ML040490423
| ML040490423 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/17/2003 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| Shared Package | |
| ML040510003 | List: |
| References | |
| 50-269/03-302 50-269/03-302 | |
| Download: ML040490423 (29) | |
See also: IR 05000269/2003302
Text
Draft Submittal
OCONEE JUNE 2003 RETAKE
EXAM 50-269/2OO3-302
OCTOBER 17,2003
Appendix D Scenario Outline Form E§-D-1
Facility: O ~ Q ~ W Scenario No.: 1 fnl Op-Test No.: -
Examiners: Operators: Tracey Roland (SRQ-U)
Kevin COQhy (RO)
Initial Conditions:
50% Reactor Power, (Snap 201)
Turnover:
OP/I/A/l IOU004 (QPS At Power) Encl. 3.2 in progress at step 2.17. Holding per
dispatcher request.
SASS in MANUAL for !&E troubleshooting
1B MDEFDW Pump OOS for PMs, expected to be returned to sewice later this shift.
k TS 3.7.5Condition A
After turnover, perform the Unit 1 portion of PP/B/A/0.61O/017' (Operability Test of 4160 V
Breakers)
Oa I Pre-Insert 1 1 SASS in manual
Block All Turbine Trips Except Manual
Od I Pre-insert
Override I I "c" HPI pump fails to start
I Override 1 C,OAK, SRO
I '&A LPSW pump suction valve closes and Standby
DumD does not auto start (TS)
MP1050 I, OATC, SRO RC Loop B Flow fails LOW
I MPS400
Reset I RCS leak isolated, SCM increases > 0°F
(N)ormal, (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor
NUWEG-1021, Draft Revision 9 Page 1 of 13
Appendix D Operator Actions Form ES-D-2
Op-Test No.: Scenario No.: I Event No.: 1 Page I of 1
Event Description: Operability test of 4166)V breakers: (N, OATC)
Time Position Applicant's Actions or Behavior
Crew response:
The OATC should perform Step 12.1 of PT/Q/A/OGIO/CI17 (Operability Test
of 4160 V Breakers).
e Ptace Unit 4 MFB1 AUTOlMAN transfer switch to "MAN".
k lSA-14/8-1 (EL Normal to SU Transfer Bus 1 Automatic
Transfer Block) actuates
e Close E l MFBI STARTUP FDR.
k 'lSA-14/A-1 (EL I T Normal Supply Breaker Bus 1 Open)
actuates
k 'lSA-14/A-3 (EL CT1 4KV SU Feeder Bus 1 Closed) actuates
e Verify N l l MFBl NORMAL FDR opens, and electrical auxiliaries
transfer.
- Close Nfl MFB1 NORMAL FDR.
Verify E l MFBl STARTUP FDR breaker opens and electrical
auxiliaries transfer.
Place Unit 1 MFBl AUTOlMAN transfer switch to "AUTO".
Place Unit 1 MFB2 AUTOlMAN transfer switch to "MAN".
> 1SA-14/8-2 (EL Normal to SU Transfer Bus 2 Automatic
Transfer Block) actuates
e Close E& MFB2 STARTUP FBR.
k ISA-14/8-2 (EL 1T Normal Supply Breaker Bus 2 Open)
actuates
SZ ISA-14iA-4 (EL CT1 4KV SU Feeder Bus 2 Closed) actuates
e Verify N21 MFB2 NORMAL FDR breaker opens and electrical
auxiliaries transfer.
- Close N21 MFB2 NORMAL FBR.
e Verify E2, MFB2 STARTUP FDR breaker opens and electrical
auxiliaries transfer.
Place Unit 4 MFB2 AIBTOIMAN transfer switch to "AUTO".
When Step 12.1 is complete or when directed by the Lead Examiner
this event is completed.
NUREG-1Q21 Draft Revision 9
I Page 2 of 13
Op-Test No.: Scenario No.: 1 Event No.: 3 Page 1 of 1
Event Description: A LPSW pump suction valve closes and standby pump does not
Time Position Applicants Actions or Behavior
Plant response:
Statalarms:
1SA-9/A-9, LPSW Header AJB Press Low
Control board indications:
LPSW-2 fA LPSW Pump Suction) indicates closed (also an OAC
alarm)
A LPSW pump amps are cycling
Crew response:
1. Refer to ARG for 1SA-9/A-9, LPSW Header A/B Press bow
OATC
2. Refer to APE4 (boss Of LPSW)
Ensure LPSW pump suction valves are open.
Note: LPSW-2 ((IF? LPSW pump suction valve) will indicate closed. The
team may dispatch an NE0 to open LPSW-2. The valve will not be able
OAK to be opened locally.
Verify LPSW pumps are cavitating
2. Pump amps erratic
> LPSW header pressure fluctuating
Ensure the Unit 1/2 STANDBY bPSW 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 kPSW pump.
Verify normal LPSW System operation is restored.
0 The SRO should call SPOC to troubleshoot the reason for the
suction valve dosing.
SRQ 0 The SRO should refer to TS:
b TS 3.7.7 (bow Pressure Service Water System) Condition A
applies. Restore required LPSW pump to operable status. 72
hours completion time.
> TS 3.3.28(LPSW pump Auto-Start Circuitry) Condition A.
Restore Auto-Start Circuitry to operable. 7 day completion time.
Event is complete when SRO has referred to TS 3.7.7 or when
NUREG-102li Draft Revision 9
.c Page 4 of 13
Op-Test No.: Scenario No.: 1 Event No.: 4 Page 1 of 1
Event Description: RC Loop B Flow fails LOW: (I, OATC)
Position Applicants Actions or Behavior
Plant response:
1. Statalarms:
1SA-2/A-5, RC Total Flow Low
1SA-%A-1, RP Channel A Trip
e ISA-1IA-3, RP Channel A FluxlimblFlow Trip
2. Control board indications:
0 RCS Flow meter shows Loop B flow at zero.
e RPS Channel A trips.
0 B S E FDW Flow instrument shows a reduction in FDW, and the A
S/G FDW Flow indicates increasing flow or off-scale High.
DELTA Tc meter indicates a large Delta Temp.
Crew response:
0 The crew should stabilize the unit by using the Plant Transient
OATC Response process. o m $-a -/L
e Take the Diamond and BOTH FBW Masters to MANUAL and stabilize
the unit.
e The SRO should refer to AP/l/Nl700/28, ICs Instrument Failures and
notify SPOC to have the instrument repaired.
0 AP/1/AIl700/28, IC§ Instrument Failures will:
k Ensure DIAMOND and BOTH FBW Masters in MANUAL.
Z Notify SPOC to select a valid RCS flow input to 16s and
investigate and repair the failed RCS flow instrumentation.
2. Ensure any associated requirements of PT/l/A/060Q/001
(Periodic Instrument Surveillance) are met for the failed
instrument.
k WHEN notified by SPOC that a valid RCS flow input has been
restored to BCS, THEN GO TO Encl 5.1 (Placing ICs in AUTO).
Note: Crew may refer to PT/6001001 (Periodic Instrument
Surveillance) due to ARPS Channel trip and may choose to place
A RPS to manual Bypass.
Event is complete when the SRO has reached the WHEN step in
ARl28 or when directed by the Lead Examiner.
NLIREG-1021 Draft Revision 9 Page 5 of 13
Op-Pest No.: Scenario No.: 1 Event No.: 5 Page 1 of 1
Event Description: BOTH MDEFDWPs Auto-start circuitry inoperable: (C, ALL) (TS)
Time Position Amticants Actions or Behavior
Note: When directed by the lead examiner, call the CR and inform
them that that I&E has determined that the Auto-start circuitry for the
BOTH MDEFDWPs are out of tolerance and technically inoperable.
Parts required for the repair are not expected for 3 days.
Crew response:
The SRB should refer to TS 3.3.44 (Emergency Feedwater Pump
initiation Circuitry) Condition B and determine that the A
MDEFDWP is inoperable.
Determine TS 3.7.5 (EFW System) Condition 6requires restoring
one MBEFBWP pump in 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> or be MODE 3 in an additional 12
hours.
SRO should determine that at unit shutdown is required and direct unit
shutdown per OP/1/N1202/004 (Operation At Power) Encl. 3.2, Power
Reduction.
Event is complete when the decision to shutdown has been made or
when directed by the Lead Examiner.
NUREG-1022, Draft Revision 9 Page 6 of 13
I Op-Test No.: Scenario No.: 1 Event No.: 6 Page 1 of 1
- Event Description: Manual unit shutdown: (R, OATC)
Position Applicants Actions or Behavior
Crew response:
Direct unit shutdown per OPIIINI 1021004 (Operation At Power) Encl. 3.2,
SRO Power Reduction.
Z. Review Limits and Precautions
2. Notify OSM to contact NRC if required.
3. Refer to OP/?106/001(Turbine Generator) to ensure operating limits
are NOT exceeded during shutdown.
4. Notify System Operations Center (SOC) or lead reduction.
Note: Due to procedure complete up to Step 2.17 the crew may net
perform steps 1-4 above.
OATC 5. Reduce reactor power in manual by inserting control rods with the
Diamond and controlling FDW flow with the FDW Masters.
BOP 6. Stop B HBPs per OQ/1/AI1106/002 D (HDP Operation)
Event is complete when reactor power has been reduced 5% or when
directed by the Lead Examiner.
NUWEG-1021, Draft Revision 9 Page 7 of 13
Op-Test NO.: Scenario No.: 1 Event No.: 7 Page Z of 1
Event Description: Reactor trip, Main Turbine Fails to trip (Lockout EHC Pumps) (c,
OAK)
Position AsDlimnt's Actions OF Behavior
Note: The reactor will trip as a result of initiating event 8 (SBLOCA).
Plant response:
Statalarms:
1SA-91A-6, RB Reactor Bldg Norm Sump Level High/Low
1SA-8/54, Process Monitor Radiation High
Control board indications:
PZR level and WCS pressure will decrease
e The reactor will trip on low RCS pressure.
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 direct the OATC to perform IMAs and the BOP to perform a
symptom check and then enter the EOP.
OATC 2. OATC will perform Immediate Manual Actions
Depress REACTOR TRIP pushbutt~n
Verify reactor power < 5% FP and decreasing
- Depress turbine TRIP pushbutton.
- Verify all turbine stop valves dosed
Lock out both EHC pumps (CT-I 8)
Mote: The OATC should diagnose that the turbine did not trip and
then perform the RNQ step which will stop and lock out both I"
pumps. This will cause the turbine t o trip.
Verify RCP seal injection available.
3. BOP wit1 perform a symptom check.
Event is complete when EHC pumps have been tripped or when
directed by the lead examiner.
NUWEG-1021, Dmft Revision 9 Page 8 of 13
3p-Test No.: Scenario No.: I Event No.:8 Page 1 of 4
Event Description: Small Break LOCA: (M, ALL)
-
Time Position
Plant response:
Applicant's Actions or Behavior
Control board indications:
o ES 1-6 actuate
0 WCS subcooling margin w1i 6 indicate 0°F.
OAK Crew response:
1 The QATC should verify IMAs compkte with the SRO and then the
~
50P SRO should direct the O A K 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.
Verify that reactor power is e 1%.
e Trip RCPs within 2 min of LOSCM (CT-1)
0 Verify 11HP-24/25 (1NIB BWST Suction) open
o Ensure all available HPI pumps operating.
Note: I C #PI pump will not be operating and an attempt should be
made to manually start the 'IC HPI pump.
Determine HPI flow in the B header is in the unacceptable region of
Figure 1 and open 1HP409 (1HP-27 Bypass). (CT-2)
e Verify that T5Vs are available.
e Disable AFBS in non-actuated channels.
0 Establish EFDW to the OTSGs to feed to LQSCM setpoint per Rule
7 (SG Feed Control). (CT-10)
0 Verify both MDEFDWPs operating. (1B MDEFDWP is ow)
0 Ensure TDEFDWP is in PULL TO LOCK. (Not performed due
1B MDEFDWP not operating)
Trip both MFBWPs and close the FDW block valves.
0 Notify SRO of SG feed status.
0 Maintain SG pressure c RCS pressure.
- Ensure Rules 3 & 8 in progress or complete.
NUREG-I 021, Draft Revision 9 Page 9 ~f 13
Op-Test No.: Scenario No.: 1 Event No.: 8 Page 2 of 4
Event Description: Small Break LOCA (M, ALL)
Time Position Applicants Actions or Behavior
SRO 3. When reporting symptoms, the QATC should inform the SRQ that ES
Channels 1-6 have actuated. The SRO should initiate EOP Encl. 5.1, ES
OATC Actuation per the parallel actions page of Subsequent Actions section or
of the LOSCM Tab. When running End. 5.1, the operator will:
e Determine which E§ channels should have actuated and verify a11
Blue bights and White Lights are iighted for the appropriate
channels.
Note: A RBCU will not receive an ES signal and will remain in HlGH
speed. The operator should diagnose this and place the A RBCU in
LOW speed.
o Place HPI in Manual.
e Verify any RCP operating. (No RCPs operating)
e Verify SCMs > 0°F and proceed to the HPI flow check when he
determines that the RCS has saturated.
The operator should determine HPI flow is adequate per Figure 1.
Note: lHP-409 should have been opened by Rule 2.
e Open 1BS-2 and IBS-2
e Place LPI pumps in manual control.
0 At SRO direction secure LPI pumps.
0 Ensure A and E3 and 3A and 3B Outside Ais Booster Fans are
operating. (CT-27)
0 lAAT ES Channels 5 & 6 have actuated,
THEN dispatch an operator to establish = 1800 cfm flow in each
PRVS filter train using 1PR-13 and 1PW-17 (Controller, Filter
I N 1B)
@ Ensure the following are open:
0 I c c - 7 and 1cc-8
e Ensure open ICF-2 and 1CF-2 ( A BCFT Outlet)
e Verify 2 HP-410 closed.
e Dispatch an operator to perform End. 5.2 (Placing RE3 Hydrogen
Analyzers In Service)
e Notify Chemistry to prepare for caustic addition.
0 The operator must get SRO approval to exit this enclosure.
NUREG-1021, Draft Revision 9 Page 10 of 13
Op-Test No.: Scenario No.: 1 Event No.: 8 Page 3 of 4
Event Description: Small Break LOCA (M, ALL)
Time Position Applicant's Actions or Behavior
SRO 4. The SRO should GO TO the LOSCM Tab per the Parallel Actions page
of the EOP Subsequent Actions section. LOSCM Tab will:
o Ensure that Rule 2 is in progress or complete.
o Verify that station ASW is not feeding any SG.
Verify that the LOSCM is not mused by excessive heat transfer.
Open I AS-40 while closing 1MS-47.
Verify all the folbowing conditions exist:
k NO RCPs are operating
i. HPI flow exists in both HPI headers
i Adequate Total WPl flow per figure 1 (Total Required HPI Flow)
0 Control steaming and feed rates on all intact SGs to maintain
cooldown rate within Tech Spec limits:
>. Tc 2 280°F 5 5Q"Fil.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
GO TO Step 70.
o Close the following: (CT-3)
5. IHP-I ( I A Letdown Cooler Inlet)
k IHP-2 ( l e Letdown Cooler Inlet)
"r 1RC-3 (Spray Block)
"r 1GWD-27 (PZR Vent Control)
Note: RCS leak will be isolated when 1RC-3 is closed.
o Maintain SG pressure RCS pressure.
Verify primary to secondary heat transfer exists.
Initiate Encl. 5.16 (SG Tube-to-Shell AT Control)
e Verify NO indications of an SGTR.
0 Verify HPI forced cooling NOT in progress.
Verify CETCs NOT increasing.
o Verify primary to secondary heat transfer is NOT excessive.
Verify NO indications of SGTR.
o Verify required RCS makeup flow within normal makeup capability.
"r RNO Transfer to LOCA CD tab.
-
NUREG-1021, Draft Revision 9 Page I t of 13
Dp-Test No.: Scenario No.:d Event No.: 8 Page 4 of 4
Event Description: Small Break LOCA: (M, ALL)
-
Time Position
5. GO TO LOCA CD tab.
Applicants Actions or Behavior
IAAT BWST level 5 19 feet transfer ECCS suctions to the WBES.
Verify ES is actuated.
Ensure all RBCUs in low speed and open ILPSW-18,l LPSW-21,
ILPSW-24, and 1LPSW-565 closed.
Initiate End. 5.35, Containment Isolation
Ensure all RB Aux fans are operating
Initiate End. 5.36 (Equipment Alignment For Plant Shutdown)
IAAT all of the following conditions exist: (Step 33)
> ALL SCMs > 0°F
> RCS pressure > LPI shutoff head
G Required HPI within normal makeup capability
If step 33 met then go to Event 9.
et crew will GO TO Step 39 and continue in
Disable a11 AFlS headers NOT actuated by selecting OFF on both
Digital Channels Z&2 on that header.
IAAT a sustained re-pressurization of the RCS occurs due to any
of the following:
G beak isolation
G Degraded heat transfer due to hot k g voiding
THEN perform Steps 42-48.
Verify at least one SG available.
Verify any loop 537. (both should be above)
Cyde PORV to maintain RCS pressure.
Ensure appropriate level and feed flow is available to SGs per
RULE 7 (SG Feed Control)
Notify TSC to evaluate starting or bumping RCPs.
Notify Chemistry to sample RCS boron hourly until MODE 5.
Event is complete when RCS SGM is greater than 0°F or when
directed by the Lead Examiner.
NUREG-1021, Draft Revision 9 Page 12 of 13
Op-Test No.: Scenario No.: -l Event No.: 9 Page 1 of Z
Event Description: RCS leak isolated, SCM increases 0°F
Time Position Applicant's Actions or Behavior
Plant response:
o SCM increases > 0°F
o PZR level increasing
Crew response:
2 . Throttle HPI pe (HPI) (CT-20)
BQP
HPI Forced Cooling not in progress
o RX power 5 1% and Core SCM > 0
Note: If SCM increases > Q"Fprior to reaching the foilowing lAAT
sa0 step the SRO may elect to transfer to Subsequent Actions based on
plant conditions changing.
2. IAAT all sf the following conditions exists:
0 ALL SGMs > 0°F
RCS pressure > LPI shutoff head
0 Required HPI within normal makeup capability
3. Verify primary to secondary heat transfer
4. Verify NO indications of SGTR
5. GO TO Subsequent Actions
Event and exam is complete when the SRO has transferred to
Subsequent Actions or when directed by the Lead Examiner.
NUREGTO22 Draft Revision 9
I Page 13 of 13
~
Scenario Outline Form ES-B-I
Appendix D __
Facility: Oconee Scenario No.: SPARE fnl Op-Test No.:
Examiners: Operators: Tracey Roland (SRO-U)
Kevin C ~ o l e y(ROj
Initial Conditions:
100% Reactor Power,(SNAP 202)
Turnover:
AMSAGIDSS bypassed for I&E testing
Unit 1 TBEFDWP 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
Ob
0C 1A MDEFDWP fails to start
1
2
6 1 CALL I 1D1 Heater Drain Pump oil leak
7
8
9
TDEFWP returned (CBP recovery)
I I
(N)ormal, (R)eactivity, (I)nstrument, (Cjomponent, (M)ajor
NUREG-1021, Draft Revision 9 Page 1 of 15
Appendix D Operator Actions Form ES-D-2
Op-Test NO.: Scenario No.: SPARE Event No.: I Page 1 of 1
Event Description: Pressurize the LDST with H2: (N, OATC)
-
Time Position Applicant's Actions or Behavior
Piant response:
1SA-0218-2 (Approaching LDST Operating Limits) actuates
Crew response:
1. Refer to ARG
BATC
a Add hydrogen to establish desired bDST pressure per
OP/l/N1106/01i' (Hydrogen System)
Refer to LDST Pressure \IS. bevel enclosure in
OP/O/Nl1O8/001 (Curves and General Information.
SRO 2. Direct the OATC to use OPII/N1106Dl7 (Hydrogen System) Encl.
3.5 (Unit 1 LDST H2 Addition) to add H2 to the LDST.
OAK e Review Limits and Precautions
e Immediately prior to pressurization determine lowest reading of
diverse LDST level indications: inches.
- For existing LDST level determine LDST Pressure allowable
per LDST Pressure vs. Level curve: psig.
Notify Operator at #2 Cage to pressurize primary hydrogen.
NOPE: Operator should be in constant communication with CR to
close 4 H-26 if 1H-I fails open.
- Direct Operator to open 1H-26 (LDST Block).
e Cycle 1H-I (LBST SUPPLY) as required to pressurize LDST
per LDST Pressure vs Level curve.
WHEN complete, ensure closed 1H-l (LDST SUPPLY).
Note: 1H-4 (LBSP SUPPL\a will fail open.
When 4H-1 (LDSP SUPPLY) Is opened or when directed by the
lead examiner this event is complete.
NUREG-I 021, Draft Revision 9 Page 2 of 15
Op-TeSt NO.: Scenario No.: SPARE Event No.: 2 Page 1 of 1
Event Description: 1 W - l fails OPEN: (C, OATC) (TS)
Time Position Applicant's Actions of Behavior
Plant response:
0 1H-1 (LDST SUPPLY) will indicate open
LDST pressure will continue to increase
Crew Response:
0 Monitor LDST Pressure and 1H-I (LDSP SUPPLY) indication
OATC and determine that I H - l (LDST SUPPLY) has failed open.
o Direct Operator to close 1H-26 (LDST Block).
Ensure LDST pressure within LDST Pressure vs. Level cuwe.
Note: LDSP pressure will NOT be within the LDST Pressure vs.
Level curve.
Refer to ARG for 1%-OZD-2 (Approaching LDST Operating
Limits) actuates.
o Determine that LDST pressure is not within LDST Pressure vs.
bevel cuwe and declare BOTH trains of HPl inoperable. Direct
the OATC to take actions to reduce LDSP pressure to within
the proper operating region of the LDST Pressure vs. Level
curve.
o Vent LDST to GWD per O$/1/AlI104/002 (HPI System).
Note: The crew will not have time to vent the LDST.
SRO should refer to TS 3.5.2(HPl) and determine that
Condition H is met. The required action is to enter LCO 3.0.3
immediately.
When the SRQ 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 15
Op-Test No.: Scenario No.: SPARE Event No.: 3 Page 1 of 1
Event Description: Tho*fails HIGH: (IpOATC)
Time Position Applicant's Actions or Behavior
Plant response:
e Loop A Thst Bixson meter reading goes to 620°F
Thot recorder 0612°F
Tave recorder and digital meter increases to -583°F
Loop A Delta T meter increases to 4 5 ° F
a Loop A Tave meter increases to ;2588"F
- Stablam ISA-2iB-3, RC Hot beg Temp High, alarms
Crew response:
OAK 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 16s 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 e SRO should refer to AP128 (ICs Instrument Failures).
When the ICs has been taken to manual and the plant is stabk or
when directed by the lead examiner this event is complete.
NUREG-1021, Draft Revision 9 Page 4 of 15
Op-Be§t NO.: Scenario No.: SPARE Event No.: 4 Page 1 of 1
1 Event Description: 1A CC Pump trips: (6, OAK)
Position Applicant's Actions or Behavior
Want response:
1. Statalarrns:
1SA-SIB-I , CC CRB RETURN FLOW LOW
1SA-SIC-?, CC COMP COOLING RETURN FLOW LOW
0 1%-21C-4, LETDOWN TEMPERATURE HIGH
2. Control Board indications:
o 4HP-5 (Letdown Isoiation) wilB close due to high letdown
temperature
Crew Response:
OATC 1, Refer to ARGs
2. Initiate AP1020 (boss of Component Cooling)
IAAT both of the following are lost:
3 CCtcaRCPs
> RCP seal injection
THEN perform the following:
l+ Trip RX
> Stop all RCPs
> Initiate APi25 (SSF EOP)
lAAT 2 two CRD stator temperatures 2 18O"F,
THEN trip RX.
o Open ICC-7 and ICC-8
OATC 0 Verify CC Surge Tank level 2 12".
Manually start the Standby CC Pump
3. Verify CC TOTAL FLOW 575 gpm
4. Verify both of the following:
Letdown in service
- LETDOWN TEMP 5 130°F
5. Step not met. Perform RNO, Initiate AP/032 (Loss of Letdown)
This event is complete when the Standby CC pump is started or
when directed by the lead examiner.
NUWEG-1021, Draft Revision 9 Page 5 of 15
Op-Test No.: Scenario No.: SPARE Event No.: 5 Page 1 of 2
Event Description: IHP-5 Fails closed: (C, OATC)
Time Position Applicant's Actions or Behavior
SRQ 1. AP1032 (Loss of Letdown)
OAK 0 Ensure IHP-120 (RC Volume Control) in HAND and closed
0 Notify chemist WCS Boron sample needed and normal letdown
line is isolated.
0 Verify CC in operation
Position the standby HPI pump switch to OFF.
Throttle 1HP-31 (RCP Sea[ Flow Control) to establish 12-15
gpm SEAL INLET HDW FLOW.
- Verify loss of letdown is due to letdown valve or interlock
failure. GO TO Step 4.29
Note: IHP-5 failure not known to the crew at this time
0 Close 1HP-6 (Letdown Orifice Stop)
- Close 1HP-7 (Letdown Control)
Ensure the following open
k ZHP-1 (1A Letdown Cooler Inlet)
). IHP-2 (4 B Letdown Cooler inlet)
i 1HP-3 (1A Letdown Cooler Outlet)
> 1HP-4 (1 B Letdown Cooler Outlet)
e Verify letdown temperature e 135°F. Perform RNQ
- Open IHP-13 (Purification IX Bypass)
0 Ensure f HP-8 (Purification IX In1et)end 1HF-9811 (Spare
SRO Purification IX Inlet & Outlet) closed
OATC Select LETDOWN HI TEMP lNTbK BYP switch to BYPASS.
Ensure 2HP-5 (Letdown isolation) is open
Note: 1HP-5 will not open from the control room.
GO TO step 4.1 I
- Verify 1HP-5 (Letdown Isolation) closed
0 Close 1HP-6 (Letdown Orifice Stop)
Close 1HP-7 (Letdown Control)
e Dispatch an operator in continuous communication with Control
Room to manually open 1HP-5 (LETDOWN ISOLATION)
Cue: Open IHP-5 and inform CR
NUREG-1021, Draf! Revision 9 Page 6 of 15
Op-Pest No.: Scenario No.: SPARE Event No.: 5 Page 2 of 2
Event Description: 1HP-5 Fails closed: (C, OATC)
Time Position Applicant's Actions or Behavior
OATC o WHEN 1HP-5 (Letdown Isolation) is open, THEN ensure CC
System in operation.
0 Verify letdown temperature 135°F. Perform RNO.
0 Open 1HP-I 3 (Purification BX Bypass)
Ensure IHP-8 (Purification IX Inlet) and 1HP-9&11 (Spare
Purification IX Inlet & Outlet) are closed
Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
0 Throttle open 1HP-7 (Letdown Control) to establish = 20 gpm.
0 WHEN letdown temperature I3O0F, THEN ensure
LETDOWN HI TEMP INTLK BYP switch in NORMAL.
0 Open 1HP-6 (Letdown Orifice Stop)
Adjust IHP-7 (Letdown Control) to control desired letdown flow.
Note: Normal letdown flow is !Z 70 gpm.
When letdown has been re-established or when directed by the
lead examiner this event is complete.
NUREG-1021, Draft Revision 9 Page 7 of 15
@-Test NO.: Scenario No.: SPARE Event No.: 6 Page 1 of I
Event Description: I D 1 Heater Drain Pump oil leak: (C, All)
Position Applicant's Actions or Behavior
When directed by the bead Examiner an NE0 will inform the
control room that the ID1 HDP has a severe oil leak.
Crew Response:
0 Refer to OPIIIAII 106/(32D, (Shutdown of the ID1 HDP)
0 SRQ should determine that d u c i n g power to 87% is required
and direct unit shutdown in accordance with one of the following:
);. AP129 (Rapid Unit Shutdown)
k OP/ZiNl102/004 (Operation At Power)
Note: A manual shutdown is required because the ICs is in
manual due t o the previous Thot failure.
Event is complete when a unit shutdown is directed by the SRO
or when directed by the Lead Examiner.
NUREG-1821 Draft Revision 9
I Page 8 of 15
Bp-Test No.: Scenario No.: SPARE Event No.: 7 Page 1 of 1
Event Descriptiun: Manual reactor power decrease: (Fa, O A K )
Time Position Applicant's Actions or Behavior
Crew Response:
SRO 1. SRO will direct the unit shutdown and continue in the AP/29 (Rapid
Unit Shutdown) or OPIIINI 102/004 (Operation At Power).
BATC 2. O A K will reduce FDW Raw with the FDW Masters and insert the
control rods manually to reduce reactor power.
Event is complete when reactor power has been reduced 5% or
when directed by the lead examiner.
NUWEG-1021, Draft Revision 9 Page 9 of 15
Og-TeSt NO.: Scenario No.: SPARE Event No.: 8 Page 1 of 2
Event Description: boss of Main Feedwater: (M,ALL}
Time Position Applicants Actions or Behavior
When directed by the Lead Examines BOTH Main FDW pumps will
trip.
Plant response:
- A MDEFDW Pump will not start
o B MDEFDW Pump will start
0 No EFW flow the A SG and level will decrease to 15 XSUR
Crew response:
SRO will direct the O A K to perform Immediate Manual actions
and the BOP to perform a Symptom Check.
SWO should transfer to Subsequent Actions of the EOP.
Subsequent Actions will:
Verify all control rods fully inserted.
Verify Main FDW in operation and controlling properly.
Z No FBW pumps a ~ operating.
e Perform RNO. Ensure Rule
3 (Loss of Main or Emergency FBW) in progress or
complete.
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.
Initiate Encl 5.5 (Pzr and LDST Level Control).
Ensure PCB 20 and PCB 21 open
Ensure Generator Field Breaker and Exciter Field Breaker is
open.
Verify AB and BB Instrument Air pressure 5 90 psig.
Verify ICS/NNI power available.
Verify all 4160V switchgear (ITC, ITD, ITE) energized.
Verify both SGs 2 550 psig.
Note: All steps may not be performed depending on the timing of
the next event.
NUWEG-1021, Draft Revision 9 Page 10 of 15
Bp-TeSt No.: Scenario No.: SPARE Event No.: 8 Page 2 of 2
I Event Description: Loss of Main Feedwater: (M,ALL)
Position Atmlicant's Adions or Behavior
OATC * Verify Main FDW operating.
k No FBW pumps operating perform RNQ Ensure Rule 3 (Loss
of Main or Emergency FDW) in progress or complete.
- Ensure SG levels approaching proper setpsint. (Rule 7)
- Verify SGMs 0°F.
This event is complete when SCM has been verified > 0°F or
when directed by the lead examiner.
NUREG-1021, Draft Revision 9 Page 11 of 15
3p-Kest No.: ____ Scenario No.: SPARE Event No.: 9 Page 1 of 3
Event Description: Loss of Main and Emergency Feedwater, 1B MBEFDWP trips
(CBP Feed): (M, ALL)
P
Time Position Amlicants Actions or Behavior
When directed by the bead Examiner 1B MDEFDW pump will trip.
Plant response:
o RCS temperature and pressure will increase
Grew response:
o The SRO should direct the OATC and the BOP to perform a
swo symptom check.
The OAT6 should determine no Main or Emergency Feedwater
BAPC is feeding the SGs and with SRO concurrence re-start RULE 3
(boss of Main and Emergency Feedwater).
RULE 3 (Lsss of Main and Emergency Feedwater) will:
IAAT NO SGs can be fed with FDW (MainlEmergency),
AND any of the following conditions exists:
RCS pressure reaches 2300 psig OR NDT limit
Pzr level reaches 3 7 5 [ W Qacc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Ensure any EFBWP operating.
RNQ step, GO TO Step 4.
Verify Main FBW NOT operating.
Place the following in MANUAL and close:
k IFDW-315 (1A EFDW Control)
> 1FDW-316 (1B EFDW Control)
NUREG-lO21, Draft Revision 9 Page 12 of 15
Op-Test No.: Scenario NQ.: SPARE Event No.: 9 Page 2 of 3
Event Description: boss of Main and Emergency Feedwater, 1B MDEFDWP trips
(CBP Feed): (M, ALL9
Time Position Applicant's Actions or Behavior
Verify all the following available:
OATC
> AnyCBP
9 TBVs
0 Disable both Digital Channels I & 2 of AFlS on both headers A
and 5:
> A Header DIG. CH. Iand 2 OFF
+ 5 Header DIG. CH. 1 and 2 OFF
Place Startup Block valve control switch for 1FDW-33 ( I A SG)
0 Position Startup Control valve 10 - 20% open on all available
SGs: 1FDW-35 on 1A SG and 1FDW-44 on 1B SG.
- Close the following:
k 1FDW-32 ( ? A Main FDW Control)
4 1FDW-41 (1B Main FBW Control)
> IFDW-31 ( I A Main FDW Block)
4 1FBW4Q (1B Main FBW Block)
bower SG pressure in available SGs to = 500 psig.
0 Control FDW flow to stabilize RCS P/T by throttling the
following as necessary: (CT-10) (CT-I 1)
4 Startup Control valves
9 TBVs
0 Dispatch an operator to perform Encl 5.26 (Manual Start of
TDEFBWP).
NUREG-1021, Draft Revision 9 Page 13 of 15
3p-Test No.: Scenario No.: SPARE Event No.: 9 Page 3 of 3
Event Description: Loss of Main and Emergency Feedwater, 1B MDEFBWP trips
(CBP Feed): (M, ALL)
____F__
-Time Position
SWO a
Applicants Actions or Behavior
SRO should transfer to the Loss of Heat Transfer (LOHT) tab
of the EOP.
The LOHT tab will:
o Ensure Rule 3 (Loss of Main cw Emergency FDW) is in
progress or complete.
lAAT core SCM = OF,
THEN GO TO Step 4.
I M P NO SGs can be fed with FDW (MainlEmergency),
AND any of the following conditions exists:
ii WCS pressure reaches 2300 psig OR NDT limit
> Pzr level reaches 375 [340aec]
THEN GO TO Step 4.
Perform RNO step:
I NOTE: 1 A l RCP provides the best Pzr spray.
a Reduce operating RCPs to one pumplloop.
WHEN any of the following conditions exists:
> Unit 1 EFDW available
> EFBW aligned from another unit
> Main FDW pump available AND reset
THEN GO TO Step 52
Note: The SRO should wait at this WHEN step until a Feedwater
source is aligned or conditions are met t o go into Forced HPI
Cooling.
This event is complete when CBP flow has been estabhshed and
the plant is stable or when directed by the lead examiner.
Op-TeSt NO.: Scenario No.: SPARE Event No.: 10 Page 1 of 1
Event Description: TDEFDWP returned (CBP feed recovery)
Time Position 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.
0 The SRO should transfer to Step 52.
sa0 0 Verify MFDW or Unit 1 EFDW available.
0 Verify Encl 5.27 (Alternate Methods For Controlling EFDW
Flow) is NOT in progress.
k Perform RNO step: GO TO Step 60.
- Verify one of the following:
)i Both MDEFDWPs operating
P TDEFDWP operating
Verify all the following:
>j Tcold > 500°F
)i TBVs available
0 Verify Tccsld 5 547°F.
k Perform RNO step:
Ensure TWP setpoint at ~ 8 8 5 psig.
GO TO Step 64.
0 Ensure TBVs in AUTO for available SGs.
0 Initiate feed to available SGs per Rule 7 (SG Feed Control)
(CT-26)
0 lAAT heat transfer is established in any SG,
THEN GO TO Step 97.
0 Control feeding and steaming of available SGs to maintain SG
level at setpoint and csoldown rate within Tech Spec limits:
0 Tcold > 280°F: 5 50°F i l/a 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 15 of 15