) RFP" seauence.
F NOTE
- 1. Placing a RFP IN SERVICE may initiate a minor Rx power change due to rise in core inlet subcooling caused by lack of initial FW heating. (Ref. 5.10)
- 2. Indicated RFP flow rate less than 0.6 x I O 6 lbmlhr is considered to be instrument noise AND is ignored by PMS in the calculation of CTP. Actual RFP flow to RPV must be maintained greater than 0.6 x IO6 Ibm/hr to ensure a valid CTP calculation.
- 3. Placing a Standby RFP IN SERVICE will result in individual RFP flows that are unmatched. Subsequent steps in this procedure section to equalize flow will match individual RFP flows and may result in minimum flow valve automatic position changes.
NRC Scenario #3 - 2008 Limerick Operating Test Page 12 of 32
Form ES.D Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
3 Event No.: 3 Event
Description:
Start C Reactor Feed Pump Time Posit ion BOP BOP BOP BOP BOP BOP Applicant's Actions or Behavior
- 10.
VERIFY the following automatic actions:
- a.
HV-006-108A(B,C), "IA (B,C) RFP Disch Vlv" (DISCH A (B,C)), for oncoming RFP opens.
- b.
Oncoming RFPT speed rises until oncoming RFP discharge pressure is nominal 10 psig below RPV pressure.
WHEN oncoming RFP discharge pressure nominal 10 psig below RPV pressure, THEN oncoming RFPT speed slowly rises until oncoming
- c.
- 11.
VERIFY oncoming AND running RFP(s) are maintaining RPV
- 12.
ENSURE oncoming AND running RFP flows are within 0.5 Mlb/hr of each other using the Flow Equalizer in accordance with S06.0.E U/1, Feedwater Level Control And Reactor Feed Pump Control Svstem Maniwlation.
- 13.
IF Flow Equalizer was activated in Step 4.2.3.12, THEN DEACTIVATE Flow Equalizer in accordance with S06.0.E U/1, Feedwater Level Control And Reactor Feed Pump Control S ys tem Ma n i pula t ion.
- 14.
WHEN oncoming RFP flow is greater than 0.6 x IO6 Ibm/hr as indicated on FI-006-1 R604A(B,C), "A(B,C) RFP Discharge" (FEED, A(B,C), FL), THEN ENSURE PMS Computer Point KO00 (k001, k002)indicates oncoming RFP flow is greater than 0.6 x I O 6 Ibm/hr.
- 15.
IF PMS Computer Point KOOONSS (KOOINSS, K002NSS) was supplied a substitute value in accordance with RT-6-038-800-1, Critical Sensor Point Substitution, when oncoming RFP was shutdown, THEN RESTORE PMS Computer Point KOOONSS (KO01 NSS, K002NSS) in accordance with RT-6-038-800-1, Critical Sensor Point Substitution for oncoming RFP.
NRC Scenario #3 - 2008 Limerick Operating Test Page 13 of 32
Form ESD-2 Appendix D Required Operator Actions Time Position BOP BOP BOP BOP Applicants Actions or Behavior
- 16.
IF low pressure (LP) FW heating is in service AND 6th FW Htr is to be placed in service, THEN PLACE 6th FW Htr in service in accordance with S02.1.A, Placing Of Feedwater Heaters In Service (Steam Side).
- 17.
ENSURE LIC-006-138 is in AUTO.
- 18.
IF Rx power is greater than 35%,
THEN REFER TO S06.8.H, Startup, Shutdown, And Operation Of The Hydrogen Water Chemistry System, for guidance in aligning Hydrogen Water Chemistry System.
- 19.
PLACE Seal Injection System for oncoming RFP in AUTOMATIC in accordance with S06.7.A, Reactor Feed Pump Seal Injection System Operating Modes.
NRC Scenario #3 - 2008 Limerick Operating Test Page 14 of 32
Form ES-Q Appendix D Required Operator Actions Position Crew SRO BOP BOP Applicant's Actions or Behavior Acknowledge numerous Div Ill DC related alarms. Identify loss of CHD pump, DW Chiller A, and CR Chiller OA. Identify cause as loss of Di!,
Ill DC.
Enters E-I FC, Loss Of Division Ill Safeguard 125 VDC Bus I FC.
CAUTION
- 1. HV-87-1 02A, "IA Drywell Chilled Water Discharge Valve," fails closed on loss of 1 OY201.
- 2. IF I A K I 11, "IA Drywell Chiller," (CHILLER A) OR OAK1 12, "Cont. End. Chiller" (CHILLER A) is running,THEN they will not trip AND tripping locally may be required to prevent damage from occurring.
IF required, THEN locally TRIP I A K I 11, "IA Drywell Chiller" (CHILLER A) by manually tripping D13 BUS-08 Bkr.
IF required, THEN locally TRIP OAK1 12, "Cont. Encl. Chiller" (CHILLER A) by manually tripping D13 BUS-I 0 Bkr.
IF required, THEN START 1 BKI 11, "1 B Drywell Chiller," (CHILLER B) in accordance with S87.1.A, Startup Of Drywell Chilled Water System.
ENSURE OBKI 12, "Cont. Encl. Chiller" (CHILLER B) AND Controt Enclosure HVAC System Loop B Fans are running.
[SRO may or may not order trip of OAK1 12 based on his interpretation of step 2.2. If OBKl12 is started and OAK1 12 is left running then OBK112 will cycle on and off due to insufficient heat load ]
I 2.5 Manually INITIATE Main Control Room Chlorine Isolation in accordance with S78.8.A, Manual Initiations Of Control Room Radition Or ChlorinelToxic Chemical Isolation.
NRC Scenario #3 - 2008 Limerick Operating Test Page 15 of 32
Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2 Scenario No.:
3 Event No.: 4 Event
Description:
Loss of Div Ill DC Time Position SRO BOP Applicant's Actions or Behavior 2.6 REFER TO GP-8, Primary and Secondary Containment Isolation Verification and Reset (Green Reset AND RESET MSlV Isolation Loaic, as reauired.
FOLLOW UP ACTIONS REFER TO LGS Emergency Plan Annex, Table 3-1.
NOTE
- 1.
The following can not be startedOR tripped from MCR:
0 OA MCR Chiller 0
1A D/W Chiller IACRD ICRHR 0
I C Core Spray Pp DIV 3 ADS (Aux Equip Room and MCR panel 10C626) can noi be activated.
Loss of BUS 1 FC results in a loss of instrument panel 10Y201.
- 2.
- 3.
NOTIFY appropriate personnel to troubleshoot problem prior to restoring power as required.
NOTE Loss of 10Y201 trips AAND C Aux BoilersAND 1A RWCU Pump due to loss of control power.
CHECK 1CD103, "Division Ill Safeguard 125V DC Battery Charger," for proper operation in accordance with S95.9.A, Routine Inspection Of Station Batteries And Chargers."
NOTE A North StackAND 1A South Stack Rad Monitors are disabled due to loss of 1 OY201.
REFER TO RMMS for loss of a North Stack AND 1A South Stack Rad Monitors.
NRC Scenario #3 - 2008 Limerick Operating Test Page 16 of 32
Form ES.D-2 Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
3 Event No.: 4 Event
Description:
Loss of Div Ill DC Time Posit ion SRO SRO i-Applicant's Actions or Behavior USE Load Analysis to identify affected BUS 1 FC AND 10Y201 REFER TO Unit 1 Tech. Spec. 3.8.2, DC Source, AND determine REFER TO Unit 2 Tech. Spec. 3.8.3, Onsite Power Distribution Loads AND TAKE appropriate LCO actions as follows:
appropriate act ions.
Systems, AND determine appropriate action.
IF Unit 1 RWCU system is out of service due to 1A RWCU Pump trip, THEN REFER TO Unit 1 Tech Spec 3.4.4 AND NOTIFY Chemistry for alternate reactor coolant conductivity sampling.
I CLEAR all faults AND Trips in memory of TIS-25-1 01 C, "NUMAC Leak Detection Monitor."
~~
Refer to Tech Specs. Identifies following affected LCOs:
0 3.3.3.c ADS (7 days) 3.5.l.a 3.3.2 Table 3.3.2-1 Item 5 0
3.5.1.b 3.8.3.1 Action b Will identify 3.8.3.1 as the limiting 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> LCO.
~
~~
~~
~~
~
PROCEED TO THE NEXT EVENT.
NRC Scenario #3 - 2008 Limerick Operating Test Page 17 of 32
Form EST=
Appendix D Required Operator Actions Applicant's Actions or Behavior Acknowledge and respond to alarms. Identify Service Water Pump 1 B trimed.
ARC-MCR-118-E1, I B SERVICE WATER PUMP BREAKER TRIP:
- 1. Dispatch Operator to 122 Plant Services Switchgear to investigate breaker trip condition AND reset relay targets on breaker.
May enter S I 0.7.A, Abnormal Service System Operation, Section 4.2, System Flow Reduction to Support One Pump Operation but expected to evaluate stability of plant and await results of attempt to start standby pump before entering S I 0.7.A.
Directs BOP to start the standby SW pump IAW S10.6.A, Swapping Operating Service Water Pumps.
[Per S I 0.7. A] :
4.2.1 MONITOR both running SW pump dP via local indication.
[Field reports 93 psid pump differential]
4.2.2 SELECT loads marked (x) for the appropriate Circ Water Temp from ATTACHMENT 1 initially, unless otherwise directed by SSVN, to achieve the expected required system flow reduction OR until nominally 117 -1 19 psid is achieved on each pump.
[CW temp 82"F, uses middle column on Att I]
4.2.3 CHECK with SSV AND ADJUST additional loads as required to maintain Unit.
[SRO is expected to concur on adjusting cooling to loads as selected on Att. 71
to valve out spare RECW Heat Exchanger.
NRC Scenario #3 - 2008 Limerick Operating Test Page 18 of 32
Appendix D Required Operator Actions Form E S - X Applicant's Actions or Behavior Op-Test No: 1 Scenario No:
3 Event No.: 5 Event Description. Service Water Pump C 'Trip BOP BOP Op-Test No: 1 Scenario No:
3 Event No.: 5 Event Description. Service Water Pump C 'Trip BOP BOP
- 3. THROTTLE 10-*077A(B), "RECW Htx SW Inlet," for in-service RECW heat exchanger AND MONITOR RECW heat exchanger outlet temp to ensure temperature does not exceed 100°F.
NOTE
- 1. TECW Train unavailability limits can be obtained from TECW System Manager.
- 2. Actions making systems unavailable should be entered into ops Logs.
- 4. IF TECW train unavailability limits will not be exceeded, THEN CLOSE 10-*033A(B), "TECW Htx SW Outlet Valve," to valve out spare TECW Heat Exchanger Otherwise, MARK this step N/A.
[ TECW System Manager reports unavailability limits WILL be exceeded. SRO marks the step N/A.]
NRC Scenario #3 - 2008 Limerick Operating Test Page 19 of 32
Form E S : Z Appendix D Required Operator Actions
~
Op-Test No.: 1 Scenario No.:
3 Event No.: 5 Event
Description:
Service Water Pump C Trip Time Position SRO BOP BOP RO Applicant's Actions or Behavior
[Per S 1 0.7. A] :
- 6. SECURE Fuel Pool SW Booster pumps per S10.8.A, Fuel Pool Service Water Booster Pump Startup, Normal Operation, And Shutdown, AND MONITOR fuel pool temperature to ensure temperature does not exceed 135°F.
[Per S I 0.8.AJ:
4.6.1 4.6.2 4.6.3 4.6.4 4.6.5 0
0 4.6.6 IF the pump being shutdown is desired to windmill, THEN IO-*I 45A( B,C), "Fuel Pool SW Booster PP Discharge,"
will remain open.
Otherwise, CLOSE 10-*145A(B,C), "Fuel Pool SW Booster PP Discharge," for the desired pump.
STOP *A(B,C)P212, "Fuel Pool SW Booster Pump" (PUMP).
ENSURE 10-*137A(B,C), "Fuel Pool Heat Exchanger SW Outlet Valve," open for each heat exchanger to be placed in service.
CLOSE 10-*137A(B,C), "Fuel Pool SW Heat Exchanger Outlet Valve," for the heat exchanger to be removed from service.
THROTTLE 10-*I 36A(B,C), "Fuel Pool Heat Exchanger SW Inlet Valve," to maintain the following:
FPCC Heat Exchanger inlet temperature from 70 EF to 125 EF using TE-53-*10 "Fuel Pool Htx Inlet" on XI-36-*01(2) at panel
- OC614.
Pump delta pressure between 21 to 30 psid.
IF required, THEN REPEAT this section to secure remaining Fuel Pool SW Booster DumDs.
[Per S I 0.7.A]:
- 7. CLOSE TV-C-O10-*51 B(A), "Drywell Chiller Service Water Supply,"
OR 10-*I 10A(B), "SW Inlet to Drywell Chiller Valve," to secure flow to the non-operating Drywell Chiller.
- 8. PERFORM the following on operating chiller:
- a.
THROTTLE TV-C-O10-*51A(B), "Drywell Chiller Service Water Supply," OR IO-*I 1 OA( B), "SW Inlet to Drywell Chi I ler. 'I MAINTAIN condenser Dressure below 180 mi.
- b.
NRC Scenario #3 - 2008 Limerick Operating Test Page 20 of 32
Appendix D Required Operator Actions Form E S - E Position BOP Applicants Actions or Behavior
~
- 9. SECURE condenser area AND condensate pump room unit coolers as required (100 gpm per unit cooler) AND MONITOR temperatures.
I O. THROTTLE IO-*022, Recombiner After Cond SW Inlet, AND MAINTAIN offgas outlet temperature below 200°F on BOP DAS Monitor XR-036-*01(2) point TE-IO-*I 5.
Op-Test No.: 1 Scenario No.
3 Event No 5 Event
Description:
Service Water Pump C Trip BOP PROCEED TO THE NEXT EVENT.
[Per S10.6.Al:
4.3 PERFORM the following checks at idle *A(B,C)P502, Service Water Pump, to be started:
[Communicates with EO]
4.4 CLOSE idle 10-*040A(B,C), SW Pump Discharge.
4.5 PERFORM the following sequence to open idle 10-*045A(B,C),
SW Pump Discharge Check Valve:
[Coordinates with 0 to vent pump locally]
CAUTION
- 1.
IF SW Pump discharge valve is not opened within three minutes after pump start,THEN pump overheating resulting in pump case distortion may occur.
IF SW pump discharge valve is not fully opened (Le. is left throttled), THEN damage to valve may occur.
- 2.
4.6 START idle *A(B,C)P502, SW Pump (PUMP), at *OC655.
4.6 Fully OPEN 10-*040A( B,C), SW Pump Discharge.
[Field operator opens discharge valve]
4.7 CLOSE 10-*310 (*309, *308), after discharge check valve opens.
4.8 VERIFY motor current for started pump less than 300 amps. -
NRC Scenario #3 - 2008 Limerick Operating Test Page 21 of 32
Form E S U Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
3 Event No.: 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI Time Position CREW SRO BOP RO SRO BOP RO SRO SRO BOP Applicant's Actions or Behavior Respond to alarms.
ARC-MCR-1 10-B1, SRV / HEAD VENT VALVE LEAKING:
- 2. IF an SRV is leaking, THEN refer to OT-I 14, Inadvertent Opening of a Relief Valve.
- 3. IF head vent line caused alarm, THEN verify head vent valve:
HV-41-1 Fool, 2 are closed.
- 4. Refer to RT-6-041-490-1, Attachment 2: SRV Leakage Determination, Monitoring Process.
ARC-MCR-I 10-62, SAFETY RELIEF VALVE OPEN:
- 2. IF the SRV opening was inadvertent, THEN refer to OT-I 14, Inadvertent Opening of a Relief Valve.
- 3. Check for loss of power to 1AY185 ckt 2.
Enters OT-I 14, Inadvertent Opening of a Relief Valve.
2.0 IMMEDIATE OPERATOR ACTIONS 2.1 PLACE both loops of Suppression Pool cooling in service.
NRC Scenario #3 - 2008 Limerick Operating Test Page 22 0' 32
Form ESrD-2 Appendix D Required Operator Actions CAUTION
- 1. IF (*A) HV-51-*F068A(B) is allowed to go full open during one pump per loop operationTHEN runout of RHRSW Pump may occur.
- 2. Starting a pump more than twice in one hour may damage DumD motor.
Op-Test No.: 1 Scenario No.:
3 Event No.: 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI Time Position SRO BOP 4.2.1 START OA(B,C,D)V543, Spray Pond Room Fan as follows:
- 1.
IF 'A' Loop pump (OA(C)-P506) is to be placed in service, THEN ENSURE OA-V543 OR OC-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681.
IF 'B' Loop pump (OB(D)-P506) is to be placed in service, THEN ENSURE OB-V543 OR OD-V543, Spray Pond Pump Room Fans, in "RUN" at OOC681.
- 2.
4.2.2 START OA(B,C,D)P506, PUMP.
4.2.3 IF not directed by SE-10 to operate RHRSW, THEN THROTTLE HV-51 -*F068A(B) to the maximum obtainable position without exceeding 11,000 gpm on FI-51-*R602A(B) while maintaining pump disch pressure (PI-I 2-001A-1 (B))
between 75 psig to 85 psig.
4.1.12 Verify [amps < 92, disch press > 75 but < 120 psig.]
4.2.1 3 Notify chemistry NRC Scenario #3 - 2008 Limerick Operating Test Page 23 of 32
Appendix D Required Operator Actions Form E S - M Op-Test No.: 1 Scenario No.: 3 Event No.:
Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI Time Position BOP Applicant's Actions or Behavior
[Per S51.8.AI ENSURE HV-51 -*F006A( B), "Shutdown Cooling Suction" ENSURE HV-51 -*F006A( B), "Shutdown Cooling Suction" ENSURE alignment of the following valves as indicated:
(SUCTION), closed.
(SUCTION), closed HV-51 -*F047A( 6)
"RHR Heat Exchanger Shell Side HV-51 -*F003A( B)
"RHR Heat Exchanger Shell Side HV-51 -*F004A( B)
"Suppression Pool Inlet"(lNLET) - OPEN Outlet"(0UTLET) - OPEN Suction"(SUCTI0N) - OPEN DISPATCH Equipment Operator to inspect breaker for Trips OR Flags prior to pump start unless a plant transient requires a start of pump.
[Mark step as N/A]
START *A(B)P202, RHR Pump (PUMP).
OPEN HV-51-*F024A(B), "RHR Pump Full Flow Test Return" (SUPP POOL CLG), AND PERFORM the following:
NOTE
- 1. Flow rate is throttled to less than 8500 gpm to prevent condensate transfer from entering Suppression Pool.
- 2. Throttling flow rates to less than 8000 gpm may induce cavitation OR damage to HV-51-*F024A(B).
- 1.
- 2.
MAINTAIN flow indicated on FI-51 -*R603A(B), "RHR Loop Flow," between 8000 to 8500 gpm.
IF greater than 8500 gpm required to maximize cooling, THEN MINIMIZE amount of time to reduce amount of water added to Suppression Pool.
CLOSE HV-C-51 -*F048A(B), HEAT EXCH BYPASS.
NRC Scenario #3 - 2008 Limerick Operating Test Page 24 of 32
Form ES.D-2 _-
Appendix D Required Operator Actions Op-Test NO.: A Scenario No.:
3 Event No.:
Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI Time Position BOP SRO BOP RO Applicant's Actions or Behavior MONITOR Suppression Pool temperature on SPOTMOS OR TE-51-*04A(B,C,D) "RHR Pump A(B,C,D) Suction" on XI-36-*01(2) at panel *OC614 AND PERFORM the following:
- 1.
MAINTAIN temperature below 90°F.
- 2.
IF Suppression Pool temperature is below 65"F, THEN CONSIDER securing system.
- 3.
IF RHRSW inlet temperature is above 56" F, AND Suppression pool temperature is lowered to within 3" F of RHRSW inlet temperature, THEN SECURE suppression pool cooling.
IF Suppression Pool temperature cannot be maintained below 9O"F, THEN PLACE another RHR loop in service to provide additional cooling as directed by SSVN.
- 4.
[Per OT-1141:
2.2 IF Suppression Pool temperature reaches 110 O F, THEN immediately PERFORM a rapid plant shutdown per GP-4 (Rapid Plant Shutdown to Hot Shutdown) AND PERFORM the following:
2.2.1 PLACE Mode Switch in "SHUTDOWN" AND ENTER T-1 00 OR T-101, as applicable AND T-102 AND EXECUTE concurrently.
3.0 3.1 0
0 0
0 0
0 FOLLOW-UP ACTIONS CONFIRM SRV is stuck open by observing:
Generator load reduction OR bypass valve closure.
RELIEF VALVE OPEN (*10-B-2) alarm.
Relief valve position lights.
Steam flowiFeed flow mismatch.
Rising Suppression Pool temperature.
Rising tailpipe temperature on XI-036-*01, "Primary Monitor BOP DAS" OR Xl-036-"02, "Backup Monitor BOP DAS" under the SRV mimic on *OC614.
SRV/HEAD VENT VALVE LEAKING (*10-B-1) OR SAFETY NRC Scenario #3 - 2008 Limerick Operating Test Page 25 of 32
Form ES-D Appendix D Required Operator Actions Position BOP Op-Test No.: 1 Scenario No.:
3 Event No.: 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI SRO SRO Applicant's Actions or Behavior REDUCE turbine inlet pressure to 900 psig.
3.2 3.2.1 3.2.2 DEPRESS the PRESSURE SETPOINT SELECTOR DECREASE pushbutton at panel *OC653.
MONITOR PI-01-*03 MN STM for 900 psig.
-I 3.3 IF Suppression Pool temperature is greater than or equal to 95"F, THEN PERFORM ST-6-060-390-*, "Suppression Pool Temperature Check" per Tech Spec. 4.6.2.1.
IF SRV remains open after turbine inlet pressure reaches 900 psig, THEN PERFORM rapid plant shutdown per GP-4, Rapid Plant Shutdown to Hot Shutdown.
3.5 NOTE During rapid power reductions, a Main Steam Line Rad Monitor Hi alarm may annunciate due to elevated hydrogen concentrations.
(CM-1) 3.6 IF Main Steam Line Rad Monitor Hi alarm annunciates, THEN ENTER T-103 AND ON-I02 AND EXECUTE concurrently.
(CM-1)
NRC Scenario #3 - 2008 Limerick Operating Test Page 26 of 32
Form ES-DI)
Appendix D Required Operator Actions Position SRO BOP Op-Test No: 1 Scenario No: 3 EventNo. 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI SRO Applicants Actions or Behavior NOTE IF SRV will not close during shutdown,THEN condensate injection must be controlled prior to reactor pressure decreasing below condensate discharge pressure to avoid flooding the vessel. This could result in SRV downcomer damage due to two-phase discharge 3.7 IF SRV will not close, THEN PERFORM the following during shutdown:
TRANSFER steam users to aux. steam as soon as possible.
MINIMIZE unnecessary reactor feed pump operation.
ENSURE condensate injection is controlled prior to depressurizing below condensate discharge pressure (nominal 600 psig) by closing the following valves as necessary:
0 HV-O6-*08A(B,C), RFP Discharge (DISCH).
0 HV-O6-*38A, *A RFP Dis Shutoff Vlv Bypass.
CONSIDER MSlV closure prior to exceeding cool down rate.
ATTEMPT SRV closure by pulling fuses for the appropriate SRV using Attachment 1 for Unit 1, AND Attachment 2 for Unit 2.
3.8 Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of discharge of steam to the Suppression Chamber from any relief valve, PERFORM ST-6-060-760-* to cycle each downcomer vacuum breaker through at least one complete cycle of full travel.
NRC Scenario #3 - 2008 Limerick Operating Test Page 27 of 32
Form ES-D Appendix D Required Operator Actions Op-Test No.: 2 Scenario No.:
3 Event No.: 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI Time Position SRO BOP RO BOP I-Applicant's Actions or Behavior
[Enters GP-41 3.1 PER S91.6.B IF transferring 1 l(12) AUX BUS to the lO(20) S/U BUS, THEN PERFORM the following:
TRANSFER house loads to startup buses in accordance with S91.6.B, Transferring House Loads To S/U Buses.
- 1.
- 2.
NOTE:
- 3.
- 4.
NOTE:
- 5.
- 6.
- 7.
- 8.
PLACE 225-1 01 02(06)/SS, "Sync Switch," to "ON."
VERIFY INCOMING AND RUNNING voltmeter read approximately 1 1 OV.
10 Startup Bus Voltage may be adjusted per S35.0.J, No. 10 Transformer Tap Changer Control (Remote) AND 20 Startup Bus Voltage may be adjusted per S35.O.H, #20 Regulating Transformer Tap Change Control (Remote-Hand).
IF INCOMlNGlRUNNlNG voltages differ by greater than 8 volts, THEN ADJUST Startup Bus Voltage to obtain less than 8 volts difference.
FEED.
CLOSE AND HOLD 252-10102(06)/CS, l o l l 1(20/12)
With the Offsite Source Breaker closed and its handswitch in the "Normal After Close" position, the Aux Feed Breaker will auto-open.
WHEN 252-1 01 02(06)/CS, 10/11(20/12) FEED, indicates closed, THEN RELEASE 252-1 01 02/CS.
VERIFY 252-1 01 13(213)/CS, AUX FEED, open.
PLACE 225-1 01 02(06)/SS, "Sync Switch," to "OFF."
ENSURE 252-1 01 13(213)/CS, AUX FEED, in "NORMAL AFTER TRIP."
~
~-
[GP-41 3.2 REDUCE Rx Recirculation System flow to minimum.
NRC Scenario #3 - 2008 Limerick Operating Test Page 28 of 32
Form ES-D-2 Appendix D Required Operator Actions Op-Test No.:
Scenario No.:
3 Event No.: 6 Event
Description:
An SRV Fails Open, Manual Reactor Scram Requires ARI 1
CT I RO I Applicant's Actions or Behavior 3.2.1 WHEN core flow reduces to nominal 6O%, THEN immediately manually SCRAM Rx AND ENTER T-1 00, Scrarn/Scram Recovery OR T-101, RPV Control, as applicable.
3.3 ENSURE Reactor Mode Switch is locked in "SHUTDOWN" within one hour following Rx scram AND key is in possession or Shift Supervision (SSV).
Enters T-101, RPV Control, on "SCRAM condition with power above 4% or unknown". Directs 'T' procedure activities.
Manually initiate RRCS AND ensure ARI initiation.
CRITICAL TASK (T-101.7)
Ensure turbine trip AND gen lockout. Continue at step RC/Q-12 (RC/Q-4).
Exits RC/Q lea.
Restore AND maintain RPV level between +12.5" AND +54" (RC/L-4).
PROCEED TO THE NEXT EVENT.
NRC Scenario #3 - 2008 Limerick Operating Test Page 29 of 32
Appendix D Required Operator Actions Form ES-pil Time Position Applicants Actions or Behavior SRO Enters T-102 on DW press above 1 68 psig SRO Enters OT-101, High Drywell Pressure (PCIP-1).
Align an RHR loop for drywell sprays, BOP RO BOP NRC Scenario #3 - 2008 Limerick Operating Test Maximize DW cooling bypassing isol per GP-8 a s necessary (DWiT-5).
Page 30 of 32
Form ES-D Appendix D Required Operator Actions Op-Test No.: 1 Scenario No.:
3 Event No.: 7 Event
Description:
Instrument Line Break in Drywell Time Position BOP Applicants Actions or Behavior
[OT-I01 Actions]:
3.1 1 3.11.1 3.11.2 3.1 1.3 3.1 1.4 IF high Drywell pressure persists, THEN ISOLATE the following:
ENSURE the following Main Steam Line sample valves closed:
HV-41-*F084, DRAIN SAMPLE INBOARD HV-41-jF085, DRAIN SAMPLE OUTBOARD ENSURE the following Recirc. sample valves closed:
HV-43-*F019, INBOARD HV-43-*F020, OUTBOARD STOP RWCU System AND ENSURE the following valves closed:
HV-C-44-*F033 using HC-44-*R606, FL HV-44-*F001, INBOARD HV-44-*F004, OUTBOARD HV-44-*F100, BOTTOM HEAD DRAIN HV-44-*F105, INLET FLOW ENSURE Main Steam Line drains closed:
HV-41 -*F016, STEAM DRAINS INBOARD HV-41 -*FO19, STEAM DRAINS OUTBOARD 3.1 I
.5 WHEN time permits, THEN PERFORM S44.2.A.
PROCEED TO THE NEXT EVENT.
NRC Scenario #3 - 2008 Limerick Operating Test Page 31 of 32
Form E S - E -
Appendix D Required Operator Actions Time Op-Test NO.:
Scenario No.:
3 Event No.: 8 Event
Description:
RHR Pump Suppression Pool Suction Line Rupture Position Applicant's Actions or Behavior CT Enter T-103, Secondary Containment Control, on "Room flooding alarm condition for areas in Table SCC-1".
Report back as EO after dispatched, to inform Control Room of location of visually observed flooding.
Isolate all systems discharging into area per T-250 unless required to suppress fire OR required to be operated by the TRIP procedure Stops RHR Pump 6.
Closes RHR Pump B Suction Valves F0048.
(SCCIL-4).
CRITICAL TASK (T-'103.4)
Enters SE-4 on reports of flooding. Directs T-290.
Spray Supp Pool per T-225 (PCIP-5).
Aligns RHR Loop A for suppression pool spray.
POST-SCENARIO :
HAVE THE APPLICANT IN THE CRS POSITION IDENTIFY THE HIGHEST EAL CLASSIFICATION FOR THE COMBINATION OF EVENTS EXPERIENCED DURING THE SCENARIO.
NRC Scenario #3 - 2008 Limerick Operating Test Page 32 of 32