ML020940524
| ML020940524 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/11/2002 |
| From: | Division of Nuclear Materials Safety II |
| To: | Duke Energy Corp |
| References | |
| 50-269/02301, 50-270/02301, 50-287/02301 | |
| Download: ML020940524 (39) | |
See also: IR 05000269/2002301
Text
FINAL SUBMITTAL
OCONEE EXAM
50-269a 270o 287/2002-301
February 11 - 15., 2002
FINAL SIMULATOR SCENARIOS
AND OUTLINES
OCONEE
02/11/2002
OPERATING EXAM
(SIMULATOR)
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Facility: Oconee Scenario No.: 1 fnl Op-Test No.:
Examiners: Operators: I -SRO (1-3)
R-OATC (1-3)
U-BOP (1-3)
Initial Conditions:
- 75% Reactor Power EOL, per dispatcher request (IC-42)
Turnover:
"* Unit 1 TD EFDW Pump OOS to repair oil leak, expected returned this shift
"* SASS in manual for I&E testing
"* AMSAC/DSS bypassed for I&E testing
"* NI-9 OOS, to be replaced next outage
"* Keowee Unit 2 00S for unplanned reasons
"* Keowee Unit 1 aligned to underground, operability test complete
"* PT/11/A0600/15 (Control Rod Movement) to be performed after turnover
Event Malfunction Event Type* Event
No. No. Description
Oa Pre-Insert TD EFDW Pump Fails to Start
MSS330
Ob Pre-Insert SASS in manual
Updater
Oc Pre-Insert AMSAC/DSS bypassed
Updater
Od Pre-Insert Keowee Unit 2 Emergency Lockout
MEL180
Ce Pre-Insert NI-9 QOS
MNI082
Of Pre-Insert "A" MSLB disabled
Override
1 N, (BOP), SRO Perform Control Rod Movement
2 MCR021 C, OATC, SRO Drop CR Group 2 Rod 6, (pip 0-01-03316) (TS)
Override Diamond blocked from AUTO operation
3 R, OATC Power Reduction
4 MPS440 C, (BOP), SRO 1A1 RCP High Vibration
(40-80%)
5 MP1281 I, OATC, SRO ATcfails HIGH when RCP secured
6 MCR022 M, OATC, SRO Second dropped control rod, requiring a manual reactor trip
7 MEL090 C, ALL ATWS
CT-1 Lockout (Loss of Power)
8 MEL180 M,ALL Keowee Unit 1 Emergency Lockout (blackout,
PRA)
- (N)ormal, (R)eactivity, (I)nstrument, C)omponent, (M)ajor
Page 1 of 15
Appendix 0 Scenario Outline Form ES-D-l (R8, Si)
Op-Test No.: __ Scenario No.: 1 Event No.: 1 Page 1 of 2
Event Description: Perform Control Rod Movement PT: (N, BOPISRO)
Time Position Applicant's Actions or Behavior
BOP/SRO Perform PT/i/A/0600/15, Control Rod Movement
Conduct pre-job briefing
Review Limits and Precautions
Place SAFETY RODS OUT BYPASS Switch in Bypass.
Take manual control of reactor and feedwater
"* SG Master in Hand
"* Diamond in manual
Test CRD Group 1
- Transfer CRD Group 1 to Aux power supply
OP/1 105/009 (Control Rod Drive System)
> Select group 1 on Group Select Switch
ALL on Single Select Switch SSelec
>Depress selector for SEQ OVERRIDE
> Depress selector for AUXILIARY
> Select JOG on Speed Selector
>Depress selector for CLAMP
> Depress selector for MANUAL TRANSFER switch until
TRANSFER CONFIRM lamp comes on followed by
CONTROL ON lamps on PI panel. All CONTROL ON
lamps on group transferred should be on.
> Depress selector for CLAMP RELEASE pushbutton.
> Depress selector for GROUP.
> IF desired, select RUN on Speed Selector. Group is
now transferred to Auxiliary Power Supply.
- Insert CRD Group 1 ý 2.5% (ý 6 seconds)
"* Withdraw CRD Group 1 to OUT LIMIT
"* Transfer CRD Group 1 to DC Hold Power Supply
> Select group 1 on Group Select Switch
> Select ALL on Single Select Switch
> Ensure SEQ OVERRIDE selected
> Depress selector for AUXILIARY
> Select JOG on Speed Selector
Page 2 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: __ Scenario No.: I Event No.: 1 Page 2 of 2
Event Description: Perform Control Rod Movement PT: (N, BOP/SRO)
Time Position Applicant's Actions or Behavior
BOP/SRO > Depress selector for CLAMP
> Depress selector for MANUAL TRANSFER switch until
TRANSFER CONFIRM lamp AND all CONTROL ON
lamps on PI panel go off.
> Depress selector for CLAMP RELEASE.
> Depress selector for GROUP.
> Depress selector for Sequence.
> Depress selector for TRANSFER RESET. Transfer is
complete.
> IF desired, select RUN on Speed Selector. Group is
now transferred to Normal Power Supply.
Test CRD Group 2
"* Transfer CRD Group 2 to Aux power supply per
OP/1 105/009 (Control Rod Drive System)
> Select group 1 on Group Select Switch
> Select ALL on Single Select Switch
> Depress selector for SEQ OVERRIDE
> Depress selector for AUXILIARY
> Select JOG on Speed Selector
> Depress selector for CLAMP
> Depress selector for MANUAL TRANSFER switch until
TRANSFER CONFIRM lamp comes on followed by
CONTROL ON lamps on PI panel. All CONTROL ON
lamps on group transferred should be on.
> Depress selector for CLAMP RELEASE pushbutton.
> Depress selector for GROUP.
> IF desired, select RUN on Speed Selector. Group is
now transferred to Auxiliary Power Supply.
"* Insert CRD Group 2 z 2.5% (ý 6 seconds)
"* Withdraw CRD Group 2
This event Is completed when Group 2 Rod 6 drops into the
core (during Group 2 withdrawal) or as directed by the lead
evaluator.
Page 3 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: Scenario No.: 1 Event No.: 2 Page 1 of 3
Event Description: Dropped Control Rod: (C, OATC/SRO) (TS)
When crew begins to withdraw CRD Group 2, rod #6 drops Into the
core.
Time Position Applicant's Actions or Behavior
Plant response:
Statalarms
"* 1SA-2/B-10, CRD Position Error
Position Indicating Panel
"* API indication of dropped rod on individual meter
"* In limit (zero %) green light on respective dropped rod.
"* Loss of respective dropped rod out limit (100%) red light.
"* Amber 7" asymmetric lights on the dropped rod and the entire
group.
Diamond Panel indications
- 9" asymmetric lamp.
- Out inhibit lamp if NI Flux is above 60%.
- Group In Limit (green) lamp on respective group.
Crew will use "plant stabilization process" to stabilize the plant.
OATC Acknowledge and verbalize to the SRO the most important Statalarm
received for the failure.
Verbalize to the SRO reactor power level and direction of movement.
BOP Recognize that a valid runback should be occurring but is not
because the ICS is in manual.
SRO The SRO should use the OAC to monitor unit status.
Determine that the use of AP/1IA/1700/15, Dropped Control Rods is
required.
Page 4 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 1 Event No.: 2 Page 2 of 3
Event Description: Dropped Control Rod: (C, OATC/SRO) (TS)
Time Position Applicant's Actions or Behavior
SRO SRO will direct actions per API1A/1700/15, Dropped Control Rods.
1. Verify _ one dropped control rod.
2. Verify _one control rod misaligned > 9" (6%) from group average.
OATC
3. Verify Reactor is critical
4. Verify runback to 55% FP in progress.
- OATC should determine that a runback is not in progress
due to ICS in manual and initiate a manual runback.
BOP 5. Initiate Enclosure 5.1 (Control of Plant Equipment During
Shutdown)
SRO 6. Notify I&E (SPOC) to perform the following:
"* Investigate cause of dropped rod
"* Prepare to reduce RPS Flux/Flow-Imbalance and RPS High
Flux setpoints.
7. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify > 1% SDM with the allowance for inoperable
control rod(s) by performing PT/i/NI 103/15, Reactivity Balance
Calculations.
8. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, ensure reactor power is less than 60% of the
allowable power per the RCP combination.
Note: The crew may elect to place the Diamond in Auto to let the
unit runback. However going to Auto is blocked by a
malfunction of the auto/manual pushbutton.
BOP 9. Transfer CRD Group 2 to DC Hold Power Supply
> Select group 2 on Group Select Switch
> Select ALL on Single Select Switch
> Ensure SEQ OVERRIDE selected
> Depress selector for AUXILIARY
> Select JOG on Speed Selector
> Depress selector for CLAMP
> Depress selector for MANUAL TRANSFER switch until
TRANSFER CONFIRM lamp AND all CONTROL ON
lamps on PI panel go off.
Page 5 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 1 Event No.: 2 Page 3 of 3
Event Description: Dropped Control Rod: (C, OATCISRO) (TS)
Time Position Applicant's Actions or Behavior
> Depress selector for CLAMP RELEASE.
> Depress selector for GROUP.
> Depress selector for Sequence.
> Depress selector for TRANSFER RESET. Transfer is
complete.
> IF desired, select RUN on Speed Selector. Group is
now transferred to Normal Power Supply.
OATC 10. Begin reducing reactor power to less than 60% with the ICS in
manual.
11. Refer to TS 3.1.5 (Safety Rod Position Limits) and determine
Condition "A" applies.
"* Verify SDM within COLR limit in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
"* Declare the rod inoperable in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
When power Is being reduced with the ICS In manual this
event is completed.
Page 6 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 1 Event No.: 3 Page 1 of 1
Event Description: Power Reduction: (R, OATC)
Time Position Applicant's Actions or Behavior
OATC/SRO The OATC will reduce reactor power with the ICS in manual.
"* Reduce FDW to reduce power
"* Insert control rods to control Tave.
Note: The crew may elect to put FDW back In AUTO. If so,
manually reducing FDW will not be required.
When power has been reduce by at least 5% or when directed
by the lead evaluator this event is completed.
Page 7 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: I Event No.: 4 Page 1 of 1
Event Description: 1A1 RCP High Vibration: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior
BOP During the power reduction Statalarm 1SA-9/D-2, RC Pump
Vibration High, will alarm.
"* The BOP should refer to the ARG
"* Verify RCP vibration conditions by using RCP OAC Display
Group RCP
"* Refer to AP/I/A/1700/16, Abnormal Reactor Coolant Pump
Operation.
> Determine if RCP immediate trip criteria is met by referring
to Enclosure 5.1 (RCP Immediate Trip Criteria).
>An immediate trip condition based on vibration is one of the
immediate trip criteria. Sustained actual Emergency High
Vibration as verified by Enclosure 5.1 (RCP Immediate Trip
Criteria).
>Since immediate trip criteria is not met then notify the OSM
and request an evaluation of the RCP vibration condition by
the RCP Component Engineer.
Statalarm 1SA-9/E2 (RCP VIBRATION EMERG HIGH) will actuate.
BOP * The BOP should determine that the trip criteria are met based
on Enclosure 5.1 (RCP Immediate Trip Criteria) and inform the
SRO.
SRO The SRO should direct the BOP to trip the 1A1 RCP.
When crew has tripped the RCP this event Is completed.
Page 8 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, S)
Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 1 of 1
Event Description: AT0 fails HIGH: (I, OATC/SRO)
Time Position Applicant's Actions or Behavior
When the 1A, RCP is secured ATcfails HIGH
"* Statalarm 1SA-02/B-5, RC Cold Leg Diff. Temperature High,
will actuate.
"* FDW flow will ratio based on the failure
"* "A" FDW flow will increase causing "A" loop Tc to decrease.
"* "B" FDW flow will decrease causing "B"loop Tc to increase.
"* This will cause actual AT0 to increase
OATC Diagnose the ATcfailure by observing the AT0 meter on 1UBI. It
should return to zero but is staying a + 3.5 degrees.
Take the Feedwater Masters to MANUAL and re-ratio feedwater
using the loop Tc meters to return actual AT0 to near zero.
SRO May refer to AP/28 (ICS Instrument Failures)
When the OATC has re-ratioed FDW and returned Tc to near
zero or when directed by the lead examiner this event Is
completed.
Page 9 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: __ Scenario No.: 1 Event No.: 6 Page 1 of 1
Event Description: Second dropped Control Rod (Manual Reactor Trip): (M, OATC/SRO)
Time Position Applicant's Actions or Behavior
After the plant is stable and when directed by the lead examiner a
second control rod will drop.
Plant response:
Statalarm
"* API indication of dropped rod on individual meter
"* In limit (zero %) green light on respective dropped rod.
"* Amber 7" asymmetric lights on the dropped rod and the entire
group.
Crew response:
OATC * The OATC should determine that a second control rod has
dropped into the core by observing the CRD PI Panel and
MANUALLY TRIP THE REACTOR. OATC will attempt to trip
the reactor by depressing the reactor trip pushbutton.
Note: The reactor will not trip when the button is depressed.
SRO 0 SRO should ENSURE that a manual reactor trip is performed.
After the reactor pushbutton has been depressed this event is
completed.
Page 10 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: Scenario No.: I Event No.: 7 Page 1 of 4
Event Description: CT-1 Lockout and an ATWS: (C, ALL)
When the manual reactor trip push button is depressed, the reactor will not trip and an
ATWS will occur. When reactor power is less than 5% the turbine will be tripped and
CT-1 (startup transformer) will lockout, which will result in a loss of power. Power will
be restored from Keowee Unit I In approximately 35 seconds via the underground
path and CT-4.
Time Position Applicant's Actions or Behavior
OATC Recognize that the Reactor should have tripped and begin
performing Immediate Manual Actions.
"* Depress REACTOR TRIP pushbutton
"* Verify reactor power < 5% FP and decreasing
The OATC should recognize that Power Range NIs are not < 5%
FP and perform Rule 1. (CT-E.1, CT-E.2)
- Verify that at least one Power Range NI is >5% FP.
- Initiate manual control rod insertion to the IN LIMIT.
- Open IHP-24 & 1HP-25 (1A and 1B BWST Suction)
- Ensure 1A or 1B HPIP is operating.
- Start 1C HPIP.
- Dispatch operators to the Cable Room and to the 600V Load
Centers 1X9 and 2X1 to de-energize the CRD System.
- Notify the Procedure Director to GO TO UNPP tab.
Adjust FDW to match reactor power and maintain Tave near
BOP setpoint.
Page 11 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: Scenario No.: 1 Event No.: 7 Page 2 of 4
Event Description: CT-1 Lockout and an ATWS: (C, ALL)
When the manual reactor trip push button is depressed, the reactor will not trip and an
ATWS will occur. When reactor power is less than 5% the turbine will be tripped and
CT-1 (startup transformer) will lockout, which will result in a loss of power. Power will
be restored from Keowee Unit I in approximately 35 seconds via the underground
path and CT-4.
Time Position Applicant's Actions or Behavior
SRO Transfer to the UNPP tab from IMAs and direct the following
actions:
" Ensure Rule 1 is in progress or complete.
"* Verify Main FDW available.
"* IAAT all power range Nis are <5% FP, THEN ensure the
turbine-generator is tripped.
>This action will result in a unit loss of power for ý 35
seconds due to CT-1 lockout. (refer to page 3 of event 7)
"* Verify all wide range NIs Ž>1% FP.
"* Maximize letdown.
"* Verify Main FDW available.
"* Adjust Main FDW flow as necessary to control RCS
temperature.
"* Verify overcooling NOT in progress.
"* Ensure makeup to the LDST is secured.
"* WHEN all NIs are <1% FP, AND decreasing, THEN continue
in this tab.
Page 12 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: I Event No.: 7 Page 3 of 4
Event Description: CT-1 Lockout and an ATWS: (C, ALL)
When the manual reactor trip push button is depressed, the reactor will not trip and an
ATWS will occur. When reactor power is less than 5% the turbine will trip and CT-1
(startup transformer) will lockout, which will result in a loss of power. Power will be
restored from Keowee Unit 1 in approximately 35 seconds via the underground path
and CT-4.
Time Position Applicant's Actions or Behavior
BOP Perform symptoms check and when asked report no other
symptoms.
When power is regained on the Main Feeder Buses perform AP/1 1,
Recovery from Loss of Power.
"* IAAT Pzr level > 80" [180" acc],
THEN ensure Pzr heaters in AUTO
"* Verify load shed is complete as indicated by LOAD SHED
COMPLETE on any ES Module (Channel 1 or 2).
"* Dispatch an operator to perform End 5.2 (Restoring Loads
Outside the Control Room).
- Dispatch an operator to perform End 5.4 (Actions to Restore
ESV System to Normal Operation).
"* Verify condenser vacuum maintained.
"* Verify IAheader pressures _>90 psig:
OATC Determine the Main Feedwater Pumps have tripped as a result of
the loss of power and perform RULE 3 (Loss of Main or Emergency
FDW).
"* Ensure any EFDWP operating
"* Initiate Enclosure 5.9 (Extended EFDW Operation)
"* Throttle Motor Driven EFDW as necessary to prevent
overcooling.
Page 13 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 4 of 4
Event Description: CT-1 Lockout and an ATWS: (C, ALL)
When the manual reactor trip push button is depressed, the reactor will not trip and an
ATWS will occur. When reactor power is less than 5% the turbine will trip and CT-1
(startup transformer) will lockout, which will result in a loss of power. Power will be
restored from Keowee Unit I in approximately 35 seconds via the underground path
and CT-4.
TimeI Position Applicant's Actions or Behavior
SRO When the turbine is tripped and power is lost:
Two possible paths
1. GO TO the "Blackout" tab per parallel actions page
- In the blackout tab, the crew will: verify power restored,
initiate AP/1 1(Recovery from Loss of Power) and transfer to
Subsequent Actions.
2. If power is restored prior to transferring to blackout tab, SRO
will complete UNPP tab.
- Determine that the reactor has tripped and power is < 1%
power.
if needed.
Emergency Operating Procedure)
3. When power is regained to the 4160-switchgear use a "Parallel
Actions" transfer from the yellow page to initiate
AP/1 1(Recovery from Loss of Power).
4. Transfer to Subsequent Actions
"* Verify all control rods are inserted
"* Verify all 4160V switchgear (1TC, 1TD, 1TE) energized.
"* Verify Main FDW is not operating and ensure SG level are
approaching 240" XSUR.
This event Is completed when power is regained to 4160V
switchgear, reactor is shutdown, EOP Subsequent Actions are
in progress, and when directed by the lead examiner.
Page 14 of 15
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: __ Scenario No.: 1 Event No.: 8 Page 1 of I
Event Description: Keowee Unit I Emergency Lockout, Unit Blackout: (M, ALL)
Time Position J Applicant's Actions or Behavior
When directed by the lead examiner Keowee Unit 1 Emergency
Lockout will occur.
Keowee Unit 1 Emergency Lockout will result in a Unit Blackout.
Emergency Operating Procedure)
The SRO will make a "Parallel Actions" transfer to the Blackout tab.
SRO S Close 1HP-31 (RCP Seal Flow Control) (CT) and 1HP-21 (RCP
Seal Return).
N Determine SGs are not being feed and dispatch operators to
the Atmospheric Dump Valves.
Note: Since the TD EFDW Pump is OOS no source of FDW is
available to the SGs until power is restored from CT- 5.
N Notify SSF operators that feeding with SSF ASW is required.
- Initiate Enclosure 5.39 (Restoration of Power) (CT-A.8)
BOP Perform Enclosure 5.39 (Restoration of Power)
"* Determine CT-1 has no voltage
"* Determine no Keowee Units operating
"* Verify CT-5 indicates 4160 volts.
"* Place the following auto/manual transfer switches in
manual:
> MFB1 AUTO/MANUAL
> MFB2 AUTO/MANUAL
> STANDBY 1 AUTO/MANUAL
> STANDBY 2 AUTO/MANUAL
> CT4 Bus 1 AUTO/MANUAL
> CT4 Bus 2 AUTO/MANUAL
> CT5 Bus 1 AUTO/MANUAL
> CT5 Bus 2 AUTO/MANUAL
"* Close SI1 and SL2 breakers
"* Close S1 and S2 breakers
Note: This will power the Main Feeder Buses.
OATC Use RULE 3 to establish EFDW flow to SGs.
This event and the exam are complete when plant is in a safe
configuration i.e. EFW is restored.
Page 15 of 15
Annendix D Scenario Outline Form ES-D-1 (R8, S1)
i
Appendix DScnroOtieFrL-Ui(,
Facility: Oconee Scenario No.: 2 fnl Op-Test No.:
Examiners: Operators: U-SRO (1-4)
I-OATC (1-3)
R-BOP (1-3)
Initial Conditions:
- 25% Reactor Power, startup in progress (IC-45)
Turnover:
"* Unit 1 TD EFDW Pump OOS to repair oil leak
"* AMSAC/DSS bypassed for I&E testing
"* NI-9 00S, to be replaced next outage
"* "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/620/009 (Keowee Hydro
Operation) after turnover and before startup continues, ONS to perform remote
Keowee start
Event Malfunction Event Type* Event
Description
No. No.
Oa Pre-Insert TD EFOW Pump Fails to Start
MSS330
Ob Pre-Insert AMSAC/DSS bypassed
Oc Pre-Insert NI-9 00S
MN1082
Od Pre-Insert "A" MSLB circuit disabled
Oe Pre-Insert Keowee Unit 2 Emergency Lockout
MEL180
Of Pre-Insert "A"CBP Breaker racked out
1 Override N, BOP, SRO Operability test Keowee Unit 1
C, BOP, SRO Keowee Unit 1 Gen Field Flashing Breaker fails to
OPEN automatically
2 MPS090 C, OATC, SRO 1HP-120 (RC Volume Control) Fails closed
3 MN1032 I, OATC, SRO Controlling NI fails LOW
4 Override Seismic event (PRA)
C, BOP, SRO 1A RBCU rupture (TS)
5 MPS020 C, ALL 1B SG Tube leak (ramp 10 - 100 gpm over 30
5%-25% min) (TS)
6 R, OATC Unit Shutdown
7 MSS360,50 M, ALL 1A Main Steam line break in RB
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)a or
Page 1 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, S)
Op-Test No.: __ Scenario No.: 2 Event No.: 1 Page 1 of 1
Event Description: Operability test Keowee Unit 1 (N, BOP/SRO)
Keowee Unit 1 Gen Field Flashing Breaker fails to OPEN
automatically (C, BOP/SRO)
Time Position J Applicant's Actions or Behavior
SRO Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to
operability test unit 1 Keowee underground.
BOP Use OP/1 106/019 (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 1 FIELD BREAKER closes
"* GEN 1 SUPPLY BREAKER closes
"* GEN 1 FIELD FLASHING BREAKER closes
3. Ensure GEN 1 FIELD FLASHING BREAKER trips.
- Candidate should diagnose that the breaker did not open
automatically and should open the breaker manually and
initiate a work request or contact SPOC.
SRO SRO should direct the BOP to continue with the startup.
Note: GEN FIELD FLASHING BREAKER automatically trips
S45 seconds after receiving close signal. Failure of breaker to
trip automatically does NOT make the KHU inoperable.
Startup procedure may continue.
SRO 4. Determines KHU #1 is operable when test complete
BOP 5. Verify ACB-1, Keowee 1 Generator Breaker, closed.
6. Verify Unit 1 EMER FDR ACB 3 closed
7. Verify ý 4.16 KV on CT4 Volts (2AB3)
8. Close SKi and SK2 (CT4 STBY BUS 1/2 FEEDER)
9. Shutdown Keowee #1.
Event is complete when operability test is complete or when
directed by the lead examiner.
.1
_________________ ____________________________
Page 2 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 2 Page 1 of 1
Event Description: 1HP-120 (RC Volume Control) Fails closed (C, OATC/SRO)
Time Position Applicant's Actions or Behavior
OATC 1HP-120 fails closed during Keowee #1 operability test. This will
allow OATC diagnoses of failure.
1. Diagnose 1HP-120 (RC Volume Control) Failed closed:
"* RCS makeup flow goes to zero.
"* PZR level begins to decrease.
"* LDST level begins to increase.
"* Valve position demand for 1HP-120 begins to increase to
the 100% demand value and valve position indication will
indicate closed (green light).
SRO 2. Refer to AP/14 (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 any HPI pump operating.
"* Verify RCP seal injection flow exists.
"* Verify RCP RCP seal injection or HPI makeup line leak is
not indicated.
"* Verify 1HP-120 has failed and GO TO Step 4.167.
"* Perform the following as necessary to maintain Pzr level >
200":
"* Close 1HP-6 (Letdown Orifice Stop)
"* Throttle 1HP-7 (Letdown Control)
"* Throttle 1HP-26 (1A HP Injection)
3. Contact SPOC to repair 1HP-120.
Note: 1HP-120 will remain failed for the duration of the
scenario.
SRO Directs and supervises AP/14 implementation
When PZR level Is being controlled manually or when directed
by the lead examiner this event is completed.
_____________I
Page 3 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: Scenario No.: 2 Event No.: 3 Page 1 of 1
Event Description: Controlling NI fails LOW (I, OATCISRO)
When directed by the lead examiner the controlling NI will fail low.
Time Position Applicant's Actions or Behavior
Plant response:
1SA-02/A-1 2, ICS Tracking, will actuate. Diamond will transfer to
manual on NI flux < 1.5% and FDW will decrease due to reactor
cross limit. RCS pressure and temperature will increase.
Crew response:
1. When the ICS TRACKING alarm is received, the candidates
should utilize the "plant stabilization process" to stabilize the
plant and recognize that the controlling NI has failed. RX will
trip on high pressure with no operator action.
OATC 2. Verify reactor power.
3. Place the FDW Masters in manual and stabilize the plant.
Adjust T,. using control rods and FDW and stabilize the plant
SRO 4. 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.
"* 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.
Page 4 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.:__ Scenario No.: 2 Event No.: 4 Page 1 of 1
Event Description: Seismic event (PRA)
1A RBCU rupture (C, BOPISRO) (TS)
Time Position Applicant's Actions or Behavior
1. 1SA-9/B-9, LPSW RBCU A Cooler Rupture will actuate and RB
normal sump level will increase.
BOP * The BOP should refer to ARG for 1SA-9/B-9
"* Verify alarm is valid by checking RBCU 1A Inlet Flow and
RBCU 1A delta flow.
"* Verify ILPSW-18 (RBCU 1A Oultlet) open
"* Verify adequate LPSW flow is available; check LPSW pump
operation
" Monitor RBNS Level for any unexplained increase (Notify
Chemistry to sample RBNS for boron to determine if a
cooler rupture has occurred.
" Diagnose a Cooler Rupture is indicated and Isolate the 1A
RBCU Cooler.
SRO 2. The SRO should determine that isolation of LPSW to a RBCU
places the Unit in Tech Spec 3.0.3, which will require a unit
shutdown.
The control room will receive a phone call from security that
indicates that a tremor has been felt but no damage has been
noted.
SRO 3. The SRO should refer to AP/05, Earthquake.
- 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 soon
the next event Is started.
Note: Team may decide at this time to begin a unit shutdown.
Refer to event 6.
When the Earthquake AP has been initiated, the RBCU has
been isolated, or at the direction of the Lead Examiner this
event is completed.
Page 5 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 5 Page 1 of 2
Event Description: 1B SG Tube leak (ramp 10 - 100 gpm over 30 min) (C, ALL) (TS)
Time Position Applicant's Actions or Behavior
1B SG tube leak occurs following RBCU isolation and initiation of
AP/5, Earthquake, or when directed by the lead evaluator.
Plant response:
1. The following alarms actuate:
"* 1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH
"* 1SA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
2. PZR level will decrease and RC makeup flow will increase.
Crew response:
ALL 1. Diagnose and take actions for a Tube leak in the 1B SG:
BOP 2. Refer to the ARG for the following alarms:
"* 1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH
"* 1SA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
SRO 3. Refer to API1IAI1700/31 (Primary to Secondary Leakage)
BOP 4. Open and white Tag TB Sump pump breakers.
SRO 5. Monitor primary parameters; PZR Level and LDST level to
determine that gross leakage exist and transfer to step 4.65.
6. Determine OTSG tube leak size is initially less than 25 gpm.
Greater than 25 will require entering the EOP.
BOP 7. Log RIA readings (a rough log is adequate)
SRO 8. Initiate a Unit shutdown to met requirements of Encl. 5.1 (Unit
Shutdown Requirements).
Note: As the scenario develops the leak will increase to greater
than 25 gpm and transfer to the EOP will be required.
Page 6 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: __ Scenario No.: 2 Event No.: 5 Page 2 of 2
Event Description: lB SG Tube leak (ramp 10 - 100 gpm over 30 min) (C, ALL) (TS)
Time Position Applicant's Actions or Behavior
SRO 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.
10. EOP SGTR tab will perform the following:
"* Determine that the Reactor is not tripped.
"* Maintain PZR level > 220 inches using Enclosure 5.5 (Pzr
BOP and LDST Level Control). (CT-D.1)
> Open HP-24 and 25 (1A and 1B BWST Suction)
> Close 1HP-5
"* Monitor RIA-16 ("A" MS Header) and 17 ("B" MS Header) to
identify all SGs with tube ruptures.
"* Start the Outside Air Booster Fans on both Units 1 and 3.
11. The SRO should direct the OATC to begin a unit shutdown at a
SRO rate between 9.9% per hour and 20% per minute (MAXIMUM
RUNBACK).
Note: A shutdown with the ICS in manual Is required.
Note: This event will remain in progress for the remainder of the
scenario.
Page 7 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 6 Page 1 of 1
Event Description: Unit Shutdown (R, OATC)
Time Position Applicant's Actions or Behavior
BOP The BOP will utilize Enclosure 5.19 (Control of Plant Equipment
During Shutdown for SGTR).
Note: With the unit at z 25% power only applicable steps will be
performed.
Notify WCC SRO to make notifications
Transfer electrical auxiliaries
"* Place 1TA AUTO/MAN transfer switch in MAN
"* Place 1TB AUTO/MAN transfer switch in MAN
"* Close 1TA SU 6.9 KV FDR
"* Close 1TB SU 6.9 KV FDR
"* Place MFB1 AUTO/MAN transfer switches in MAN
"* Place MFB2 AUTO/MAN transfer switches in MAN
"* Close Ell MFB1 STARTUP FDR
"* Close E2 1 MFB2 STARTUP FDR
OATC/SRO The OATC will use the FDW Masters and the Diamond to reduce
power while monitoring Reactor Power, Tave, and other plant
parameters.
Ifthe reactor trips automatically the team must return to IMAs.
Note: the team may manually trip the reactor if PZR level cannot
be maintained with full HPI. This may occur because of the tube
leak and RCS cooldown.
When a unit shutdown of > 5% has occurred or when directed
by the lead examiner this event is concluded.
If the reactor is manually tripped activate event 7.
Page 8 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: __ Scenario No.: 2 Event No.: 7 Page 1 of 2
Event Description: 1A Main Steam line break in RB (M,ALL)
1A main steam line break will occur following event 6 as directed by
the lead examiner.
Time Position Applicant's Actions or Behavior
ALL Plant response:
Statalarm 1SA-02/A-9, MS Press High/Low, 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 Crew should respond to the MSLB in the "IA" SG
SRO 2. The SRO will "Parallel Action" to transfer to the Excessive Heat
Transfer (EHT) tab and direct the Crew's actions as follows:
3. The OATC will perform IMAs.
T> Depress REACTOR TRIP pushbutton
> Verify reactor power < 5% FP and decreasing
> Depress TURBINE TRIP pushbutton
> Verify all turbine stop valves closed
> Verify RCP seal injection available
4. The OATC will verify the performance of IMAs while the BOP
performs a symptoms check.
OATC 5. IfSCM = 0°F then the OATC will perform Rule #2 (Loss of SCM)
after receiving concurrence from the SRO. (CT-Al, A2)
"* Trip ALL RCPs within 2 minutes
"* Ensure open 1HP-24 and 1HP-25
"* Ensure ALL HPI pumps operating
"* Ensure open 1HP-26 and 1HP-27
"* Verify required HPI flow per header
"* Verify TBVs available
Page 9 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: __ Scenario No.: 2 Event No.: 7 Page 2 of 2
Event Description: 1A Main Steam line break in RB (M,ALL)
Time Position Applicant's Actions or Behavior
"* 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 (1FDW-33, 31, 42, 40) in
CLOSE:
"* Maintain SG pressure < RCS pressure
BOP 6. The BOP will perform Rule #5 (Main Steam Line Break) after
receiving concurrence from the SRO. (CT-B.I.3)
"* Stop 1A MDEFDW Pump
"* Initiate both trains of MSLB isolation
"* Ensure both Main FDW pumps tripped
"* Steam 1B SG to maintain CETCs constant
7. Enclosure 5.1 (ES Actuation) will be performed.
SRO 8. Excessive Heat Transfer (EHT) tab will:
& Verify excessive heat transfer stopped
BOP * Throttle HPI to stabilize RCS pressure and maintain PZR
level > 80" (180" acc)
- Verify letdown in service
B.1.1)
SRO * Minimize SCM using the following methods as necessary:
(CT-B.1.2)
>* De-energizing all PZR heaters
> Using PZR spray
> Throttling HPI
- Initiate Enclose 5.16 (SG Tube-to-Shell AT Control)
a 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.
Page 10 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, S1)
Facility: Oconee Scenario No.: 2 fnl rev.1 Op-Test No.:
Examiners: Operators: U-SRO (1-4)
I-OATC (1-3)
R-BOP (1-3)
Initial Conditions:
0 35% Reactor Power, shutdown in progress (IC-45)
Turnover:
"* Unit 1 TD EFDW Pump OOS to repair oil leak
"* AMSAC/DSS bypassed for I&E testing
"* NI-9 OOS, to be replaced next outage
"* "A" Condensate Booster Pump OOS, breaker to be replaced
"* Keowee Unit 2 00S 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, ONS to perform remote Keowee start
Event Malfunction Event Type* Event
No. No. Description
Ga Pre-insert TD EFDW Pump Fails to Start
MSS330
Gb Pre-insert AMSAC/DSS bypassed
Oc Pre-Insert NI-9 OOS
MN1082
Gd Pre-insert "A" MSLB circuit disabled
Ge Pre-insert Keowee Unit 2 Emergency Lockout
MEL180
Of Pre-insert "A" CBP Breaker racked out
0* R, OATC Unit Shutdown
1 Override N, BOP, SRO Operability test Keowee Unit 1
C, BOP, SRO Keowee Unit 1 Gen Field Flashing Breaker fails to
OPEN automatically
2 MPS090 C, OATC, SRO 1HP-120 (RC Volume Control) Fails closed
3 MN1032 I, OATC, SRO Controlling NI fails LOW
4 Override Seismic event (PRA)
C, BOP, SRO 1A RBCU rupture (TS)
5 MPS020 C, ALL 1B SG Tube leak (ramp 10 - 100 gpm over 30
5%-25% min) (TS)
6 R, OATC Unit Shutdown
7 MSS360,50 M, ALL 1A Main Steam line break in RB
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Page 1 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 0* Page 1 of 1
Event Description: Unit Shutdown (R, OATC)
Time Position Applicant's Actions or Behavior
OATC/SRO The OATC will use the FDW Masters and the Diamond to reduce
power from 35% to -28% 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.
Note: the OATC will turnover duties to another RO once power
change requirement is satisfied as determined by the lead
examiner.
Page la of 10
Aooendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: __ Scenario No.: 2 Event No.: 1 Page 1 of 1
Event Description: Operability test Keowee Unit I (N, BOP/SRO)
Keowee Unit I Gen Field Flashing Breaker falls to OPEN
automatically (C, BOP/SRO)
Time Position I Applicant's Actions or Behavior
SRO Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to
operability test unit 1 Keowee underground.
Use OP/1106/019 (Keowee Hydro At Oconee) to perform an
SOP "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 1 FIELD BREAKER closes
"* GEN 1 SUPPLY BREAKER closes
"* GEN 1 FIELD FLASHING BREAKER closes
3. Ensure GEN 1 FIELD FLASHING BREAKER trips.
- Candidate should diagnose that the breaker did not open
automatically and should open the breaker manually and
initiate a work request or contact SPOC.
SRO SRO should direct the BOP to continue with the startup.
Note: GEN FIELD FLASHING BREAKER automatically trips
< 45 seconds after receiving close signal. Failure of breaker to
trip automatically does NOT make the KHU Inoperable.
Startup procedure may continue.
SRO 4. Determines KHU #1 is operable when test complete
BOP 5. Verify ACB-1, Keowee 1 Generator Breaker, closed.
6. Verify Unit 1 EMER FDR ACB 3 closed
7. Verify ý 4.16 KV on CT4 Volts (2AB3)
8. Close SKi and SK2 (CT4 STBY BUS 1/2 FEEDER)
9. Shutdown Keowee #1.
Event is complete when operability test is complete or when
directed by the lead examiner.
Page 2 of 10
ADoendix D Scenario Outline Form ES-D-1 (R8, S1)
Op-Test No.: __ Scenario No.: 2 Event No.: 2 Page 1 of 1
Event Description: 1HP-120 (RC Volume Control) Fails closed (C, OATCISRO)
Time Position Applicant's Actions or Behavior
OATC 1HP-1 20 fails closed during Keowee #1 operability test. This will
allow OATC diagnoses of failure.
1. Diagnose 1HP-1 20 (RC Volume Control) Failed closed:
"* RCS makeup flow goes to zero.
"* PZR level begins to decrease.
"* LDST level begins to increase.
"* Valve position demand for 1HP-120 begins to increase to
the 100% demand value and valve position indication will
indicate closed (green light).
SRO 2. Refer to AP/14 (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 any HPI pump operating.
"* Verify RCP seal injection flow exists.
"* Verify RCP RCP seal injection or HPI makeup line leak is
not indicated.
"* Verify 1HP-120 has failed and GO TO Step 4.167.
"* Perform the following as necessary to maintain Pzr level >
200":
"* Close 1HP-6 (Letdown Orifice Stop)
"* Throttle 1HP-7 (Letdown Control)
"* Throttle 1HP-26 (1A HP Injection)
3. Contact SPOC to repair 1HP-120.
Note: IHP-120 will remain failed for the duration of the
scenario.
SRO Directs and supervises AP/14 implementation
When PZR level is being controlled manually or when directed
by the lead examiner this event is completed.
Page 3 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: Scenario No.: 2 Event No.: 3 Page 1 of 1
Event Description: Controlling NI fails LOW (I, OATC/SRO)
When directed by the lead examiner the controlling NI will fail low.
Time Position Applicant's Actions or Behavior
Plant response:
1SA-02/A-1 2, ICS Tracking, will actuate. Diamond will transfer to
manual on NI flux < 1.5% and FDW will decrease due to reactor
cross limit. RCS pressure and temperature will increase.
Crew response:
1. When the ICS TRACKING alarm is received, the candidates
should utilize the "plant stabilization process" to stabilize the
plant and recognize that the controlling NI has failed. RX will
trip on high pressure with no operator action.
OATC 2. Verify reactor power.
3. Place the FDW Masters in manual and stabilize the plant.
Adjust Ta* using control rods and FDW and stabilize the plant
SRO 4. 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.
"* 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.
Page 4 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 4 Page 1 of 1
Event Description: Seismic event (PRA)
1A RBCU rupture (C, BOP/SRO) (TS)
Time Position Applicant's Actions or Behavior
1. 1SA-9/B-9, LPSW RBCU A Cooler Rupture will actuate and RB
normal sump level will increase.
BOP * The BOP should refer to ARG for 1SA-9/B-9
"* Verify alarm is valid by checking RBCU 1A Inlet Flow and
RBCU 1A delta flow.
"* Verify 1LPSW-18 (RBCU 1A Oultlet) open
"* Verify adequate LPSW flow is available; check LPSW pump
operation
"* Monitor RBNS Level for any unexplained increase (Notify
Chemistry to sample RBNS for boron to determine if a
cooler rupture has occurred.
"* Diagnose a Cooler Rupture is indicated and Isolate the 1A
RBCU Cooler.
SRO 2. The SRO should determine that isolation of LPSW to a RBCU
places the Unit in Tech Spec 3.0.3, which will require a unit
shutdown.
The control room will receive a phone call from security that
indicates that a tremor has been felt but no damage has been
noted.
SRO 3. The SRO should refer to AP/05, Earthquake.
- 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 soon
the next event is started.
Note: Team may decide at this time to begin a unit shutdown.
Refer to event 6.
When the Earthquake AP has been initiated, the RBCU has
been isolated, or at the direction of the Lead Examiner this
event is completed.
Page 5 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, $1)
Op-Test No.: __ Scenario No.: 2 Event No.: 5 Page 1 of 2
Event Description: 1B SG Tube leak (ramp 10 - 100 gpm over 30 min) (C, ALL) (TS)
Time Position Applicant's Actions or Behavior
1B SG tube leak occurs following RBCU isolation and initiation of
AP/5, Earthquake, or when directed by the lead evaluator.
Plant response:
1. The following alarms actuate:
"* 1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH
"* 1SA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
2. PZR level will decrease and RC makeup flow will increase.
Crew response:
ALL 1. Diagnose and take actions for a Tube leak in the 1B SG:
BOP 2. Refer to the ARG for the following alarms:
"* 1SA-8/B-9, RM PROCESS MONITOR RADIATION HIGH
"* 1SA-8/D-10, RM CSAE EXHAUST RADIATION HIGH
SRO 3. Refer to AP/11A/1700131 (Primary to Secondary Leakage)
BOP 4. Open and white Tag TB Sump pump breakers.
SRO 5. Monitor primary parameters; PZR Level and LDST level to
determine that gross leakage exist and transfer to step 4.65.
6. Determine OTSG tube leak size is initially less than 25 gpm.
Greater than 25 will require entering the EOP.
BOP 7. Log RIA readings (a rough log is adequate)
SRO 8. Initiate a Unit shutdown to met requirements of Encl. 5.1 (Unit
Shutdown Requirements).
Note: As the scenario develops the leak will increase to greater
than 25 gpm and transfer to the EOP will be required.
Page 6 of 10
Appendix D Scenario Outline Form ES-D-11 (R8, $1)
Op-Test No.: __ Scenario No.: 2 Event No.: 5 Page 2 of 2
Event Description: 1B SG Tube leak (ramp 10 - 100 gpm over 30 min) (C, ALL) (TS)
Time Position Applicant's Actions or Behavior
SRO 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.
10. EOP SGTR tab will perform the following:
"* Determine that the Reactor is not tripped.
"* Maintain PZR level > 220 inches using Enclosure 5.5 (Pzr
BOP and LDST Level Control). (CT-D.1)
- Open HP-24 and 25 (1A and 1B BWST Suction)
>Close 1HP-5
"* Monitor RIA-16 ("A" MS Header) and 17 ("B" MS Header) to
identify all SGs with tube ruptures.
"* Start the Outside Air Booster Fans on both Units 1 and 3.
11. The SRO should direct the OATC to begin a unit shutdown at a
rate between 9.9% per hour and 20% per minute (MAXIMUM
RUNBACK).
Note: A shutdown with the ICS in manual is required.
Note: This event will remain in progress for the remainder of the
scenario.
Page 7 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 6 Page 1 of 1
Event Description: Unit Shutdown (R, OATC)
Time Position Applicant's Actions or Behavior
BOP The BOP will utilize Enclosure 5.19 (Control of Plant Equipment
During Shutdown for SGTR).
Note: With the unit at ý 25% power only applicable steps will be
performed.
Notify WCC SRO to make notifications
Transfer electrical auxiliaries
"* Place 1TA AUTO/MAN transfer switch in MAN
"* Place 1TB AUTO/MAN transfer switch in MAN
"* Close 1TA SU 6.9 KV FDR
"* Close 1TB SU 6.9 KV FDR
"* Place MFB1 AUTO/MAN transfer switches in MAN
"* Place MFB2 AUTO/MAN transfer switches in MAN
"* Close Ell MFBl STARTUP FDR
"* Close E2 1 MFB2 STARTUP FDR
OATC/SRO The OATC will use the FDW Masters and the Diamond to reduce
power while monitoring Reactor Power, Tave, and other plant
parameters.
Ifthe reactor trips automatically the team must return to IMAs.
Note: the team may manually trip the reactor if PZR level cannot
be maintained with full HPI. This may occur because of the tube
leak and RCS cooldown.
When a unit shutdown of > 5% has occurred or when directed
by the lead examiner this event is concluded.
If the reactor is manually tripped activate event 7.
Page 8 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Sl)
Op-Test No.: __ Scenario No.: 2 Event No.: 7 Page 1 of 2
Event Description: 1A Main Steam line break In RB (M, ALL)
1A main steam line break will occur following event 6 as directed by
the lead examiner.
Time Position Applicant's Actions or Behavior
ALL Plant response:
Statalarm 1SA-02/A-9, MS Press High/Low, 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 Crew should respond to the MSLB in the "IA" SG
2. The SRO will "Parallel Action" to transfer to the Excessive Heat
SRO Transfer (EHT) tab and direct the Crew's actions as follows:
3. The OATC will perform IMAs.
T> Depress REACTOR TRIP pushbutton
> Verify reactor power < 5% FP and decreasing
> Depress TURBINE TRIP pushbutton
> Verify all turbine stop valves closed
> Verify RCP seal injection available
4. The OATC will verify the performance of IMAs while the BOP
performs a symptoms check.
OATC 5. If SCM = 00 F then the OATC will perform Rule #2 (Loss of SCM)
after receiving concurrence from the SRO. (CT-Al, A2)
"* Trip ALL RCPs within 2 minutes
"* Ensure open 1HP-24 and 1HP-25
"* Ensure ALL HPI pumps operating
"* Ensure open 1HP-26 and 1HP-27
"* Verify required HPI flow per header
"* Verify TBVs available
I I
Page 9 of 10
Appendix D Scenario Outline Form ES-D-1 (R8, Si)
Op-Test No.: __ Scenario No.: 2 Event No.: 7 Page 2 of 2
Event Description: 1A Main Steam line break In RB (M, ALL)
Time Position Applicant's Actions or Behavior
"* 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 (1FDW-33, 31, 42, 40) in
CLOSE:
"* Maintain SG pressure < RCS pressure
BOP 6. The BOP will perform Rule #5 (Main Steam Line Break) after
receiving concurrence from the SRO. (CT-B.1.3)
"* Stop 1A MDEFDW Pump
"* Initiate both trains of MSLB isolation
"* Ensure both Main FDW pumps tripped
"* Steam 1B SG to maintain CETCs constant
7. Enclosure 5.1 (ES Actuation) will be performed.
SRO 8. Excessive Heat Transfer (EHT) tab will:
- Verify excessive heat transfer stopped
BOP * Throttle HPI to stabilize RCS pressure and maintain PZR
level > 80" (180" acc)
- Verify letdown in service
B.1.1)
SRO * Minimize SCM using the following methods as necessary:
(CT-B.1.2)
> De-energizing all PZR heaters
> Using PZR spray
> Throttling HPI
- Initiate Enclose 5.16 (SG Tube-to-Shell A T 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.
I
______________________________
Page 10 of 10
CREW TURNOVER
(Revised)
INITIAL CONDITIONS:
1. Unit 1: MODE 1, 35% Reactor Power
- 430 EFPD
- Shutdown in progress
2. Unit 2: MODE 1, 100% Reactor Power
3. Unit 3: MODE 1,100% Reactor Power
TURNOVER:
1. Unit 1 TD EFDW Pump OOS to repair oil leak, expected returned this shift
- TS 3.7.5, Condition "B", 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time
2. AMSAC/DSS bypassed for I&E testing
0 SLC 16.7.2, Condition "A"and "B", 7 day completion time
3. NI-9 00S, to be replaced next outage
"* SLC 16.10.5
"* TS 3.3.13, Condition "A", 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time
5. "A" Condensate Booster Pump OOS, breaker to be replaced
6. Keowee Unit 2 00S for unplanned reasons
- TS 3.8.1, Condition "C", 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time
7. Keowee Unit 1 aligned to underground
8. To satisfy SR 3.8.1.3, the operability test of Keowee Unit 1 is to be performed per PT/620/009
(Keowee Hydro Operation), ONS to perform remote Keowee start
9. Begin Enclosure 3.2 (Power Reduction) of OP/11/Al1021004, Operation At Power, after turnover.
Scenario 2