ML042190116
| ML042190116 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/17/2004 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Bradley Jones Duke Energy Corp |
| References | |
| 50-269/04-301, 50-270/04-301, 50-287/04-301 | |
| Download: ML042190116 (41) | |
See also: IR 05000269/2004301
Text
Final Submittal
QCQNEE JUNE 2004 EXAM
50-26912004-301,
50-270/2004-301, &
50-287/2004-301
-
JUNE 14 18 & 25,2004
1. IS ES-
-. . ~ ~ ~ ~ ~~ ~.. .~~~~~. ..... .... ... -~
Appendix B Scenario Outline .... Form ES-5-1
.....
...... __._ ......
Facility: Oconee Scenario No.: 1 fnl Bp-Test No.: 1
Examiners: Operators:
Initial Conditions:
45% Reactor Power (Snap 201)
Turnover:
Startup in progress after adding oil to 1B1 RCP
0 1A Main FDW pump operating
SASS in MANUAL for I&E troubleshooting
1E! MDEFCIW Pump 00s
After turnover. the crew should start 1B1 RCP
Event
Description
SASS in manual
1B MDEFDW Pump QOS
OC I Pre-Insert
MP129Q I Block All Turbine Trips Except Manual
.- ... ._-
"A" RBCU fails to receive ES signal
..-. ...
Start 1B1 RCP
AC Oil Lift pump will not develop adequate
discharge pressure
1A HPI pump sheared shaft, (TS)
3a Override Standby HPI Pump fails to start / Restore Letdown
4 I MP105Q I I, OATC. SRO RC Loop B Flow fails LOW
MPl08Q
5 I Override I CALL BWST rupture (TS)
6 I MPS11Q I R, QATC, SRO Manual unit shutdown due to BWST level
1A Main FDW ~ u m trips u
Main Turbine Fails to thp (Lockout EHC Pumps)
8 I MPS400 I MALL RCS leak to SBLOCA (ramp over 10 minutes)
"IC" HPI pump trips requiring rapid RCS CID due
to dearaded HPI
(N)ormal, (R)eactivity, (I)nstrument, (1 Iomponent, (M)ajor
NUREG-1021, Draft Revision 9 Page 1 of 16
~.~~~~~ -~.~.. ..~~~. . . .... ._
.-
.Appendix
.... - D .. ~
..... Operator Actions .. ...
Form
.- ES-B-2
Qp-TeSt NO.: - Scenario No.: 1 Event No.: 1 Page 1 of 1
Event Description: Start 1E1 RCB: (N, BOP)
___.
Time Position Applicant's Actions or Behavior
-
Crew response:
BOP The BOP should use the in progress procedure OP/1/N1103/006 (RCP
Operation) Enclosure 4.1 (RCP Start) to start the 1E1 RCP.
Open ILPSW-9&10 (181 RC PUMP MTR CLR IN & OUT) and verify
both valves open by using the OAC indications.
Review Limit and Precautions
Note:
No more than two RCP(s) may be operated when RCS is 250 O F .
Either AC or DC Oil Lift Pump may be used
e A 6 Qil Lift Pump may take > 2 minutes to develop adequate discharge
pressure
AC and DC Oil Lift Pumps will automatically trip after 3 minutes
e Oil Lift PUMPmay NOT start unless switch has been placed to "QFF"
after last start .. .... .... .....
e Announce "Starting 1B l RCP" via plant page.
e Start AC Oil Lift Pump on 1E1 RCP.
When the 1E1 RCP AC Oil Lift Pump has been started this event is
completed.
NUREG-1021, Draft Revision 9 Page 2 of 16
Op-Test No.: ~
Scenario No.: 1 Event No.: 2 Page 1 of 1
Event Descristion: 1B1 RCP AC Oil Lift pump will not develop adequate discharge
pressure: (C, BOP)
Time Position Applicant's Actions or Behavior
P
BOP Note: The AC Oil Lift Pump will not develop adequate discharge
press to clear the Low Press indication prior to tripping OH. The
operator will have to determine that the AC Oil Lift Pumped tripped
and start the DC Oil Lift Pump.
Monitor the status of AC Oil Lift Pump low discharge pressure on the
OAC and when it clears, start 1B l RCP. (will not clear)
IF AC Oil Lift Pump automatically trips after 3 minutes, start DC Oil Lift
Pump.
Monitor the status of QC Oil Lift Pump low discharge pressure on the
OAC and when it clears, start 1E31 RCP.
After RCP is at full speed, ensure Oil Lift Pump stopped.
Position any Oil Lift Pump switch(s) that were operated to "OFF.
Use the OAC to monitor RCP parameters for proper operation.
SI30 Contact SPOC to investigate and repair 1B1 RCP A 6 Oil Lift pump.
This event is complete when the 1B1 RCP is started or when directed
by the lead examiner.
NUREG-1021, Draft Revision 9 Page 3 of 16
Op-Test No.: - Scenario No.: 1 b!eRt NO.: 3 Page 1 of 2
Event Description, A HPI Pump sheared shaft and the standby HPI pump fails to
auto start: (C, BOP) (TS)
Time
- Position
Plant response:
Applicants Actions or Behavior
I
Statalarms:
ISA-2/B-2 (HP RCP Seal Injection Flow High/Low)
ISA-2/C-2 (HP Injection Pump Disch. Header Pressure
High/Low)
Board indications:
RC Makeup Flow = 0 gpm
1A HPI Pump = 0 amps
PZR level will begin to decrease and LDST level will begin to
increase.
Crew response:
1. Refer to ARG for above Statalarms
2. SRO shouid refer to AP1014 (Loss of Normal Makeup and(or
0 Verify no HPI pump operating
BOP 0 Close 1HP-5 (Letdown Isolation)
Place IHP-120 (RC Volume Control) in HAND and closed
0 Place IHP-31 (RCP Seal Flow Control) in HAND and closed
Start standby HPI pump ( l e HPI pump)
Slowiy open 1HP-31 in small increments until = 8 gpm/RCP is
achieved.
Re-establish normal makeup through 1HP-120.
Reduce IHP-7 demand to 0%.
Close IHP-6
Ensure the following open:
4 IHP-1
4 IHP-2
4 IHP-3
4 IHP-4
NUREG-1021, Draft Revision 9 Page 4 of 16
Bp-Test No.: - Scenario No.: 1 Event No.: 3 Page 2 of 2
Event Description: A HBI Bump sheared shaft and the standby HPI pump fails to
auto start: (C, BOP)
-Time
- Position Applicants Actions or Behavior
Open IHP-5
Throttle open 1HP-7 for = 20 gpm letdown flow.
Open IHP-6
Adjust 1HP-7 for desired letdown flow.
Place 1HP-31 in auto.
sa0 3. Refer to Tech Spec 3.5.2High Pressure Injection
Condition A
Required Action: Restore HPI pump to OPERABLE status
Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
Note: Due to sequence of events, SRO may not review the TS
during the scenario. Follow-up questions may be required to
ensure knowledge of this competency.
Event is complete when normal makeup and letdown is
established or when directed bv the lead examiner.
NUREG-1021, Draft Revision 9 Page 5 of 16
._
Ip-Test NO.: - Scenario No.: 1 Event Ne.: 4 Page 1 of 1
fvent Description: RC Loop B Flow fails LOW: (I, OhTC)
n___
Time Position Applicants Actions or Behavior
s_
Plant response:
1. Statalarms:
0 1SA-2/A-4, RC LOOPB Flow LOW
1SA-2A-5, RC Total Flow Low
ISA-VA-1~RP Channel A Trip
ISA-1/A-3, RP Channel A Flux/lmb/Flow Trip
2. Control board indications:
RCS Flow meter shows Loop B flow at zero.
RPS Channel A trips
B S/G FDW Flow instrument shows a reduction in FDW, and the A
S/G FDW Flow indicates increasing flow or off-sale High.
e DELTA Tc meter indicates a large Delta Temp.
Crew response:
e The crew should stabilize the unit by using the Plant Transient
BATC Response process.
Take the Diamond and BOTH FDW Masters to MANUAL and stabilize
the unit.
The SRQ should refer to AP/28, ICs Instrument Failures and notify
SPOC to have the instrument repaired.
AQ/28, ICS Instrument Failures (Case 4E RCS Flow Failure) will:
k Ensure DIAMOND and BOTH FDW Masters in MANUAL.
P Notify SPOC to select a valid RCS flow input to ICS and
investigate and repair the failed RCS flow instrumentation.
P Ensure any associated requirements of PT/1/N0600/001
(Periodic Instrument Surveillance) are met for the failed
instrument.
k WHEN notified by SFQC that a valid RCS flow input has been
restored to ICs, THEN GO TO Encl 5.1 (Placing ICs in AUTQ).
Note: Crew may refer to PT/600/001 (Periodic Instrument
Surveillance) and TS 3.3.1 (RPS Instrumentation) due to h RPS
Channel trip and may choose to place ARPS to manual Bypass.
Event is complete when the SRQ has reached the WHEN step in
hP/28 or when directed by the Lead Examiner.
NUREG-1021, Draft Revision 9 Page 6 of 16
3p-Test NO.: - Scenario No.: I Event No.: 5 Page 1 of 1
Event Description: Borated Water Storage Tank (BWST) rupture: (6, ALL) (TS)
Position Applicants Actions or Behavior
Plant response:
Statalarms:
1%-3iD-8, BWST level HighiLow
Control board indications:
BWST level decreases to = 40 feet.
Simulator operator cue: After the BWST low level alarm actuates and
NE0 will call the Control Room via the Emergency line and
communicate to the control room that the Hi-Dye crane has struck
the Unit 1 BWST with its mast and has penetrated the tank. Water is
pouring out of the break.
Crew response:
1. Refer to ARG for ISA-3/D-8, BWST level HighiLow
SRO 2. Refer to TS 3.5.4 (BWST)
Determine TS 3.5.4 Condition B met. Restore BWST to Operable
Status in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
If this time cannot be met TS 3.5.4 Conditions C will apply. Be is
Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3. Determine a unit shut down is required.
4. Initiate a unit shutdown in accordance with OPil/a/l102/004
(Qperation At Power).
Note: The unit shutdown will be performed in manual due to the
previous failure of RCS flow.
Event is complete when a unit shutdown is directed by the SRO or
when directed by the Lead Examiner.
NUREG-1021, Draft Revision 9 Page 7 of 16
Op-Test NO.: - Scenario No.: 1 Event No.: 6 Page 4 of I
Event Description: Manual unit shutdown due to BWST level: (R, OATC)
Time Position Applicant's Actions or Behavior
Crew response:
SRO Direct unit shutdown per O Q / I / N I102/004 (Operation At Power) Encl. 3.2,
Power Reduction or AP/29, Rapid Unit Shutdown.
OP/1/N1102/004 (Operation At Power) End. 3.2, Power Reduction
OATC
1. Review Limits and Precautions
2. Notify OSM to contact NRC if required.
3. Refer to OP/1106/001 (Turbine Generator) to ensure operating limits
are NOT exceeded during shutdown.
4. Notify System Operations Center (SOC) or leaad reduction.
5. Reduce reactor power in manual by inserting control rods with the
Diamond, controlling FDW flow with the FDW Masters, and controlling
turbine header pressure with the Turbine Master.
AP129, Rapid Unit Shutdown
1. Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown).
2. Notify WCC Sa0 to initiate Encl 5 2 (WCC SRO Support During Rapid
Unit Shutdown).
3. Announce AP entry using the PA system.
4. Verify ICs in AUTO. (It's in MANUAL)
OATC 5. Initiate manual power reduction to desired power level.
6. 60 TO Step 4.7.
7. Verify both Main FDWPs operating. (Only 1A MFDWP operating) GO
TO Step 4.1 2.
8. Verify Rx shutdown is required.
9. Close 1HP-16.
10. Position 1HP-14 to BLEED.
12. Close 1HP-7.
Event is complete when reactor power has been reduced 5% or when
directed by the Lead Examiner.
.
NUREG-1021, DraR Revision 9 Page 8 of 16
Op-Test No.: - Scenario No.: 1 Event No.: 7 Page 1 of 1
Event Description: 1A Main FDW pump trip:
Main Turbine Fails to trip (Lockout HC Pumps) (C, OATC)
Position Applicant's Actions or Behavior
Plant response:
la Main FDW pump trips resulting in a reactor trip.
e The Main Turbine should trip but does not. This will result in a
reduction of steam pressure in both SGs until actions are taken to
trip the turbine. The will result in RCS overcooling until the turbine is
tripped.
Crew response:
SRO 1. SRO will enter the EOP.
OATC 2. OATC will perform Immediate Manual Actions
o Depress REACTOR TRIP pushbutton
Verify reactor power 5% FP and decreasing
0 Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed
Note: The OATC should diagnose that the turbine did not trip and
then perform the RNO step which will stop and lock out both EHC
pumps. This will cause the turbine to trip. (CT-18)
Verify RCP seal injection available.
3. BOP will perform a symptom check and Rule 3 (Loss of Main or
Event is complete when EHC pumps have been tripped or when
directed b y the lead examiner.
NUREG-1022, Draft Revision 9 Page 9 of 16
3p-Test No.: - Scenario No.: 1 Event No.: 8 Page 1 of 4
-Time Position
Plant response:
Applicant's Actions or Behavior
1. Statalarms:
1SA-9/A-6, RB Reactor Bldg Norm Sump Level High/Low
ISA-8/B-9, Process Radiation Monitor High
2. Control board indications:
RBNS level increases
PZR level will decrease very slowly due to the leak and IHP-5
being closed.
Note: If crew refers to API2 (Excessive RCS Leakage) go to page 15
for more information.
Crew response:
SRO The SRO will refer to EOQ Subsequent Actions
1. Verify all control rods fully inserted.
2. Verify Main FBW in operation.
3. Verify Main FDW controlling properly.
4. Verify TBVs controlling SG pressure = 1010 psig.
6. Dispatch an operator with Encl 5.29 (MSRV Locations) to verify all
MSRVs have reseated.
1, Verify ES is required. (Not required) RNO will initiate Encl 5.5(Pzr
and LBST bevel Control).
2. Use Encl. 5.5 (PZR and LBST bevel Control) to try and maintain
PZR inventory and LDST inventory.
Start standby HPI pump
- Throttle IHP-26 open
Start 1C HPI pump
Note: The RCS will eventually saturate with all HPI injecting.
NUREG-I 021, Draft Revision 9 Page 10 of 16
3p-Test No.: - Scenario No.: 1 Event No.: 8 Page 2 of 4
Position Applicants Actions or Behavior
OATC 1, When ES Channels 1 and 2 actuate, an operator should inform the SRO
that ES Channels 1 and 2 have actuated.
SRO 2. The SRO should initiate EOQ End. 5.1, ES Actuation per the parallel
actions page of Subsequent Actions section or of the LOSCM Tab.
OATC 3. When running Encl. 5.1, the operator will:
Determine which ES channels should have actuated and verify all
Blue Lights and White Lights are lighted for the appropriate
channels.
Note: A RBCU will not receive an ES signal and will rerndn in HIGH
speed. The operator should diagnose this and place the A RBCU in
LOW speed.
Place HPI in Manual.
Verify Rule 2 in progress or complete.
Qpen IBS-I and IBS-2
Determine NO RCPs operating and GO TQ Step 9.
Piace LPI pumps and 1LP-17/18 in manual control.
At St30 direction secure LPI pumps.
Ensure A and B and 3A and 38 Outside Air Booster Fans are
operating. (CT-27)
Verify 1CF-1/2 open.
Verify 1HP-410 closed.
Notify Chemistry to prepare for caustic addition.
Secure makeup to the LDST.
Close 1LPSW-I 39
Fail Open 1LPSW-251/252
Open 1LPSW-45
Dispatch an operator to perfurm Encl. 5.2 (Placing RB Hydrogen
Analyzers In Service)
Dispatch an operator to establish 1000 cfm in each PRVS filter
train.
The operator must get Sa0 approval to exit this enclosure.
NUREG-1021, Draft Revision 9 Page 11 of 16
Event Description: RCS leak to Small Break LOCA (ramp over 10 minutes): (M,ALL)
Crew response:
SRO 1. The BOP should inform the SRO that the RCS has saturated and obtain
SRO concurrence to perform Rule #2, Loss Of SCM.
BOP Verify that reactor power is < 1%.
e Trip RCPs within 2 min of LOSCM (CT-I)
Verify that HPI is performing as required.
0 Verify that LQIflow in any header is < 2000 gpm.
Verify that TBVs are available.
Disable AFlS in non-actuated channels.
0 Establish EFDW to the OTSGs to feed to LOSCM SP per Rule 7 (SG
Feed Control). (CT-10)
Verify both MBEFDWPs operating. (B IMDEFDWP is off)
Ensure TDEFDWP is in PULL TO LOCK. (Not performed due I B
MDEFDWP not operating)
0 Trip both MFQWPs and close the FDW block valves.
Maintain SG pressure RCS pressure.
NUREG-1021, Draft Revision 9 Page 12 of 16
3p-Test No.: - Scenario No.: 1 Event No.: 8 Page 4 of 4
-Time Position
Applicant's Actions or Behavior
3. The Sa0 should GO TO the LOSCM Tab per the Parallel Actions page
of the EOP Subsequent Actions section. LOSCM Tab will:
Ensure that Rule #2 is in progress or complete.
e Verify that station ASW is not feeding any SG.
Verify that the LOSCM is not caused by excessive heat transfer.
Verify transfer to LOCA CD tab not required due to no LPI flow.
Verify all the following conditions exist:
> NO RCPs are operating
>. HPI flow exists in both HPI headers
2. Adequate Total HPI flow per figure 1 (Total Required HPI Flow)
Open 1AS-40 while closing 1MS-47.
Control steaming and feed rates on all intact SGs to maintain
cooldown rate within Tech Spec limits:
>. Tc 2 280T 5 5 0 W % hour
2. Tc 280OF 5 25"FI % hour
GO TO Step 91.
Close IRC-4
Note: When directed by the Lead Examiner 1C HPI pump will trip.
NUREG-1022, Draft Revision 9 Page 13 of 16
Op-Test No.: - Scenario No.: 1 Event No.: 9 Page 1 of 1
Event Description: IC HPI pump trips requiring rapid RCS CID due to degraded HPl
Position Applicants Actions or Behavior
-
Plant response:
Crew response:
1. BOP should indicate to the SI30 that the 1C HPI pump has tripped.
2. SRO should recognize that conditions have changed and transfer Lo
the beginning of the LOSCM tab.
SRO Ensure that Rule #2 is in progress or complete.
E Verify that station ASW is not feeding any SG.
Verify that the LOSCM is NOT caused by excessive heat transfer.
Verify transfer to LOCA CB tab NOT required due to no LPI flow.
E Verify all the following conditions exist:
i NO RCPs are operating
GOTOStep 13
0 Start both MBEFDW pumps. (15 MD EFQWP NOT available)
e Establish 300 gpm to each SG
Initiate full depressurization of both SGs utilizing TBVs or AQVs
Initiate feed to all available SGs to LOSCM setpoint at maximum
allowable rate (per Table 3 (Emergency FDW Pump and Header
hdaximum Flow Limits) of Rule 7 (SG Feed Control)).
0 WHEN SCM is > OF,
OR all the following conditions exist:
2, NO RCPs operating
i. HPI flow in both HPI headers
THEN maintain SG pressure RCS pressure utilizing one of the
following:
2, TBVs
i- ADVs
Note: Will wait at this WHEN step until IAAT (6) is met on LPI flow.
vent and exam is complete when directed by the Lead Examinee.
NUREG-1021, Draft Revision 9 Page 14 of 16
Op-Test No.: - Scenario No.: 1 Event No.: 8 Page 4 of 1
Event Description: RCS leak to Small Break LQCA (ramp over 10 minutes): (M, ALL)
Supplemental information if crew refers to APE (Excessive RCS Leakage)
Time Position Applicants Actions or Behavior
Crew response:
BOP I,Refer to ARG for 1SA-9/A-6, RB Reactor Bldg Norm Sump Level
Higk/Low
SRQ 2. Refer to AP/002, Excessive RCS Leakage
3. Close 1HP-5 (Letdown Isolation)
4. Initiate End. 5.1 (Leak Rate Determination)
5. lAaT LDST level is 5 40, ensure open IHP-24 and 1HP-25 ( 1 N l B
BWST Suction)
6. Ensure OSM, STA, RP are notified
7. Monitor trend of T6 APQ2for increases (OAC)
8. Verify NO leakage through PORV and close 4RC-4
9. Identify leak is in the RB and GO TO Step 4.20
I O . Place standby CC pump switch to OFF.
11. Close l C C - I / l # P - l and 1CC-2/1#P-2
12. Verify leakage has stopped (has Rot)
13. Verify re-establishing LD is desired (it is not due size of leak)
14. Ensure RB isolation valves are closed.
I 5 Use Encl. 5.5 (PZR and LDST Level Control) to try and maintain
PZR inventory and LBST inventory.
Start standby HPI pump
Throttle 1HP-26 open
Start I C HPI pump
Note: The RCS will eventually saturate with all HPI injecting.
NUREG-I 021, Draft Revision 9 Page 15 of 16
CRITICAL TASKS
1. CT-18, Turbine Trip
2. CT-1, Trip All RCPs
3. CT-10, Establish FW Flow and Feed SGs
4. CT-27, Implementation of Control Room Habitability Guidance
NUREG-I 021, Qraft Revision 9 Page 16 of 16
..... .~.
'Appendix 6.- .~...
Scenario
.-
outline
. . ...
Foih
.... ES-D-1
Facility: Oconee Scenario No.:2 fnl Op-Test No.: f
Examiners: Operators:
Initial Conditions:
35% Reactor Power, startup in progress (Snap-202)
Turnover:
AMSAClDSS bypassed for I&E testing
NI-9 OOS, to be replaced next outage
" 1 A SG AFIS Digital Channel 1 circuit 00s
0 "A" Condensate Booster Pump OOS, breaker to be replaced
Keowee Unit 2 00s for unplanned reasons
Keowee Unit 1 aligned to underground
e Operability test of Keowee Unit 1 is to be performed per PT/620/809 (Keo ee Hydro
Operation) after turnover and before startup continues, ONS to perform remote
Keowee start
Event
No.
I Malfunction
NO.
I Event Type* I Event
DescriDtion
'W AFIS circuit disabled
od I Pre-Insert
MEL180
I I Keowee Unit 2 Emergency Lockout
I I ' I '
2 Override C, BOP, SR8 Keowee Unit 1 Gen Field Flashing Breaker fails to
OPEN autornaticallv
Seismic event (PRA)
I Unit Shutdown
(N)ormal, (R)eactivity, (I)nstrurnent, (C)omponent, (M)ajor
NUREG-2021, Draft Revision 9 Page 1 of 15
.~ ....... ~~ ~ ~ ~ ~ ~~
.~. .~ . ..
Appendix D Scenario
... Outline
-.
Form ES-D-1
._._. .~.
.-
3p-Test No.: - Scenario No.: 2 Event No.: 1 Page 1 of 1
- vent Description: Operability test Keowee Unit 4 (N, BOWSRO)
Position Applicant's Actions or Behavior
SRO Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to
operability test unit 1 Keowee underground.
Use OP//4106/019 (Keowee Hydro At Oconee) to perform an
'Automatic Startup" of Keowee Unit 1
Initial Conditions
1. Verify applicable Statalarms and breaker positions
2. Notify Keowee operator to give Oconee control of Keowee # 1 I
3. Review Limits and Precautions
Procedure
1, Place UNIT 1 LOCAL MASTER switch to "START AND hold
until Keowee Unit starts.
2. Verify the following:
GEN 1 FIELD BREAKER doses
a GEN 1 SUPPLY BREAKER closes
GEN 1 FIELD FLASHING BREAKER closes
Event is complete when operability test is in progress.
NUREG-1021, Draft Revision 9 Page 2 of 15
Op-Test No.: - Scenario No.: 2 Event No.: 2 Page 1 of 1
Event Description: Keowee Unit 1 Gen Field Flashing Breaker fails to OPEN
automatically (C, BOWSRO)
Position Applicant's Actions or Behavior
BOP 3. Ensure GEN 1 FIELD FLASHING BREAKER trips.
Candidate should diagnose that the breaker did not open
automatically and should open the breaker manually and
initiate a work request or contact SPOC.
SRO should direct the BOP to continue with the startup.
Note: GEN FIELD FLASHING BREAKER automatically trips
r; 45 seconds after receiving close signal. Failure of breaker to
trip automatically does NOT make the KHU inoperable.
Startup procedure may continue.
BOP 4. Determines KHU # I is operable when test complete
5. Verify ACB-1, Keowee 1 Generator Breaker, closed.
6. Verify Unit 1 EMER FBR ACE3 3 closed
7. Verify = 4.16 KV on CT4 Volts (2AB3)
8. Close SKI and SK2 (CT4 STBY BUS 112 FEEDER)
9. Shutdown Keowee #I.
Event is complete when operability test is complete or when
directed by the lead examiner.
NUREG-1021, Draft Kevision 9 Page 3 of 15
.~~. ... .. .~
Appendix. 5 Scenario Outline Form ES-5-1 .
..
.
.
...,.. ..,
..
Op-Test No.: - Scenario No.: 2 Event No.: 3 Page 1 of 1
Event Description: 2 HP-120 (RC Volume Control) Fails closed (C, OATCISRO)
Time
7
allow OATC diagnoses of failure.
1. Diagnose 1HP-220 (RC Volume Control) Failed closed:
RCS makeup flow goes to zero.
PZR level begins to decrease.
LDST level begins to increase.
Valve position demand for 1HP-120 begins to increase to
the 100% demand value and valve position indication will
indicate closed (green light).
SRO 2. Refer to APll4 (Lossof Normal Makeup andlor RCP Seal
Injection.
Determine Seal Injection is not lost
Determine loss of suction to HPI pumps has not occurred.
e Verify HPI pump operating.
Verify RCP seal injection flow exists.
Verify RCP RCP seal injection or HPI makeup line leak is
not indicated.
Verify IHP-120 has failed and GO TO Step 4.467.
Perform the following as necessary to maintain Pzr level >
200:
1 Close IHP-6 (Letdown Orifice Stop)
1 Throttle IHP-7 (Letdown Control)
1 Throttle IHP-26 ( I A HP Injection)
IHP-120 to HAND and dosed
3. Contact SPOC to repair 1HP-120.
Note: 2HP-I20 will remain failed for the duration of the
scenario.
When PZR level is being controEled manually or when directed
by the lead examiner this event is completed.
NUREG-1021. Draft Revision 9 Page 4 of 15
.... ~~~~~..~..
Appendix B-- Scenario
.... Outline~.~ ~~~. ... .
Form ES-D-Z
3p-Test No.: __ Scenario No.: 2 Event No.: 4 Page 1 of 1
Event Description: Controlling NI fails LOW (I, OATCISRO)
When directed by the lead examiner the controlling 611 will fail low.
-Time Position Applicant's Actions or Behavior
Plant response:
?SA-WA-12, ICs Tracking, will actuate.
Diamond will transfer to manual on NI flux < 1.5%.
0 FDW will decreese due to reactor moss limit.
RCS pressure and temperature will increase.
Crew response:
1. When the ICs TRACKING alarm is received, the candidates
OATC should utilize the "Plant Transient Response" to stabilize the
plant and recognize that the controlling NI has failed. RX will
trip on high pressure with no operator action.
2. Verify reactor power.
SRQ
3. Place the FDW Masters in manual and stabilize the plant.
Adjust ,T, using control rods and FDW and stabilize the plant
4. The SRO should direct the NCQs to check OAC and the
control board NI meters to determine the status of the NI
signals that mn be used in the ICs.
e Refer to AP/28, 16s Instrument Failures
SPOC should be contacted to repair NI-5.
Note: The ICS will remain in manual for the remainder of the
scenario.
Nhen the plant is stable or when directed by the lead
Examiner this event is completed.
NUREG-1021, Draft Revision 9 Page 5 of 15
. ...... ~~~~~~ ..... ..
Appendix
.... D . ~ ~ .
Scenario
.. .
i5utline.. .. .- ..~.Form ES-D-1-
Op-Test No.: - Scenario No.: 2 Event No.: _5_ Page 1 of 2
Event Description: Seismic event (PRA)
1A RBCU rupture (C, BOP/SRO) (TS)
___a_
- Time Position Applicant's Actions or Behavior
Cue: Call the Control Room (4911) to report a seismic event
but no plant damage.
1. ISA-9IB-9, LPSW RBCU A Cooler Rupture will actuate and RB
normal sump level will increase.
The BOP should refer to ARG for 1SA-SIB-9
Verify alarm is valid by checking RBCU 1A Inlet Flow and
RBCU 1A delta flow.
Verify ILPSW-18 (RBCU ZA Outlet) open
Verify adequate LPSW flow is available; check LPSW pump
operation
Monitor RBNS Level for any unexplained increase (Notify
Chemistry to sample RBNS for boron to determine if a
cooler rupture has occurred.
SRO Diagnose a Cooler Rupture is indicated and Isolate the I A
RBCU Cooler.
Enter appropriate TS for RBCU inoperable (TS 3.6.5
Condition 5).
Close ILPSW-16 ( I A RBCU INLET)
Perform TS 3.6.3 Condition C for closed containment
system.
Open vent or drain.
Close ILPSW-18 ( I A RBCU OUTLET)
Refer to SLC 16.9.12 (Additional LPSW and Siphon Seal
Water System Operability Requirements)
NUREG-1021, Draft Revision 9 Page 6 of 15
..... .............. ....... ..... .......
Appendix D ........
Scenario
__ Outline .......
Form ES-D-1
..
Op-Test No.: - Scenario No.: 2 Event No.: 5 Page 2 of 2
Event Description: Seismic event (PRA)
ZA RBCU rupture (C, BOPISRO) (TS)
Time Position Applicant's Actions or Behavior
The control room will receive a phone call from security that
indicates that a tremor has been felt but no damage has been
noted.
2. The SRO may refer to AFV05. Earthquake.
Dispatch operators to perform plant inspections
Note: No damage will be reported.
- Notify SPOC to develop the Strong Motion Accelerometer
tape.
SRO *Verify NO fuel handling activities in progress.
- These items may not be completed depending on how soon
the next event is started.
When the Earthquake AP has been initiated, the RBCU has
been isolated, or at the direction of the Lead Examiner this
event is completed.
NUREG-1021, Draft Revision 9 Page 7 of 15
.. ..... .~ ... ~.
~ ~
Appendix D .... ..- . .. Scenario Outline
.~~.
~.~ . ~ ~ ~ . . . .. Form ES-D-I
Op-Test NO.: - Scenario No.: 2 Event No.: A Page 1 of 2
Event Description: ?B SG Tube leak (50gpm) (C, ALL) (TS)
Position Applicant's Actions or Behavior
1B SG tube leak occurs following RBCU isolation and initiation of
AW5, Earthquake, or when directed by the lead evaluator.
Plant response:
1. The following alarms actuate:
ISA-8/54, RM PROCESS MONITOR RADIATION HIGH
lSA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
0 ISA-8/A-9, RM Area Monitor Radiation High
2. PZR level will decrease and RC makeup flow will increase.
Crew response:
ALL 1. Diagnose and take actions for a Tube leak in the 1B SG:
BQP 2. Refer to the ARG for the following alarms:
ISA-8/59, RM PROCESS MONITOR RADIATION HIGH
1SA-8/B-10, RM CSAE EXHAUST RADIATION HIGH
SRO 3. Refer to AP/1/Nl700/31 (Primary to Secondary Leakage)
BOP 4. Open and white Tag TB Sump pump breakers.
swo 5. Monitor primary parameters; PZR Level and LDST level to
determine that gross leakage exist and transfer to step 4.65.
6. Determine OTSG tube leak sine is greater than 25 gpm and will
require entering the EQP.
BOP 7. Log RIA readings (a rough log is adequate)
SRO 8. Initiate a Unit shutdown to met requirements of End. 5.1 (Unit
Shutdown Requirements).
9. Primary inventory should be monitored and when the leak rate is
determined to be > 25 gpm transfer to the SGTR tab of the EOP.
Note: The team may determine the leak is initially greater than
25 gprn and go directly to the EOP.
NUREG-1021, Draft Revision 9 Page 8 of 15
........ ........ ..... ...
-Appendix D ... . . . . scenario Outline
........ ... Form E§-D-I
Op-Test No.: Scenario No.: 2 Event No.: Page 2 of 2
Event Description: 1B SG Tube leak (50 gpm) (C, ALL) (TS)
a__.
Time Position Applicants Actions or Behavior
- ...... ....
SRO I O . EOP SGTR tab will perform the fallowing:
Determine that the Reactor is not tripped.
0 Maintain PZR level 2.220 inches using Enclosure 5.5 (Pzr
and LDST Level Control).
Estimate SGTR Leakrate. (leak is = 50 gpm)
Monitor RIA-16 (AMS Header) and 17 (B MS Header) to
identify all SGs with tube ruptures.
11. Betermine ICS is NOT in AUTO and direct the OATC to initiate a
manual power reduction to < 15%.
12. Initiate Encl. 5.19 (Control of Plant Equipment During Shutdown
for SGTR)
BOP Note: A shutdown with the ICS in manual is required.
Note: This event will remain in progress for the remainder ob the
scenario.
NUREG-1021, Drafl Revision 9 Page 9 of 15
. ~ ~ . ....~.
~ ~ ~ ...
Appendix D-- .._.-
_ Scenario Outline
~~~~~~~~. .~.... ..~
Form ES-B-1
Op-Test No.: - Scenario No.: 2 Event No.: 7 Page 1 of 1
Event Description: Unit Shutdown (R, OATC)
~
Time Position Applicant's Actions or Behavior
~
0ATCISRO The OATC will use the FDW Masters and the Diamond to reduce
power while monitoring Reactor Power, Tave, and other plant
parameters.
If the reactor trips automatically the team must return to IMAs.
BOP The BOP will utilize Enclosure 5.19 (Control of Plant Equipment
During Shutdown for SGTR).
Note: With the unit at i~ 25% power only applicable steps will be
performed.
Notify WCC SRO to make notifications
Transfer electrical auxiliaries
e Place I T A AUTOlMAN transfer switch in MAN
0 Place 1TB AUTOIMAN transfer switch in MAN
0 Close I T A S4J 6.9 KV FBR
- Close I T B SU 6.9 KV FDR
- Place MFBI AUTO/MAN transfer switches in MAN
e Place MFB2 AUTO/MAN transfer switches in MAN
Close E l r MFBI STARTUP FDR
Close E2, MFB2 STARTUP FDR
When a unit shutdown of > 5% has occurred or when directed
by the lead examiner this event is concluded.
NUREG-1021, Draft Revision 9 Page 1Qof 15
.. ~ ~ ~ ~ ~ ~ ~ ..~~...
Appendix D Scenario Outline
~~~~~ .~ ..
Form
. ..... ES-D-1~
Op-Test No.: - Scenario No.: 2 Event No.: 8 Page 1 of 3
Event Description: 1B Main Steam line break in RB (M, ALL)
1B main steam line break will occur following event 7 as directed by
the I id examiner.
Time Position Applicants Actions or Behavior
ALL Plant response:
Statalarm 1SA-OZA-9, MS Press HighlLow, actuates
A and 6main steam (MS) pressure decreases
A MS line pressure stops decreasing
e 5MS line pressure continues to decrease
RCS may saturate
Crew response:
1. The O A K will perform IMAs.
P Depress REACTOR TRIP pushbutton
SRO t. Verify reactor power 5% FP and decreasing
> Depress TURBINE TRIP pushbutton
P Verify all turbine stop valves closed
OATC i Verify RCP seal injection available
2. The OATC will verify the performance of IMAs while the BOP
performs a symptoms check.
3. The SRO will Parallel Action to transfer to the Excessive Heat
Transfer (EHT) tab and direct the Crews actions as follows:
4. If SCM = 0°F then the OATC will perform Rule #2 (Loss of SCM)
after receiving concurrence from the SRO.
OATC
e Trip ALL RCPs within 2 minutes (CT-1)
e Ensure open 1HP-24 and 1HP-25
Ensure ALL HPl pumps operating
Ensure open IHP-26 and 1HP-27
Verify required HPI flow per header
Verify TBVs available
NUREG-1021, Draft Revision 9 Page 11 of 15
.~.. ~..~
.~ .
Appendix B~.
.. ~ Scenario
~ ~ ~ .Outline
.~
. ~ . ~. . .
.
Form ES-B-'I
.~
lp-Test No.: - Scenario No.: 2 Event No.: 8 Page 2 of 3
Zvent Description: 1A Main Steam line break in RB (M, ALL)
__._
Time Position Applicant's Actions or Behavior
e Control EFDW as required to raise level to intact SGs to
proper setpoint per RULE 7 (SG Feed Control)
-
m Trip both Main FDWPs
Place FDW block valve switches (1FBW-33, 31.42,40) in
CLOSE:
m Maintain SG pressure < RCS pressure
BOP 5, If SCM = 0°F then the SRO with transfer to LBSCM tab which
will:
Ensure Rule 2 (Loss of SCM) is in progress or complete.
- Verify Station ASW feeding any SG. (it is not)
Verify LOSCM caused by excessive heat transfer (it was)
GO TO EHT tab.
6. The BOP will perform Ruie #5 (Main Steam Line Break) after
BOP receiving concurrence from the SRO.
Stop 1B MDEFDW Pump (CT-17)
Initiate AFlS 1B SG Digital Channels 1 and 2
0 Ensure both Main FDW pumps tripped
Steam I A SG to maintain CETCs constant (CT-12)
7. Endosure 5.1 (E3 Actuation) will be performed.
ES Channels 7 and 8 will not actuate on high RB pressure
and will require manual actuation.
__._
NUREG-1021, Draft Revision 3 Page 12 of I 5
..... ~~ ~ ~
~. -~
Scenario Outline Form ES-D-1
Appendix D .. ~. ~~~~~~ . .~ . ..
&-Test No.: - Scenario No.: 2 Event No.: Page 3 of 3
Event Description: 1A Main Steam line break in RB (M, ALL)
Time Position Applicant's Actions or Behavior
-
__
SRO 8. Excessive Heat Transfer (EHT) tab will:
Ensure Rule 5 (Main Steam bine Break) in progress or
complete.
Close 1FBW-382, 1MS-26, 1MS-76, 1MS-36, IMS-84,
Throttle #PI to stabilize RCS pressure and maintain PZR
level > 8 0 (180" acc)
Verify letdown in service
Feed and steam all intact SGs to stabilize RCS P/T. (CT-I 1)
Verify 1MS-24/33 are closed.
Open 1AS-8
Close ISSH-I, 1SSH-3, ISSH-9.
Minimize SCM using the following methods as necessary:
(CT-7)
k 5e-energizing all PZR heaters
P Using PZR spray
> Throttling #PI
Initiate Enclose 5.16 (SG Tube-to-Shell A T Control)
GO TO Steam Generator Tube Rupture (SGTR) tab.
NUREG-1021, Draft Revision 9 Page 13 of 15
....
Scenario-Outline .~ Form ~ ~-67
Appendix
... D . .. ..
lp-Test No.: - Scenario No.: _2_ Event No.: A Page 3 of 3
Event Description: 1A Main Steam line break in RB (M, ALL)
Time Position Applicant's Actions or Behavior
-
s_
SRQ 9. Steam Generator Tube Rupture (SGTR) tab will:
8 Verify Rx tripped.
e Initiate Encl 5.5 (Pzr and LDST Level Control) to maintain
. Pnr level 140. - 180. [175. - 215. acc].
Start the A and B Outside Air Booster Fans.
0 Monitor RlAs 16 and 17 to identify all SGs with a tube
rupture.
0 Dispatch an operator to open the TB Sump pump breakers.
a Notify RP to survey both MS lines for radiation.
8 Secure any unnecessary offsite release paths. (Main
Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector,
.. etc.).
Verify Main FDW or EFDW controlling properly.
. Open 1HP-24/25
Secure makeup to LDST.
.
e Maintain both SG pressures < 950 psig
Minimize core SCM using the following methods:
P De-energize all Pzr heaters
2. Use Pnr spray
. P Maintain Pzr level 140. 180. [ I 7 5 - 215. accj
Initiate a cooldown using the intact SG.
When directed by the Lead Examiner the event and scenario is
completed.
NUREG-1021, Draft Revision 9 Page 44 of 15
~~
.. ...~
~
.~ .~
Appendix D .. . Scenario ouilinne
...~.~~~
Form E§-D-1
.' .
.
CRITICAL TASKS
1. CT-17, Isolate Overcooling SG
2. CT-11~Control SG pressure to Maintain RC Temperature Constant.
3. CT-7, Minimize SCM
NUREG-I 021, Draft Revision 9 Page 15 of 15
....... . . . . ........
Appendix D ........ .~ ~ ~ ~ ~ Scenario ~ u t i..i..n...e... .....
...Form ~s-D-1
Faality: Oconee Scenario No.: 3 fnl Op-Test No.: 1
Examiners: Operators:
Initial Conditions:
200% Reactor Power (Snap-203)
Turnover:
AMSAC/DSS bypassed for I&E testing
SASS in MANUAL for I& testing
Event
Ob Pre-Insert SASS in Manual
oc I I AMSACDSS bypassed
1 MCSOO4 I,OATC, SRO Controlling Tave fails HIGH
2 I Override I GALL I BLPSW pump trips (TS)
Large Break LOCA
Switchyard Isolation
I Keowee 1 lockout (blackout)
CT-1 Lockout
...
- ....................... ................. ......................... ............
(Njomal. (H)eac!ivity, (I)nslrurrrent, (C)cmponent, (M)ajor
NUREG-1021, Draft Revision 9 Page 1 of 9
. ... -. ..
Appendix D .~. . . SGnario Outline .
F o ES-D-1
~
op-Test No.: - Scenario No.: Event No.: 1 Page 1 of 1
Event Description: Controlling Tave fails HIGH: (I, OATC)
Applicant's Actions or Behavior
Plant response:
1SA-OZA-12, ICS Tracking, will actuate due to neutron and
feedwater cross-limits.
Controlling Tave will indicate = 596.4" F.
Actual loop A & E3 Tsve will decrease until operator stops
RCS pressure and temperature will decrease.
Crew response:
When the ICs TRACKING alarm is received, the candidates
should utilize the "Plant Transient Response" process to stabilize
the plant and recognize that the controlling Tave has failed. RX
will trip on variable low pressure with no operator action.
Verbalize to the SRO reactor power level and direction of
movement.
Place the FBW Masters in manual and stabilize the plant. Use
control rods and FDW to stabilize the plant
0 The SR6 should:
Refer to AW28, ICs Instrument Failures
- Contact S W C to repair controlling Tave.
Note: The ICs will remain in manual for the remainder of the
scenario.
When the plant is stable or when directed by the lead examiner
this event is completed.
NUREG-1021, Draft Revision 9 Page 2 of 9
.. ....
-Appendix D.~. ~
Scenario Outline .~
~ .... ~
Form E§-D-1
Op-Test No.: - Scenario No.: 3 Event No.: 1_ Page 1 of 1
Event Description: W
LPSW pump trips: (C, ALL) (TS)
Time Position Applicants Actions or Behavior
.~~ .- __ .~
Plant response:
StataIarms:
1SA-9/A-9. LPSW Header N B Press Low
Control board indications:
- B LPSW pump indicates tripped
Crew response:
BOP Refer to ARG for 1SA-9/A-9, LPSW Header N B Press Low
SRO Refer to AP/24 (Loss of LPSW) which will:
Ensure LPSW pump suction valves are open:
Verify NO LPSW pumps are cavitating and GO TO §tep 4.6.
Ensure all available (NOT previously cavitating) LPSW pumps
operating.
Verify normal LPSW System operation has NOT been restored
and GO TO Step 4.9.
Dispatch an operator to perform Encl 5.1 (Local Operator
Actions).
lAAT conditions permit,
THEN start the LPSW pumps that were stopped in Step 4.5 due
to cavitation.
SRO should refer TS 3.7.7 (Low Pressure Service Water) and
determine that LCO 3.0.3 applies and commence a unit
shutdown.
When a unit shutdown has been commenced or when directed
by the lead examiner this event is completed.
NURG-1021, Draft Revision 9 Page 3 of 9
.... .., .~~~..__ ~.
_
-
Appendix
.. B .. ~~ .~-. Scenario Outline
. ~. Form E§-D-1-
Scenario No.:3 Event No.: 3_ Page 1 of 1
Event DescriDtion: Unit Shutdown (R, O A K )
-Time Position Applicant's Actions or Behavior
The OATC will use the FBW Masters and the Diamond to reduce
BATCISRO power while monitoring Reactor Power, Tave, and other plant
parameters.
When a unit shutdown of 5% has occurred or when directed
by the lead examiner this event is concluded.
NUREG-1021, Draft Revision 9 Page 4 of 9
.-.. .~
Appendix B .~..
Scenario Outline
..~..
Form ES-D-1
lp-Test No.: - Scenario No.: 3 Event No.: 4 Page 1 of 4
- vent Description: Large Break LOGA and Switchyard Isolation: (M, ALL)
Time Position Applicant's Actions or Behavior
_ I._1
ALL Plant response:
Control board indications:
D A Switchyard isolation will occur.
D RCS subcooling margin will indicate 0°F.
m ES 1-6 actuate
D Power will be lost and then regained from Keowee #1 via the
underground.
Crew response:
1. The OATC perform IMAs the O A K to perform a symptom check.
OATC
2. The BOP should report symptoms and inform the SKO that the
BOP RCS has saturated and obtain Sa0 concurrence to perform Rule
2. Loss of SCM.
Verify that reactor power is c 1%.
Trip RCPs within 2 min of LOSCM (CT-1)
Verify any HPI pump is available.
Open 1HP-24/25 ( I N I B BWST Suction) open
Start all available #PI pumps operating.
Open 1#P-26/27 (1AilB HP Injection) open
Verify at least two HPI pumps are operating using two diverse
indications. (Le. pump amps and flow)
lAAT HPI flow in any header is in the Unacceptable Region of
Figure 1
THEN perform Steps 10 -12. (flow is acceptable)
Throttle "B" HPI flow to c 475 gpm.
lAAT either of the following exist:
P LPI FLOW TRAIN A plus LPI FLOW TRAIN B 2 3300
GPM (LPI flow will be met)
P Only one LPI header operating, AND flow in that header is
2 2850 gprn. GO TO Step 14.
WHEN directed bv the CR SRO
THEN EXIT this rile.
OATC 3. O A K will perform Enclosure 5.1 (ES actuation) (CT-20)
NUREG-1021 Draft Revision 9 Page 5 of 9
~. ~.~~ ~~ . .~~~ ...
Scenario Outline Form ES-D-1
~-
Appendix D ..... . . ~ ~ .-..
~ ~.
3p-Test No.: - Scenario No.: 3 Event No.: 8 Page 2 of 3
- vent Description: Large Break LOCA and Switchyard Isolation: (M, ALL)
~
Time Position Applicant's Actions or Behavior
SRO 4. The SRO should refer to the Parallel Actions and transfer to the
LOSCM tab.
5. The LOSCM tab will:
Refer to Parallel Actions and:
> Direct an RO to Initiate APll1 (Recovery from Loss of
Power)
Note: APll1 can not be implemented until an RO completes
either Rule 2 or Enclosure 5.1.
Z Direct an RO to announce plant conditions.
Ensure Rule 2 (Loss of SCM) is in progress or complete
a Verify Station ASW feeding any SG.
IAAT either of the following exists:
i LPI FLOW TRAIN A plus LPI FLOW TRAIN B = 3300
gpm
> Only one LPI header in operation with header flow =
2858 gpm
- THEN GO TO LOCA CB tab.
The LOCA CB tab will:
0 IAAT BWST level is = 19',
THEN initiate Encl 5.12 (ECCSSuction Swap to RBES).
Verify ES actuated.
Perform the following:
> Ensure all RBCUs in low speed.
>. Open ILPSW-18.
> Open ILPSW-21.
>, Open 1bPSW-24.
P Close 1LPSW-565.
When directed by the lead examiner this event is concluded.
_._
NUREG-1021, Draft Revision 9 Page 6 of 9
-. ~~~~~
Appendix. 5
.~~~. Scenario
. ~ .Outline
~. ~~
Form ES-B-1
Op-Test No.: __ Scenario No.: 3 Event No.: 9 Page 1 of 2
Event Description: Keowee 1 and CT-1 lockout (blackout): (M,ALL)
When directed by the Lead Examiner Keowee 1 will trip and CT-
1 will lock out.
Plant response:
Loss of power to the Main Feeder Buses (Blackout) will occur.
m The unit will remain in a Blackout condition until actions are taken
by the operators per Enclosure 5.38 (Restoration Of Power).
The TB EFDW pump will be feeding h e SG to remove decay heat.
Crew response:
SRO The SRQ will transfer to the Blackout tab which will:
Verify two ROs available to perform Control Room actions.
~. ...
NOTE
During performance of Encl 5.38 (Restoration of Power),
progression through the Blackout tab should...continue.
..
Notify one RO to perform Encl 5.38 (Restoration of Power).
- IAAT power is restored to any of the following:
2. 1TC
>, 1TD
2. 1TE
THEN GO TO Step 4.
Verify any SG is being fed.
0 Feed and steam available SGs as necessary to stabilize RCS
QATC
PIT.
IAAT NO SGs are being fed
AND any source of EFDW (Unit 1 or another unit) becomes
available,
THEN perform Steps 9 - 11.
I GO TO Step 12.
IAAT EFDW from any source is insufficient to maintain stable
acs P/T,
THEN notify SSF operator that feeding SGs with SSF ASW is
required
I I * Verify Encl 5.38 (Restoration of Power) in progress or
complete.
NUREG-1021, 5rafl Revision 9 Page 7 of 9
-. . .. .- .~~ .
-.Appendix
. D... ~.~~ ____Scenario Outline Form ES-D-1
Op-Test No.: __ Scenario No.: 3 Event No.: S _ Page 2 of 2
Event Description: Keowee 1 and CT-1 lockout (blackout): (M, ALL)
___I
-Time Position
Applicant3 Actions or Behavior
The BOP will perform Encl 5.38 (Restoration of Power) which will:
Place 1HP-31 in HAND and reduce demand to 0.
Close 1HP-21.
Verify either MFB energized (MFBs are de-energized)
Verify CT-? indicates 4165 volts. (Cf-I has no voltage)
Verify both Standby Bus #I and Standby Bus W2 are de-
energized.
Verify all Keowee units operating. (Keowee 1 is locked out)
Emergency start both Keowee units
Notify Keowee Operator to place all operating Keowee units in
Bconee Control.
Close UNIT 2 EMER FDR ACB 4 (power will be restored)
(CT-8)
When the Main Feeder Buses are energized or when directed by
the Lead Examiner the event and scenario is completed.
NUREG-1521, Draft Revision 9 Page 8 of 9
..~.. .... ... ~ ~. ~ _ _ .~
Appendix D ... ... ..... ~mnariooutline F O I ES-D-1
~
CRITICAL TASKS
1. CT-27, Implementationof Control Room Habitability Guidance
2. CT-8. Electrical power alignment
NUREG-1021, Draft Revision 9 Page 9 of 9