ML091110260
| ML091110260 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/13/2009 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-269/09-301, 50-270/09-301, 50-287/09-301, ES-D-1 50-269/09-301, 50-270/09-301, 50-287/09-301 | |
| Download: ML091110260 (66) | |
Text
Appendix D Scenario Outline Form ES-D-1 March,2009 Facility: Oconee Scenario No.: 1 RO FS Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
65% Reactor Power EOL (SNAP 202) 1 B2 RCP OOS-secured -2 hrs ago Xe building up from down power maneuver Turnover:
AMSAC/DSS bypassed for I&E testing SASS in Manual for I&E testing on SG level and Pzr levels.
0.3 gpm leak into the RBNS (LPSW)
Event Malfunction Event Type*
Event No.
No.
Description Oa Pre-Insert AMSAC/DSS bypassed Updater Ob Pre-Insert 1 HP-24 and 1 HP-25 fail closed Updater Oc Pre-Insert SASS in Manual Updater Od
- MP1300, Reactor fails to trip automatically AOR Will trip from CR 1
Override N, BOP, SRO Pump RBNS, 1 LWD-2 fails to close (TS) 2 MCS008 C, BOP, SRO Seismic event Failure of AS Controller 3
MPI160 I, OATC, SRO Th Fails High MPI171 4
Override C, BOP, SRO 1A RBCU RuptLJre (TS) 5 MPS110 C,OATC,SRO 1 HP-5 fails closed (air line break) (TS) 6 MPS010 ALL 1A SGTL 1 - 50 gpm over 10 minutes, (TS) 7 R, OATC, SRO Manual Plant Shutdown 8
Override C,OATC,SRO 1 A2 RCP Trips, Reactor fails to trip 9
Override M, ALL Blackout MEL 180 CT -1 Lockout KHU 2 Emergency Lockout Regain power from Keowee Unit 1 via UG
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Page 1 of 21
Appendix D Scenario Outline Form ES-D-2 March. 2009 Op-Test No.: __ Scenario No.: 1 Event No.: 1 Page 1 of 1 Event
Description:
Pump RBNS, 1 LWO-2 fails to close: (N, BOP/SRO) (TS)
Time Position BOP/SRO Applicant's Actions or Behavior Crew response:
BOP uses OP/11A111 04/007 Encl 4.1 to pump the Reactor Building Normal Sump (RBNS).
OP/1/A/1104/007 Ene! 4.1 Verify MWHUT level adequate to receive waste volume.
Position the following:
o Open 1 LWD-1 (RB NORMAL SUMP ISOLATION) o Open 1 LWD-2 (RB NORMAL SUMP ISOLATION).
Fire Timer # 1 to fail 1 LWO-1 open Start one or both of the following:
NOTE:
Changes in LAWT levels may occur during pumping.
RIA Alarms may be indicative of gas leakage.
If RBNS level was above 14" when pumps were started a level increase following securing the RBNS pumps may occur.
WHEN RBNS level is at desired level or:::: 6" (low level alarm).
THEN ensure pump(s) stopped.
Position the following:
o Close 1 LWD-1 (RB NORMAL SUMP ISOLATION) o Close 1 LWD-2 (RB NORMAL SUMP ISOLATION).
NOTE: 1 LWO-2 will fail to close SRO will refer to TS 3.6.3 (Containment Isolation) Condition A. De-energize 1 LWD-1 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The event is complete when TS 3.6.3 is referred to or when determined by the Lead Examiner.
Page 2 of 21
Appendix D March,2009 Op-Test No.: __
Event
Description:
Timer #2 Time Position BOP/SRO SRO/BOP Scenario Outline Form ES-D-2 Scenario No.: 1 Event No.: 2 Page 1 of 1 Seismic event Failure of AS Controller: (C, BOP/SRO)
Applicant's Actions or Behavior Cue: Call the Control Room (4911) as security to report a seismic event but no plant damage is visible.
Fire Timer #2 to fail Unit 3 AS header controller Plant response:
1 SA06/C-1 0, AS HDR PRESS LOW will actuate 1MS-126 & 1MS-129 MAIN STM TO SU STM PRESS controller will indicate AS pressure < 300 psig and decreasing.
Crew response:
SRO may enter AP/5, Earthquake; NEOs perform inspections.
1 SA06/C-1 0 Verify proper operation of MS/AS controller on Unit supplying Auxiliary Steam Header (U3).
IF necessary, transfer AS Header to another Unit per OP/1/A/1106/22 (Auxiliary Steam System).
Cue: when called by Unit 1 as Unit 3, direct U1 to take control of the AS header.
OP/1/A11106/22 (Auxiliary Steam System) Enc14.2 Notify Unit 3 to reduce setpoint on AS controller.
Ensure 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller in "MANUAL".
Ensure closed 1 MS-126 & 1 MS-129 (MAl N STM TO SU STM PRESS).
Perform one of the following: Open 1 MS-24 (or Open 1 MS-33 )
Manually throttle open 1 MS-126 & 1 MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure.
Continue to throttle 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) to increase Aux Steam Header pressure to== 300 psig.
WHEN Aux Steam Header is== 300 psig: Adjust 1 MS-126 & 1 MS-129 (MAIN STM TO SU STM PRESS) controller setpoint to match Aux Steam Header pressure.
Place 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller to "AUTO".
Notify Unit 3 to secure AS supply.
When directed by the team, Fire Timer #15 to secure Unit 3 supplying Aux Steam When the Unit 1 AS controller is in AUTO or when directed by the lead examiner this event is completed.
Page 3 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 3 Page 1 of 1 Event
Description:
Th Fails HIGH (I, OATC/SRO Timer #3 Time Position Applicant's Actions or Behavior Pla'nt Response:
1A Th will fail HIGH Tave will indicate HIGH Feedwater flow will increase Control Rods will insert 1SA-2/B3 (RC Hot Leg Temp High) 1SA-2/B4 (RC Average Temperature High/Low) 1SA-2/A12 (ICS Tracking)
Crew Response:
When the Statalarms are received, the candidates should utilize the "Plant Transient Response" process to stabilize the plant.
Verbalize to the SRO reactor power level and direction of movement.
OA TC Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant.
The SRO should:
o Refer to AP/28, ICS Instrument Failures o
Contact SP~C to repair the failed instrument.
Note: The ICS will remain in manual for the remainder of the scenario.
SRO/OATC AP/1/A11700/028, ICS Instrument Failures Verify plant conditions are stable as indicated by the following:
NI power change of < 2% from current NI power indication AND thermal power best:::; pre-transient power level Tave change of < 2°F from current Tave indication THP/SG Outlet Pressure change of < 30 psig from current THP/SG Outlet Pressure RCS pressure change of < 150 psig from current RCS pressure GO TO the section 4A (RCS Temperature)
Notify sp~c BOP PERFORM an instrumentation surveillance using applicable table in Encl 5.3 (ICS Instrument Surveillances) for the failed instrument.
Verify computer readouts 01A1692 and 01A1693 agree within 3°F When Encl 5.3 has been performed, or when directed by the lead examiner this event is completed.
Page 4 of 21
Appendix 0 March,2009 Op-Test No.: __
Event
Description:
Timer #4 Time Position BOP SRO Scenario Outline Form ES-O-2 Scenario No.: 1 Event No.: 4 Page 1 of 2 1A RBCU rupture (C, BOP/SRO) (TS)
Applicant's Actions or Behavior NOTE: Event 5 will be initiated concurrently with Event 4.
Plant Response:
1 SA-9/B-9, LPSW RBCU A Cooler Rupture 1SA-9/A-6, RB Normal Sump Level High/Low RB normal sump level will increase Crew Response:
ARG for 1 SA-9/B-9 Verify alarm is valid by checking RBCU 1 A Inlet Flow and RBCU 1 A delta flow.
Verify 1 LPSW-18 (RBCU 1A Outlet) open Verify adequate LPSW flow is available; check LPSW pump operation Monitor RBNS Level for any unexplained increase (Notify Chemistry to sample RBNS for boron to determine if a cooler rupture has occurred.
Diagnose a Cooler Rupture is indicated and Isolate the 1 A RBCU Cooler.
Enter TS for RBCU inoperable (TS 3.6.5 Condition B).
Close 1 LPSW-16 (1A RBCU INLET) o Fire Timer 5 - To Initiate Event 5 (1 HP-5 Fails Closed)
Perform TS 3.6.3 Condition C for closed containment system.
Open vent or drain.
Close 1 LPSW-18 (1A RBCU OUTLET)
Refer to SLC 16.9.12 (Additional LPSW and Siphon Seal Water System Operability Requirements)
Page 5 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 4 Page 2 of 2 Event
Description:
1A RBCU rupture (C, BOP/SRO) (TS) lillie Position Applicant's Actions or Behavior SRO SRO may conservatively enter AP/05, Earthquake Dispatch operators to perform plant inspections Note: No damage will be reported.
- Notify SP~C 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.
When the RBCU has been isolated, or at the direction of the Lead Examiner this event is completed.
Page 6 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 1 of 2 Event
Description:
1HP-5 Fails Closed (air line break) (C,OATC/SRO)
Timer #5 Time Position Applicant's Actions or Behavior Plant Response:
OATC 1 HP-5 green closed light is lit Pzr Level slowly increases LDST Level slowly decreases Crew Response:
OATC/SRO Enters AP/32, Loss of Letdown Place 1 HP-120 in HAND and reduce demand to zero.
Initiate makeup to LDST as required.
Position the standby HPI pump switch to OFF.
Throttle 1 HP-31 to establish 12 - 15 gpm SEAL INLET HDR FLOW.
GO TO Step 4.10 per Table in AP/32 Close 1 HP-6.
Close 1 HP-7.
Open 1 HP-5.
Open 1 HP-5 RNO actions as follows:
o Dispatch NEO in continuous communications with control room to manually open 1 HP-5 NEO manually opens 1 HP-5 NOTE: This will tie up the control room phone used and one phone in the console for the rest of the scenario o
Enter TS 3.6.3 When 1 HP-5 is open, THEN continue.
Place CC system in operation.
Verify letdown temperature < 135°F.
Throttle 1 HP-7 to establish -20 gpm Open 1 HP-6 Adjust 1 HP-7 to control desired letdown flow.
Page 7 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 5 Page 1 of 2 Event
Description:
1HP-S Fails Closed (air line break) (C, OATC/SRO)
Time Position Applicant's Actions or Behavior OATC/SRO Re-establish normal makeup through 1 HP-120.
Notify SPOC to initiate repairs on 1 HP-5.
Verify seal injection flow reduced in Step 4.7.
Re-establish normal RCP seal injection flow.
Position the standby HPI pump switch to AUTO.
WHEN repairs are complete on 1 HP-5 (LETDOWN ISOLATION)
(East Pen Rm), THEN perform the following:
A. _ Locally turn 1 HP-5 handwheel fully clockwise.
B.
EXIT TS 3.6.3.
NOTE: 1 HP-S will not be repaired during this scenario When 1 HP-S is manually opened and NEO is stationed locally then this event is complete or when directed by Lead Examiner.
Page 8 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 6 Page 1 of 2 Event
Description:
1A SGTL 1 - 50 gpm over 10 minutes: (SRO) (TS)
Timer#6 Time Position Applicant's Actions or Behavior Plant response:
1SA8/A9 (RM AREA MONITOR RADIATION HIGH)
BOP/SRO 1 SA8/E1 0 (N-1-6 RM PRIMARY TO SECONDARY TUBE LEAK) 1 SA8/D1 0 (RM CSAE EXHAUST RADIATION HIGH)
SRO 1SA8/B9 (RM PROCESS MONITOR RADIATION HIGH) 1 RIA 59 indicating 3 gpm increasing NOTE: Leak rate will ramp to 50 gpm over the next 10 minutes.
Crew response:
Enter AP/31 (Primary to Secondary Leakage)
IAAT primary to secondary leak rate is ~ 25 gpm (36,OOOgpd),
THEN GO TO Unit 1 EOP.
IAAT either of the following exists for 1 RIA-54: is in High alarm or inoperable; THEN Dispatch an operator to open and white tag the following:
1XD-R3C (1A TURBINE BUILDING SUMP PUMP BKR) 1XE-R3D (1B TURBINE BUILDING SUMP PUMP BKR)
IAA T gross tube leakage is indicated by ali increase in normal RC makeup flow, THEN GO TO Step 4.79.
Verify OAC primary to secondary leak rate calculation available (including 1 RIA-40 operable).
Determine primary to secondary leakage rate using OAC point 01P1599 (EST TOTAL PRI TO SEC LEAKRATE).
Page 9 of 21
Appendix D Scenario Outline' Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 6 Page 2 of 2 Event
Description:
1A SGTL 1*50 gpm over 10 minutes: (SRO) (TS)
Time Position BOP/SRO Applicant's Actions or Behavior Crew response:
AP/31 (Primary to Secondary Leakage)... continued Make notifications of primary to secondary leakage per OMP 1-14 Initiate a unit shutdown using the following as necessary to meet requirements of Encl 5.1 (Unit Shutdown Requirements):
o AP/29 (Rapid Unit Shutdown) o OP/1/A11102/004 (Operation at Power) o OP/1/A11102/010 (Controlling Pro(;edure for Unit Shutdown)
IAA T primary to secondary leakage increases, THEN modify shutdown as required by Encl 5.1 (Unit Shutdown Requirements).
Notify Radwaste to stop all liquid releases in progress until sample results assure release rates within limits.
Stop all gaseous releases in progress until sample results assure release rates within limits.
Make up to the UST only as necessary to maintain UST level> 7'.
Event is complete when EOP entry is made or when directed by the lead examiner.
Page 10 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 1 of2 Event
Description:
Manual Plant Shutdown: (R, OATC/SRO)
Time Position BOP/SRO OATC Applicant's Actions or Behavior Crew response:
SGTR tab of EOP Maintain Pzr level;:: 220" by initiating Encl 5.5 (pzr and LDST Level Control).
o Utilize the following as necessary to maintain desired Pzr level:
Standby HPI pump 1 HP-26 1 HP-7 1 HP-5 1 HP-120 setpoint or valve demand o
If LDST tank level cannot be maintained, Open 1 HP-24/25 and close 1HP-16.
IAAT Pzr level decreasing with all available HPI, AND Rx power is > 18%, THEN perform the following:
o Trip the Rx.
o GO TO IMA tab.
Verify all of the following:
o Rx power> 40%
o 1 RIA-59 operable o
1 RIA-60 operable Determine leak rate using the following:
o 1 RIA-59 o
1RIA-60 Notify OSM of SGTR leakrate Initiate manual power reduction to < 15%.
o Use control rods and lead with FDW masters.
Initiate Encl. 5.19 (Control of Plant Equipment During Shutdown for SGTR).
WHEN, < 15% power and auxiliaries transferred, continue Page 11 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 7 Page 2 of 2 Event
Description:
Manual Plant Shutdown: (R, OATC/SRO)
Time Position BOP SRO Applicant's Actions or Behavior Initiate Encl 5.19 (Control of Plant Equipment During Shutdown for SGTR).
Monitor RIAs to identify all SGs with a tube rupture:
o 1RIA-16/17 o
1 RIA-59/60 when Rx power> 40%
Start the TURBINE TURNING GEAR OIL PUMP, 1A through 1 E TURBINE BRNG OIL LIFT PUMPs, TURBINE MOTOR SUCTION PUMP Transfer electrical auxiliaries Notify CR SRO that unit auxiliaries have been transferred.
Start the AlB OUTSIDE AIR BOOSTER FANs (CT-27) (within 30 minutes of entry condition to the EOP for a SGTR (25 gpm leak>>
Notify Unit 3 to start the 3A13B OUTSIDE AIR BOOSTER FANs Stop the 1A11 B MSRH DRN PUMPs Place 1 FDW-53/65 in manual and close.
Place 1 HD-37/52 in DUMP.
Place 1A11 B FDWP SEAL INJECTION PUMP switch to START.
Start 1A11 B FDWP AUXILIARY OIL PUMP.
WHEN Rx power is < 80%, THEN stop the 1 E1/1 E2 HTR DRN PUMPs SGTR Tab Cont.
WHEN both of the following exist:
o Reactor power is== 15% FP o
Unit auxiliaries have been transferred o
THEN continue in this procedure.
Depress turbine TRIP pushbutton.
Verify all TURBINE STOP VALVES closed.
Open the following:
o PCB 20 o
PCB 21 Perform the following:
o Open the Generator Field Breaker.
o Position EXCITATION switch to OFF.
Verify TBVs controlling SG pressure as expected.
Reduce Rx power to s 5% FP.
Event is complete when reactor power has been reduced ~
5-15% or when directed by the lead examiner.
Page 12 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 8 Page 1 of 1 Event
Description:
1A2 RCP Trips; Reactor fails to trip: (C, OATC, SRO)
Quick Stike: 1A2 RCP OFF I
Time Position Applicant's Actions or Behavior Plant response:
1SA1/A1, B1, C1, D1 (RPCHANNELA, B,C,DTRIP) 1SA1/B7, B7, C7, D7 (RP CHANNEL A, B, C, D RCP/FLUX TRIP) 1SA2IA-3 (RC LOOP A FLOW LOW) 1SA1/A-5 (RC TOTAL FLOW LOW)
Crew response:
OATC/SRO Crew recognizes that the reactor should have tripped but did not.
BOP/SRO SRO OATC to SRO "Reactor Should Have Tripped" SRO directs the OATC to perform Immediate Manual Actions (IMAs)
OATC depresses the Rx TRIP pushbutton. (CT-24) (within 30 seconds of reactor trip conditions)
NOTE: Reactor will trip when the pushbutton is depressed.
Verify reactor power < 5% FP and decreasing.
Depress turbine TRIP pushbutton.
Verify all turbine stop valves closed.
Verify RCP seal injection available.
SRO directs the BOP to perform a Symptoms Check:
Verify reactor power < 5% FP and decreasing Verify All SCMs > OaF Verify no loss of heat transfer Verify no excessive heat transfer Inform SRO that a SGTR does exist.
Transfers to EOP Subsequent Actions Performs Parallel Actions page Event is complete when the reactor has been manually tripped or when directed by the lead examiner.
Page 13 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 1 of 7 Event
Description:
Blackout: (M, ALL)
Timer #9 Time Position OATC/SRO BOP OATC/BOP Applicant's Actions or Behavior Plant response:
KHU #2 Emergency Lockout CT -1 Lockout MFBs will de-energize Crew response:
Perform Immediate Manual Actions (IMAs)
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.
IF CC is unavailable, THEN immediately perform the following:
AP/25 o
Stop all RCPs.
o Notify CR SRO to initiate AP/25 (Standby Shutdown Facility Emergency Operating Procedure).
Obtain the following items:
Vital area access key ring Flashlight Proceed to the SSF.
NOTE: BOP will be stopped before leaving the control room and informed that Unit 2 RO will perform SSF actions.
Perform Symptom Check Power Range Nls < 5% decreasing All SCMs > OaF Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW); TDEWFP will be available Uncontrolled Main steam line(s) pressure decrease SGTR CSAE Offgas alarms Process monitor alarms (RIA-40, 59, 60)
Area monitor alarms (RIA-16/17)
Page 14 of 21
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 2 of 7 Event
Description:
Blackout: (M, ALL)
Time Position OATC Applicant's Actions or Behavior Crew response:
Rule 3 (Loss of Main Feedwater(only))
IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND any of the following exist:
oRCS pressure reaches 2300 psig OR o
NDT limit _ Pzr level reaches 375" [340" acc]
o THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Start EFDW pumps to feed all intact SGs (TDEFWP)
Verify any SCM:::; O°F; RNO-If overcooling or exceeding Rule 7 limits, THEN throttle EFDW as necessary.
Initiate Encl. 5.9, Extended EFW Operation o
Make up to the UST o
Start TDEFWP BEARING OIL COOLING PUMP SRO SRO will transfer to EOP Subsequent Actions and transfer to the BLACKOUT tab from the Parallel Actions Page Notify plant staff Emergency Dose limits are in affect.
Direct an RO to announce plant conditions using the plant page and notify the OSM to reference EP and NSD 202.
SRO will direct the BOP to perform Encl. 5.38 (Restoration of Power)
Page 15 of 21
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.:_-,--
Scenario No.: 1 Event No.: 9 Page 3 of 7 Event
Description:
Blackout: (M, ALL)
Time Position SRO Applicant's Actions or Behavior Crew response:
Blackout Tab Position the following to OFF:
o 1AMD EFDWP o
1B MD EFDWP Feed and steam available SGs as necessary to stabilize RCS PIT.
NOTE:
Feeding SGs with EFDW is desired above HPI Forced Cooling.
Step 6 should be performed prior to re-performing Rule 3.
IAA T EFDW from any source is insufficient to maintain stable RCS PIT, THEN notify SSF operator that feedingSGs with SSF ASW is required.
IAAT power is restored to any of the following:
1TC 1TD 1TE THEN Initiate AP/11 (Recovery from Loss of Power).
(SEE NEXT PAGE FOR AP/11 steps)
GO TO Subsequent Actions Tab SRO will continue in Blackout Tab until power is restored then go back to the above IAAT step, initiate AP/11 and then transfer to the Subsequent Actions tab.
SRO will transfer to the SGTR tab from the parallel Actions Page Page 16 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 4 of 7 Event
Description:
Blackout: (M, ALL)
Time Position OATC/BOP Applicant's Actions or Behavior Crew response:
RO will perform Encl. 5.38 (Restoration of Power) (CT-8) (Not met if Encl. 5.38 completed with power NOT restored.)
Place 1 HP-31 in HAND and reduce demand to O.
Close 1HP-21.
Verify MFB1/2 energized (NOT); GO TO Step 8 Verify CT-1 indicates - 4160 volts (NOT); GO TO Step 18 Verify both STNDY Busses de-energized Verify both Keowee units operating (NOT)
Emergency start Keowee units Notify Keowee Operator to place all Keowee units in Oconee Control.
Ensure one of the following is closed for an operating Keowee unit:
o UNIT 1 EMER FDR ACB 3 (restores power)
Verify CT-4 indicates::::: 4160 volts.
Place the following transfer switches in MAN:
o CT 4 BUS 1 AUTO/MAN o
CT 4 BUS 2 AUTO/MAN Place the following switches in ON:
oSTBY BUS 1 SYNCHRONIZING oSTBY BUS 2 SYNCHRONIZING Close the following breakers:
o SK1 CT4 STBY BUS 1 FEEDER o
SK2 CT 4 STDY BUS 2 FEEDER Place the following switches in OFF:
oSTBY BUS 1 SYNCHRONIZING oSTBY BUS 2 SYNCHRONIZING Verify Standby Bus #1 energized.
Place the following switches in MAN:
o MFB1 AUTO/MAN o
MFB2 AUTO/MAN o
STANDBY 1 AUTO/MAN o
STANDBY 2 AUTO/MAN Open the following breakers:
o N11 MFB1 NORMAL FDR o
N21 MFB2 NORMAL FDR o
E11 MFB1 STARTUP FDR o
E21 MFB2 STARTUP FDR Close the following breakers:
o S1 1 STBY BUS 1 TO MFB1 o
S21 STBY BUS 2 TO MFB2 Page 17 of21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 5 of 7 Event
Description:
Blackout: (M, ALL)
Time Position OATC/BOP Applicant's Actions or Behavior Crew response:
Having just completed Encl. 5.38, the SRO may direct an RO to perform AP/11 AP/11 (Recovery from Loss of Power).
Announce AP entry using the PA system.
Verify load shed has initiated Verify load shed is complete as indicated by LOAD SHED COMPLETE on any ES Module (Channel 1 or 2).
Close the following breakers:
1TC INCOMING FDR BUS 1/2 1TD INCOMING FDR BUS 1/2 1TE INCOMING FDR BUS 1/2 Verify a 230KV Switchyard Isolation has occurred. (It has NOT)
Simultaneously press RESET on both of the following pushbuttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
MFB UNDERVOL TAGE CHANNEL 1/2 RESET Verify all condensate flow has been lost for < 25 minutes and condensate operation is desired. If condensate flow is lost> 25 minutes, place all CBPs to OFF and GO TO Step 4.34 o
Place all HWP control switches to OFF.
o Place all CBP control switches to OFF.
o Place 1 FDW-53/65 in MANUAL and close.
o Place 1C-10 FAIL SWITCH in MANUAL.
o Close 1C-10.
o Using a plant page, clear TB Basement and TB third floor of non-essential personnel.
o Start one HWP Dispatch an operator to "Restore Loads Outside the Control Room".
Page 18 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 6 of 7 Event
Description:
Blackout: (M, ALL)
Time Position OATC/BOP Applicant's Actions or Behavior An RO could be performing Encl. 5.5, once power has been restored, as described below.
Crew response:
RO will make up to RCS per Ene!. 5.5 (Pzr and,LDST Level Cont)
Utilize the following as necessary to maintain desired Pzr level:
Standby HPI pump 1 HP-26 1HP-7 1HP-5 1 HP-120 setpoint or valve demand IAAT LOST level CANNOT be maintained, THEN open 1 HP-24, open 1 HP-25 and close 1 HP-16.
NOTE: 1 HP 24 and 1 HP-25 fail closed.
IF both BWST suction valves (1 HP-24 and 1 HP-25) are closed, THEN perform the following: (CT-30) (CT requires supplying HPI suction from LPI before HPI pumps lose suction. i.e.
low/cycling amps.)
Start 1A LPI PUMP.
Start 1 B LPI PUMP.
Open the following:
1 LP-15 1 LP-1 (3 1 LP-9 1 LP-1 0 1 LP-6 1LP-7 IF two LPI Pumps are running only to provide HPI pump suction, THEN secure one LPI pump.
Dispatch an operator to open 1 HP-363 (LETDOWN LINE TO LPI PUMP SUCTION BLOCK)
Page 19 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 1 Event No.: 9 Page 7 of 7 Event
Description:
Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Once power is restored and the SRO has transferred out of the SBO tab to Subsequent Actions, the SRO will transfer to the SGTR tab.
Crew response:
ALL SGTR tab Maintain Pzr level 140" - 180" Start A and B Outside Air Booster Fan (CT-27)
Notify Unit 3 to start 3A and 3B Outside Air Booster Fans Monitor RIAs 16 and 17 to identify all SGs with a tube rupture.
Notify RP to survey both MS lines for radiation.
Secure any unnecessary offsite release paths. (Main Vacuum Pumps, TDEFDWP, Emergency Steam Air Ejector, etc.)
Open the following:
o 1 HP-24 o
1 HP-25 NOTE: 1 HP-24 and 1 HP-25 fail closed. See previous page for step to align Secure makeup to LOST.
Maintain both SG pressures < 950 psig using either of the following: 1) TBVs 2) Dispatch two operators to perform End 5.24 (Operation of the ADVs)
Minimize core SCM using the following methods: (CT-7) (Will fail CT if SCM is lost due to reduction in SCM. Progress must be made in reducing SCM.)
o De-energize all Pzr heaters o
Use Pzr spray o
Maintain Pzr level 140" - 180" IAAT RCS de-pressurization methods are inadequate in minimizing core SCM, o
Cycle PORV as necessary When crew takes action to minimize SCM or when directed by the lead examiner, the event is complete.
Page 20 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 CRITICAL TASKS
- 1. CT-24, ATWS
- 2. CT-30, Control RCS Inventory
- 3. CT-27, Implementation of Control Room Habitability Guidance
- 4. CT-7, Minimize SCM
- 5. CT-8, Electrical Power Alignment Page 21 of 21
Appendix D Scenario Outline Form ES-D-1 March,2009 Facility: Oconee Scenario No.: 2 RO FS Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
100% Reactor Power (SNAP-205)
Turnover:
SASS in Manual
- AMSACIDSS bypassed for I&E testing 1 NI-9 OOS, to be replaced next outage "1A" SG AFIS Digital Channel 1 auto-initiate circuit OOS-TS "A" Condensate Booster Pump OOS, breaker to be replaced
- 1 B MFDWP on Handjack for MGU work; completed; NEO on station at 1 B MFDWP I&E performing instrument calibrations Event Malfunction Event Type*
Event No.
No.
Description Oa Pre-Insert AMSAC/DSS bypassed Ob Pre-Insert NI-900S MNI082 Oc Pre-Insert "A" AFIS circuit disabled AOR "B" AFIS circuit disabled Od Pre-Insert ES channels 7 and 8 fail to actuate Oe Pre-Insert 1 HP-26 failed closed Of Pre-Insert 1A MDEFWP fails to start 1
N, BOP, SRO Remove/restore 1 B MFWP from Hand Jack 2
Override C, BOP, SRO Inadvertent ES Channel 4 actuation (TS) 3 Override C, OATC, SRO Pressurizer Spray Valve fails open 4
MPI050 I, OATC, SRO RC Loop B Flow Fails LOW MPI080 Small RCS Leak (TS) 5 MPS400 C, BOP, SRO RCS Leak, 50 gpm 6
R, OATC, SRO Manual power reduction due to RCS Leak 7
- MSS370, M, ALL 1 B Main Steam line break in RB 100 ES Channels 7 & 8 fail to actuate
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)ajor Page 1 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
1 Page 1 of 1 Event
Description:
Remove 1 B MFWP from Handjack (N, BOP/SRO)
Time Position SRO BOP Applicant's Actions or Behavior Direct BOP to perform OP/1/N11 06/002 B (FWPT Operation),
Encl. 4.13, Taking the 1 B FDWPT Off Handjack.
BOP, use the above procedure Encl. 4.13, and remove the 1 B FDWPT from Handjack and restore speed control to the 1 B MGU (motor gear unit)
Initial Conditions:
- 2. 1 B FDWPT controlled from Motor Speed Changer.
- 3. Review Limits and Precautions Procedure
- 1. Remove tag from 1 B Main FDWP (ICS) station
- 3. Establish communications with the local NEO
- 4. Exercise the 1 B MGU (ICS) station by running MGU down to the LSS and then back up to HSS; verify smooth operation.
- 5. Turn FWT 1 B HANDJACK switch to "OFF" NOTE: Two successful decreases verifies control with Motor Gear Unit
- 7. Increase 1 B FDWPT Motor Speed Changer.
- 8. Verify 1 B FDWPT speed does NOT increase.
- 9. Run 1 B FWPT Motor Speed Changer to "HSS".
IF U1 is in Mode 1 or 2 with 1A FDWPT in auto:
- 10. Verify 1A MAIN FDW PUMP (ICS) in "AUTO".
- 11. Place 1 B MAIN FDW PUMP (ICS) in "AUTO".
- 12. Verify ICS adjusts 1B FDWPT speed to balance suction flow.
Event is complete when the 1 B FDWPT (leS) station is in AUTO, or when directed by the lead examiner the event is completed.
Page 2 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
2 Page 1 of 1 Event
Description:
Inadvertent ES Channel 4 actuation (TS) (C, BOP/SRO)
(Timer #2)
Time Position Applicant's Actions or Behavior BOP Plant response:
BOP/SRO BOP Note: Activate Timer #3 when BOP is occupied with RZ Module.
Statalarms:
1SA-1/D-10, ES CHANNEL 4 TRIP Control Board indications:
ES Channel 4 actuated 1 B LPI Pump starts 1 B LPI Train aligns Band C LPSW Pumps start Crew response:
- 2. Crew may perform Plant Transient Response.
AP/1/A/1700/042 (Inadvertent ES Actuation) actions:
Close 1 HP-24 and 1 HP-25 (should already be closed)
Ensure AP/42 Enc!. 5.1 (Side Board Actions) is in progress (NOTE: Contains no actions for the BOP for ES 4)
Verifies ES 3 or 4 has actuated Place the affected components in MANUAL: (RZ Module) o ES Channel 4 = LPI-P1 Band 1 LP-18 Stop the 1 B LPI PUMP Close 1 LP-18
- 4. WHEN ready to restore, THEN continue. ES 4 components will remain in Manual for the rest of the scenario and will require the crew to manually reinitiate them.
SRO refers to TS 3.3.7 (ES Digital Channels). Condition A applies; Declare associated components inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SRO refers to TS 3.3.6 (ESPS Manual Initiation). Condition A applies; Restore to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Event is complete when ES 4 components are secured or when directed by the lead examiner.
Page 3 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
3 Page 1 of 1 Event
Description:
PZR Spray Valve Fails OPEN: (C, OATC/SRO)
(Timer #3)
Time Position OATC BOP/SRO OATC Applicant's Actions or Behavior Note: This event will occur during Event 2.
Note: Activate Timer #3 when BOP is occupied at RZ Module.
Plant response:
RCS pressure will decrease 1 SA-2/D-3, RC PRESS HIGH/LOW Crew response:
- 1. Refer to ARG Verify all Pzr heaters are ON Verify Pzr Spray valve closed and/or Pzr Spray block valve closed Note: If the block valve is not closed, the reactor will trip on variable low pressure and ES actuation will occur.
If the operator identifies 1 RC-1 has failed open, he should immediately close the block valve per IMAs of AP/44 Evaluate reducing or isolating letdown flow Increase makeup flow as required
- 2. SRO enters to 1AP/44, Abnormal Pzr Pressure Control
- 3. _IAAT all of the following conditions exist:
_ RC pressure < 2155 psig
_ RC pressure decreasing without a corresponding decrease in PZR level
_ PZR heaters are on THEN close the following:
_1RC-1 1 RC-3
- 4. Verify Pzr heaters maintaining RCS pressure w/in bands
- 5. Notify SP~C
- 6. Ensure TS requirements met
- 7. WHEN repairs are complete, THEN place 1 RC-1 and 1 RC-3 in the desired positions.
Note: The PZR spray valve will remain failed for the remainder of the scenario.
When RCS pressure decrease has been stopped, or when directed by the lead examiner this event is completed.
Page 4 of 13
Appendix 0 Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
4 Page 1 of 1 Event
Description:
RC Loop B Flow fails LOW: (I, OATC/SRO) Small RCS Leak (TS)
(Timer #4)
Time Position OATC SRO Applicant's Actions or Behavior Plant response:
Statalarms:
1 SA-2/ A-4, RC Loop B Flow Low 1SA-2/A-5, RC Total Flow Low 1SA-1/A-1, RP Channel A Trip 1SA-1/A-3, RP Channel A Flux/1mb/Flow Trip Control board indications:
RCS Flow meter shows Loop B flow at zero.
RPS Channel A trips.
B S/G FDW Flow instrument shows a reduction in FDW, and the A S/G FDW Flow indicates increasing flow or off-scale High.
DELTA Tc meter indicates a large Delta Temp.
RB normal sump level slowly increasing Crew response:
The crew stabilizes using the "Plant Transient Response" process.
Take Diamond and BOTH FDW Masters to MANUAL; stabilizes the unit.
SRO may enter AP/2 (Excessive RCS Leakage) if the increase in RB normal sump rate is observed. (highly unlikely due to size of leak.)
The SRO may refer to TS 3.4.13 (RCS Operational Leakage) and determine that Condition A, Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and Condition B, Be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are in affect. This is for an unidentified leak> 1 gpm.
SRO enters to AP/28, ICS Instrument Failures and notifies SP~C.
AP/28. ICS Instrument Failures (Case 4E RCS Flow Failure) will:
o Ensure DIAMOND and BOTH FDW Masters in MANUAL.
o Notify SP~C to select a valid RCS flow input to ICS and investigate and repair the failed RCS flow instrumentation.
o Ensure any associated requirements of PT/1/A/06001001 (Periodic Instrument Surveillance) o WHEN notified by SP~C a valid RCS flow input has been restored, THEN GO TO Encl 5.1 (Placing ICS in AUTO).
Note: Crew may refer to PT/600/001 (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 AP/28 or when directed by the Lead Examiner.
Page 5 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
5 Page 1 of 2 Event
Description:
RCS Leak: (C, BOP/SRO)
Timer #5 Time Position SRO BOP Applicant's Actions or Behavior Plant response:
Alarms:
OAC RB Normal Sump Temp HI HI 1 SA-9/A-6 (RB NORMAL SUMP HIGH/LOW) 1SA-8/B-9 (RM Process Monitor Radiation HIGH)
Control Board indications:
PZR and LDST level deceasing RC makeup flow increasing RB normal sump level increasing Crew response:
The SRO may refer to TS 3.4.13 (RCS Operational Leakage) and determine that Condition A, Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and C9ndition B, Be in MODE 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are in affect. This is for an unidentified leak> 1 gpm.
Note: SRO may not refer to TS during the scenario due to other events occurring.
SRO enters AP/2 (Excessive RCS Leakage), which will:
Initiate makeup to LDST using Encl 5.5 (pzr and LDST Level Control) of U1 EOP If desired, makeup to the LDST from 1A BHUT.
Utilize the following as necessary to maintain desired PZR level:
Standby HPI pump 1 HP-26 1HP-7 1 HP-5 1 HP-120 setpoint or valve demand Page 6 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
5 Page 2 of 2 Event
Description:
RCS Leak: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior Crew response:
Place 1HP-14 in NORMAL Announce AP entry using the PA system.
Initiate Encl 5.1 (Leak Rate Determination).
IAAT additional makeup flow to LDST is desired, AND 1A Bleed Transfer Pump is operating, THEN dispatch an operator to close 1 CS-48 (1A BHUT RECIRC)
Notify the OSM to reference the Emergency Plan and OMP 1-14 (Notifications).
Shut down using:
OP/1/N1102/004 (OPS At Power) Enclosure 4.2 (Power Reduction)
AP/29 (Rapid Unit Shutdown)
Simulator operator: If the SRO elects to shutdown using Ops At Power, call as the OSM and direct the crew to use AP/29.
When the SRO has made the decision to shutdown, or when directed by the lead examiner the event is completed.
Page 7 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
6 Page 1 of 2 Event
Description:
Manual Power Reduction: (R, OATe, SRO)
Time Position SRO BOP Applicant's Actions or Behavior SRO directs shutdown per AP/29 (Rapid Unit Shutdown:
Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown)
Stop 1A & 1B MSRH DRN PUMP Place 1 FDW-53 and 1 FDW-56 in MANUAL and close.
Place 1 HD-37 and 1 HD-52 in DUMP.
Start the following pumps:
~ 1A & 1 B FDWP Seal Injection Pump
~ 1A & 1B FDWP Aux Oil Pump WHEN NI Power ~ 80%, Secure 1 E1 & 1 E2 HTR DRN PUMPs Transfer electrical auxiliaries Place 1 TA & 1 TB AUTO/MAN transfer switch in MAN Close 1TA SU 6.9 KV FDR Verify 1TA NORMAL 6.9 KV FDR opens Close 1 TB SU 6.9 KV FDR Verify 1TB NORMAL 6.9 KV FDR opens Place MFB1 AUTO/MAN transfer switches in MAN Place MFB2 AUTO/MAN transfer switches in MAN Close E11 MFB1 STARTUP FDR Verify N11 MFB1 NORMAL FDR opens Close E21 MFB2 STARTUP FDR Verify N21 MFB2 NORMAL FDR opens Page 8 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
6 Page 2 of 2 Event
Description:
Manual Power Reduction: CR, CATe, SRO)
Time Position SRO OATC BOP Applicant's Actions or Behavior Notify WCC SRO to initiate Encl 5.2 (WCC SRO Support During Rapid Unit Shutdown).
Announce AP entry using the PA system.
Verify ICS in AUTO. (its not)
NOTE: The OATC must be aware of the Pzr Spray Valve failure and use the Spray Block Valve to initiate spray as needed.
Initiate manual power reduction to desired power level.
The OA TC will reduce reactor power with the ICS in manual.
Reduce FDW to reduce power Insert control rods to control Tave.
Shutdown the 1 B FDWP.
When power has been reduce by at least 5% or when directed by the lead evaluator this event is completed.
Page 9 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
7 Page 1 of 3 Event
Description:
1 B Main Steam Line break in RB (M, ALL)
Timer #7 Time Position ALL Applicant's Actions or Behavior Plant response:
Statalarm 1 SA-02/A-9, MS Press High/Low "A" and "B" Main Steam (MS) pressure decreases Reactor trips:
"A" MS line pressure stops decreasing "B" MS line pressure continues to decrease Crew response:
The OATC will perform IMAs.
~ Depress REACTOR TRIP pushbutton OATC
~ Verify reactor power < 5% FP and decreasing
~ Depress TURBINE TRIP pushbutton
~ Verify all turbine stop valves closed
~ Verify RCP seal injection available OATC verify I MAs BOP performs a Symptoms Check SRO SRO refers to "Parallel Actions"; transfers to the Excessive Heat Transfer (EHT) tab:
OATC IAA T SCM = O°F then the OATC will perform Rule #2 (Loss of SCM) after receiving concurrence from the SRO.
~ Trip ALL RCPs within 2 minutes (CT-1).
~ Ensure open 1 HP-24 and 1 HP-25
~ Ensure ALL HPI pumps operating
~ Ensure open 1 HP-26 and 1 HP-27
~ Verify required HPI flow per header
~ Verify TBVs available Page 10 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
8 Page 2 of 3 Event
Description:
1 B Main Steam Line Break in RB (M, ALL)
Time Position BOP SRO BOP OATC/BOP Applicant's Actions or Behavior The BOP performs Rule #5 (Main Steam Line Break) after receiving concurrence from the SRO.
Initiate AFIS 1 B SG Digital Channels 1 and 2 Stop 1 B MDEFDW Pump (CT must be met prior to completing Rule 5)
Ensure both Main FDW pumps tripped Isolates all feedwater to the 1 B SG (FDW-316, -42, -40)
Start 1 TD EFDW PUMP Open 1 AS-40 while closing 1 MS-47 WHEN overcooling is stopped, adjust steaming of unaffected SG (1A SG) to maintain CETCs constant. (CT control SG heat removal and/or throttle HPI to prevent the PORV from lifting)
CAUTION Thermal shock conditions may develop if HPI is NOT throttled and RCS pressure NOT controlled.
WHEN all of the following exist: Core SCM >0° F, Rx Pwr:::; 1 %,
and Pzr Level increasing, THEN perform the following to stabilize RCS PIT:
~ Throttle HPI
~ Reduce 1 HP-120 setpoint to >100" (180" ACC)
~ Adjust steaming of unaffected SG (1A SG) to maintain CETCs constant (CT control SG heat removal and/or throttle HPI to prevent the PORV from lifting)
Ensure Rule 3 (Loss of Mn & EFW) is in progress or complete Perform Enclosure 5.1 J ES Checklist (See Attached Checklist)
Page 11 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: __ Scenario No.:
2 Event No.:
8 Page 3 of 3 Event
Description:
1 B Main Steam line break in RB (M, ALL)
Time Position Applicant's Actions or Behavior SRO Excessive Heat Transfer (EHT) tab will:
SRO Ensure Rule 5 (Main Steam Line Break) in progress or complete.
Close 1 FDW-41 and 1 FDW-44.
Close 1 FDW-382, 1 MS-26, 1 MS-76, 1 MS-36, 1 MS-84, 1 FDW-369.
Throttle HPI per Rule 6 Verify letdown in service Feed and steam all intact SGs to stabilize RCS PIT. (CT control SG heat removal and/or throttle HPI to prevent the PORV from lifting)
Verify 1 MS-24/33 are closed.
Open 1AS-8 Close 1SSH-1, 1SSH-3, 1SSH-9.
Minimize SCM using the following methods as necessary:
(CT-7)
~ De-energize all PZR heaters
~ Use PZR spray
~ Throttle HPI
Initiate Enclose 5.16 (SG Tube-to-Shell L\\ T Control)
GO TO FCD tab (if one SG is isolated).
Forced Cooldown tab Establish and maintain appropriate level and pressure in*
available intact SGs.
When directed by the Lead Examiner the event and scenario is completed.
Page 12 of 13
Appendix 0 Scenario Outline Form ES-D-1 March,2009 CRITICAL TASKS
- 1. CT-17, Isolate Overcooling SG
- 2. CT-11, Control SG pressure to Maintain RC Temperature Constant.
- 3. CT-7, Minimize SCM
- 4. CT-1, Trip All RCPs (only if a loss of SCM (O'F) occurs)
Page 13 of 13
Appendix D Scenario Outline Form ES-D-1 March 2009 Facility: Oconee Scenario No.: 4 RO FS Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
- 75% Reactor Power EOl (SNAP222)
Turnover:
AMSAC/DSS bypassed for I&E testing
- SASS in Manual for I&E testing
- 1 B GWD Tank release in progress
- TO EFDWP OOS for maintenance
- Keowee Unit 2 OOS for unplanned reasons
- Keowee Unit 1 aligned to underground (ACB-3 Closed)
- Operability test of Keowee Unit 1 is to be performed per PT/6201009 (Keowee Hydro Operation) after turnover. ONSto perform remote Keowee start. Begin at Encl. 13.1 at Step 2.2 Event Malfunction Event Type*
Event No.
No.
Description Oa Pre-Insert AMSAC/DSS bypassed Updater Ob Pre-Insert 1 C HPIP fail to start Updater Oc Pre-Insert 1 RC-4 failed open Updater Od Pre-Insert Keowee Unit 2 Emergency lockout MEL 180 Oe Pre-insert Block All Reactor Trips, including manual pb 1
N, BOP, SRO Operability test Keowee Unit 1 2
MPS360 C, OATC, SRO 1 HP-31 fails OPEN 3
Updater C, BOP, SRO Operating lPSW pump trips, Standby fails to auto start (TS) 4 MCS004 I, OATC, SRO Controlling Tave fails HIGH 5
MSS200 C, BOP, SRO Vacuum leak 6
MCR021 C,OATC,SRO Dropped Control Rod, Manual Power Reduction MCR022 (TS) 7 MPI300 M, All 2nd dropped CR Override ATWS-UNPP MSS010 Main FDW Pumps Trip MSS020 PORV fails OPEN after lifting - AOR
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Page 1 of 17
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 1 Page 1 of 3 Event
Description:
Operability test Keowee Unit 1 (N, BOP/SRO)
Time Position Applicant's Actions or Behavior Note: This event is run in parallel with event 2.
Direct BOP to perform PT/620/009 (Keowee Hydro Operation) to SRO operability test Unit 1 Keowee Underground power path.
PT/6201009 Enc!. 13.1! KHU-1 Operability Verification Verify various Statalarms NOT in alarm BOP Ensure the following:
~ PERMISSIVE AUTO START light on.
. ~ UNIT 1 MASTER SELECTOR switch in "AUTO".
~ EXCITER MANUAL/AUTO Red AUTO light ON, Green MANUAL light OFF.
~ EXCITER STOP/START Green STOP light ON, Red START light OFF.
Notify Keowee Operator to perform the following:
~ On CB2, verify all required PREREQ lights are lit.
~ Position MASTER TRANSFER switch for KHU-1 to "REMOTE".
Simulator operator: use QUICK STRIKE to place KHU-1 to Remote.
Ensure UNIT 1 SYNC 230 KV selector in "MAN".
Place AND hold UNIT 1 LOCAL MASTER switch to "START" position for >10 seconds until KHU-1 starts.
Verify EXCITER STOP/START Red START light ON, Green STOP light OFF.
Perform the following:
After 60 seconds steady operation, record the following:
~ KHU-1 OUTPUT VOLTS KV (Oconee Control Room Indication - 2AB3)
~ KHU-1 digital speed RPM (KHU-1 Control Room Indication - CB-3)
Cue from Keowee C/R Operator: Keowee RPMs = 128.
Page 2 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 1 Page 2 of 3 Event
Description:
Operability test Keowee Unit 1 (N, BOP/SRO)
Time Position BOP Applicant's Actions or Behavior PT/620/009 (Continued)
Verify CT4 energized by 13.8 KV Underground Power Path:
IF both Standby Buses are NOT energized, perform the following:
~ Ensure TS 3.8.1 Condition D has been entered for Underground Power Path.
~ IF overhead power path is inoperable, ensure TS 3.8.1 Condition I has been entered.
IF Standby Bus 1 NOT energized Verify - 4.16 KV on CT 4 Volts Ensure CT5 BUS 1 AUTO/MAN transfer switch in MAN Ensure CT 4 BUS 1 AUTO/MAN transfer switch in MAN Place STBY BUS 1 SYNCHRONIZING switch to ON Close SK1 CT4 STBY BUS 1 FEEDER Verify - 4.16 KV on Standby Bus 1 Volts Open SK1 CT 4 STBY BUS 1 FEEDER Place STBY BUS 1 SYNCHRONIZING switch to OFF Place CT 4 BUS 1 AUTO/MAN transfer switch to AUTO IF Standby Bus 2 NOT energized Verify - 4.16 KV on CT 4 Volts Ensure CT5 BUS 2 AUTO/MAN transfer switch in MAN Ensure CT 4 BUS 2 AUTO/MAN transfer switch in MAN Place STBY BUS 2 SYNCHRONIZING switch to ON Close SK2 CT 4 STBY BUS 2 FEEDER
- -Verify - 4.16 KV on Standby Bus 2 Volts Open SK2 CT 4 STBY BUS 2 FEEDER Place STBY BUS 2 SYNCHRONIZING switch to OFF Place CT 4 BUS 2 AUTO/MAN transfer switch to AUTO
. Page 3 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 1 Page 3 of 3 Event
Description:
Operability test Keowee Unit 1 (N, BOP/SRO)
Time Position BOP Applicant's Actions or Behavior PT/6201009 (Continued)
IF SK breakers were cycled, perform the following as desired Ensure TS 3.8.1 Condition D has been exited IF overhead Power Path is inoperable, ensure TS 3.8.1 has been exited IF KHU-1 was started from Oconee Control Room, perform the following:
~ Position UNIT 1 SYNC 230 KV switch to "AUTO".
~ Verify ACB 1 KEOWEE 1 GENERATOR BKR closed.
CAUTION: Do NOT lower MVARS to less than zero (Q) before taking the KHU off line. This will prevent excitation current from burning the contacts on the generator breakers when KHU-1 is shut down.
Perform the following concurrently as required:
~ Adjust load to zero (0) MWs with UNIT 1 SPEED CHANGER MOTOR.
~ Adjust MVARS to zero (0) with UNIT 1 AUTO VOLTAGE ADJUSTER.
Place UNIT 1 LOCAL MASTER switch to "STOP" AND hold in "STOP" position for> 10 seconds.
NOTE: Placing UNIT 1 MASTER SELECTOR to "AUTO" shuts off the AC H.P. Lift Pump and closes the Generator Cooling Water valve. This action prevents KHU-1 from creeping.
Ensure UNIT 1 MASTER SELECTOR to "AUTO".
Verify TURBINE 1 GATE POSITION indicator is at zero (0).
Notify Keowee to place KHU-1 MASTER TRANSFER switch in "LOCAL".
Ensure UNIT 1 SYNC 230 KV selector in "AUTO".
Perform the following:
~ Verify acceptance criteria met.
~ IF acceptance Criteria NOT met, notify SRO.
Event is complete when operability test is finished, or when directed by the lead examiner.
Page 4 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 2 Page 1 of 1 Event
Description:
1 HP-31 Fails Open: (C; OATC, SRO)
Timer #2 Time Position OATC/SRO Applicant's Actions or Behavior Note: This event is run in parallel with event 1.
Plant response:
1SA2/B-2 (HP RCP Seal Inlet Header Flow High/Low) (42 gpm)
Crew response:
ARG for 1 SA2/B-2: High Alarm Verify high seal flow conditions with individual RCP seal indications 1 HP-31 may have failed open/mid-position. Take manual control of 1 HP-31 and throttle to maintain 32 gpm.
IF flow CANNOT be reduced in above manner, adjust 1 HP-31 (RCP Seal Flow Control) per OP/1/A/11 04/002 (HPI system)
When flow is reduced manually to - 32 gpm or when directed by the lead examiner this event is completed.
Page 5 of 17
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 4 Event No.: 3 Page 1 of 1 Event
Description:
Operating LPSW pump trips, Standby fails to auto start:
Use Quick Strike to trip 'A' LPSW pump Time Position SRO/BOP SRO Applicant's Actions or Behavior Plant response:
1SA-9/A-9 (LPSW Header A Press Low)
LPSW Header NB Pressure Low Crew response:
Refer to ARG for 1 SA-9/A-9 (LPSW Header NB Press Low)
~ Refer to AP/24 (Loss of LPSW)
AP/24 (Loss of LPSW)
Start all available (NOT previously cavitating) LPSW pumps. (C)
Verify normal LPSW System operation is restored. (Yes)
NOTE:
The SRO should call SPOC to troubleshoot the reason for the suction valve closing, the Auto Start failure and determine if the "A" LPSW pump was damaged due loss 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 or when directed by the Lead Examiner.
Page 6 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 4 Page 1 of 1 Event
Description:
Controlling Tave failed HIGH (I, OATC, SRO)
Timer #4 Time Position SRO/OATC SRO OATC BOP Applicant's Actions or Behavior Plant response:
1SA-02/A-12, ICS Tracking, will actuate due to neutron and feedwater cross-limits.
Controlling Tave will indicate:::: 596.4° F.
Actual loop A & B Tave will decrease until operator stops transient.
RCS pressure and temperature will decrease.
Crew response:
Statalarms; candidates perform "Plant Transient Response" process to stabilize the plant.
~ Verbalize to the SRO reactor power level and direction of movement.
~ Place the Diamond and both FDW Masters in manual and position as necessary to stabilize the plant.
The SRO should:
~ Refer to AP/28, ICS Instrument Failures
~ Contact SP~C to repair controlling Tave.
Note: The ICS remains in manual for the rest of scenario.
AP/28 (ICS Instrument Failures)
Verify plant conditions are controlled or stable as indicated by the following:
~ NI power change < 2% from current NI power indication AND thermal power best s pre-transient power level
~ Tave change < 2°F from current Tave indication
~ THP/SG Outlet Press. change < 30 psig from current THP/SG Outlet Press.
~ RCS pressure change < 150 psig from current RCS pressure GO TO the section 4A (RCS Temperature)
Notify SP~C PERFORM an instrumentation surveillance using applicable table in Encl 5.3 (ICS Instrument Surveillances) for the failed instrument.
When the SRO reaches the WHEN step (5) in Section 4A or when directed by the lead examiner this event is completed.
Page 7 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 3 Event No.: 5 Page 1 of 1 Event
Description:
Timer #5 Time Position Applicant's Actions or Behavior Plant response:
1SA-03/A-6, COND VACUUM LOW (25" decreasing) occurs within 5:::: minutes OAC alarm, Main Condenser Vacuum LOW BOP Crew response:
SRO BOP Refer to the ARG and AP/27, Loss of Condenser Vacuum.
AP/27: Loss of Condenser Vacuum
- 1. IAAT condenser vacuum is:5 22" Hg, THEN tripRX.
- 2. Dispatch operators to perform Encl. 5.1 (Main Vacuum Pump Alignment) and look for vacuum leaks.
- 3. Start all Main Vacuum Pumps.
Booth Operator: Open V-22, 24, 26, 28, and 30 using MANUAL Valves; THEN wait 3 minutes and call as NEO and report that the MVPs are aligned to the Unit 1 Main Condenser
- 4. Ensure 1V-186 is closed.
Booth Operator: per lead examiner direction TIMER 15 to reset vacuum leak; do not allow the crew to trip the Rx on low (-22" Hg) vacuum
- 5. Ensure Stm pressure to Stm Air Eject A, B, C > 255 psig.
- 6. Verify Stm Seal Hdr Press> 1.5 psig.
- 7. Start 1 D CCW pump.
- 8. Verify Condensate flow ~ 2300 gpm.
- 9. WHEN condenser vacuum is stable, AND Encl 5.1 (Main Vacuum Pump Alignment) is complete, THEN EXIT this procedure.
Cue: (Booth Operator): Once vacuum has been stabilized call the CR as the NEO and report that the vacuum leak has been isolated (1A FWP Pumping trap) and reset the vacuum malfunction. OR reset at the direction of the Lead Examiner.
When vacuum has been recovered or when directed by the lead Examiner, the event is complete.
Page 8 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 6 Page 1 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC/SRO) (TS)
Timer #6 Time Position Applicant's Actions or Behavior Plant Response:
Stat alarm 1SA2/A10 (CRD GLOBAL TROUBLE)
Stat alarm 1SA2/B10 (CRD ASYMMETRIC ROD ALARM)
Stat alarm 1 SA2/D9 (CRD OUT INHIBIT)
Crew Response:
SRO SRO should enter AP/15 (Dropped or Misaligned Control Rods)
AP/15 R,OATC BOP IAAT more than one control rod is dropped or misaligned >6%
(> 9") from the group average, THEN trip the Rx.
Verify Rx is critical.
Verify Rx runback to 55% FP in progress.
NOTE: Runback will not be occurring due to ICS in MANUAL.
RNO: Initiate power reduction to 55% FP at ~ 1 %/min.
Initiate Encl 5.1 (Control of Plant Equipment During Shutdown).
(See next page)
Notify SPOC to perform the following:
Investigate cause of dropped or misaligned control rod.
Prepare to reduce the following trip setpoints:
RPS Flux/Flow-Imbalance RPS High Flux NOTE: Tech Spec 3.1.4 requires verification of SDM > 1% Aklk or initiation of boration to achieve SDM within limits within an hour of the misaligned or dropped control rod.
Verify> 1 % SDM with allowance for the inoperable control rod per PT/1/A/1103/015 (Reactivity Balance Calculation).
USE COLR curve for 4 RCPs and 1 inoperable rod.
Page 9 of 17
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 4 Event No.: 6 Page 2 of 2 Event
Description:
Dropped Control Rod, Manual Power Reduction (C, OATC/5RO) (T5)
Time Position SRO Applicant's Actions or Behavior Crew Response:
SRO should refer to TS for the dropped control rod.
Enter TS 3.1.4 (Control Rod Group Alignment Limits)
Condition A: (One trippable CR inoperable or not aligned to within 6.5% of its group average height or both).
- 1. Restore Control Rod Alignment OR
- 2. Verify SDM OR Initiate Boron to restore SDM AND Reduce Thermal Power to ~ 60% of allowable thermal power AND Reduce nuclear overpower trip setpoints (fluxlflow/imb) to
~ 65.5% of the allowable thermal power AND Verify the potential ejected rod worth is within assumptions of rod ejection analysis.
Ensure requirements of TS 3.2.3 (Quadrant Power Tilt) are met.
When T5 3.1.4 is entered, or when directed by the lead examiner this event is completed.
Page 10 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 1 of 6 Event
Description:
2nd dropped CR,ATWS, Main FDW Pumps Trip, PORV fails OPEN Time Position ALL OATC 1 RC-4 Fails OPEN (M, ALL)
Timer #7 and #8 Applicant's Actions or Behavior Plant Response:
Second Control Rod drops Rod bottom lights for second dropped control rod MFWPs trip MD EFDWPs start SG levels decrease and go dry RCS Pressure decreases Pzr level decreases initially, then increases Crew Response:
Upon recognizing the second dropped control rod, the crew manually trips the reactor.
Simulator Operator: Verify timer #8 automatically actuates (or Fire Timer #8) when the reactor trip push button is depressed.
OATC performs IMAs; determines that reactor did not trip and performs Rule 1 (A TWS)
Rule 1 (CT-24) (30 seconds to drive control rods or initiate emergency boration)
Initiate manual control rod insertion to the IN LIMIT.
Notify CR SRO to GO TO UNPP tab.
Open the following:
~ 1 HP-24 AND 1 HP-25 Ensure only one of the following operating:
~ 1A HPI PUMP
~ 1B HPI PUMP Start 1 C HPI PUMP.
NOTE: The 1 C HPIP will NOT start RNO: Start the standby HPIP and open 1 HP-4D9 Open the following:
~ 1 HP-26 AND 1 HP-27 Dispatch one operator to open 6DDV CRD breakers on the following:
~ 1X9-5C (U-1 CRD NORM FDR BKR)
~ 2X1-5B (U-1 CRD ALTERNATE FDR BKR)
EXIT this rule Page 11 of 17
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 2 of 6 Event
Description:
2nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL)
, Time Position Applicant's Actions or Behavior ALL Crew Response:
UNPP tab Ensure Rule 1 (A TWS / Unanticipated Nuclear Power Production) is in progress or complete.
Verify Main FDW is operating and in AUTO. (In Manual-RNO)
~ IF Mn FDW is in MANUAL, THEN adjust MFW flow as necessary to control RCS temperature IAAT Main FDW is NOT operating, THEN perform the following:
~ Trip the turbine-generator.
~ Start all available EFDW pumps IAAT all power range Nls are < 5% FP, THEN trip the turbine-generator Verify any wide range NI > 1 % FP.
Perform the next three steps only if> 1 % FP:
Open the following:
~ 1RC-4
~ 1HP-5 Maximize letdown.
Secure makeup to LDST.
WHEN all wide range Nls are::; 1 % FP, AND decreasing, THEN continue.
Adjust SG pressure as necessary to stabilize RCS temperature using either of the following:
TBVs Dispatch two operators to perform Encl 5.24 (Operation of the ADVs).
Throttle HPI per Rule 6 (HPI). (Should not throttle due to PORVopen)
Verify PORV is closed. RNO: Close the PORV (PORV will not close).
Adjust letdown flow as desired.
Verify RCP seal injection available GO TO Subsequent Actions tab Page 12 of 17
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 3 of 6 Event
Description:
2nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL)
Time Position BOP Applicant's Actions or Behavior Crew Response:
Completes a symptom check and then performs Rule 3 (Loss of Main Feedwater)
Rule 3 Verify any EFDW pump operating. (MDEFWPs running)
Verify any SCM S OaF.
CAUTION ATWS events may initially require throttling to prevent exceeding pump limits and additional throttling once the Rx is shutdown to prevent overcooling.
IF overcooling, OR exceeding limits in Rule 7 (SG Feed Control), THEN throttle EFDW, as necessary. (CT-16) (Throttle less than 600 gpm I MDEFDW pump within 3 minutes.)
IAAT Unit 1 EFDW is in operation, THEN initiate Encl 5.9 (Extended EFDW Operation).
OATC/BOP EncI5.9. Extended EFDW Operation OATC/BOP Perform the following as required to maintain UST level> 7.5':
~ Makeup with demin water.
~ Place CST pumps in AUTO.
Perform Enclosure 5.1. ES Checklist (See Attached Checklist)
~ Contains Step to start Control Room Outside Air Booster Fans (CT-27) (Implementation of Control Room Habitability)
Page 13 of 17
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 4 of 6 Event
Description:
2nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL))
Time Position SRO/BOPI OATC Applicant's Actions or Behavior Plant Response:
With the PORV and 1 RC-4 failed open and only 2 HPIPs to fill the RCS, SCM will slowly decrease to zero (saturation) while the Pzr fills. When solid, pressure will increase and SCM will be re-established Crew Response:
The SRO will transfer to the Subsequent Actions tab from the UNPP tab.
Subsequent Actions tab Verify all control rods fully inserted.
Verify TBVs controlling SG pressure at desired setpoint.
Dispatch an operator with Encl 5.29 (MSRV Locations) to verify all MSRVs have reseated.
Initiate Encl 5.5 (pzr and LOST Level Control).
Open PCB 20 and PCB 21 Perform the following:
~ Open the Generator Field Breaker.
~ Position EXCITATION switch to OFF.
Verify Aux Bldg and Turbine Bldg Instrument Air pressure;::: 90 psig.
Verify ICS/NNI power available.
Note: When subcooling is lost, the OATCIBOP will perform Rule 2 (Loss of Subcooling Margin) and the SRO will transfer to the LOSCM tab.
Page 14 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 5 of 6 Event
Description:
2nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL)
Time Position Applicant's Actions or Behavior Plant Response:
Loss of Subcooling Margin Crew Response:
BOP/OATC will perform Rule 2 (Loss of Subcooling Margin).
BOP/ OATC Rule 2 IAA T all the following exist:
Any SCM :s; OaF Rx power:S; 1%
Open 1 HP-24 and 1 HP-25 Start all available HPI pumps.
Open 1 HP-26 and 1 HP-27.
Verify at least two HPI pumps are operating using two diverse indications.
IAA T the following limits are exceeded 1A & 1 B HPI pumps operating with 1 HP-409 open and Total flow of 950 gpm (incl. seal injection) THEN throttle HPI to maximize flow :s; flow limit.
Select OFF on AFIS HEADER A and B Establish 300 gpm to 1A and 1 B SGs.
IAAT any SCM :s; OaF, THEN feed to the LOSCM setpoint in all intact SGs.
IF SCM> 0 F, THEN control EFDW as required to raise level in intact SGs to proper setpoint per Rule 7 (SG Feed Control)
Place FDW block valve switches for 1 FDW-33, 1 FDW-31, 1 FDW-42, and 1 FDW-40 in CLOSE:
Page 15 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 4 Event No.: 7 Page 6 of 6 Event
Description:
2nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL)
Time Position SRO Applicant's Actions or Behavior Plant Response:
Loss of Subcooling Margin Crew Response:
The SRO will transfer to the LOSCM tab LOSCM tab OATC/BOP Verify all of the following exist:
NO RCPs operating HPI flow in both HPI headers Adequate total HPI flow per Figure 1 (Total Required HPI Flow)
Open 1 AS-40 while closing 1 MS-47.
Perform the following:
Control steaming and feed rates on all intact SGs to maintain cooldown rate within Tech Spec limits:
Tcold > 280°F: $ 50°F / Y2 hr Tcold $ 280°F: $ 25°F / Y2 hr Utilize either TBVs or ADVs: Close 1 RC-4.
NOTE: 1 RC-4 will not close.
Close 1GWD-17, 1HP-1, 1HP-2, and 1 RC-3 Maintain SG pressure < RCS pressure utilizing TBVs or ADVs Verify primary to secondary heat transfer exists.
Initiate Encl 5.16 (SG Tube-to-Shell /:::;. T Control).
Verify required RCS makeup flow within normal makeup capability. (it is NOT)
NOTE: RCS makeup flow exceeds normal makeup capability.
GO TO LOCA CD tab.
When transfer to LOCA CD tab is made, or when directed by the lead examiner this event is completed.
Page 16 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 CRITICAL TASKS
- 1. CT-24, ATWS
- 2. CT-16, FDW Flow Control
- 3. CT-1, Trip All RCPs
- 4. CT-27, Implementation of Control Room Habitability Page 17 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Facility: Oconee Scenario No.: 5 RO FS Op-Test No.: 1 Examiners:
Operators:
Initial Conditions:
0.01 % below POAH (SNAP 225)
Turnover:
Unit 1 Startup in progress SASS in manual CFT pressure low, requires N2 addition
- Startup procedure at step 2.32 Event Malfunction Event Type*
Event No.
No.
Description Oa Override 1 C HPI Pump fails to start Ob Pre-insert 1A RBCU fails to receive ES signal MPS350 1
Override N, BOP, SRO Pressurize "A" CFT with N2 1 N-298 (N2 Fill CFT 1A), fails OPEN (TS) 2 R, OATC, SRO Increase power to 3% and place ICS in AUTO 3
MPI150 I, OATe, SRO PZR "A" RTD Fails LOW (TS) 4 MPS120 C, BOP, SRO 1A HPI Pump sheared shaft and standby HPI Override pump fails to start (TS) 5 MPS247 C, BOP, SRO 1 B1 RCP Lower Seal Failure 6
Override C, OATC, SRO Continuous Rod Withdrawal 7
MPS400 M,ALL SBLOCA 1 C HPI Pump fails to start requiring rapid RCS C/O due to degraded HPI 8
MPS400 M,ALL LBLOCA
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 1 Page 1 of 1 Event
Description:
Pressurize "A" CFT; N2 1 N*298 fails OPEN (N, BOP/SRO)
Timer #1 Time Position BOP SRO SRO Applicant's Actions or Behavior Crew response:
Refer to OP/11 04/001, Enclosure 4.7 (Pressure Makeup To CFTs Using Nitrogen) to adjust CFT pressure.
~ Cue: Time compression used to open 1N*137. This is used to speed the opening of the valve. It would take time for the NEO to travel from work control to the Auxiliary Building.
- 2. Open 1 N-298 (N2 Fill CFT 1 A)
Simulator Operator: When 1 N*298 is open, Fire Timer #1 to fail it open.
SRO will refer to TS 3.6.3 (Containment Isolation) Condition A and B when both nitrogen valves are open (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
- 3. Monitor 1 A CFT pressure
- 4. WHEN pressurization of 1 A CFT is complete, close 1 N-298
- 5. Determine 1 N-298 has failed to close:
Red "open" light lit CFT pressure continues to increase
- 6. Inform the SRO.
Direct the NEO to close 1 N-137 (CFTs Supply).
Simulator Operator: use manual valves page when directed to close 1N*137.
Note: If 1N*137 is not closed immediately, CFT pressure will continue to increase, possibly outside of TS limits (575*625 psig).
SRO will refer to TS 3.6.3 (Containment Isolation) Condition A when only 1 nitrogen valve is open (31 days)
- 7. Verify 1A CFT pressure is stable.
When CFT pressurization is stopped or when directed by the lead examiner this event is completed.
Page 2 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 2 Page 1 of 1 Event
Description:
Increase reactor power to 3% and place ICS in AUTO: (R, OATC, SRO)
Time Position SROIOATC BOP Applicant's Actions or Behavior Crew response:
OP/1/A/1102/001 (Controlling Procedure for Unit Startup)
NOTE:
POAH is normally achieved from 0.05 to 0.15% power on Wide Range Indications.
When POAH is achieved: TBVs will begin to open, 1 HP-120 will begin to close, TAVE will increase, & SUR will decrease with negative Moderator Temperature Coefficient.
Begin reactor power increase to ::::::3% FP. (Manual Control Rod Withdrawal).
Begin raising 1 HP-120 (RC VOLUME CONTROL) setpoint to ::::::
220" as power increases.
At ::::::3% Power as indicated on NI-5, NI-6, and NI-9 (ICS median select):
Place REACTOR MASTER to "AUTO".
Place DIAMOND to "AUTO".
Ensure TURBINE MASTER Setpoint to :::::: 885 psig.
Event is complete when ICS is placed in AUTO or when directed by the lead examiner.
Page 30f 15
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 5 Event No.: 3 Page 1 of 1 Event
Description:
PZR "A" RTD Fails LOW: (I, BOP, SRO) (TS)
Timer #3 Time Position BOP Applicant's Actions or Behavior Plant response:
Statalarms:
1 SA-2/C-3, RC Pressurizer Level Hi/Low OAC, RC PZR level 1 &3 mismatch OAC, RC PZR level 2&3 mismatch Board indications:
PZR level 1 and 2 indicates:::: 133 inches PZR level 3 indicates:::: 220 inches and slowly increasing Crew response:
Refer to the ARG:
Check alternate PZR level indications.
Check for proper Makeup/Letdown flows and adjust to restore proper level.
o RO may take 1 HP-120 to manual to control PZR level.
SRO Refer to Technical Specification 3.4.9, Pressurizer.
Refer to Technical Specification 3.3.8, PAM Instrumentation.
o Condition A applies Refer to PT/1/A/0600/o01 (Periodic Instrument Surveillance).
BOP 0
Select PZR level 3 for level control.
Call sp~c to repair PZR "A" RTD This event is complete when PZR level 3 has been selected and 1 HP-120 returned to AUTO or when directed by the lead examiner.
Page 4 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.:
Scenario No.: 5 Event No.: 4 Page 1 of 2 Event
Description:
"1A" HPI Pump sheared shaft and the standby HPI pump fails to auto start: (C; BOP, SRO) TS Timer #4 Time Position BOP SRO BOP Applicant's Actions or Behavior Plant response:
Statalarms:
1 SA-2/B-2 (HP RCP Seal Injection Flow High/Low) 1 SA-2/C-2 (HP Injection Pump Disch. Header Pressure High/Low)
Board indications:
RC Makeup Flow = -0 gpm RCP SI flow = -0 gpm 1A HPI Pump amps low = -10 amps PZR level will begin to decrease and LDST level will begin to increase.
Crew response:
Refer to ARGs: Refer to AP/14 AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection)
Announce AP entry Verify any HPI pump operating (go to RNO)
~ Close 1 HP-5 (Letdown Isolation)
~ Place 1 HP-120 in HAND and closed
~ Place 1 HP-31 in HAND and closed
~ Attempt to start the Standby HPIP (1 B HPIP starts)
Slowly open 1 HP-31 in small increments until:::::: 8 gpm/RCP is achieved.
Re-establish normal makeup through 1 HP120.
Reduce 1 HP-7 demand to 0%.
Close 1 HP-6 Open the following:
~ 1 HP-1 (1A Letdown Cooler Inlet)
~ 1 HP-2 (1 B Letdown Cooler Outlet)
~ 1HP-3 (1A Letdown Cooler Inlet)
~ 1 HP-4 (1 B Letdown Cooler Outlet Simulator operator: Crew may secure the 1A HPIP and direct NEO to open & rack out the 1A HPIP breaker. (Use Quick Strike to open breaker and remove fuses)
Page 5 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 4 Page 2 of 2 Event
Description:
"1A" HPI Pump sheared shaft and the standby HPI pump fails to auto start: (C; BOP, SRO) TS Time Position Applicant's Actions or Behavior Open 1 HP-5 Throttle open 1 HP-7 for::::: 20 gpm letdown flow.
Open 1 HP-6 Adjust 1HP-7 for desired letdown flow.
Place 1 HP-31 in AUTO.
SRO Refer to Tech Spec 3.5.2 High Pressure Injection Condition "A" Required Action: Restore HPI pump to OPERABLE status Completion Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Note: Due to sequence of events, SRO may not review the TS during the scenario. Follow-up questions may be required to ensure knowledge of this competency.
This event is complete when 1 HP-31 is placed in AUTO or when directed by the Lead Examiner.
Page 6 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 5 Page 1 of 2 Event
Description:
1 B1 RCP lower Seal Failure: (C, BOP/SRO)
Timer #5 Time Position BOP SRO SRO BOP Applicant's Actions or Behavior Plant response:
1SA-06/C-5, RC PUMP 1B1 CAVITY PRESS HI/LOW 1SA-06/C-6, RC PUMP 1B1 SEAL RETURN FLOW HI/LOW Crew response:
Refer to the ARGs Refer to AP/16, Abnormal RCP Operations Notify OSM to request evaluation by RCP Component Engineer.
.IAAT the failure is identified, THEN GO TO the applicable section: 4A Seal Failure Stop the affected RCP (1 B 1 )
IAA T any of the following indicate loss of all RCP seals:
);>
RB RIAs increasing or in alarm (RIA-4, 43 - 46)
);>
RCS Tave constant with LOST level decreasing more than normal
);>
Quench Tank level rate increasing
);>
RB Normal Sump rate increasing THEN initiate AP/02 (Excessive RCS Leakage).
Verify the following are open:
);>
1 HP-20
);>
1HP-21 Verify 1 HP-232 is open Verify Mode 1 or 2 Verify three RCPs will remain operating after affected RCP is tripped Page 7 of 15
Appendix 0 Scenario Outline Form ES-O-2 March, 2009 Op-Test No.: __ Scenario No.: 5 Event No.: 5 Page 2 of 2 Event
Description:
181 Rep lower Seal Failure: (e, 80P/SRO)
Time Position Applicant's Actions or Behavior Verify Rx power is.::: 70%
Verify FDW masters in Auto Stop 1 B1 RCP Verify ICS re-ratios feedwater Initiate Encl 4.3 (Special Instructions for < 4 RCP Operation) of OP/1/A/1102/004 IAAT RCP has been shut down for >30 minutes, THEN close the associated RCP motor cooler inlet/outlet valve (1 LPSW-9 & 10)
When the 181 Rep has been secured or when directed by the lead Examiner, the event is complete.
Page 8 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 6 Page 1 of 1 Event
Description:
Continuous Rod Withdrawal: (I, OATC)
Timer #6 Time Position OATC Applicant's Actions or Behavior Plant response:
Control Rods withdrawing without operator action NI-5 thru NI-9 indicate increasing reactor power SURs on Wide Range Nls increasing OUT light lit on Diamond Crew response:
The candidates should utilize the "Plant Transient Response" process to stabilize the plant and recognize that control rods are withdrawing without a valid signal.
Verbalize to the SRO reactor power level and direction of movement.
Place the Diamond and both FDW Masters in MANUAL to stabilize the plant.
~ The crew should insert control rods and monitor reactor power and wide range startup rate to stabilize the plant SRO The SRO should:
Refer to SOMP 1-02, Reactivity Management, Attachment 9.1 and discuss a recovery plan Contact SP~C to investigate the continuous rod withdrawal.
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 9 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 7 Page 1 of 4 Event
Description:
SBLOCA: (M, ALL)
Timer #7 Time Position Applicant's Actions or Behavior Plant response:
Control board indications:
1 SA-2/D-3, RC PRESS HI/LOW RCS Pressure and PZR level decreasing ES 1-6 actuate Reactor Trip RCS subcooling margin will indicate OaF Crew response:
ALL Trip the Reactor due to MU being beyond "Normal Makeup OATC BOP SRO Capability" (160 gpm).
The SRO will direct the OATC to perform IMAs and the BOP a symptom check.
OATC will perform IMAs
~ 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.
The BOP will perform a symptom check and will have no symptoms to report.
SRO will transfer to the Subsequent Actions Tab.
NOTE: As RCS pressure decreases and Pzr level decreases, the RCS will Saturate.
SA tab Verify all control rods fully inserted.
Verify Main FDW in operation Verify Main FDW operating properly Verify TBVs controlling at - 1010 psig Page 10 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 7 Page 2 of 4 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior RCS saturates; obtain SRO concurrence to perform Rule 2 OATC/BOP Rule 2, Loss of SCM OATC/BOP IAAT all the following exist:
Any SCM::; QOF Rx power::; 1 %
Open 1 HP-24/25 Start all available HPI pumps. (Only 1 B HPIP will be left)
Open 1 HP-26/27 Verify at least two HPI pumps are operating using two diverse indications. (RNO - only one HPIP)
Maximize HPI flow::; 475 gpm (including seal injection for A hdr)
(CT-5, Control HPI)
Dispatch two operators to align ADVs Select OFF on both Digital Channels on AFIS HEADER A&B Notify CR SRO to:
Suspend Rule 3 until directed by LOSCM tab Degraded HPI exists EXIT this rule Perform Enclosure 5.1, ES Checklist (See Attached Checklist)
Page 11 of 15
Appendix D Scenario Outline Form ES-D-2 March, 2009 Op-Test No.: __ Scenario No.: 5 Event No.: 7 Page 3 of 4 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior SRO SRO will transfer to the LOSCM tab.
SRO/BOPI OATC LOSCM tab Ensure Rule 2 (Loss of SCM) is in progress or complete.
IAA T either of the following exists:
~ LPI FLOW TRAIN A plus LPI FLOW TRAIN B ~ 3400 gpm
~ Only one LPI header in operation with header flow ~ 2900 gpm THEN GO TO LOCA CD tab.
Verify all of the following exist:
~ NO RCPs operating
~ HPI flow in both HPI headers
~ Adequate total HPI flow per LOSCM Tab Figure 1 (Total Required HPI Flow)
(RNO - HPI is inadequate)
Start both MDEFWPs Start the TDEFWP Establish 300 gpm to each of the SGs:
~ 1ASG
~ 1B SG Initiate full depressurization of both SGs utilizing either of the following;
~ TBVs
~ ADVs Initiate feed to all available SGs to the LOSCM setpoint at maximum allowable rate (per Table 3, Emergency FDW Pump and Header Maximum Flow Limits) of Rule 7 (SG Feed Control)
(CT-10, Establish EFDW flow and Fed SGs)
Trip Both Main FDW Pumps Ensure Rule 3 (Loss of Main or Emergency FDW ) is in progress or complete Page 12 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 7 Page 4 of 4 Event
Description:
SBLOCA: (M, ALL)
Time Position SRO/BOP OATC OATC/BOP Applicant's Actions or Behavior Open 1 AS-40 while closing 1 MS-47 GO TO Step 37 Close 1 RC-4 WHEN all SCMs are> OaF, OR all the following exist:
~ NO RCPs operating
~ HPI flow in both HPI headers
~ Adequate total HPI flow per Figure 1 (Total Required HPI Flow)
THEN maintain SG pressure < RCS pressure utilizing either of the following:
~ TBVs ADVs Rule 3 Loss of Main or Emergency Feedwater Initiate Encl 5.9 (Extended EFDW Operation)
Perform the following to maintain UST level> 7.5':
Makeup with demin water Place CST pumps in AUTO Start TD EFDWP BEARING OIL COOLING PUMP.
Notify CR SRO to set priority based on the NOTE above and EOP activities.
When the SRO reaches the WHEN step above or when directed by the lead examiner this event is completed.
Page 13 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: __ Scenario No.: 5 Event No.: 8 Page 1 of 1 Event
Description:
LBLOCA (M, All)
Timer #8 Time Position Applicant's Actions or Behavior Plant Response:
RCS pressure decreases rapidly Core and Loop Subcooling Margins indicate '0' or '-0' (flashing)
ES Channels 1-8 if not previously actuated will now actuate OATC/BOP Crew response:
RO performing Encl. 5.1, ES Actuation, must recognize that the 1M T Step 14 will need to be performed and LPI Pumps restarted. (CT-4, Initiate LPI)
SRO may direct an RO to perform a Symptoms Check:
RO performs Symptom Check Crew should recognize LOSCM 1M T Step 6 now exists.
LOSCM IMT Step 6:
IAA T either of the following exists:
~ LPI FLOW TRAIN A plus LPI FLOW TRAIN B ~ 3400 gpm
~ Only one LPI header in operation with hdr flow ~ 2900 gpm THEN GO TO LOCA CD tab.
LOCA CD tab Perform the following:
~ Ensure all RBCUs in low speed.
~ Open 1 LPSW-18.
~ Open 1 LPSW-21.
~ Open 1 LPSW-24.
Initiate Encl 5.35 (Containment Isolation).
Start all RB Aux fans Dispatch an operator to remove the tags and close the Core Flood Tank Isolation valves Dispatch a operators to locally isolate the SGs WHEN CETCs are::; 400°F, THEN continue in this procedure.
When transfer to LOCA Cooldown tab or when directed by the lead examiner, this event is completed Page 14 of 15
Appendix D Scenario Outline Form ES-D-2 March,2009 CRITICAL TASKS
- 1. CT-1, Trip ALL RCPs
- 2. CT-10, Establish EFDW flow and Feed SGs
- 3. CT-27, Implementation of Control Room Habitability Guidance
- 4. CT-5, Control HPI
- 5. CT-4, Initiate LPI Page 15 of 15