ML042330112
| ML042330112 | |
| 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: ML042330112 (74) | |
See also: IR 05000269/2004301
Text
Draft Submittal
(Pink Paper)
1.
Operating Test Simulator Scenarios
QCQNEE JUNE 2004 EXAM
50-26912004-301 I
50-270/2004-301, &
50-28712004-301
JUNE 14 - 18 & 25,2004
Aooendix D
Scenario Outline
Form ES-D-1
Facility: Qcsnee
Scenario No.: 1 RO
Op-Test No.: 1
Examiners:
Operators:
Initial Conditions:
e
Turnover:
e
e
45% Reactor Power (Snap 201)
Startup in progress after adding oil to 1B1 RCP
?A Main FBW pump operating
SASS in MANUAL for I&E troubleshooting
1 B MDEFDW Pump 00s
After turnover, the crew should start 161 RCP
Pre-Insert
MP1290
I
Re-Insert
MPS350
I
..........
1
2
I Override
I 2342481
I
MPS120
Override
MP1050
MFI080
5
1 Override
I C A L L
6
I MPS110
I R. OATC. SRO
L
(N)ormal, (R)eactivity,
(I)nstrument,
(1
Event
Description
SASS in manual
~
~~
~
~~
.................................................
-
.- . __ -
-
I
B MDEFDW Pump 00s
Block All Turbine Trips Except Manual
A RBCU fails to receive ES signal
Start 1B1 RCP
AC Oil Lift pump will not develop adequate
discharae Dressure
1A HPI pump sheared shaft, (TS)
Standbv HPI PumD fails to start
RC Loop B Flow fails LOW
BWST ruDture (TS)
Manual unit shutdown due to BWST level
I A Main FDW pump trips
Main Turbine Fails to trip (Lockout EHC Pumps
RCS leak to SRl.OCA (ramp over 10 minutes)
.................................................................................
,
I C HPI pump trips requiring rapid RCS C/B di
to deqraded HPI
iomponent,
(M)ajor
NUREG-1021, Draft Revision 9
Page 1 of 15
. . . . . .
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- . . . . . . .
-.
.-
Appendix
...........
D
.....
Operator Actions
.....
.......
Form ES-B-2 ....
-
Op-Test NO.: -
Scenario No.: 1
Event No.: 1
Page 1 of 7
Event Description:
~
Time
Position
Start 1B1 RCP: (61, BOP)
.._I_~.~
.
Applicant's Actions or Behavior
Crew response:
The BOP should use the in progress procedure 0P/1/Af1103/006 (RCP
Operation) Enclosure 4.1 (RCP Start) to start the 1 B1 RCP.
Review Limit and Precautions
Open 1 IQSW-9&10 (1 B1 RC PUMP MTR CLR IN & OUT) and verify
both valves open by using the OAC indications.
Note:
No more than two RCP(s) may be operated when RCS is e 250 OF.
Either A 6 or DC Oil Lift Pump may be used
AC Oil Lift Pump may take > 2 minutes to develop adequate discharge
pressure
AC and DC Oil Lift Pumps will automatically trip after 3 minutes
Oil Lift Pump may NOT start unless switch has been placed to "OFF"
after last start
Announce "Starting 151 RCP" via plant page.
Start AC Oil Lift Pump on 1 B1 RCP.
........................
When the 1Bl RCP AC Oii Lift Pump has been started this event is
completed.
NUREG-1021, Draft Revision 9
Page 2 of 15
Op-Test No.: -
Scenario No.: 1
Event No.: 2
Page 1 of 1
Event Description:
Position
1B1 RCP AC Oil Lift pump will not develop adequate discharge
pressure: (C, BOP)
Applicant's Actions or Behavior
Note: The AC Oil Lift Pump will not develop adequate discharge
press to clear the Low Press indication prior to tripping off. 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 1B1 RCP. (will not clear)
IF AC Oil Lift Pump automatically trips after 3 minutes, start DC Oil Lift
Pump.
Monitor the status of DC Oil Lift Pump low discharge pressure on the
OAC and when it clears, start 1BZ 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.
rhis event is complete when the lB1 RCP is started or when directed
3y the lead examiner.
NUREG-1 021, Draft Revision 9
Page 3 of 15
Op-TeSt NO.: ~
Scenario No.: 1
Event 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)
Position
Applicants Actions or Behavior
Plant response:
Statalarms:
1SA-2/B-2 (HP RCP Seal Injection Flow High/Low)
ISA-2iC-2 (HP Injection Pump Disch. Header Pressure
HighlLow)
Board indications:
0
0
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:
4 . Refer to ARG for above Statalarms
2. SRO should refer to AP/014 (Loss of Normal Makeup andlor
RCP Seal Injection)
0
0
e . . .
. .
0
Verify no HPI pump operating
Close 1 HP-5 (Letdown Isolation)
Place 1 HP-120 (RC Volume Control) in HAND and closed
Place IHP-32 (RCP Seal Flow Control) in HAND and closed
S t x i standby #PI pump (IB MPI pump)
Slowly open 1 HP-32 in small increments until = 8 gpmlRCP is
achieved.
Re-establish normal makeup through 1 HP-120.
Reduce IHP-7 demand to 0%.
Close 1 HP-6
Ensure the following open:
> IHP-1
Z 1HP-2
r
IHP-3
> 1HP-4
NUREG-7021, Draft Revision 9
Page 4 of 15
i
Position
Applicants Actions or Behavior
.....
....
Scenario No.: 1
Event No.: 3
Page 2 of 2
A HBI Pump sheared shaft and the standby HPI pump fails to
Event Description:
to start: (C, BOP)
Open IHP-5
Throttle open 1HP-7 for = 20 gprn letdown flow.
Open IWP-6
0
Place IHP-31 in auto.
Adjust ZHP-7 for desired letdown flow
3. Refer to Tech Spec 3.5.2 High Pressure Injection
Condition A
Required Action: Restore #Pi pump to OPERABLE status
m
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. Folbw-up questions may be required to
ensure knowledge of this competency.
Event is complete when normal makeup and letdown Is
established or when directed by the lead examiner.
NUREG-1021, Draft Revision 9
Page 5 of 15
Position
O A K
RC Loop B Flow fails LOW (I, OATC)
......-
.~ ~
Page 1 of 1
Event Description:
Applicants Actions or Behavior
Plant response:
1. Statalarms:
1 SA-2/A-4, RC hoop El Flew LOW
e
1 SA-2/A-5, RC Total Flow Low
ISA-l/A-l, RP Channel A Trip
ISA-IIA-3, RP Channel A Flux/lmb/Flow Trip
2. Control beard indications:
0
RCS Flow meter shows Loop E3 flow at zero.
e
RPS Channel A trips.
5 S/G FDW Flow instrument shows a reduction in FDW, and the A
S/G FDW Flow indicates increasing flew or off-scale High.
DELTA Tc meter indicates a large Delta Temp
Crew response:
The crew should stabilize the unit by using the Plant Transient
Response process.
0
Take the Diamond and BOTH FDW Masters to MANUAL and stabilize
the unit.
The SRO should refer to AP/28, ICS Instrument Failures and notify
SPOC to have the instrument repaired.
AP/28, ICs Instrument Failures (Case 4E RCS Flow Failure) will:
ii Ensure DIAMOND and BOTH FDW Masters in MANUAL.
> Notify SPOC lo select a valid WCS flow input to ICs and
investigate and repair the failed RCS flow instrumentation.
ii Ensure any associated requirements of PT/1/A/0600/001
(Periodic Instrument Surveillance) are met for the failed
instniment.
)i WHEN notified by SPOC that a valid RCS flow input has been
restored to ICs, THEN GO TO Encl 5.1 (Placing ICs in AUTO).
Note: Crew may refer to PT16001001 (Periodic Instrument
Surveillance) and TS 3.3.1 (RPS Instrumentation) due to A RPS
Channel trip and may choose to place A RPS to manual Bypass.
Event is complete when the SRO has reached the WHEN step in
AP128 or when directed by the Lead Examiner.
NUREG-1021, Draft Revision 9
Page 6 sf 15
3p-Test NO.: _I_ Scenario No.: 1
Event No.: 5
Page 1 of 1
Event Description:
-
Time -
Position
Borated Water Storage Tank (BWST) rupture: (C, ALL) (TS)
Applicant's Actions or Behavior
Plant response:
Statalarrns:
1SA-3/D-8, BWST level HighiLow
Control board indications:
e
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 1 SA-3/B-8, BWST level High/Low
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 OP/1IA11102/004
(Operation 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 SRQ or
when directed by the Lead Examiner.
NUREG-I 021, Draft Revision 9
Page 7 of 15
3p-Test NO.: -
Scenario No.: 1
Event No.: 6
Page I
of I
Event Description:
Manual unit shutdown due to BWST level: (R, O A K )
Position
OATC
Applicant's Actions or Behavior
Crew response:
Direct unit shutdown per OP/l/NI 102/004 (Operation At Power) End. 3.2,
Power Reduction
4 . 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 lead reduction.
5. Reduce reactor power in manual by inserting control rods with the
Diamond. controlling FDW flow with the FBW Masters, and controlling
turbine header pressure with the Turbine Master.
Event is complete when reactor power has been reduced 5% OF when
directed by the Lead Examiner.
NUREG-1021, Draft Revision 9
Page 8 of 15
3p-Test No.: -
Scenario No.: 1
Event No.: 7
Page 1 of 1
Event Description:
~~
~
Position
1A Main FDW pump trip:
Main Turbine Fails to trip (Lockout EHC Pumps) (C, O A K )
Applicant's Actions or Behavior
Plant response:
0
1A Main FDW pump trips resulting in a reactur trip.
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:
2. OATC will perform Immediate Manual Actions
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)
3
BOP will perform a symptom check and Rule 3 (Loss of Main ur
Emergency Feedwater).
Verify RCP seal injection available.
- - ~ . _ _ ~ - _ _ _ ----
Event is complete when EHC pumps have been tripped or when
directed by the lead examiner.
NUREG-1021, Draft Revision 9
Page 9 of 15
Sp-Test NO.: __ Scenario No.: 1
Event No.: 8
Page 1 of 4
- vent Description:
RCS leak to Small Break LOCA (ramp over 10 minutes): (Mi, ALL)
Position
Applicants Actions or Behavior
Plant response:
1. Statalarms:
ISA-9/A-6, RB Reactor Bldg Norm Sump Level HighiLow
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 1 HP-5
being closed.
Crew response:
1. Refer to ARG for 1 SA-9iA-6, RB Reactor Bldg Norm Sump Level
High/Low
2. Refer to AP1002, Excessive RCS Leakage
3. Close IHP-5 (Letdown Isolation)
4. Initiate Encl. 5.1 (Leak Rate Determination)
5. IAAT LDST level is 5 40, ensure open 1 HP-24 and IHP-25 (IN4 B
BWST Suction)
6. Ensure OSM, SPA, RP are notified
7. Monitor trend of T6 AP02 for increases (OAC)
9. Verify NO leakage through PORV and dose IRC-4
9. Identify leak is in the RB and GO TQ Step 4.20
10. Place standby CC pump switch to OFF.
11. Close ICC-1iIHP-1 and ICC-2/1HP-2
12. Verify leakage has stopped (has not)
13. Verify re-establishing bD is desired (it is not due size of leak)
14. Ensure RB isolation valves are closed.
15. Use Enci. 5.5 (PZR and bBST Level Control) to try and maintain
PZR inventory and LDST inventory.
Start standby HPI pump
Throttle 1 HP-26 open
Start I C HPI pump
Note: The RCS will eventuaily saturate with ail HPI injecting.
NUREG-1021, Draft Revision 9
Page 1Bof 15
Op-PeSt NO.: -
Scenario No.: 1
Event No.: 8
Page 2 of 4
Event Description:
Time -
Position
SRQ
RCS leak to Small Break LOCA (ramp over 10 minutes): (NI, ALL)
Applicant's Actions or Behavior
Plant response:
RCS subcooling margin will = 0°F.
Crew response:
1. SRO should direct the 8ATC to perform a symptoms check.
2. The BOP should inform the SRO that the RCS has saturated and obtain
SRO concurrence to perform Rule #2, boss of SCM.
.
0
0
e . . . .
e . . .
Verify that reactor power is c 1%.
Trip RCPs within 2 min of LOSCM (CT-1)
Verify that HPI is performing as required.
Verify that LPI flow in any header is c 1000 ggm.
Verify that TBVs are available.
Disable AFIS in non-actuated channels.
Establish EFDW to the QTSGs to feed to LOSCM SP per Rule 7 (SG
Feed Control). (CT-10)
Verify both MDEFDWPs operating. (1B MBEFDWP is off)
Ensure TDEFDWP is in PULL TO LOGK. (Not performed due I B
MDEFDWP not operating)
Trip both MFDWPs and close the FDW block valves.
Maintain SG pressure 6 RCS pressure.
Ensure Rules 3 & 8 done or in progress
NUREG-1021, Draft Revision 9
Page I 1 of 15
Dp-Test NO.: __ Scenario No.: 1
Event No.: 8
Page 3 of 4
Event Description:
RCS leak to Small Break LOCA (ramp over 10 minutes): (M, ALL)
Time
__
Position
Q A X
Applicant's Actions or Behavior
3. When ES Channels 1 and 2 actuate, an operator should inform the SRO
that ES Channels 1 and 2 have actuated. The SRQ should initiate EOP
End. 5.1, ES Actuation per the parallel actions page of Subsequent
Actions section or of the LOSCM Tab. 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 remain in HIGH
speed. The operator should diagnose this and place the "A" RBCU in
LOW speed.
.
0
e
e . .
0 . .
Place HPI in Manual.
Verify SCMs 0°F and proceed to the #PI flcw check when he
determines that the RCS has saturated.
The operator should determine HPI flow.
Open 1 BS-I and 1 BS-2
Place LPI pumps in manual control.
At SRO direction secure LPI pumps.
Ensure A and B and 3A and 38 Outside Air Booster Fans are
operating. (CT-27)
Dispatch an operator to perform Encl. 5.2 (Placing RB Hydrogen
Analyzers In Service)
Notify Chemistry to prepare for caustic addition.
The operator must get SRQ approval to exit this enclosure.
NUREG-1021~ Draft Revision 9
Page 12 of 15
3p-TeSt NO.: __ Scenario No.: 1
Event No.: 8
Page 4 of 4
Event Description:
. -
Position
RCS leak to Small Break LOGA (ramp over 10 minutes): (M, ALL)
Applicant's Actions or Behavior
4. The SRO 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 OF complete
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 ail the following conditions exist:
2. NO RCPs are operating
> HPI flow exists in both #PI headers
4 Adequate Total HPI flow per figure 1 (Total Required HPI flow)
Open 1AS-40 while closing 4 MS-47.
Control steaming and feed rates on all intact SGs to maintain
cooldown rate within Tech Spec limits:
> Tc:
280°F
5 5OW % hour
> Tc c 280°F 5 2 5 W % hour
e
GO TO Step 91.
Close IRC-4
Note: When 1RC-4 is closed 1C HPI pump will trip.
NUREG-1021, Draft Revision 9
Page 13of 15
-
. .. -
Qp-Test No.: -
Scenario No.: 1
Event No.: 9
Page 1 of 1
Event Description:
Time -
Position
SRQ
IC HPI pump trips requiring rapid RCS CID due to degraded HPI
ADDlicants Actions or Behavior
Plant response:
Crew response:
1. BOP should indicate to the SRO that the I C #PI pump has tripped.
2. SRO should recognize that conditions have changed and transfer to
the beginning of the LOSCM tab.
Ensure that Rule #2 is in progress or complete.
Verify that station ASW is not feeding any SG.
Verify that the LOSCM is NOT caused by excessive heat transfer.
Verify transfer to LQCA CD tab NOT required due to no LPI flow.
Verify all the following conditions exist:
2. NO RCPs are operating
>. HPI flow exists in both HPI headers (No flow in the B
> Adequate Total HPI flow per figure 1 (Total Required #PI Flow)
GO TO Step 13
Start both MDEFDW pumps and the TDEFDW pump. (IB MD
EFDWP NOT available)
Establish 300 gpm to each SG
Initiate full depressurization of both SGs utilizing TBVs or ADVs.
Initiate feed to all available SGs to LOSCM setpoint at maximum
allowable rate (per Table 3 (Emergency FDW Pump and Header
Maximum Flow Limits) of Rule 7 (SG Feed Control)).
WHEN SCM is > O T ,
OR all the following conditions exist:
0 NO RCPs operating
2. HPI flow in both HPI headers
2. Adequate total HPI flow per Figure 1 (Total Required HPI Flow)
THEN maintain SG pressure
following:
> TBVs
2. ADVs
RCS pressure utilizing one of the
Vote: Will wait at this WHEN step until lAAT (6) is met on LPI flow.
Event and exam is complete when SG depressurization is in
wogress or when directed by the Lead Examiner.
NUREG-1021, Draft Revision 9
Page 14 of 15
CRITICAL TASKS
1. CT-18, Turbine Trip
2. (3-1, Trip All RCPs
3. CT-10, Establish FW Flow and Feed SGs
4. CT-27, Implementation of Control Room Habitability Guidance
NUREG-1021, Draft Revision 9
Page 150f 15
__
~.
Appendix D
Scenario Outline
~
Form ES-D-I
Facility: Oconee
Scenario No.: 2 RO
Op-Test NO.: 1
Examiners:
Operators:
Initial Conditions:
Turnover:
0
35% Reactor Power, startup in progress (Snap-202)
AMSAClDSS bypassed for 18rE testing
Nl-9 OOS, to be replaced next outage
IA SG AFIS Digital Channel 1 circuit 00s
K Condensate Booster Pump OOS, breaker to be replaced
Keowee Unit 2 OOS for unplanned reasons
Keowee Unit 1 aligned to underground
Operability test of Keowee Unit 1 is to be performed per PT/620/009 (Keowee Hydro
Operation) after turnover and before startup continues, ONS to perform remote
Keowee start
A AFIS circuit disabled
! B AFIS circuit disabled
I
I
I
Od
Pre-Insert
Keowee Unit 2 Emergency Lockout
MEL180
I
~
~~
I
Pre-Insert 1
I ES channels 7 and 8 fail to actuate
I
1
I
5
I
Override
I
I Seismic event (PRA)
I C, BOP, SRO I IA RBCU rupture (TS)
6
I
MPSOZO
I C,ALL
I 1B SG Tube leak, 50 qprn (TS)
(N)ormal. (R)eactivity, (I)nstrument, (Clomponent, (M)ajor
NUREG-1021, Draft Revision 9
Page 1 of 14
-
-
Appendix B
Scenario Outline
Form E§-D-1
-
.-
~~~
.
Op-Test No.: -
Scenario No.: 2 Event No.: 1
Page 1 of 1
Event Description: Operability test Keawee Unit 1 (N, BQPISRO)
Position
§BO
Applicants Actions or Behavior
Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to
operability test unit 1 Keowee underground.
Use OP/i 106/019 (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.
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 I
FIELD BREAKER closes
0
GEN 1 SUPPLY BREAKER closes
GEN 1 FIELD FLASHING BREAKER closes
Event is complete when operability test is in progress.
NUREG-1Q21, Draft Revision 9
Page 2 of 14
~
-
.-
~.
Appendix D
Scenario Outline
Form ES-D-I
-
.-
-
-
E
Op-Test NO.: ___ Scenario No.: 2
Event No.: 2
Page 1 of 1
Event Description: Keowee Unit 1 Gen Field FIasking Breaker fails to OPEN
automatically (C, BOPISRO)
k
I
...
I
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 reauest or contact SPOC.
11
1
SRo
1 SRO should direct the BOP to continue with the startup.
Note: GEN FIELD FLASHING BREAKER automatically trips
s 45 seconds after receiving close signal. Failure of breaker to
trip automatically does NOT make the KHU inoperable.
Startup procedure may continue.
4. Determines KHU # I is operable when test complete
5. Verify ACB-1, Keowee I
Generator Breaker, closed.
6. Verify Unit 1 MER FDR ACB 4 closed
7. Verify e 4.16 KV on CT4 Volts (2883)
/I
I
I 8. Close SKI and SK2 (CT4 STBY BUS 1/2 FEEDER)
bility test is complete or when
NUREG-1021, Draft Revision 9
Page 3 of 44
-~
~
~ -_-_
-,
Appendix D
--.--.-.-_.-.--.-__-.-I-._-.-
Scenario Outline
Form ES-D-1
Op-Test NO.: __ Scenario No.: 2
Event No.: 3
Page 1 of 1
Event Description: IHP-120 (RC Volume Control) Fails closed (C, OATCISRO)
Time
__
Position
OATC
.
Applicant's Actions or Behavior
IHP-120 fails closed during Keowee # I operability test. This will
allow OATC diagnoses of failure.
1. Diagnose 1 HP-120 (RC Volume Control) Failed closed:
0
RCS makeup flow goes to zero.
PZR level begins to decrease.
LDST level begins to increase.
Valve position demand for IHP-120 begins to increase to
the 100% demand value and valve position indication will
indicate closed (green light).
2. Refer to APil4 (Loss of Normal Makeup and/or RCP Seal
Injection.
Determine Seal Injection is not lost
Determine loss of suction to HPI pumps has not occurred.
Verify a
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 4.167.
Perform the following as necessary to maintain Pzr level >
200:
=
Close 1 HP-6 (Letdown Qrifice Stop)
9
Throttle IHP-7 (Letdown Control)
=
Throttle 1HP-26 (IA HP Injection)
IHP-120 to HAND and closed
3. Contact SPOC to repair 1HP-120.
Vote: IHP-120 will remain failed for the duration ofthe
scenario.
Nken PZR level Is being controlled manually or when directed
by the lead examiner this event is completed.
NUREG-1021, Draft Revision 9
Page 4 of 14
- .-
.-
__
~
Appendix D
Scenario Qutline
Form ES-D-1
~
~.
Op-Test No.: ~
Scenario No.: 2
Event No.: 4
Page 1 of 1
Event Description: Controlling NI1 fails LOW (I, OATCISRO) (TS)
When directed by the lead examiner the controlling NI will fail low.
Position
OATC
SUO
Applicant's Actions or Behavior
Plant response:
e
ISA-02iA-12, ICs Tracking, will actuate.
Diamond will transfer to manual on NI flux < 1.5%.
e
Crew response:
FDW will decrease due to reactor cross limit.
RCS pressure and temperature will increase,
1.
2.
3.
4.
When the ICs TRACKING alarm is received, ... e candidates
should utilize the "Plant Transient Response" to stabilize the
plant and recognize that the controlling NI has failed. Rx will
trig on high pressure with no operator action.
Verify reactor power.
Place the FDW Masters in manual and stabilize the plant.
Adjust T,,
using control rods and FDW and stabilize the plant
The SRO should direct the NCOs to check OAC and the
control board NI meters to determine the status of the NI
signals that can be used in the ICs.
e
Refer to AP/28, ICs Instrument Failures
SPOC should be contacted to repair NI-5.
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 5 of 14
-
Appendix D
~
Scenario Outline -
Form ES-D-1
Op-Test No.: -
Scenario No.: 2
Event No.: 5
Event Description:
Seismic event (PRA)
1A RBCU rupture (C, BOPISRO) (TS)
~
~~
Page 1 of 2
Time
Position
Applicant's Actions or Behavior
Cue: Call the Control Room (4911) to report a selsmie event
but no plant damage.
1. 1 SA-9/B-9, LPSW RBCU A Cooler Rupture will actuate and RB
normal sump level will increase.
The BOP should refer to ARG for 1 SA-9/B-9
Verify alarm is valid by checking RBCU 1.4 Inlet Flow and
RBCU l A delta flow.
Verify I
LPSW-18 (RBCU 1A Outlet) open
Verify adequate LPSW flow is available; check LPSW pump
operation
Monitor RBNS bevel for any unexplained increase (Notify
Chemistry to sample RBNS for boron to determine if a
cooler rupture has occurred.
Diagnose a Cooler Rupture is indicated and isolate the 1A
RBCU Cooler.
Enter appropriate TS for RBCU inoperable (TS 3.6.5
Condition 6).
Ciose ILPSW-16 (1A RBCU INLET)
Perform TS 3.6.3 Condition C for closed containment
system.
Open vent or drain.
Close ILPSW-18 (IA 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 14
~~
~
~ _ _
~ ~ _ _
__
Appendix D
Scenario Outline
Form ES-B-1
-.
. -.
~
3p-Test No.:
~
Scenario No.: 2
Event No.: 5
Event Description:
Seismic event (PRA)
I A RBCU rupture (C, BOPISRO) (TS)
Page 2 of 2
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 SRQ may refer to APi05, Earthquake.
0
Dispatch operators to perform plant inspections
Note: No damage will be reported.
- Notify SPOC to develop the Strong Motion Accelerometer
tape.
- Verify NO fuel handling activities in progress.
- These items may not be completed depending on how SQQn
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 14
~~
~
~
~
. .-
__
.~
. .
. .
Appendix
.
.
6-
Scenario Outline
~ ~ ~ ~ ~ _ _ _
Form ES-B-1
__I
-.
.~
Scenario No.: 2
Event No.: 6
Page 1 of 2
Event Description: 1B SG Tube leak (50 gpm) (C, ALL) (TS)
Time
Position
-.
ALL
suo
. ..
...
~ .~
~~~.
Applicant's Actions or Behavicr
..~.
.. ~..
.....~
15 SG tube leak occurs following RBCU isolation and initiation of
APE, Earthquake, or when directed by the lead evaluator.
Plant response:
1. The following alarms actuate:
ISA-8\\64, RM PROCESS MONITOR RADIATION HIGH
ISA-8/B-10, RM CSAE EXHAUST RADIATION HIGH
0
2. PZR level will decrease and RC makeup flow will increase
Crew response:
1. Diagnose and take actions for a Tube leak in the 18 SG:
2. Refer to the ARG for the following alarms:
ISA-8/A-9, RM Area Monitor Radiation High
1SA-8/D-1O9 RM CSAE Exhaust Radiation High
ISA-8/94, RM PROCESS MONITOR RADIATION HIGH
ISA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
3. Refer to AQ/l/Af1700/31 (Primary to Secondary Leakage)
4. Open and white Tag T9 Sump pump breakers.
5. Monitor primary parameters; PZR Level and LDST level to
determine that gross leakage exist and transfer tc step 4.65.
6. Determine OTSG tube leak size is greater than 25 gpm and will
require entering the EOP.
7. Log RIA readings (a rough log is adequate)
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 EQP.
NUREG-102? Draft Uevision 9
Page % of 14
___
Appendix D
Scenario Outline
Form ES-D-1
~
.-
.
~~
~-
Op-Test No.: -
Scenario No.: 2
Event No.: 6 _
Page 2 of 2
Event Description: 1B SO Tube leak (50 gpm) (C, ALL) (TS)
Time
Position
- .
.~~
..
Applicant's Actions or Behavior
.
I O . EOP SGTR tab will perform the following:
e
Maintain PZR level 220 inches using Enclosure 5.5 (Pzr
Determine that the Reactor is not tripped.
and LBST Level Control).
Estimate SGTR Leakrate. (leak is 50 gpm)
Monitor RIA-16 ("A" MS Header) and 17 ("B" MS Header) to
identify all SGs with tube ruptures.
Z 1. Determine ICs is NOT in AUTO and direct the OATG to initiate a
12. initiate Encl. 5.19 (Control of Plant Equipment During Shutdown
Note: A shutdown with the ICs in manual is required.
Note: This event will remain in progress for the remainder of the
scenario.
manual power reduction to 6 15%.
for SGTR)
NUREG-1021, Draft Revision 9
Page 9 of 14
.. ...
-.
~
Form ES-D-I
.
.-
.-
.~
Scenario Otline
Appendix I:
Op-Test No.: __ Scenario No.: 2
Event No.:
Page 1 of 1
Event Description: Unit Shutdown (R, OATC)
Time
-
-
Position
OATC/SRO
Applicant's Actions or Behavior
The OATC wiil 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 lMAs
The BOP will utilize Enclosure 5.19 (Control of Plant Equipment
During Shutdown for SGTR).
Note: With the unit at = 25% power only applicable steps will be
performed.
Notify WCC SRO to make notifications
Transfer electrical auxiliaries
Place ITA AUTO/MAN transfer switch in MAN
Place ITB AUVO/MAN transfer switch in MAN
Close ITA SU 6.9 KV FDR
Close 1TB SU 6.9 KV FDR
Place MFBI AUTO/MAN transfer switches in MAN
Place MFB2 AUTO/MAN transfer switches in MAN
Close El, MFBl 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-1022, Draft Revision 9
Page 10 of 14
~
.
~
. . ..
..~~~..
Form ES-D-1
Appendix
~...
D
..~~...
.
ScenarioOitline
. .
~~~~~
-
..
....
~.
Op-Test No.: __ Scenario No.: 2
Event No.: 8
Page 1 of 3
Event Description: 1A Main Steam line break in RB (M,
ALL)
1A main steam line break will occw following event 7 as directed by
.. .
_....
Id examiner.
. ~ .
Applicant's Actions or Behavior
__I
Time
the
Position
ALL
O A K
OATC
Plant response:
Statalarm 1 SA-02/A-9, MS Press HighlLow, actuates
"A and "B" main steam (MS) pressure decreases
- " B MS line pressure stops decreasing
"A MS line pressure continues to decrease
RCS may saturate
Crew response:
1. The OATC will perform IMAs.
k Depress REACTOR TRIP pushbutton
2. Verify reactor power c 5% FP and decreasing
'i Depress TURBINE TRIP pushbutton
i. Verify all turbine stop valves closed
'i Verify RCP seal injection available
2. The OATC will verify the performance of IMAs while the BOP
peliorms a symptoms check.
3. The Sa0 will "Parallel Action" to transfer to the Excessive Heat
Transfer (EHT) tab and direct the Crew's actions as follows:
4. If SCM = 0°F then the OAT6 will perform Rule #2 (Loss of SCM)
after receiving concurrence from the SRO.
Trip ALL RCPs within 2 minutes (CT-1)
0
Ensure open 1 HP-24 and 1 HP-25
Ensure ALL HPI pumps operating
Ensure open IHP-26 and 1 HP-27
0
Verify required HPI flow per header
Verify TBVs available
NUREG-1021, Draft Revision 9
Page 11 of 14
Scenario No.: 2
Event No.: 8
Page 2 of 3
3p-Test NO.: -
Event Description: 1A Main Steam line break in RB (M,
ALL)
Time -
Position
~~
..
.__-
Applicant's Actions or Behavior
Feed all intact SGs
Control EFDW as required to raise level to intact SGs to
proper setpoint per RULE 7 (SG Feed Control)
Trip both Main FDWPs
Place FDW block valve switches (1 FDW-33,31,42,40) in
CLOSE:
Maintain SG pressure < RCS pressure
e
5. If §CM = 0°F then the SRO with transfer to LOSCM tab which
will:
Ensure Rule 2 (boss 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)
0
-
GO TO EHT tab.
6. The BOP will perform Rule #5 (Main Steam Line Break) after
receiving concurrence from the SRO.
Stop 1A MDEFDW Pump (CT-17)
Initiate AFlS 1A SG Digital Channels 1 and 2
Ensure both Main FBW pumps tripped
Steam 15 SG to maintain CETCs constant (CT-14)
7. Enclosure 5.1 (ES 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 9
Page 12 of 14
~
~
~
~
~
~
..... ~.~
..........
Appendix B
. . . . . . . . .~
Scenario Outline
Form ES-0-1
~
. .. . . . . . . . .
Op-Test NO.: -
Scenario No.: 2 Event No.: A
Page 3 of 3
Event Description: I A Main Steam line break in RB (M, ALL)
.__I___.____.I.._._..._
Position
Applicant's Actions or Behavior
8. Excessive Heat Transfer (EHT) tab will:
Verify excessive heat transfer stopped
Throttle HPI to stabilize RCS pressure and maintain PZR
level > 80" (1 80" acc)
Verify letdown in service
Feed and steam all intact SGs to stabilize RCS PTT. (CT-11)
Minimize SCM using the following methods as necessary:
(CT-7)
i. De-energizing all PZR heaters
i. Using PZR spray
P Throttling HPI
Initiate Enclose 5.16 (SG Tube-to-Shell AT Control)
GO TO Steam Generator Tube Rupture (SGTR) tab.
When the SRO has transferred to the SGTR tab or when
directed by the Lead Examiner the event and scenario is
completed.
NUREG-1021, Draft Revision 9
Page 13 of 14
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~
~~~
~
~
~
~~~ ~-.
~
. . ..
.
. . . .
Form ES-6)-1
...... ~.~~~~~~~~~~~
Scenario
......
~
Butline
-~
~
Appendix D
CRITICAL TASKS
1. CT-17, Isolate Overcooling SG
2. CT-I 1, Control SG pressure to Maintain RC Temperature Constant.
3. CT-7. Minimize SCM
NUREG-1 021, Draft Revision 9
Page 14 of 14
__
~
Appendix D
Scenario Outline
F
o
~
ES-D-I
~~
~
.-
Event Description: Place I
B MFDWPT on Handjack (N, BOP/SRO)
.- -. .
Position
Applicant's Actions or Behavior
Crew response:
The SRO will direct the OATC to perform Enclosure 4.9 (Placing 1 B
FDWPT on Handjack).
Place I E MAIN FDW PUMP (ICS) in "HAND" located on IUBZ.
NOTE:
e Control of 15 FDWPT with 1B FDWPT Motor Speed Changer
indicated when 15 FDWPT speed and/or suction flow decreases.
Two successful decreases should be achieved to ensure control.
~ _ _ _-
_ _ _ _ -
~ - -
Run I B FDWPT Motor Speed Changer down to control I
5
FDWPT.
Turn FWT 1 B HANDJACK switch to "ON".
Event is complete when operability test is complete or when
directed by the lead examiner.
NUREG-1 021, Draft Revision 9
Page 2 of 14
~
___
Appendix D
Scenario Outline
Form ES-D-1
~
Op-Test NO.: -
Event Description:
Time -
Position
Scenario No.: 3
Event No.: 2
Page I
of 1
A LPSW pump suction valve closes and standby pump does not
-
.
auto start: (C, BOP) (TS)
.
ADolicants Actions or Behavior
Plant response:
Statalarms:
ISA-S/A-S, LPSW Header N B Press Low
Control board indications:
LPSW-2 (A
LPSW Pump Suction) indicates closed (also an OAC
aiarm)
A
LPSW pump amps are cycling
Crew response:
1, Refer to ARG for 1SA-9/A-9, LPSW Header N B Press Low
2. Refer to AW24 (Loss of LPSW)
0
Ensure LPSW pump suction valves are open.
Note: LPSW-2 (A
LPSW pump suction valve) will indicate closed. The
team may dispatch an NE0 to open LPSW-2. The valve will not be able
to be opened locally.
Verify LPSW pumps are cavitating
2 Pump amps erratic
2 LPSW header pressure fluctuating
Ensure the Unit 1/2 STANDBY LPSW PUMP AUTO START
CIRCUIT is DISABLED.
Stop the affected pump. Stop A
LPSW pump.
Ensure all available (NOT previously cavitating) LPSW pumps
operating. Start C LPSW pump.
Verify normal LPSW System operation is restored.
The SRO should call SPOC to troubleshoot the reason for the
suction valve closing, the Auto Start failure and determine if the 6A
LPSW pump was damaged due 105s of suction.
The SRO should refer to TS:
> TS 3.7.7 (Low Pressure Service Water System) Condition A
applies. Restore required LPSW pump to operable status. 72
hours completion time.
P TS 3.3.28 (LPSW pump Auto-Start Circuitry) Condition A.
Restore Auto-Start Circuitry to operable. 7 day completion time.
0
0
Note: TS 3.3.28 may be addressed as a follow up question.
Event is complete when SRO has referred to TS 3.7.7 or when directed
by the Lead Examiner.
NUREG-1021, Draft Revision 9
Page 3 of 14
.... .
.
..~~~...
Form ES-D-1
~~~~~~~~
.~
Scenario Outline
.
.
~
~
~ ~.
Appendix D ..~~..
- .~
.. . .
,
-
.~
...
. _._
Op-Test No.: __ Scenario No.: 3
Event No.: 3
Page 1 of 1
Event Description:
Position
O A K
PZR Level # 1 Fails LOW (Iv OATC) (TS)
Applicanrs Actions or Behavior
Note: While the BOP is involved with Event 2, this event will start to
ensure the OATC takes the required actions.
Plant response:
Statalarms
ISA-YC-3, RC Pressurizer Level High/Low
ISA-2/C-4, RC Pressurizer Level Emerg High/Low
e
Front board (IUBI) indications:
PZR bevel 1 indicates 0"
1 HP-120 (RC Volume Control) throttles open
Makeup flew increases to = 160 gpm.
e
Crew response:
RefertoARG
i. Check alternate PZR level indications (1UB1 and OAC) and
determine that PZR level 1 has failed low.
P Check for proper Makeup/Letdown flows and adjust to restore proper
level.
+ Select an alternate PZR level channel on 1 UBI.
SRO should direct the OATC to take actions to restore normal PZR level.
SRO should direct the OATC to refer to PT/600/001 (Periodic Instrument
Surveillance) SASS Manual Operation and have the OATC select an
alternate PZR level channel on 1 UBI.
SRO should refer to TS 3.3.8 (PAM Instrumentation) Table 3.3.8-1.
P Two PZR level channels are required. No action required.
When an alternate PZR level channel has been selected and BZR level
is stable or when directed by the lead evaluator this event is
completed.
NUREG-1021, Draft Revision 9
Page 4 of 14
- -
.-
~
~
Appendix D
Scenario Outline
Form ES-D-1
-. -
-.
-
.-
~
Scenario No.: _3_
Event No.: A
Page 1 of 1
Qp-Test No.: __
Event Description: Controlling Tave fails HIGH: (I, OATC)
Time -
Position
OATC
Applicant's Actions or Behavior
Plant response:
ISA-021A-22, IC§ Tracking, will actuate due to neutron and
feedwater cross-iirnits.
Controlling Tave will indicate 596.4" F.
Actual loop A & B Tave will decrease until operator stops
RCS pressure and temperature will decrease.
e
e
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
The §BO should:
Refer to AP/28, ICs Instrument F a h e s
Contact SPOC 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 5 of 14
_ _
~
-
.
~
~
_
_
_
~
~
_
_
~
-
Appendix D
Scenario Outline
Form ES-D-1
..__
~
Op-Test No.: -
Scenario No.: A
Event No.: 5
Page 1 of 1
Event Description: TCC notifies crew of grid disturbance: (C, BOP)
Position
._
..
Applicants Actions or Behavior
Plant response:
Crew response:
BOP should refer to ARG for SA-16/C-1. ARG will:
Computer alarms for 230 KV Red and Yellow Bus voltage low
SA-16/C-1,230 KV SWYD ISOLATE ES PERMIT actuates
MVARs on the generator increases
Notify the System Operating Center (SOC) of Low Voltage
Condition and instruct the System Operating Center (SOC) to
take corrective action to raise the Switchyard 230 KV Yellow
Bus voltage to 229.468 KV.
NOTE: Components which are out of service in this condition are
the Required Offsite Sources as specified in TS 3.8.1 and 3.8.2.
IF the 230 KV Switchyard voltage remains 227.468 KV for >
10 minutes, enter TS Condition 3.8.1.J or 3.8.2.A on ail three
units.
Verify the Underground Feeder path, through Transformer CT-
4; and both Standby Buses are operable.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provide BACKUP POWER from bee Steam
Station per OP/O/NI 107/003 (100 KV Power Supply).
0
Note: If asked, Unit 2 will perform this procedure.
Notify Unit 2 and 3 Control Room personnel of the impending
conditions.
Refer to AQ/1/N1700/034 (Degraded Grid).
e
NUREG-1021, Draft Revision 9
Page 6 of 14
~
~
~ _ _ _ _ _ _ _
~
Appendix D
Scenario Outline
Form ES-8-2 -
Op-Test No.: __ Scenario No.: 3_
Event No.:
Page 2 of 2
Event Describtion: TCC notifies crew of grid disturbance: (C, BOP)
_I_g
Time
Position
SROBOP
Applicant's Actions or Behavior
~
-
SRO should direct AP/M which will:
e
e
a
Notify the O§M and STA.
Verify Unit 2 is performing AP134.
Verify generator output within limits of the appropriate capability
curve based on generator voltage.
Note: Generator voltage will be = 19 KV and enclosure 5.1
should be used.
SRO should direct the BOP to vsrify generator output within limits
of enclosure 5.1 (Capability Curve).
The BOP should determine that the generator output is outside of
the limits of enclosure 5.1 and inform the SRO.
SRO should direct the BOP the adjust MVARs to maintain
generator output within limits of the capability curve.
The BOP should adjust MVARs using EXCITER VOLTAGE
ADJUSTER to maintain generator output within limits of the
appropriate capability curve.
m
When MVARS have been adjusted or when directed by the lead
examiner this event is completed.
___ l_l___
__ -- -- -- _ - _ _ - -
NUREG-1021, Draft Revision 9
Page 7 of 14
Form ES-D-1
__
Scenario Outline
.__.._
Appendix D
Qp-Test NO.: ~
Scenario No.: 4
Event No.: 6
Page 1 of 1
Event Description: "B" LPSW pump trips: (6,
ALL) (TS)
Time
Position
SRQ
Auolicant's Actions or Behavior
Plant response:
Statalarms:
Control board indications:
Crew response:
Refer to ARG for ISA-9/A-9, LPSW Header N B Press Low
Refer to AP/24 (Loss of LPSW) which will:
1SA-9/A-9, LPSW Header N B Press Low
"B" LPSW pump indicates tripped
Ensure LPSW pump suction valves are open:
Verify NO LPSW pumps are cavitating and GO TO Step 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.
NUREG-1021, Draft Revision 9
Page 8 of 14
Form ES-DIf
. .~
~~
Op-Test No.: ~
Scenario No.: 3 Event No.: 9
Page 1 of 1
Event Bescription: Unit Shutdown (R, QATCJ
Time -
-
Position
OATCiSRO
Applicant's Actions or Behavior
-
The OATC will use the FDVV Masters and the Diamond to reduce
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 9 of 14
Dp-Test NO.: __ Scenario No.: 3
Event No.: A
Page 1 of 3
Event Description: Large Break LOCA and Switchyard Isolation: (M, ALL)
_LI_ _-
Position
ALL
OATC
OATC
.
_
-
~
Applicants Actions or Behavior
Plant response:
Control board indications:
ES 1-6 actuate
e
A Switchyard Isolation will occur due to degraded system voltage
in conjunction with an ES signal.
RCS subcooling margin will indicate 0°F.
Power will be lost and then regained from Keowee #I via the
underground.
Crew response:
I, The OATC perform IMAs the OATC to perform a symptom check.
2. The BOP should report symptoms and inform the SRO that the
RCS has saturated and obtain SRO concurrence to perform Rule
2, Loss of SCM.
e
e . .
0
.
. .
Verify that reactor power is < 1%.
Trip KCPs within 2 rnin of LOSCM (CT-1)
Notify SRO of KCP status.
Verify any HPI pump is available.
Open IHP-24/25 (IN15 BWST Suction) open
Start all available HPI pumps operating.
Open 1HP-26/27 (?A/15 HP Injection) open
Verify at least two HPI pumps are operating using two diverse
indications. (Le. pump amps and flow)
IAAT HPI flow in any header is in the Unacceptable Region of
Figure 1
THEN perform Steps 10 -12. (flow is acceptable)
Thronle B
HPI flow to e 475 gpm.
IAAT either of the following exist:
> LPI FLOW TRAIN A plus LPI FLOW TRAIN B 2 3300
GPM (LPI flow will be met)
> Only one LPI header operating, AND flow in that header is
2 2850 gpm. GO TO Step 14.
WHEN directed by the CR SRO
THEN EXIT this rule.
3. OATC will perform Enclosure 5.1 (ES actuation) (CT-40)
NUREG-1 021, Draft Revision 9
Page 10 of 14
Position
Op-Test No.:
~
Scenario No.: 3- Event No.: 8
Page 2 of 3
Event Description: barge Break LOCA and Switchyard Isolation: (M,
ALL)
Applicant3 Actions or Behavior
4. The SRO should refer to the Parallel Actions and transfer to the
LOSCM tab.
5. The LOSCM tab will:
e
Refer to Parallel Actions and:
> Direct an RO to Initiate APllI (Rwvety from LOSS of
Power)
Note: AWl1 can not be implemented until an RO completes
either Rule 2 or Enclosure 5.2.
B Direct an RO to announce plant conditions,
e
Ensure Rule 2 (Loss of SCM) is in progress or complete.
Verify Station ASW feeding any SG.
lAAT either of the following exists:
L LPI FLOW TRAIN A plus LPI FLOW TRAIN 3 = 3300
gpm
B Only one LPI header in operation with header flow =
2850 gpm
THEN GO TO LOCA CD tab.
The LOCA CB tab will:
e
IAAT BWST level is = 19',
THEN initiate Encl 5.12 (ECCS Suction Swap to RBES).
Verify E§ actuated.
e
Perform the following:
'i. Ensure all RBCUs in low speed.
2. Open ILPSW-18.
ii Open ILPSW-21.
ii Open ILQSW-24.
B Close ILPSW-565.
I
When the SRO transfers to LOCA CD tab or when directed by
the lead examiner this event is concluded.
NUREG-1 021, Draft Revision 9
Page 1 I of 14
~~
Form ES-D-1
Op-Test No.: -
Scenario No.: 3 Event No.: 9
Page 1 of 2
Event Description: Keowee 1 and CT-1 lockout (blackout):
._.__
Time
I
Position
OATC
Auolicant's Actions or Behavior
When directed by the Lead Examiner Keowee I
will trip and CT-
1 will lock out.
Plant response:
Crew response:
The SRO will transfer to the Blackout tab which will:
Loss of power to the Main Feeder Buses (Blackout) will occur.
The unit will remain in a Blackout condition until actions are taken
by the operators per Enclosure 5.38 (Restoration Of Power).
The TD EFDW pump will be feeding the SG to remove decay heat.
Verify two ROs available to perform Control Room actions.
~ .~..
... . ..
....
NOTE
During performance of Encl5.38 (Restoration of Power),
progression . .. through the Blackout
. . . ~ ~ ~ ~
tab should continue.
~.
. . . .
..
Notify one 86 to perform Encl 5.38 (Restoration of Power).
IAAT power is restored to any of the following:
> ITC
> ITD
> ITE
THEN GO TO Step 4.
Verify any SG is being fed
Feed and steam available SGs as necessary to stabilize RCS
P/T.
IAAT NO SGs are being fed
AND any source of EFDW (Unit 1 or another unit) becomes
available,
GO TO Step 42.
IAAT EFDW from any source is insufficient to maintain stable
RCS PTT,
THEN notify SSF operator that feeding SGs with SSF ASW is
required
Verify Encl 5.38 (Restoration of Power) in progress or
complete.
THEN perform Steps 9 - 11.
NUREG-1021, Draft Revision 9
Page 12 of 44
Op-Test No.: -
Scenario No.: 3 Event No.: 9
Event Description: Keowee 1 and CT-1 lockout (blackout):
Time
Position
Page 2 of 2
Applicant's Actions or Behavior
-.
The BOP will perform Encl 5.38 (Restoration of Power) which will:
Place 1 HP-31 in HAND and reduce demand to 0.
Close I
HP-21.
Verify either MFB energized (MFBs are de-energized)
Verify CT-1 indicates 4160 volts. (CT-1 has no voltage)
Verify both Standby Bus # I and Standby Bus #2 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
Oconee 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-I 021, Draft Revision 9
Page 13 of 14
..
~~~~~
~
.~
~
Appendix D
Scenario Outline
Form ES-D-i
~
~~
CRITICAL TASKS
1. (7-27, Implementation of Control Room Habitability Guidance
2. (3-8, Electrical power alignment
NUREG-I 021, Draft Revision 9
Page 14 of 14
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...
Scenario Outline
Form ES-D-1
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..~..
Appendix D
-.
Facility: Oconee
Scenario No.: 4 RO
Op-Test NO.: 1
Examiners:
Operators:
Initial Conditions:
100% Reactor Power (Snap 204)
Turnover:
AMSAClBSS bypassed for I&E testing
LDST pressure is LOW
Unit 1 TDEFDWP has been out of service for bearing replacement for about 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />
Expect it to be returned to service within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Event
NO.
Oa
I_.I_
Ob
oc
1
2
4 -
__
4
5
6
7
8
3
10 -
. -
t
Pre-insert
MSS330
Pre-insert
MSS2BO
..
I
MSSOIO
MSS020
-==.=-
(N)ormal, (R)eadivity, (I)nstrument,
( 8
Event
Description
AMSACIDSS bypassed
TDEFWP fails to start
.
~ -.
....
.
1A MDEFBWP fails to start
Pressurize LDST with H2
1 H-I
~ LDST Supply, fails open (TS)
1A CC Pump trips (I
B CC Pump fails to auto
start)
Th Fails HIGH (TS)
1 D1 Heater Drain Pump oil leak
Manual reactor power decrease
Loss of Main Feedwater
-. .......
...... .-
....
......
Loss ot Main and Emergency Feedwater, 1 U
MDEFDWP trips (CBP Feed) ....
..... .-
.
......
TDEFWP returned (CBP recovery)
)omponent, (M)ajor
NUREG-1 021, Draft Revision 9
Page 1 of 18
.......................
Aooendix D
Ooerator Actions
Form ES-D-2
Op-Test No.: -
Scenario No.: 4
Event No.: 1
Page 1 of 1
Event Description:
Pressurize the LDST with H2: (N, BOP)
Time -
-
Position
Applicant's Actions or Behavior
Plant response:
1SA-02/D-2 (Approaching LDST Operating Limits) is in alarm
Crew response:
1. Refer to ARG
Add hydrogen to establish desired LDST pressure per
OP/1/A/1106/019 (Hydrogen System)
Refer to LDST Pressure vs. Level enclosure in
QP/Q/A/I 108/001 (Curves and General Information.
2. Direct the OATC to use 0P/1/N1106/019 (Hydrogen System) Encl.
3.5 (Unit 1 LDST H2 Addition) to add H2 to the LDST.
Review Limits and Precautions
0
Immediately prior to pressurization determine lowest reading of
diverse LDST level indications: -
inches.
For existing LDST level determine LDST Pressure allovmble
per LDST Pressure vs. Level curve: -
psig.
Notify Operator at H2 Cage to pressurize primary hydrogen.
.........
NOTE: Operator should be in constant communication with CR to
close I
H-26 if I
H-I fails open.
.........
0
Direct Operator to open 1 H-26 (LDST Block).
Cycle 1 H-I (LDST SUPPLY) as required to pressurize LDST
per LDST Pressure vs Level curve.
WHEN complete, ensure closed 1 H-I (LDST SUPPLY).
Note: 1H-l (LDST SUPPLY) will fail open.
When 1H-I (LDST SUPPLY) is opened this event is complete.
NUREG-1021, Draft Revision 9
Page 2 of 18
IH-I fails OPEN: (C, BOP) (TS)
Op-Test No.: -
Scenario No.: 4
Event No.: 2
Page 1 of 1
Event Description:
Op-Test No.: -
Scenario No.: 4
Event No.: 2
Page 1 of 1
Event Description:
Applicant's Actions or Behavior
Plant response:
1 H-I (LDST SUPPLY) will indicate open
LDST pressure will continue to increase
Crew Response:
0
Monitor LDST Pressure and 1H-I (LDST SUPPLY) indication
and determine that 1H-I (LDST SUPPLY) has failed open.
Direct Operator to close 1H-26 (LDST Block).
Ensure LDST pressure within LDST Pressure vs. Level curve.
Note: LDST pressure will NOT be within the LDST Pressure vs.
Level curve.
Refer to ARG for ISA-021D-2 (Approaching LDST Operating
Limits) actuates.
Determine that LBST pressure is not within LDST Pressure vs.
Level curve and declare BOTH trains of #PI inoperable. Direct
the OATC to take actions to reduce LDST pressure to within
the proper operating region of the LDST Pressure vs. Level
curve.
Vent LDST to GWD per OQ/1/A/1104/002 (HPI System).
Note: The crew will not have time to vent the LDST.
8
SRO should refer to TS 3.5.2 (HPI) and determine that
Condition H is met. The required action is to enter LCO 3.0.3
immediately.
When the SRO has declared BOTH trains of HPI inoperable or
when directed by the lead examiner this event is complete.
NUREG-1021, Draft Revision 9
Page 3 of 18
..
Op-Test No.: -
Scenario No.: 4
Event No.: 3
Event Description:
Position
Page 1 of 3
Asolicant's Actions or Behavior
Plant response:
1. Statalarms:
1 SA-SIB-1, CC CRD RETURN FLOW LOW
e
ISA-SIC-1, CC COMP COOLING RETURN FLOW LOW
1%-2/C-1, LETDOWN TEMPERATURE HIGH
2. Control Board indications:
IHP-5 (Letdown Isolation) will close due to high letdown
temperature
Crew Response:
1. Refer to ARGs
2. Initiate AP/020 (Less of Component Cooling)
IAAT both of the following are lest:
- r CCtoRCPs
2. RCP seal injection
THEN perform the following:
2. Trip RX
3 Step all RCPs
- r
Initiate API25 (SSF EOP)
MAT 2 two CRB stator temperatures 2 180°F.
THEN trip RX.
0
Open 166-7 and 1CC-8
c
Verify CC Surge Tank level 5 12".
Manually start the Standby CC Pump
3. Verify CC TOTAL FLOW
575 gpm
4. Verify both of the following:
0
Letdown in service
LETDOWN TEMP 5 130°F
5. Step not met. Perform RNO, Initiate AP/032 (Loss of Letdown)
NUREG-1921, Draft Revision 9
Page 4 of 18
Scenario No.: 4
Event No.: 3
Page 2 of 3
Op-Test No.: -
Event Description:
y__I
Time
Position
OATC
Applicant's Actions or Behavior
Crew Response:
6. AP/032 (Loss of Letdown) will:
e
e
Initiate makeup to LDST with boron concentration RCS boron
Ensure 1 HP-120 in HAND and reduce demand to zero.
concentration as required.
Notify Chemistry of the following:
i, Current RCS boron sample is needed for possible unit
shutdown.
i. Normal letdown line is isolated.
IAAT Pzr level 5 260:
AND letdown CANNOT be established,
THEN initiate unit shutdown at )) 20%/min per AW29 (Rapid
Unit Shutdown).
IAAT Pzr level 5 375".
THEN trip Rx.
Verify CC system in operation.
Position the standby HPI pump switch to OFF.
Throttle IHP-31 to establish 12 - 15 gpm SEAL INLET HDR
FLOW.
Verify loss of letdown is NOT due to letdown valve or interlock
failure and then GO TO Step 4.29.
WHEN letdown can be re-established,
THEN ensure proper operation of the CC System.
Close 1 HP-6 and 1 HP-7
Ensure the following are open:
0
0
0
e
e
3 IHP-I
i, IHP-2
> IHP-3
i, IHP-4
NUREG-1021, Draft Revision 9
Page 5 of 18
Op-Test No.: -
Scenario No.: 4
Event No.: 3
Page 3 of 3
Event Description:
Time
= Position
Applicant's Actions or Behavior
Crew Response:
.
e
e
e
0
0 .
0 .
0
0 . .
Verify letdown temperature < 135°F (it is not)
Open 1HP-13.
Ensure the following are closed:
i, IHP-8
2. IHP-9&11
Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
Open 1 HP-5.
Throttle open 1HP-7 to establish )) 20 gpm.
WHEN letdown temperature < 13O"F,
THEN WWI~T
LETDOWN HI TEMP INTLK BYP switch in
NORMAL.
Open 1 HP-6.
Adjust IHP-7 to control desired (70 gpm) letdown flow.
Re-establish normal makeup through IHP-220.
Verify SEAL INLET HDR FLOW 12 - 15 gpm.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
This event is complete when Seal Flow is returned to normal (32
gpm) or when directed by the lead examiner.
NUREG-1021, Draft Revision 9
Page 6 of 18
~
.
.
op-Test No.: -
Scenario No.: 4
Event No.: 4
Page 1 of 1
Event Description:
Tht fails HIGH: (I, OATC) (TS)
Time -
Position
OATC
Applicant's Actions or Behavior
Plant response:
Loop A Thot Dixson meter reading goes to 620'F
Thot recorder
Tave recorder and digital meter increases to 2583°F
Loop A Delta T meter increases to -65°F
Loop A Tave meter increases to 0588'F
Statalarm ISA-ZYB-3, RC Hot Leg Temp High, alarms
0
Crew response:
The crew should use Plant Transient Response to stabilize the
unit. Reactor Diamond and the FDW Master should be taken to
manual to stabilize the plant.
Depending on when ICs is taken to manual, FDW flow may be
greater than 100%. If this is true, taking ICs to hand will allow NI
Power to begin to increase to match FDW flow. When this occurs,
the OATC will be required to decrease FDW flows to stop the power
increase.
SRO should refer to AW28 (ICs Instrument Failures) and TS 3.3.1
RPS Instrumentation.
When the ICs has been taken to manual and the plant is stable or
when directed by the lead examiner this event Is complete.
NUREG-1821, Draft Revision 9
Page 7 Qf 18
Bp-Test No.: __ Scenario No.: 4
Event No.: 5
Page 1 of 1
Event Description:
ID1 Heater Drain Pump oil leak: (C, All)
Position
Applicants Actions or Behavior
When directed by the Lead Examiner an NE0 will inform the
control room that the ID1 HDP has a severe oil leak.
Crew Response:
E
Refer to OPIIINI 106/02B, (Shutdown of the 1 D1 HDP)
SRB should determine that reducing power to 8?% is required
and direct unit shutdown in accordance with one of the following:
F APE9 (Rapid Unit Shutdown)
> OQ/l/Nl102/004
(Operation At Power)
Note: A manual shutdown is required because the IGS is in
manual due to the previous Thot failure.
Event is complete when a unit shutdown is directed by the SRO
or when directed by the Lead Examiner.
NUREG-2022, Draft Revision 9
Page 8 of 18
Scenario No.: 4
Event No.: 6
Page 1 of 1
Manual reactor power decrease: (R, OATC)
Event Description:
Time
Position
Applicant's Actions or Behavior
Crew Response:
1. SRO will direct the unit shutdown and continue in the APQ9 (Rapid
Unit Shutdown) or OPI1/A/1102/004
(Operation At Power).
2. OATC will reduce FDW flow with the FDW Masters and insert the
control rods manually to reduce reactor power.
I
I
Event is complete when reactor power has been reduced 5% or
I when directed by the lead examiner.
I
NUREG-1021, Draft Revision 9
Page 9 of 18
I
I
Op-Test No.: -
Scenario No.: 4
Event No.: 7
Page 1 of 2
Event Description: Turbine Trip, ATWS: (C, OATC)
._
.~~...
ize that the Reactor should have tripped and begin
I
!
0
Depress REACTOR TRIP pushbutton
Verify reactor power < 5% FP and decreasing
The OATC should recognize that Power Range Nls are not < 5%
FP and perform Rule 1. (CT-24)
Verify that at least one Power Range NI is r5% FP.
Initiate manual control rod insertion to the IN LIMIT.
Open 1 HP-24 & 1 HP-25 (IA and 1 B BWST Suction)
Ensure 1A or I B HPIP is operating.
Start I C HPIP.
0
Open 1 HP-26 & 1 WP-27 ( I A and 1 B HP Injection)
Dispatch operators to the Cable Room and to the 600V Load
Centers 1x9 and 2x1 to de-energize the CRD System.
Notify the SRO to GO TO UNPP tab.
i
Performs a Symptoms Check and then may adjust FDW to
match reactor power and maintain Tave near setpoint.
Transfer to the UNPP tab from IMAs and direct the following
actions:
0
Announce plant conditions
Verify Main FDW available.
IAAT a
power range Nls are 4%
FP, THEN trip the turbine-
generator.
Verify a wide range Nls 21 % FP.
Open 4 RC-4 and 1 HP-5
Ensure Rule 1 is in progress or complete.
Maximize letdown.
Verify Main FDW available.
NUREG-1021, Draft Revision 9
Page 10 of 18
Op-Test No.: -
Scenario No.: 4
Event No.: 7
Event Description: Turbine Trip, ATWS: (C, OATC)
Page 2 of 2
Time
. . . .. -
Position
SRQ
..
0
0
w
0
.
ADDlicant's Actions or Behavior
Adjust Main FDW flow as necessary to control RCS
temperature.
Verify overcooling NOT in progress.
Secure makeup to the LDST.
WHEN
in this tab.
Adjust SG pressure as necessary to stabilize RCS temperature
using TBVs.
Throttle HPI per Rule 6 (HPI).
Adjust letdown flow as desired.
Verify RCP seal injection available.
60 TO Subsequent Actions tab.
Nls are 4
% FP, AND decreasing, THEN continue
._~.__
..
. . .-
This event is complete when the SRB transfers Subsequent
Actions tab or when directed by the lead examiner.
....
NUREG-Z022, Draft Revision 9
Page 11 of 18
Scenario No.: 4
Event No.: 8
Page 1 of2
3p-Test No.: -
Event Description:
Time
. .-
Position
Loss of Main Feedwater: (C, ALL)
.. -
-
~ ..
..~...
Applicants Actions or Behavior
-. .
. . ..
When directed by the Lead Examiner BOTH Main FDW pumps will
trip.
Plant response:
K MDEFDW Pump will not start
B MDEFDW Pump will start
No EFW flow the A SG and level will decrease to
15 XSUR
Crew response:
SRO will direct the OATC to perform Immediate Manual actions and
the BOP to perform a Symptom Check.
SRO should transfer Subsequent Actions after IMAs are complete.
Subsequent Actions will:
Verify all control rods fully inserted.
Verify Main FDW in operation and controlling properly
i. No Main FBW pumps are operating. Perform RNO. Ensure
Rule 3 (boss of Main or Emergency FDW) in progress or
complete.
Verify 1 RIA-40 operable.
-
Verify TBVs controlling SG pressure = 1010 psig.
Dispatch an operator with Encl 5.29 (MSRV Locations) to verify
all MSRVs have reseated.
Verify ES is NOT required and initiate Encl 5.5 (Pzr and LDST
Level Control).
Open PCB 20 and PCB 21
Open Generator Field Breaker and Exciter Field Breaker
Verify A5 and TB Instrument Air pressure 2 90 psig.
Verify ICS/NNI power available.
Verify all 4160V switchgear (ITC, ITB, ITE) energized.
Verify both SGs > 550 psig.
0
NUREG-1021, Draft Revision 9
Page 12 of 18
Op-Test No.: -
Scenario No.: 4
Event No.: 8
Page 2 of 2
Event Description:
Lose of Main Feedwater: (C, ALL)
Time
~
Position
-
O A K
......
Applicant's Actions or Behavior
....-~
.
. . . .~..
...~
Verify Main FBW operating.
> No Main FDW pumps operating perform RNO Ensure Rule 3
(Loss of Main or Emergency FDW) in progress or complete.
Ensure SG levels approaching proper setpoint. (Rule 7)
Verify &I SCMs > 0°F.
Note: There will be not feed to the "A" SG at this time.
This event ';;'complete
whenSCM has been verified'>-O"F or
when directed by the lead examiner.
NUREG-1021, Draft Revision 9
Page 13 of 18
rr__y___
3p-Test No.: -
Scenario No.: 4
Event No.: 9
Page 1 of 3
Event Description:
Loss of Main and Emergency Feedwater, 1B MDEFDWP trips
(CBP Feed): (M, ALL)
_____
Time
Position
OATC
Applicant's Actions or Behavior
M e n directed by the Lead Examiner 1B MDEFDW pump will trip.
Plant response:
RCS temperature and pressure will increase
Crew response:
The SRO should direct the O A K and the BOP to pel .-rm a
symptom check.
The OATC should determine no Main or Emergency Feedwater
is feeding the SGs and with SRO concurrence re-start RULE 3
(Loss of Main and Emergency Feedwater).
WLE 3 (Loss of Main and Emergency Feedwater) will:
IAAT NO SGs can be fed with FBW (Mainihergency),
AND any of the following conditions exists:
RCS pressure reaches 2300 psig OR NBT limit
Pzr level reaches 375 [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling)
Ensure any EFBWP operating.
RNO step, GO TO Step 4.
Verify Main FDW NOT operating.
Place the following in MANUAL and close:
> IFDW-315 (IA EFDW Control)
'i- 1 FDW-316 (1 B EFDW Control)
NUREG-1021, Draft Revision 9
Page 14 of 18
Scenario No.: 4
Event No.: 9
Page 2 of 3
Op-Test No.: -
Event Description:
Time -
Position
OATC
Loss of Main and Emergency Feedwater, 18 MDEFDWP trips
(CBP Feed): (M, ALL)
Applicant's Actions or Behavior
Verify all the following available:
> AnyCBP
'i. TBVs
Disable both Digital Channels 1&2 of AFlS on both headers A
and 0:
'i. A Header DIG. CH. 1 and 2 OFF
P B Header DIG. CH. 1 and 2 OFF
Place Startup Block valve control switch for IFDW-34 (IA SG)
Position Startup Control valve 10 - 20% open on all available
SGs: 1 FDW-35 on 1 A SG and 1 FDW-44 on 1 B SG.
0
Close the following:
> IFDW-32 (IA Main FDW Control)
> 1FDW-41 (18 Main FDW Control)
> IFBW-31 ( l A Main FDW Block)
k 1 FDW-40 (1 3 Main FDW Block)
Lower SG pressure in available SGs to = 500 psig
Control FDW flow to stabilize RCS P/T by throttling the
following as necessary: (CT-26)
k Startup Control valves
'i. TBVS
Notify CR SRO that CBP feed is in progress.
Dispatch an operator to perform End 5.26 (Manual Start of
TDEFDWP).
NUREG-IQ21, Draft Revision 9
Page 15 of 18
Position
Op-Test NO.: -
Event Description:
Scenario No.: 4
Event No.: 9
Page 3 of 3
Loss of Main and Emergency Feedwater, 1B MDEFDWP trips
(CBP Feed): (M, ALL)
Awlicant's Actions or Behavior
SRO should transfer to the "boss of Heat Transfer" (LOHT) tab
of the EOP.
The LOHT tab will:
e
Ensure Rule 3 (Loss of Main or Emergency FDW) is in
progress or complete.
IAAT core SCM = O T ,
THEN GO TO Step 4.
IAAT NO SGs can be fed with FDW (MainEmergency),
AND any of the following conditions exists:
ii RCS pressure reaches 2300 psig OR NDT limit
ii Pzr level reaches 375" [34Q acc]
THEN GO TO Step 4.
Perform RNO step:
.~.~~..
I NOTE: 1Al RCP provides
- ~ .
-. . ..
. . . . .
the best Pzr spray.
Reduce operating RCPs to one pumpiloop.
WHEN any of the following conditions exists:
2;- Unit 1 EFDW available
2'
EFDW aligned from another unit
2'
Main FDW pump available AND reset
THEN GO TO Step 53
Note: The SRO should wait at this WHEN step until a Feedwater
source is aligned or conditions are met to go into Forced HPI
Cooling.
~.
This event is-complete when CBP f h w has been established and
the plant is stable or when directed by the lead examiner.
NUREG-1021 Draft Revision 9
Page 16 of 18
Scenario No.: 4
Event No.: 10
Page 1 of 1
Op-Test No: -
Position
Event Description:
TDEFDWP returned (CBP feed recovery)
Applicant's Actions or Behavior
...
Note: When directed by the lead examiner SPOC will call the
control room and inform them that the TDEFDWP has been
repaired and can be used.
The SRO should transfer to Step 53.
Verify MFDW or Unit 1 EFDW available.
Verify Encl 5.27 (Alternate Methods For Controlling EFDW
Flow) is NOT in progress.
Verify Main FBW pump available and reset. (FDW pumps are
not reset) Perform RNO
0
GOTOStep56
Verify Main FBW pump available and reset. (it is not)
Verify one of the following:
> Both MDEFBWPs operating
fi TDEFDWP operating
Verify all the following:
> Tcold
500°F
fi TBVs available
Verify Tcold 5 547°F.
fi Perform RNO step:
Ensure THP setpoint at ~ 8 8 5
psig.
GO TO Step 66.
Ensure TBVs in AUTO for available SGs.
Initiate feed to available SGs per Rule 7 (SG Feed Control)
IAAT heat transfer is established in any SG,
THEN GO TO Step 79.
Control feeding and steaming of available SGs to maintain SG
level at setpoint and cooldown rate within Tech Spec limits:
e
(CT-26)
Tcold > 280°F:
5 50°F / % hr
This event and the exam is complete when TDEFDWP flow to the
SGs have been established and the plant is stable or when
directed by the lead examiner.
NUREG-1021, Draft Revision 9
Page 170f 18
CRITICAL TASKS
1. CT-24, Shutdown Reactor - ATWS
2. CT-26, Restore Feed To A Dry SG
NUREG-?021, Draft Revision 9
Page 18 of 18
SCENERIO ATTRIBUTES
_I__.
. . .
~
.
Malfunctions after EO$ (1 -2)
Abnormal Events (2-4)
-
Major Transients (1-2)
I I
1
EOPs Entered (1-2)
EOP Contingencies (0-2)
Critical Tasks (2-3)
. ._
._
..~
........
~..
CRITICAL TASKS
Scenario 1 :
1. CT-18, Turbine Trip
2. CT-1, Trip All RCPs
3. CT-IO, Establish FW Flow and Feed SGs
4. CT-27, Implementation of Control Room Habitability Guidance
Scenario 2:
1. CT-I 7, Isolate Overcooling SG
2. CT-I 1, Control SG pressure to Maintain RC Temperature Constant.
3. CT-7, Minimize SCM
4. CT-27, Implementation of Control Room Habitability Guidance
Scenario 3:
1 . CT-1 I Trip All RCPs
2. CT-27, Implementation of Control Room Habitability Guidance
3. CT-8, Electrical power aiignment
Scenario 4:
1. CT-24, Shutdown Reactor - ATWS
2. CT-26, Restore Feed T A Dry SG (intact or trickle feed)
..........
. ~ ~ .
....
~.
~
Form ES-B-I
.......
..........
.....
.....
..-.
Scenario Outline
Appendix D
Facility: Oconee
Scenario No.: 1 RQ
Op-Test NO.: -
Examiners:
Operators:
Initial Conditions:
Turnover:
a
45% Reactor Power
Startup in progress after adding oil to 1B1 RCP
I A Main FDW pump operating
SASS in MANUAL for I&E troubleshooting
1 B MDEFDW Pump OOS
After turnover. the crew should start 1 B1 RCP
Pre-Insert
MSS270
I
.....
-. .
I
Oc
Pre-Insert
MP1290
Pre-Insert
Od
I MPS350
5
I Override
I C.ALL
6
I MPS110
I R. O A K . SRO
8
I MPS400
I M A L L
(N)ormal, (R)eactivity,
(I)nstrument, (
Event
Description
SASS in manual
1 B MBEFDW Pump OOS
......
..............
............
MOCK All Turbine Trips Except Manual
"A RBCU fails to receive ES signal
Start 481 RCP
AC Oil Lift pump will not develop adequate
discharge pressure
I A HPI pump sheared shaft, (TS)
Standby HPI Pump fails to start
Re: Loop B Flow fails LOW
BWST rueture (TS)
Manual unit shutdown due to BWST level
1A Main FDW pump trips
Main Turbine Fails to trip (Lockout EHC Pumps)
RCS leak to SBLOCA ( r a m over 10 minutes)
"IC" HPI pump trips requiring rapid RCS C/D due
to degraded HPI
omponent, (M)ajor
NUREG-1021, Draft Revision 9
Page 1 of 76
Scenario #I
Overview RQ
Initial Conditions: Unit 1: 45% power - EOL, Unit 2: loo%, Unit 3: 100%
Turnover:
e
Startup in progress after adding oil to 1 B1 RCP
l A Main FDW pump operating
SASS in MANUAL for I&E troubleshooting
1 B MDEFDW Pump 00s
After turnover, the crew should start 1 B1 RCP
E
1) Start 1B1 RCP: (N, BOP)
a) Reactor power was reduced so oil could be added to the 1 E37 RCP. The oil
addition has been completed and the crew is directed to start the 1B1 RCP per
OPI11BIZ 103/006.
TIME = 5 minutes
2) 1B1 RCP AC Oil Lift pump will not develop adequate discharge pressure:
a) Prior to starting the l B 1 RCP, the RCP AC Oil Lift pump will be started. The
OAC should be monitored and the RCP started after the low oil pressure alarm
clears. The low pressure condition will not clear and the AC Oil Lift pump will stop
after three minutes. The operator should follow procedural guidance and use the
DC Oil Lift pump and complete starting the 1 B4 RCP.
(C, BOP)
TIME = 5 minutes, TOTAL 10 min.
3) A HPl Pump sheared shaft and the standby HPI pump fails to auto start: (C,
BOP) (TS)
a) The 1A HPI Pump shaft will shear. This will cause low RCP seal injection flow
and the standby HPI pump will not auto start. This will require entry into APl014
(Loss of Normal MIU andlor RCP SI). The standby HPI will be started and RCP
seal injection re-established.
b) The SRO should refer to Tech Spec 3.5.2 (High Pressure Injection) for the failed
HPI pump.
TIME = 15 minutes. TOTAL 25 min.
4) RC Loop B Flow fails LOW: (II O A K )
a) The failure will cause Main FDW to re-ratio. The crew should utilize Piant
Transient Response and take the Diamond and BOTH FDW Masters to MANUAL
to stabilize the plant.
b) The SRO should refer to APE8 (16s Instrument Failures).
TIME = 5 minutes, TOTAL 30 min.
Scenario #I
Overview RO
5) BWST rupture: (C, ALL) (TS)
a) A crane will damage the BWST resulting in level rapidly decreasing to =24 feet.
b) The SRO shouid refer to TS 3.5.4 and determine that a unit shutdown is
TIME = 10 minutes, TOTAL 40 min.
required.
6) Manuas unit shutdown: (R, QATC)
a) The ICS will be in manual because of a previous instrument failure. FDW and
TIME = 10 minutes. TOTAL 50 min.
Control Rods will be controlled to manually shutdown the unit.
7) I A Main FDW pumps trip and Main Turbine Fails to trip (Lockout EHC Pumps):
(C, QATC)
a) 1A Main FDW pump wili trip resulting in a reactor trip. The Main Turbine should
trip but does not. This will result in a reduction in steam pressure in both SGs
until actions are taken to trip the turbine. The will result in RCS overcooling until
the Main Turbine is tripped.
and then perform the RNO step which will stop both EHC pumps. This will cause
the turbine to trip.
b) Whiie performing IMAs, the OATC should diagnose that the turbine did not trip
TIME = 1 minutes, TOTAL 51 min.
E) RCS leak to SBLQCA (ramp over 10 minutes): (M, ALL)
a) The WCS leak will require entry into APl2 (Excessive RCS Leakage). The leak
will increase causing a loss of SCM.
b) RULE 2 (Loss of SCM) will be implemented and the SRO will transfer to the boss
of Subcooling Margin (LOSCM) tab of the EOP. The SRO wili then transfer to
the LOCA Cooldown (LOCA CD) tab of the EOP.
c) EOP Enclosure 5.1 (E§ Actuation) will be implemented. The " A RBCU will not
receive an ES signal and wil& not go bo LOW speed. The RO shouid diagnose this
and place the "A RBCU in LOW speed.
TIME = 20 minutes, TOTAL 71 min.
9) V C " HPI pump trips requiring rapid RCS CID due to degraded HPI :
a) When the RCS saturates the I C HPI pump will trip. This will require a rapid RCS
TIME = 10 minutes. TQTAL 81 min.
CID.
Page 2 of 2
Facility: Oconee
Scenario No.: 2 RO
Op-Test No.: 1
Examiners:
Operators:
lnitial Conditions:
Turnover:
0
0
35% Reactor Power, startup in progress (IC-45)
AMSAC/BSS bypassed for I&E testing
NI-9 OOS, to he replaced next outage
"A" AFIS circuit 00s
"A" Condensate Booster Pump OOS, breaker to be replaced
Keowee Unit 2 00s for unplanned reasons
Keowee Unit I aligned to underground
Operability test of Keowee Unit 1 is to be performed per PT/620/00
Operation) after turnover and before startup continues, ON§ to per
Keowee start
~
Event
No.
Oa -
-
Ob
oc
Od
Oe
1
2
3
4 -
5
6
7 -
8
- N)orm
E__
. . . . . . . . . . . . . . . . . . . . .
,
Maifunctior?
No.
Pre-inseit
Pre-Insert
MN1082
Re-Insert
Pre-Insert
MELI80
Pre-Insert
Override
MPSO9C
MN1032
Override
MPSO20
MSS360.50
(R)eactivi
(Keowee Hydro
.m remote
" A AFIS circuit disabled
I ES channels 7 and 8 fail to actuate
C. OATC. §RO I 1 HP-I20 (RC Volume Control) fails closed
Controlling NI fails LOW (TS)
I
Seismic event (PBA)
, (I)nstrument, (C)ornponent, (M)ajor
NUREG-1021, Draft Revision 9
Page 1 of 10
Scenario #2 Overview
Initial Conditions: Unit 1: 35% power - 430 EFPD, Unit 2: 100%. Unit 3: 100%
Turnover:
e
Unit 1 TD EFDW Pump 00s to repair oil leak
e AMSAC/DSS bypassed for l&E testing
NI-9 OQS, to be replaced next outage
"A" AFlS circuit 00s
"K Condensate Booster Pump QOS, breaker to be replaced
0
Keowee Unit 2 OQS for unplanned reasons
Keowee Unit 1 aligned to underground
Operability test of Keowee Unit 1 is to be pesformed per PT/620/089 (Keowee
Hydro Operation) after turnover and before startup continues, ONS to perform
remote Keowee start
I) Operability test Keowee Unit 1 with failure of Gen Field Flashing Breaker:
a) Keowee Unit 1 will be started from the control room as part of the operability test.
TIME = 10 minutes
2) Operability test Keowee Unit 1 with failure of Gen Field Flashing Breaker:
a) During startup the Gen Field Flashing Breaker fails to open automatically. This
should be recognized and the breaker should be opened manually. This does not
make the Keowee unit inoperable.
TIME = 5 minutes. TOTAL 15
3) lHP-120 (RC Volume Control) Fails CLOSED: (C, OATC)
a) I
HP-428 (RC Volume Control) Fails CLOSED due to a ruptured diaphragm. This
should be diagnosed and AQI14, Loss of Normal HPI Makeup and/or RCP Seal
Injection, should be followed. The AP will give guidance on maintaining PZR
level and instruct the crew to call SPOC to repair the valve. 1 HP-I 20 (RC
Volume Control) will remain broken for the remainder of the scenario.
NOTE: Events 1 and 2 will occur at about the same time.
TIME = 10 minutes, TOTAL 25 min.
4) Controlling NI fails LOW: (I, QATC)
a) The crew should utilize the "plant stabilization process" to stabilize the plant and
recognize that the contreliing NI has failed. The ICs will be placed in manual to
stabilize the unit. The 16s will remain in manual for the remainder ofthe
scenario.
TIME = 5 minutes. TOTAL 30 min.
Page 1 of2
Scenario #2 Overview
5) Seismic event (PRA) and 1A RBCU rupture: (C, BOP) (TS)
a) A seismic event will occur which will cause the 1A RBCU to rupture. AP15,
Earthquake, will be entered. RBCU rupture should be diagnosed and
subsequently isolated to prevent diluting the RB sump.
TIME = 5 minutes. TOTAL 35 rnin.
6) 1B SG Tube leak (50 gpm): (C, ALL) (TS)
a) The seismic event will also cause a 50 gpm tube leak in the 1 B Steam
Generator. The team may enter AP131 Primary to Secondary Leakage. After
determining the leak is greater than 25 gpm the Sa0 will transfer to the Steam
Generator Tube Rupture tab of the EOP. This tab will direct a unit shutdown.
TIME = 20 minutes. TOTAL 55 min.
7) Unit Shutdown: (R, OATC)
a) As a result of the previous instrument failure the unit shutdown will be conducted
with the ICs in manual. If the crew did not return 1HP-120 (RC Volume Control)
to auto, primary inventory will also require manual control during the shutdown.
TIME = 5 minutes, TOTAL 60 min.
8) 1A Main Steam line break in RB: (M, ALL)
a) A main steam line break will occur in the 1A main steam line. This will require
the use of RULE 5, Main Steam Line Break to isolate the leak. RULE 2, boss of
SCM will be required if the RCS saturates. The CRSRO will transfer to the
Excessive Heat Transfer tab of the EOP to ensure excessive heat transfer has
been stopped and the plant stabilized. Transfer will then be made back to the
Steam Generator Tube Rupture tab of the EOP. The scenario will be compkted
when the l A main steam line has been isolated and a transfer to the Steam
Generator Tube Rupture tab of the EOP aihs been made.
TIME = 15 minutes, TOTAL 75 rnin.
Page 2 of 2
~~
~~~~
~
~
~
~
~
~
~
~
~
~
~ ~ ~ . ~ . .
Appendix D
Scenario Outline
....... Form ES-D-1
Facility: Oconee
Scenario No.: 3 RO
Op-Best NO.: 1
Examiners:
Operators:
Initial Conditions:
Turnover:
0
0
100% Reactor Power (IC-41)
AMSAClDSS bypassed for I&E testing
SASS in MANUAL for I&E testing
Problems noted with 1B MFDWP control, after turnover place 1B MFDWP on
handjack
Event
Malfunction
NO. I
No.
Pre-l nsert
...........
2 l7EG--
Override
T
4
MCS004
5
1
6
I
Override
I
(N)ormal, (R)eactivii
Event Type* -
N. OATC. SRO
1. OAK. SRO
~.
~
~~
~
~~ .....................
C. ALL
R, OATC, SRO
M, ALL
(I)nstrument,
Event
Description
-
TDEFDWP fails to start
SASS in Manual
AMSAClDSS bypassed
Place 1B MFDWPT on Handiack
PZR Level # I Fails LOW (TS)
A LPSW pump suction valve closes and Standby
DumD does not auto start (TS)
Controlling Tave fails HIGH
TCC notifies crew of grid disturbance (Implement
APl34)
Manual plant shutdown
Large Break LOCA
Switchyard kolation
Keowee 1 lockout (blackout)
C)omponent, (M)ajor
NUREG-1021, Draft Revision 9
Page 1 of 10
Scenario #3 Overview
Initial Conditions: Unit I
- 100% power - 430 EFPD, Unit 2: ZOO%, Unit 3: 100%
Turnover:
0
AMSAC/DSS bypassed for I&E testing
0
SASS in MANUAL for I&E testing
0
Problems noted with 15 MFDWP control, after turnover place 1 E3 MFDWP on
handjack
1) Place 1 B MFDWPT on Handjack: (N, OATC)
a) 1E3 MFDWP hand/auto station will be planed in manual and then the pump will be
TIME = 10 minutes
placed on Handjack.
2) PZR Level #f 1 Fails LOW: (I, BOP)
a) 1 HP-120 opens and RCS makeup flow will increase. The crew should determine
b) The SRO should refer to PT/600/001 (Periodic Instrument Surveillance) SASS
that PZR level 1 has failed low and refer to ARGs.
Manual Operation and have the OATC select an alternate PZR level channel on
1UB1.
TIME = 10 minutes, TOTAL 20 min.
3) A LPSW pump suction valve closes and standby pump does not auto start:
(C, BOP) (TS)
a) The crew should refer to ARG and AP/24 (Lass of LPSW). AP124 will direct the
crew to stop the pump with the closed suction valve and start the standby LPSW
pump.
b) The SRO should refer to TS 3.7.7 (Low Pressure Service Water System).
TIME = 10 minutes, TOTAL 30 min.
4) Controlling Tave fails HIGH: (I, OATC)
a) The crew should utilize the plant stabilization process to stabilize the plant and
recognize that controlling Tave has failed. The IC§ will be placed in manual to
stabilize the unit. The BCS will remain in manual for the remainder of the
scenario.
TIME = 10 minutes, TOTAL 40 min.
Page 1 of 2
Scenario #3 Overview
5) TCC notifies crew of grid disturbance: (C, BOP)
a) The crew should implement AP/34 (Degraded Grid) and verify that the generator
is operating within the capability curve. MVAWs will require adjustment to meet
the capability curve.
TIME = 10 minutes. TOTAL 50 min.
6) B LPSW pump trips: (C, ALL) (TS):
a) After MVARs have been adjusted the B LPSW pump will trip. The crew should
restart AP124 (Loss of LPSW). APE4 will direct the crew to cross-tie Unit 182
LPSW to Unit 3. The SRO should determine that with only I LPSW pump
operable on Unit 1 & 2 entry into TS 3.0.3 and a unit shutdown is required.
TIME = 10 minutes, TOTAL 60 min.
7) Unit Shutdown: (R, QATC)
a) As a result of the previous instrument failure the unit shutdown will be conducted
with the ICs in manual. If the crew did not return IHP-I28 (RC Volume Control)
to auto, primary inventory will also require manual control during the shutdown.
TIME = 10 minutes. TOTAL 70 min.
8) Large Break LOCA and Switchyard Isolation: (M,
ALL)
a) A large break LOCA will occur. Due to the degraded switchyard volatage a
Switchyard Isolation will occure when ES actuates. The crew will enter the EOP.
Power will automatically return via Keowee 1 and CT-4. The SRO will utilize the
LOSCM and the LOCA CB tabs to mitigate the event.
TIME = 5 minutes, TOTAL 75 min.
9) Keowee 1 lockout (blackout):
a) After the SRO transfers to the LOCA CD tab, Keowee Unit 1 will Emergency
Lockout which results in a Unit Blackout. This will cause the SWO to transfer to
the Blackout tab of the EOP for guidance on manually restoring power to Unit 1s
Main Feeder Busses by swapping the Keowee underground feeder. The
scenario will be completed after power has been restored to the Main Feeder
Buses and APll1 has been restarted.
TIME = 20 minutes. TOTAL 85 min.
Page 2 of 2
~
..... ~ ~ ~ ~ . . .
.
. .~.
.....
._
Form ES-D-I
-.~~..
._
..~.
.. -
Scenario Outline
Appendix D
. .. .....
Facility: Oconee
Scenario No.: 4 RO
Op-Test No.: 1
Examiners:
Operators:
Initial Conditions:
Turnover:
LDST pressure is LOW
0
100% Reactor Power
AMSACIDSS bypassed for I&E testing
Unit 1 YDEFBWP has been out of service For bearing replacement for about 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />.
Expect it to be returned to service within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Event
1
Malf. No.
Pre-Insert
Pre-insert
MSS330
Re-insert
MSS260
Override
MPS290
Override
MP1171, 100
MP1500, 100
MSSCIO
MSS020
MSS270
MSS330
Reset
Event Type*
I, QATC, SRO
C, ALL
R, OATC, SRO
C, OATC, SRO
c, ALL
M, ALL -
(I)nstrument, (
Event
Description
AMSACIDSS bypassed
TBEFWP fails to start
IA MBEFDWP fails to start
__
Pressurize LDST with H2
1 H-I. LDST SUOO~V.
fails oDen (TS)
l A CC Pump trips (1 B CC Pump fails to auto
start)
Th Fails HIGH (TS)
1 B1 Heater Drain Pump oil leak
Manual reactor power decrease
Loss of Main Feedwater
Loss of Main and Emergency Feedwater, 1 B
MDEFDWP trips (CBP Feed)
TDEFWP returned (CBP recovery) -
omponent, (M)ajor
NUREG-2021, Draft Revision 9
Page 1 of 16
Scenario 4 Overview RO
Initial Conditions: Unit I:
100% power - EOL, Unit 2: ?OB%, Unit 3: 108%
Turnover:
- AMSAC/DSS bypassed for I&E testing
8
LDST pressure is LOW
8
Unit 1 TDEFDWP has been out of service for bearing replacement for about 16
hours. Expect it to be returned to service within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
1) Pressurize the LDST with H: (N, BOP)
Crew should refer to the LDST Pressure vs Level curve. The crew should then add
H2 to the LDST.
TIME = 10 minutes
2) 1 H-I fails OPEN: (C, BOP) (PS)
During the H2 addition to the LDST, 1 H-I (LDST Supply) will fail OPEN re9uiring the
OATC to direct the primary NEQ to close the isolation valve to stop the H addition.
Isolation by the NE0 will be delayed and BOTH trains of #PI must be declared
inoperable due to operation outside of permissible Operating Region on the LDST
Pressure vs Level curve.
TIME = 5 minutes, TOTAL 25 min
a) The crew should refer to ARG and to AP/020 (Loss of Component Cooling). The
b) The crew should initiate investigation and repair of I A CC pump and I B CC auto
TIME = 5 minutes. TOTAL 20 min.
OATC should manually start the standby CC pump.
start failure.
4) That fails HIGH: (I, OATC)
a) The crew should diagnose the failure and stabilize the plant by using the Plant
b) The OATC should place both FDW Masters and the Diamond Panel to manual to
c) This failure will not be repaired and the ICS will remain in manual.
d) The Si30 should refer to AW28 (ICs Instrument Failures).
TIME = 5 minutes, TOTAL 25 min
Transient Response process.
mitigate the transient and stabilize the plant.
5) lD1 Heater Drain Pump oil leak: (C, All)
a) The basement NE0 will notify the control room that the 1 D1 HDP has a severe
oil leak. Crew should refer to OP/1//1106/002D (Shutdown of the 4B1 HDP).
The SRO should direct the crew to reduce CTP to e 89% and secure the 1 BZ
HDP.
TIME = I O minutes. TOTAL 35 min.
Page I of 2
Scenario 4 Overview RQ
6) Manual reactor power decrease: (R, QATC)
a) The OATC should seduce power with the control rods and the FDW Masters in
TIME = 15 minutes. TOTAL 50 min.
manual.
7) Turbine Trip, ATWS: (C, QATC)
a) The turbine will trip but the reactor will not trip. The OATC will perform IMAs and
determine that the reactor has not tripped. The OATC will perform Ruie 1
(ATWSIUnanticipated Nuclear Power Production). The SRO will enter the EOP
and transfer to the UNPP tab.
TIME = 10 minutes. TOTAL 60 min.
8) Loss of Main Feedwater: (C, ALL)
a) After the reactor has been shutdown and the SRO transfers back to Subsequent
Actions both main FDW pumps will trip. Rule 3 (boss of Main or Emergency
Feedwater) should be implemented. The failure of la MDEFDWP should be
diagnosed and the 1B MDEFDWP should be aligned to feed both headers.
TIME = 10 minutes. TOTAL 70 min.
9) Loss of Main and Emergency Feedwater, 1B MDEFDWP trips (CBP Feed): (M,
ALL)
a) After flow has been estabiished through both headers the 1B MDEFDWP will trip
This results in a total loss of Main and Emergency Feedwater. The SRO should
transfer to the Loss of Heat Transfer (LOHT) tab of the EOP. The QATC should
feed the OTSGs using the CBPs per the guidance in Rule 3 (Loss of Main or
Emergency Feedwater).
TIME = 10 minutes, TOTAL 80 min.
1O)TDEFDWP returned (CBP feed recovery)
a) After the plant is stable, the crew will be notified that the TBEFBWP has been
repaired and is now available. The SRO will direct the crew to recover from CBP
feed by using the TBEFDWP to feed the SGs per EOP guidance. When the
TDEFBWP is feeding the SGs and the unit is stable the scenario may be
stopped.
TIME = 10 minutes, TOTAL 90 min.
Page 2 of 2