ML091110235
| ML091110235 | |
| 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-2 50-269/09-301, 50-270/09-301, 50-287/09-301 | |
| Download: ML091110235 (89) | |
Text
l:f!<,AD Su~"'l+-kd el\ 10 '\1 ).cot 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, 1LWO-2 fails to close: (N, BOP/SRO) (TS)
Time Position Applicant's Actions or Behavior Crew response:
BOP uses OPllIAl11 04/007 Encl 4.1 to pump the Reactor Building Normal Sump (RBNS).
BOP/SRO OP/1/A/1104/007 Ene! 4.1
- Verify MWHUT level adequate to receive waste volume.
- Position the following:
o Open 1LWD-1 (RB NORMAL SUMP ISOLATION) o Open 1LWD-2 (RB NORMAL SUMP ISOLATION).
- Start one or both of the following:
o 1A RB NORM SUMP PUMP o 1B RB NORM SUMP PUMP.
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 1LWD-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 1LWD-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 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 2 Page 1 of 1 Event
Description:
Seismic event Failure of AS Controller: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior Cue: Call the Control Room (4911) to report a seismic event but no plant damage is visible.
Plant response:
BOP/SRO
- 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/S, Earthquake; NEOs perform inspections.
1SA06/C-1 0
- Verify proper operation of MS/AS controller on Unit supplying Auxiliary Steam Header.
SRO/BOP OP/11A11106/22 (Auxiliary Steam System) Enc14.2
- Notify Unit 3 to reduce setpoint on AS controller.
NOTE:
1MS-24 is preferred source of MS to AS.
- Perform one of the following:
o Open 1MS-24 (or Open 1MS-33 )
NOTE:
MS to Aux Steam flow should NOT exceed 240,000 Ibm/hr on any single unit.
- Manually throttle open 1MS-126 & 1 MS-129 (MAl N STM TO SU STM PRESS) to increase Aux Steam Header pressure.
- Continue to throttle 1 MS-126 & 1 MS-129 (MAl N STM TO SU STM PRESS) to increase Aux Steam Header pressure to::= 300 psig.
- WHEN Aux Steam Header is ::= 300 psig: Adjust 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller setpoint to match Aux Steam Header pressure.
- IF required, adjust 1MS-126 & 1MS-129 (MAIN STM TO SU STM PRESS) controller setpoint to::= 300 psig.
Notify Unit 3 to secure AS supply.
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 2 Event
Description:
Th Fails HIGH (I, OATC/SRO Time Position Applicant's Actions or Behavior Plant 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-21B4 (RC Average Temperature High/Low)
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.
OATC
- 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 SPOC 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 S pre-transient power level
- Tave change of < 2°F from current Tave indication
- THP/SG Outlet Press. change of < 30 psig from current THP/SG Outlet Press.
- GO TO the section 4A (RCS Temperature)
- PERFORM an instrumentation surveillance using applicable table in Encl 5.3 (lCS Instrument Surveillances) for the failed instrument.
- Verify computer readouts 01 A 1692 and 01 A 1693 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 D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 4 Page 1 of 2 Event
Description:
1A RBCU rupture (C, BOP/SRO) (TS)
Time Position Applicant's Actions or Behavior Plant Response:
- Verify alarm is valid by checking RBCU 1A Inlet Flow and RBCU 1A delta flow.
- Verify 1LPSW-18 (RBCU 1A Outlet) open
- 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.
- Enter TS for RBCU inoperable (TS 3.6.5 Condition B).
- Close 1LPSW-16 (1A RBCU INLET)
- Perform TS 3.6.3 Condition C for closed containment system.
- Open vent or drain.
- Close 1LPSW-18 (1A RBCU OUTLET)
Page 5 of 21
Appendix 0 Scenario Outline Form ES-O-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)
II -rime Position Applicant's Actions or Behavior SRO SRO may conservatively enter 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.
SRO * *Verify NO fuel handling activities in progress.
- These items may not be completed depending on how soon the next event is started.
When the 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:
1 HP-5 Fails Closed (air line break) (C, OATC/SRO)
II '
Position Applicant's Actions or Behavior Plant Response:
OATC
- 1HP-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 1HP-120 in HAND and reduce demand to zero.
- Initiate makeup to LOST as required.
- Position the standby HPI pump switch to OFF.
- GO TO Step 4.28 per Table in AP/32
- Place CC system in operation.
- Close 1HP-6.
- Close 1HP-7.
- Open the following:
- Verify letdown temperature < 135°F.
- Open 1HP-5; RNO GO TO Step 4.10
- Close 1HP-6.
- Close 1HP-7.
- Open 1HP-5; RNO actions as follows o Dispatch NEO to manually open 1HP-5; manually opens it o Enter TS 3.6.3
- Throttle 1HP-7 to -20 gpm
- Open 1HP-6
- Adjust 1HP-? to control desired letdown flow.
(
Page? 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:
Letdown High Temperature Interlock Failure (C, OATC/SRO)
Time Position Applicant's Actions or Behavior OATC/SRO
- Re-establish normal makeup through 1HP-120.
- 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 1HP-5 (LETDOWN ISOLATION)
(East Pen Rm), THEN perform the following:
A. _ Locally turn 1HP-5 handwheel fully clockwise.
B. EXIT TS 3.6.3.
Exit this procedure When 1 HP-5 is manually opened and NEO is stationed locally then this event is complete or when directed by Lead Examiner.
Page 8 of 21
Appendix 0 Scenario Outline Form ES-O-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)
Time Position Applicant's Actions or Behavior Plant response:
1SAS/A9 (RM AREA MONITOR RADIATION HIGH)
BOP/SRO 1SAS/E1 0 (N-16 RM PRIMARY TO SECONDARY TUBE LEAK) 1SAS/D10 (RM CSAE EXHAUST RADIATION HIGH) 1SAS/B9 (RM PROCESS MONITOR RADIATION HIGH) 1RIA 59 indicating 3 gpm increasing NOTE: Leak rate will ramp to 50 gpm over the next 10 minutes.
Crew response:
SRO 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 1RIA-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 (1 B TURBINE BUILDING SUMP PUMP BKR)
- IAAT gross tube leakage is indicated by an increase in normal RC makeup flow, THEN GO TO Step 4.79.
- 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.: 5 Page 2 of 2 Event
Description:
1A SGTL 1 - 50 gpm over 10 minutes: (SRO) (TS)
Time Position Applicant's Actions or Behavior Crew response:
AP/31 (Primary to Secondary Leakage) ... continued BOP/SRO
- 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 OP/1/A/1102l004 (Operation at Power) o OP/1/A/1102l010 (Controlling Procedure for Unit Shutdown)
- IAAT 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.: 6 Page 1 of 2 Event
Description:
Manual Plant Shutdown: (R, OATC/SRO)
Time Position Applicant's Actions or Behavior Crew response:
- Maintain Pzr level;:: 220" by initiating Encl 5.5 (pzr and LDST BOP/SRO Level Control).
- Utilize the following as necessary to maintain desired Pzr level:
o Standby HPI pump o 1HP-26 o 1HP-7 o 1HP-5 o 1HP-120 setpoint or valve demand
- IAAT Pzr level decreasing with all available HPI, AND Rx power is > 15%, THEN perform the following:
o Trip the Rx.
o GO TO IMA tab.
- Verify all of the following:
o Rx power> 40%
o 1RIA-59 operable OATC o 1RIA-60 operable
- Determine leak rate using the following:
o 1 RIA-59 o 1 RIA-60
- 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 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 6 Page 2 of 2 Event
Description:
Manual Plant Shutdown: (R, OATC/SRO)
Time Position Applicant's Actions or Behavior Initiate Encl 5.19 (Control of Plant Equipment During Shutdown for BOP SGTR).
- Monitor RIAs to identify all SGs with a tube rupture:
o 1RIA-16/17 o 1RIA-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 1Al1 B MSRH DRN PUMPs cr
- Place 1FDW-53/65 in manual and close.
Place 1HD-37/52 in DUMP.
Place 1A11B FDWP SEAL INJECTION PUMP switch to START.
- Start 1A11 B FDWP AUXILIARY OIL PUMP.
WHEN Rx power is < 80%, THEN stop the 1E1/1 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.
- Reduce Rx power to S 5% FP.
Event is complete when reactor power has been reduced by 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.: 7 Page 1 of 1 Event
Description:
1A2 RCP Trips; Reactor fails to trip: (C, OATC, SRO)
I Time Position Applicant's Actions or Behavior Plant response:
- 1SA1/A1, B1, C1, D1 (RP CHANNEL A, B ,C ,DTRIP)
- 1SA1/B7, B7, C7, D7 (RP CHANNEL A, B, C, D RCP/FLUX TRIP)
- 1SA1/A-5 (RCTOTAL FLOW LOW)
Crew response:
OATC/SRO Crew recognizes that the reactor should have tripped but did not.
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:
BOP/SRO
- Verify reactor shutdown
- Verify no loss of heat transfer
- Verify no excessive heat transfer
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.: 8 Page 1 of 7 Event
Description:
Blackout: (M, ALL)
Time Position 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)
OATC/SRO
- Depress REACTOR TRIP pushbutton.
NOTE: Reactor will trip when the pushbutton is depressed.
- Verify reactor power < 5% FP and decreasing.
- Depress turbine TRI P pushbutton.
- Verify all turbine stop valves closed.
- Verify RCP seal injection available.
- IF CC is unavailable, THEN immediately perform the following:
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%
OATC/BOP
- Power Range Nls decreasing
- Any SCM < ODF
- Loss of Main and Emergency FDW (including unsuccessful manual initiation of EFDW); TDEWFP will be available
- Uncontrolled Main steam line(s) pressure decrease
- 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.: 8 Page 2 of 7 Event
Description:
Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
Rule 3 (Loss of Main Feedwater) only OATC
- 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 :s; OaF; RNO If overcooling or exceeding Rule 7 limits, THEN throttle EFDW as necessary.
- Initiate Encl. 5.9, Extended EFW Operation
- Make up to the UST
- 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.
Page 15 of 21
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 8 Page 3 of 7 Event
Description:
Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
Enc!. 5.38 (Restoration of Power)
ALL
- Position the following to OFF:
NOTE:
Feeding SGs with EFDW is desired above HPI Forced Cooling.
Step 6 should be performed prior to re-performing Rule 3.
- IAAT EFDW from any source is insufficient to maintain stable RCS PIT, THEN notify SSF operator that feeding SGs 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 transfer to the Subsequent Actions tab.
SRO SRO will transfer to the SGTR tab Page 16 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 8 Page 4 of 7 Event
Description:
Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
RO will perform Encl. 5.38 (Restoration of Power) (CT-8) (Not met OATC/BOP if Encl. 5.38 completed with power NOT restored.)
- Place 1HP-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 CT4 BUS 1 AUTO/MAN o CT4 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 CT4 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 S2 1 STBY BUS 2 TO MFB2 Page 17 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 8 Page 5 of 7 Event
Description:
Blackout: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
Having just completed Encl. 5.38, the SRO may direct an RO to OATC/BOP perform AP/11 AP/11 (Recovery from Loss of Power).
- 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 FOR BUS 1/2
- 1TD INCOMING FOR BUS 1/2
- 1TE INCOMING FOR BUS 1/2 Verify CT-1 is energizing a MFB. (It's NOT)
Verify a 230KV Switchyard Isolation has occurred. (It has NOT)
Simultaneously press RESET on both of the following push buttons to reset Main Feeder Bus Monitor Panel Load Shed Circuitry:
- MFB UNDERVOLTAGE CHANNEL 1/2 RESET Verify all condensate flow has been lost for < 25 minutes and condensate operation is desired.
Place all HWP control switches to OFF.
Place all CBP control switches to OFF.
Place 1FDW-53/65 in MANUAL and close.
Place 1C-10 FAIL SWITCH in MANUAL.
Close 1C-10.
Using a plant page, clear TB Basement and TB third floor of non-essential personnel.
Start one HWP.
Page 18 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 8 Page 6 of 7 Event
Description:
Blackout: (M, ALL) e Position Applicant's Actions or Behavior An RO could be performing Encl. 5.5, once power has been restored, as described below.
OATC/BOP Crew response:
RO will make up to RCS per Ene!. 5.5 (pzr and LOST Level Cont)
- Utilize the following as necessary to maintain desired Pzr level:
- Standby HPI pump
- 1H P-120 setpoint or valve demand
NOTE: 1 HP 24 and 1 HP-25 fail closed.
- IF both BWST suction valves (1 HP-24 and 1HP-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 1B LPI PUMP.
- Open the following:
- 1LP-1 0
Page 19 of 21
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 1 Event No.: 8 Page 7 of 7 Event
Description:
Blackout: (M, ALL)
I Time Position Applicant's Actions or Behavior Once power is restored and the SRO has transferred out of the SBO tab to Subsequent Actions and finally to the SGTR tab Crew response:
SGTR tab SRO/OATC/
- Maintain Pzr level 140" - 180" BOP
- 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 1HP-24 o 1HP-25 NOTE: 1 HP-24 and 1 HP-25 fail closed. See previous page for step to align
- Secure makeup to LDST.
- Maintain both SG pressures < 950 psig using either of the following: 1) TBVs 2) Dispatch two operators to perform Encl 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 0 Scenario Outline Form ES-0-2 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 IS Op-Test No.: 1 Examiners: Operators:
Initial Conditions:
- 100% Reactor Power (SNAP-205)
Turnover:
- SASS in Manual
- AMSAC/DSS bypassed for I&E testing
- "A" Condensate Booster Pump OOS, breaker to be replaced
- 1B MFDWP on Handjack for MGU work; completed; NEO on station at 1B 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 1HP-26 failed closed Of Pre-Insert 1A MDEFWP fails to start 1 N, BOP, SRO Remove/restore 1B 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 LIS ?)
MPI080 Small RCS Leak (TS) 5 MPS400 C, BOP, SRO RCS Leak, 50 gpm (TS) 6 R,OATC,SRO Manual power reduction due to RCS Leak 7 MSS370, M,ALL 1B Main Steam line break in RB 100 ES Channels 7 & 8 fail to actuate
- (N)ormal, (R)eactivity, (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 Applicant's Actions or Behavior SRO Direct BOP to perform OP/1/A/1106/002 B (FWPT Operation),
Encl. 4.13, Taking the 1B FDWPT Off Handjack.
BOP, use the above procedure Encl. 4.13, and remove the 1B BOP FDWPT from Handjack and restore speed control to the 1B MGU (motor gear unit)
Initial Conditions:
- 2. 1B FDWPT controlled from Motor Speed Changer.
- 3. Review Limits and Precautions Procedure
- 1. Remove tag from 1B Main FDWP (ICS) station
- 3. Establish communications with the local NEO
- 4. Exercise the 1B MGU (ICS) station by running MGU down to the LSS and then Back up to HSS; verify smooth operation.
- 5. Turn FWT 1B HANDJACK switch to "OFF" NOTE: Two successful decreases verifies control with Motor Gear Unit
- 7. Increase 1B FDWPT Motor Speed Changer.
- 8. Verify 1B FDWPT speed does NOT increase.
- 9. Run 1B 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 1B 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.: - L Event No.: 2 Page 1 of 1 Event
Description:
Inadvertent ES Channel 4 actuation (TS) (C, BOP/SRO)
Time Position Applicant's Actions or Behavior BOP Plant response:
Statalarms:
- ES Channel 4 actuated
- 1B LPI Pump starts
- 1B LPI Train aligns
- Band C LPSW Pumps start Crew response:
BOP/SRO 2. Crew may perform Plant Transient Response.
AP/1/A/17001042 (Inadvertent ES Actuation) actions:
- Ensure AP/42 Enc!. 5.1 (Side Board Actions) is in progress (NOTE: Contains no actions for the BOP for ES 4)
- Stop the 1B LPI PUMP
- Close 1LP-18
- 5. 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.
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.: --- Event No.: ~ Page 1 of 1 Event
Description:
PZR Spray Valve Fails OPEN: (C, OATC/SRO)
Time Position Applicant's Actions or Behavior Note: This event will occur during event 2.
Plant response:
- RCS pressure will decrease
- 1SA-2/D-3, RC PRESS HIGH/LOW Crew response:
BOP/SRO 1. Refer to ARG
- Verify all Pzr heaters are ON
- Verify Pzr Spray valve closed and/or Pzr Spray block valve OATC closed Note: If the block valve is not closed, the reactor will trip on variable low pressure and ES actuation will occur.
- Evaluate reducing or isolating letdown flow
- Increase makeup flow as required 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 D 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)
Time Position Applicant's Actions or Behavior Plant response:
Statalarms:
- 1SA-2/A-4, RC Loop B Flow Low
- 1SA-21A-5, RC Total Flow Low
- 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.
OATC
- 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 SRO normal sump rate is observed. (highly unlikely due to size of leak.)
AP/28, ICS Instrument Failures (Case 4E RCS Flow Failure) will:
o Ensure DIAMOND and BOTH FDW Masters in MANUAL.
o Notify SPOC 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 SPOC 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.:------2..- Page 1 of 2 Event
Description:
RCS Leak: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior Plant response:
Alarms:
Control Board indications:
- PZR and LDST level deceasing
- RC makeup flow increasing
The SRO may refer to TS 3.4.13 (RCS Operational Leakage) and SRO 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.
Note: SRO may not refer to TS during the scenario due to other events occurring.
SRO enters AP/2 (Excessive RCS Leakage), which will:
- If desired, makeup to the LDST from 1A BHUT.
- Utilize the following as necessary to maintain desired PZR level:
- Standby HPI pump
- 1HP-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
- 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 1CS-48 (1 A BHUT RECIRC)
- Notify the OSM to reference the Emergency Plan and OMP 1-14 (Notifications).
- Shut down using:
- OP/1/A/1102l004 (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 0 Scenario Outline Form ES-D-1 March,2009 Op-Test No.: _ _ Scenario No.: -L Event No.: 6 Page 1 of 2 Event
Description:
Manual Power Reduction: (R, OATe, SRO)
Time Position 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
- Start the following pumps:
~ 1A & 1B FDWP Seal Injection Pump
~ 1A & 1B FDWP Aux Oil Pump
- WHEN NI Power.::s 80%, Secure 1E1 & 1 E2 HTR DRN PUMPs Transfer electrical auxiliaries
- Place 1TA & 1TB AUTO/MAN transfer switch in MAN
- Close 1TA SU 6.9 KV FOR
- Verify 1TA NORMAL 6.9 KV FOR opens
- Close 1TB SU 6.9 KV FOR
- Verify 1TB NORMAL 6.9 KV FOR opens
- Place MFB1 AUTO/MAN transfer switches in MAN
- Place MFB2 AUTO/MAN transfer switches in MAN
- Close E11 MFB1 STARTUP FOR
- Verify N11 MFB1 NORMAL FOR opens
- Close E21 MFB2 STARTUP FOR
- Verify N21 MFB2 NORMAL FOR opens Page 8 of 13
Appendix D Scenario Outline Form ES-D-1 March,2009 Op-Test No.: _ _ Scenario No.: ~2~ Event No.: .§ Page 2 of 2 Event
Description:
Manual Power Reduction: (R, OATC, SRO)
Time Position Applicant's Actions or Behavior SRO
- Verify ICS in AUTO. (its not)
OATC 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 OATC will reduce reactor power with the ICS in manual.
- Reduce FDW to reduce power
- Insert control rods to control Tave.
- Shutdown the 1B 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 S Main Steam Line break in RS (M, ALL)
Time Position Applicant's Actions or Behavior Plant response:
ALL
- Statalarm 1SA-02lA-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 IMAs
- BOP performs a Symptoms Check SRO SRO refers to "Parallel Actions"; transfers to the Excessive Heat Transfer (EHT) tab:
- IAAT SCM = OaF then the OATC will perform Rule #2 (Loss of SCM) after receiving concurrence from the SRO.
OATC
~ Trip ALL RCPs within 2 minutes (CT-1)
~ 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 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 Applicant's Actions or Behavior The BOP performs Rule #5 (Main Steam Line Break) after receiving BOP concurrence from the SRO.
- Stop 1B MDEFDW Pump (CT-17)
- Ensure both Main FDW pumps tripped
- Start 1 TD EFDW PUMP
- WHEN overcooling is stopped, adjust steaming of unaffected SG (1 A SG) to maintain CETCs constant (CT-11)
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 S 1%,
BOP and Pzr Level increasing, THEN perform the following to stailize RCS P!T:
~ Throttle HPI
~ Reduce 1HP-120 setpoint to > 100" (180" ACC)
~ Adjust steaming of unaffected SG (1A SG) to maintain CETCs constant (CT-11)
- Ensure Rule 3 (Loss of Mn & EFW) is in progress or complete 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:
1B Main Steam line break in RB (M, ALL)
Time Position Applicant's Actions or Behavior SRO Excessive Heat Transfer (EHT) tab will:
- Ensure Rule 5 (Main Steam Line Break) in progress or complete.
- Throttle HPI per Rule 6
- Verify letdown in service
- Verify 1MS-24/33 are closed.
- Open 1AS-8
- Minimize SCM using the following methods as necessary:
(CT-7)
~ De-energize all PZR heaters
~ Use PZR spray
~ Throttle HPI
~ Use PORV
- Initiate Enclose 5.16 (SG Tube-to-Shelll!.. T Control)
- GO TO FCD tab (if one SG is isolated).
SRO 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 D 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
(
Page 13 of 13
(
Appendix 0 Scenario Outline March,2009 Facility: Oconee Scenario No.: 3 RO IS Op-Test No.: 1 Examiners: Operators:
Initial Conditions:
- 88% Reactor Power (SNAP 224)
Turnover:
- PT/1/A/02901003, Turbine Valve Movement, in progress
- SASS in MANUAL for I&E troubleshooting
- GWD Tank 1B release is in progress Event Malf. No. Event Type* Event No. Description Oa Pre-Insert SASS in manual Ob Pre-Insert TO EFDW Pump Fails to start MSS330 Oc Pre-Insert Block All Turbine Trips Except Manual MPI290 Od Pre-Insert 1C HPI Pump Fails to Start 1 N, BOP, SRO PT/1/A/02901003, Turbine Valve Movement, in progress; testing CV1 2 MPI281 I, OATC, SRO f). Tc Fails High 3 SRO Loss of Oil on the 1B MDEFDW Pump (TS) 4 MSS200 C, BOP, SRO Vacuum leak 5 MPS290 C, BOP, SRO 1A CC Pump trips (1 B CC Pump fails to auto start)
Override 6 MSS570 SRO UST leak (TS) 7 R,OATC,SRO Manual unit shutdown due to UST level 8 MSS010 Main FDW pumps trips MSS020 C,OATC,SRO Main Turbine Fails to trip (Lockout EHC Pumps) 9 MPS260 M,ALL Loss of EFDW (last 1A MDEFWP) - CBP feed 10 Override M, ALL CBPs trip -Loss of ALL FDW - HPI Forced Cooling
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Page 1 of 17
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 1 Page 1 of 1 Event
Description:
PT: Turbine Valve Movement At Power: (N; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew response:
BOP The BOP should use the in progress procedure PT/1/A/0290/003 (Turbine Valve Movement) Enclosure 13.2, Control Valve Movement At Power, at step 2.6 to test CV1 :
__IF required, select "Control Valve 1 & 2 Test".
__Verify "Test Permissive" is ON.
__ Record CV1 pretest position: % Open.
__ Select "Initiate Test" for Control Valve 1 Test.
IF any of the following conditions occur, select "Abort CV1 Test":
- NI POWER changes> 2%. (R.M.)
- ICS Turbine Master trips to HAND. (R.M.)
- Turbine vibration> 10 mils for> 5 seconds.
( IF "Test Failed" is "ON" AND CV1 is NOT fully closed, select "Abort CV1 Test".
IF "Test Failed" is "ON" AND CV1 remains closed perform the following:
- Do NOT select "Abort CV1 Test". (R.M.)
- Notify WCC & Engineering that the (FASV) for the Control Valve under test is stuck in the energized state.
NOTE: Control Valves which are not in their normal position could result in asymmetrical loading on the Turbine bearings.
- Monitor Turbine Vibrations closely if in this abnormal state.
__Verify CV1 "Test Successful" ON.
__Verify CV1 test indicator reset.
__Verify CV1 within +/- 5.0% of pretest position.
Perform the following:
- Verify acceptance criteria met.
- IF acceptance criteria NOT met, notify SRO.
__ Stop Standby EHC pump.
__ Place Standby EHC pump control switch to "AUTO".
Page 2 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 When the PT is completed and EHC pumps returned to normal alignment or when directed by the Lead Examiner this event is completed.
Op-Test No.: _ _ Scenario No.: 3 Event No.: 2 Page 1 of 1 Event
Description:
L\Tc fails HIGH: (I, OATC/SRO)
Time Position Applicant's Actions or Behavior Plant Response:
- FDW flow will ratio incorrectly based on the failure
- "A" FDW flow will increase causing "A" loop Tc to decrease.
- "B" FDW flow will decrease causing "B" loop T c to increase.
- This will cause actual L\Tc to increase (become more negative). Failure to adjust FDW flow will result in OPT.
- Statalarm 1SA-02lB-5, RC Cold Leg Diff. Temperature High, will actuate if actual L\Tc increases to +/-5°F Crew Response:
- Crew should perform Plant Transient Response (PTR)
- Diagnose the L\Tc failure by observing the L\Tc meter ALL on 1UB1. It should return to zero but is staying a +
OATC 3.5 degrees.
- Take the Diamond and Feedwater Masters to MANUAL and re-ratio feedwater using the loop Tc meters to return actual L\T c to near zero.
- Refer to AP/28 (ICS Instrument Failures)
- Verify Entry is due to an Instrument Failure SRO
- Verify plant parameters stable
- GO TO Section 4F, L\Tc Failure
- Ensure 1A & 1B FDW Masters and Delta Tc are in HAND.
- Re-ratio feedwater flow to establish - 0° F L\T c
- Ensure any associated requirements of PT/1/A/06001001 are met When the SRO reaches the WHEN step (5) in Section 4F or when directed by the lead examiner this event is completed.
Page 3 of 17
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 3 Page 1 of 1 Event
Description:
Loss of Oil on the 1B MDEFDW Pump; (TS, SRO) 111111::' Position Applicant's Actions or Behavior Note: A NEO will call the control room and state the following:
"The 1B MDEFDW pump has an oil leak and no oil is visible in the bubbler."
Booth Operator: Start Event 4 after waiting 3 minutes Crew response:
The SRO should determine that the 1B MDEFDW pump is inoperable and refer to TS 3.7.5 (Emergency Feedwater System)
SRO TS 3.7.5 Condition A with a 7 day completion time is in affect.
Notify SPOC to investigate and repair. May place the 1B MDEFDW pump is OFF and/or direct that the breaker for the 1B MDEFDW pump should be opened.
When the TS has been referenced and when directed by the Lead Examiner the event is completed.
Page 4 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 4 Page 1 of 1 Event
Description:
Time Position Applicant's Actions or Behavior Plant response:
- OAC alarm, Main Condenser Vacuum LOW Crew response:
BOP Refer to the ARG and AP/27, Loss of Condenser Vacuum.
AP/27: Loss of Condenser Vacuum SRO
- 1. IAAT condenser vacuum is s 22" Hg, THEN trip RX.
BOP 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 mins 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 FIRE 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 1D CCW pump.
- 8. Verify Condensate flow ~ 2300 gpm.
- 9. WHEN condenser vacuum is stable, AND Ene! 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 (1 A 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 5 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 5 Page 1 of 3 Event
Description:
1A CC Pump trips, 1 B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicant's Actions or Behavior Plant response:
- 1SA-2/C-1, LETDOWN TEMPERATURE HIGH
- 1HP-5 (Letdown Isolation) will close due to high letdown temperature
- CC Total Flow Low
- Component Cooling Pressure Low Crew Response:
- Determine low flow is due to CC Pump failure AND Standby CC Pump did NOT start and perform the following:
~ Verify CC Surge Tank level> 18"
~ Start Standby CC Pump Note: The SRO may not initiate AP/20 if the standby pump is started per the ARG.
- Initiate AP/20 (Loss of Component Cooling)
- Verify CC Surge Tank level ~ 12".
- Manually start the Standby CC Pump
- Verify CC TOTAL FLOW> 575 gpm
- If Letdown> 130°F, THEN:
- Close 1HP-5,
- Initiate AP/032 (Loss of Letdown)
Page 6 of 17
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 5 Page 2 of 3 Event
Description:
1A CC Pump trips, 1B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew Response:
- If AP/20 (Loss of Component Cooling) not entered, Statalarm 1SA-2/C-1 will direct initiating AP/32 (Loss of Letdown)
AP/32 , Loss of Letdown:
BOPI
- Place 1HP-120 in HAND and reduce demand to zero.
OATC BOP
- Initiate makeup to LOST as required (Encl. 5.5 or OP/1/A/1103/004)
- Notify Chemistry of the following:
).> Current RCS boron sample is needed for possible unit shutdown.
).> Normal letdown line is isolated.
- IAAT Pzr level ~ 260",
AND letdown CANNOT be established, THEN initiate unit shutdown at ::= 20%/min per AP/29 (Rapid Unit Shutdown).
- IAAT Pzr level ~ 375", THEN trip Rx.
- Verify CC system in operation.
- Position the standby HPI pump switch to OFF.
- Verify loss of letdown is due to UD temperature high and then GO TO Step 4.28.
- WHEN letdown can be re-established, THEN ensure proper operation of the CC System.
- Open the following:
).> 1HP-1
).> 1HP-2
).> 1HP-3
).> 1HP-4 Page 7 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 5 Page 3 of 3 Event
Description:
1A CC Pump trips, 1 B CC Pump Fails to Auto Start: (C; BOP, SRO)
Time Position Applicant's Actions or Behavior Crew Response:
SRO/
- Verify letdown temperature < 135°F (it is not)
OATC
- Open 1HP-13.
- Close the following:
~ 1HP-8
~ 1HP-9&11
- Select LETDOWN HI TEMP INTLK BYP switch to BYPASS.
- Open 1HP-5.
- Throttle open 1HP-7 to establish === 20 gpm.
- WHEN letdown temperature < 130°F, THEN place LETDOWN HI TEMP INTLK BYP switch in NORMAL.
- Open 1H P-6.
- Adjust 1HP-7 to control desired (-77 gpm) letdown flow.
- Re-establish normal makeup through 1HP-120.
- Re-establish normal RCP seal injection flow.
- Position the standby HPI pump switch to AUTO.
This event is complete when Seal Flow is returned to normal (32 gpm) or when directed by the lead examiner.
Page 8 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 6 Page 1 of 1 Event
Description:
UST Leak: (TS, SRO)
Time Position Applicant's Actions or Behavior Plant response:
- OAC Alarm - Turbine Sump Pumps A and B ON
Booth Operator: As an NEO call (or radio) the CR and report "Water is leaking out of the UST; is running down the UST Riser piping. I can't tell where the leak is coming from."
1SA-06/A-11 UPPER SURGE TANK LEVEL LOW (comes in later; 6')
BOP NOTE: When UST level reaches 7.5 ft., Train 1 and Train 2 UST Riser Auto Isol Actuated will isolate the Hotwell
- Open DW-4 (#1 UST Makeup Control)
- Check hotwell level to determine if hotwell level control valves have malfunctioned SRO
- Check system for leaks if it appears that water is being lost.
~ Condition A and the Required Action is to 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 />.
- SRO should determine a unit shutdown is required.
- Direct unit shutdown per AP/29 (Rapid Unit Shutdown)
Booth Operator: If candidate elects to use OP for Unit Shutdown, call as the OSM, direct use of AP-29 for shutdown of the unit.
Event is complete when a unit shutdown is directed by the SRO or when directed by the Lead Examiner.
Page 9 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 7 Page 1 of 1 Event
Description:
Manual unit shutdown due to UST level: (R; OATC, SRO)
Time Position Applicant's Actions or Behavior Crew response:
SRO AP/29 (Rapid Unit Shutdown)
Initiate Encl 5.1 (Support Actions During Rapid Unit Shutdown).
- Start the following pumps:
_ 1A FDWP SEAL INJECTION PUMP
_ 1A FDWP AUXILIARY OIL PUMP
_ 1 B FDWP AUXILIARY OIL PUMP
_ 1 B FDWP SEAL INJECTION PUMP
- WHEN CTP is :s; 80%, THEN continue.
_ Stop 1E HTR DRN PUMP.
_ Place 1HD-254 switch to OPEN.
_ Stop 1 E2 HTR DRN PUMP.
_ Place 1HD-276 switch to OPEN.
- Verify Turbine-Generator shutdown is required.
- Transfer 6.9 KV electrical auxiliaries by placing 1T Al1 TB transfer switches to MAN, Closing 1TAl1 TB SU 6.9 KV FDR and verifying 1TAl1 TB NORMAL 6.9 KV FDR opens.
- Transfer 4 KV electrical auxiliaries by placing MFB1/MFB2 transfer switches to MAN, Closing E1 (Startup FDR) and verifying N1 (Normal FDR) opens. Closing E2 (Startup FDR) and verifying N2 (Normal FDR) opens
- Notify CR SRO that unit auxiliaries have been transferred.
SROI AP/29 (Rapid Unit Shutdown) .....
OATC
- Verify ICS in AUTO. (its NOT) RNO 1. _ Initiate manual power reduction to desired power level (15%)
Event is complete when reactor power has been reduced 5% or when directed by the Lead Examiner.
Page 10 of 17
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 8 Page 1 of 2 Event
Description:
Main FDW Pumps Trip:
Main Turbine Fails to trip (Lockout EHC Pumps) (C, OATC, SRO)
Time Position Applicant's Actions or Behavior Plant response:
- Both Main FDW pump trips resulting in a reactor trip.
- The Main Turbine should trip but does not. This will result in a reduction of steam pressure in both SGs until actions are taken to trip the turbine. The will result in RCS overcooling until the turbine is tripped.
Crew response:
- OATC will perform Immediate Manual Actions OATC >> Depress REACTOR TRIP pushbutton
>> Verify reactor power < 5% FP and decreasing
>> Depress turbine TRIP pushbutton.
>> Verify all turbine stop valves closed Note: The OATC should diagnose that the turbine did NOT trip and then perform the RNO step which will stop and lockout both EHC pumps. This will cause the turbine to trip. (CT-18)
CT-18 Note: If AFIS actuates prior to the Main Turbine being Tripped, this critical task is NOT met.
>> Verify RCP seal injection available.
BOP (1A MD EFDW pump will be the only pump feeding a SG.)
- Encl. 5.9 will be performed per Rule 3:
>> Place 1FDW-316 in MANUAL and Close
>> Locally open 1FDW-313 and 1FDW-314
>> Throttle open 1FDW-316. (Feeds both SGs wi 1A MDEFWP)
- The SRO will transfer to Subsequent Actions. OATC will perform Encl. 5.5 (pzr and LOST Level Control) while the SRO reads to him.
Event is complete plant is stable and Subsequent Actions are in progress or when directed by the lead examiner.
Page 11 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 8 Page 2 of 2 Event
Description:
Main FDW Pumps Trip:
Main Turbine Fails to trip (Lockout EHC Pumps) (C, OATC, SRO)
Time Position Applicant's Actions or Behavior Crew response:
SRO Subsequent Actions:
BOPI
- Verify all control rods fully inserted OATC
- Verify Main FDW in operation (RNO) Ensure Rule 3 in progress
- Verify TBVs maintaining - 1010 psig
- Verify 1 RIA-40 operable with OFF GAS BLOWER operating
- Verify ES required (RNO) Initiate Encl. 5.5
- Open PCB 20 & 21
- Open Generator & Exciter Field Breaker
- Verify Aux Bldg & Turb Bldg Instrument Air pressure> 90 psig
- Verify ICS/NNI power available
- Verify all 4160 v switchgear energized
- Verify both SGs > 550 psig
- Ensure Rule 3 in progress and SG levels approaching setpoint
- Verify any RCP operating Event is complete plant is stable and Subsequent Actions are in progress or when directed by the lead examiner.
Page 12 of 17
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 9 Page 1 of 2 Event
Description:
LOSS of EFDW - CBP Feed: (M, ALL)
When directed by the lead examiner, trip the 1A MD EFDW Pump.
lillie Position Applicant's Actions or Behavior Plant response:
Control board indications:
- Loss of EFDW flow as indicated on Total EFDW flow gauge
- 1A MD EFDW pump will indicate tripped (red light off)
Crew response:
SRO SRO will transfer to LOHT tab:
- Ensure Rule 3 in progress; (*BOP re-performs Rule 3 - see below)
- IAAT NO SGs can be fed with FDW (Main/CBP/Emergency),
AND any of the following exists:
- Pzr level reaches 375" [340" acc]
THEN GO TO Step 4. (RNO - perform steps below)
- Reduce operating RCPs to one pump/loop
- IF EFDW flow has been re-established to any SG per Rule 3 (Loss of Main or Emergency FDW) or Encl 5.27 (Alternate Methods for Controlling EFDW Flow), THEN GO TO Step 71.
WHEN any of the following exists: (SRO will wait at this step)
~ Unit 1 EFDW available
~ EFDW aligned from another unit
~ Main FDW pump available AND reset THEN GO TO Step 53.
BOP *Re-perform Rule 3, Loss of Main or Emergency FDW
- IAAT NO SGs can be fed with FDW ...
- Start EFDW pumps to feed all intact SGs. (none will operate)
- Verify any EFDW pump operating. (none)
..... BOP actions in Rule 3 for aligning CBP feed continued on next page Page 13 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 9 Page 2 of 2 Event
Description:
Loss of EFDW - CBP Feed: (M, ALL)
Time Position Applicant's Actions or Behavior Crew response:
- Simultaneously position Startup Control (1 FDW-35 and 1FDW-44) valves 10 - 20% open on all intact SGs:
CT-11
- Control FDW flow to stabilize RCS PIT by throttling the following as necessary Startup Control valves AND TBVs. (CT-11)
- Place the 1 FDW-38 and 1 FDW-47 switches to OPEN.
- Dispatch an operator to perform Encl 5.26 (Manual Start of TDEFDWP).
- Verify cross-tie with Unit 2 is desired.
- Dispatch an operator to open 2FDW-313/314 (2A12B EFDW LINE DISCH TO 2A S/G X-CONN)
- Dispatch another operator to 1FDW-313 have them notify the CR when in position
- WHEN either of the following exists:
~ Alternate unit EFW cross connects are open
~ 1 TD EFDW PUMP is operating THEN continue.
Booth Operator: Verify it is appropriate and FIRE TIMER to fail Pzr Spray "as-is" (closed) so that RCS pressure can increase faster to 2300 psig.
When CBP feed established or when directed by the lead Examiner, this event is completed
(
\
Page 14 of 17
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 10 Page 1 of 2 Event
Description:
CBPs Trip - Loss of ALL FDW - HPI Forced Cooling: (M, ALL)
Time Position Applicant's Actions or Sehavior Plant response:
- Startup flow gauge goes to zero Crew response:
- Re-perform Rule 3, Loss of Main or Emergency FDW SOP
- IAAT NO SGs can be fed with FDW (Main/CSP/Emergency),
AND any of the following exist:
- Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
- Start EFDW pumps to feed all intact SGs. (NO EFWPs available)
- Verify any EFDW pump operating.
- Place the following in MANUAL and close 1 FDW-315 and 1FDW-316
- Verify 1 TD EFDW PUMP is available for manual start.
- Verify cross-tie with Unit 2 is desired.
- Dispatch an operator to open 2FDW-313/314 (2A12S EFDW LINE DISCH TO 2A S/G X-CONN)
- Dispatch another operator to 1FDW-313 have them notify the CR when in position
- WHEN either of the following exists:
o Alternate unit EFW cross connects are open o 1 TD EFDW PUMP is operating THEN continue.
SRO/
- IAAT NO SGs can be fed with FDW (Main/CSP/Emergency),
OATC AND any of the following exist:
~ RCS pressure reaches 2300 psig OR NDT limit
~ Pzr level reaches 375" [340" acc]
THEN PERFORM Rule 4 (Initiation of HPI Forced Cooling).
Page 15 of 17
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 3 Event No.: 10 Page 2 of 2 Event
Description:
CBPs Trip - Loss of ALL FDW - HPI Forced Cooling: (M, ALL) me Position Applicant's Actions or Behavior Crew response:
SROI Rule 4 (Initiation of HPI Forced Cooling). (CT-14)
CT-14 OATC Note: If Safety Valves (Codes) lift, this critical task is NOT met.
- Verify any HPI pump can be operated.
- Open 1RC-4.
- Open PORV.
- Verify at least two HPI pumps operating
- Verify flow in both HPI headers is in the acceptable region of Figure 1 (Required HPI Flow Per Header).
- Ensure PORV open.
- De-energize all Pzr heaters.
- Close 1HP-5.
~ Close: TBVs, 1 FDW-35, 1FDW-44
- EXIT this rule.
LOHT Tab: (after performance of Rule 4)
- Verify two HPIPs operating & acceptable flow exists in both hdrs
{, Event and exam is complete when the SRO has transferred to HPI Cooldown tab or when directed by the Lead Examiner.
Page 16 of 17
Appendix 0 Scenario Outline Form ES-O-2 March,2009 CRTICAL TASKS
- 1. CT-18, Turbine Trip
- 3. CT-14, Initiate HPI Forced Cooling Page 17 of 17
Appendix D Scenario Outline Form ES-D-1 March , 2009 Facility: Oconee Scenario No.: 4 RO IS 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
- 1B GWD Tank release in progress
- TD 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 and before startup continues, ONS to 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 1C HPIP fail to start Updater Oc Pre-Insert 1RC-4 failed open Updater Od Pre-Insert Keowee Unit 2 Emergency lockout MEl180 Oe Pre-insert Block All Reactor Trips, including manual pb 1 N, BOP, SRO Operability test Keowee Unit 1 2 MPS360 C,OATC,SRO 1HP-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 Updater C, BOP, SRO HPSW Jockey pump trip, altitude valve fail CLOSED (SlC) 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)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 18
Appendix D Scenario Outline Form ES-D-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 operability test Unit 1 Keowee Underground power path.
SRO PT/620/009 Encl. 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 MANUAUAUTO 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".
- 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 18
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 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 CT4 Volts
- Ensure CT5 BUS 1 AUTO/MAN transfer switch in MAN
- Ensure CT4 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 CT4 STBY BUS 1 FEEDER
- Place STBY BUS 1 SYNCHRONIZING switch to OFF
- Place CT4 BUS 1 AUTO/MAN transfer switch to AUTO
- I F Standby Bus 2 NOT energized
- Verify - 4.16 KV on CT4 Volts
- Ensure CT5 BUS 2 AUTO/MAN transfer switch in MAN
- Ensure CT4 BUS 2 AUTO/MAN transfer switch in MAN
- Place STBY BUS 2 SYNCHRONIZING switch to ON
- Close SK2 CT4 STBY BUS 2 FEEDER
- Verify - 4.16 KV on Standby Bus 2 Volts
- Open SK2 CT4 STBY BUS 2 FEEDER
- Place STBY BUS 2 SYNCHRONIZING switch to OFF
- Place CT4 BUS 2 AUTO/MAN transfer switch to AUTO Page 3 of 18
Appendix 0 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 Applicant's Actions or Behavior PT/620/009 (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 (0) 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 18
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:
1HP-31 Fails Open: (C; OATC, SRO)
Time Position 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 1SA2IB-2: High Alarm BOP/SRO
- Verify high seal flow conditions with individual RCP seal indications
- 1HP-31 may have failed open/mid-position. Take manual control of 1HP-31 and throttle to maintain 32 gpm.
- IF flow CANNOT be reduced in above manner, adjust 1HP-31 (RCP Seal Flow Control) per OP/1/A/1104/002 (HPI system)
When flow is reduced manually to - 32 gpm or when directed by the lead examiner this event is completed.
Page 5 of 18
Appendix 0 Scenario Outline Form ES-O-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:
Time Position Applicant's Actions or Behavior Plant response:
~ Refer to AP/24 (Loss of LPSW)
AP/24 (Loss of LPSW)
SRO/BOP
- 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.
Restore Auto-Start Circuitry to operable. 7 day completion time.
SRO Event is complete when SRO has referred to TS or when directed by the Lead Examiner.
Page 6 of 18
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)
Time Position Applicant's Actions or Behavior Plant response:
- 1SA-02lA-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" SRO/OATC 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.
SRO AP/28 (ICS Instrument Failures)
OATC
- 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 BOP 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 18
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 4 Event No.: 5 Page 1 of 2 Event
Description:
HPSW Jockey pump trip, altitude valve fail closed: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior Plant Response:
- Stat Alarm 1SA9/D-S (HPSW JOCKEY PUMP OFF)
- HPSW system pressure decreasing.
Crew Response:
SRO Refer to ARG 1SA9/A-S, 1SA9/D-S BOP 1SA9/A-S (and 1SA9/D-S)
- Verify (call SPOC) proper jockey pump operation
- IF HPSW Header Pressure continues to decrease AND Elevated Storage Tank Level is NOT dropping; i.e., altitude valve stuck closed and jockey pump not providing adequate supply, manually start a HPSW Pump.
- Refer to OP/0/Al1104/011 (High Pressure Service Water).
OP/0/Al1104/011 Limits & Precautions
- HPSW Pumps A & B have a minimum flow requirement of 1450 gpm.
- Normal system flow demand is approximately 200 gpm.
- IF altitude valve closes while an HPSW pump is still running, pump will be deadheaded.
- Do NOT operate an HPSW pump with altitude valve isolated, unless provisions have been made to ensure pump will NOT be operated below its minimum flow.
- SLC 16.9.Sa requires any time a Turbine Driven Emergency Feedwater Pump OR a HPI Pump is required to be operable, EWST level shall be ~ 70,000 gallons.
- HPSW Pump(s) can operate with the Altitude Valve closed AND NO additional system flow for S 15 minutes.
- Open Fire Hydrant for minimum flow.
Note: If flow not established pump will trip in 15 minutes.
Page 8 of 18
Appendix 0 Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 4 Event No.: 5 Page 2 of 2 Event
Description:
HPSW Jockey pump trip, altitude valve fail closed: (C, BOP/SRO)
Time Position Applicant's Actions or Behavior Crew Response:
SRO Refer to SLC 16.9.8a (HPSW requirements to support loss of LPSW and CCW).
HPSW shall be available as follows:
- b. EWST level shall be ~ 70,000 gallons.
- c. HPSW shall be available to provide backup cooling water to the Turbine Driven Emergency Feedwater Pump bearing oil cooler Condition A:
- Operations perform Risk Assessment considering equipment out of service.
AND
- Log unavailability duration in the Operations Log for Maintenance Rule performance monitoring.
When it is determined that the HPSW pump has to be cycled (or left running if a hydrant is opened) or when directed by the lead examiner this event is completed.
Page 9 of 18
Appendix 0 Scenario Outline Form ES-O-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)
Time Position Applicant's Actions or Behavior Plant Response:
Stat alarm 1SA2/A10 (CRD GLOBAL TROUBLE)
Stat alarm 1SA2IB1 0 (CRD ASYMMETRIC ROD ALARM)
Stat alarm 1SA2/D9 (CRD OUT INHIBIT)
Crew Response:
SRO SRO should enter AP/15 (Dropped or Misaligned Control Rods)
AP/15
- 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.
R,OATC
- Initiate Encl 5.1 (Control of Plant Equipment During Shutdown).
BOP (See next page)
- Notify SP~C 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% .a.klk 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/A111 03/015 (Reactivity Balance Calculation).
USE COLR curve for 4 RCPs and 1 inoperable rod.
Page 10 of 18
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/SRO) (TS)
Time Position 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 .:s 60% of allowable thermal power AND Reduce nuclear overpower trip setpoints (flux/flow imb) to
.:s 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 TS 3.1.4 is entered, or when directed by the lead examiner this event is completed.
Page 11 of 18
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 1 RC-4 Fails OPEN (M, ALL)
Time Position 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:
ALL Upon recognizing the second dropped control rod, the crew manually trips the reactor.
OATC 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:
- Ensure only one of the following operating:
~ 1A HPI PUMP
~ 1B HPI PUMP
- Start 1C HPI PUMP.
NOTE: The 1C HPIP will NOT start RNO: Start the standby HPIP and open 1HP-409
- Open the following:
~ 1X9-SC (U-1 CRD NORM FOR BKR)
~ 2X1-SB (U-1 CRD ALTERNATE FDR BKR)
- EXIT this rule.
Page 12 of 18
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:
2 nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1RC-4 Fails OPEN (M, ALL)
Time Position Applicant's Actions or Behavior ALL Crew Response:
UNPP tab
- Ensure Rule 1 (ATWS / 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.
- Open the following:
~ 1RC-4
~ 1HP-5
- Maximize letdown.
- Secure makeup to LDST. {8}
- WHEN all wide range Nls are:S; 1% FP, AND decreasing, THEN continue.
- Dispatch two operators to perform Encl 5.24 (Operation of the ADVs).
- Adjust letdown flow as desired.
- Verify RCP seal injection available
- GO TO Subsequent Actions tab.
Page 13 of 18
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 4 Event No.: 7 Page 3 of 6 Event
Description:
2 nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1 RC-4 Fails OPEN (M, ALL)
Time Position Applicant's Actions or Behavior Crew Response:
Completes a symptom check and then performs Rule 3 (Loss of BOP Main Feedwater)
Rule 3
- Verify any EFDW pump operating. (MDEFWPs running)
- Verify any SCM :s; O°F.
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).
Enc15.9
- Perform the following as required to maintain UST level> 7.5':
>- Makeup with demin water.
>- Place CST pumps in AUTO.
Page 14 of 18
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:
2 nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN 1RC-4 Fails OPEN (M, ALL>>
Time Position Applicant's Actions or Behavior Plant Response:
With the PORV and 1RC-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 SRO/BOPI
- Verify all control rods fully inserted.
OATC
- Initiate EncIS.S (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 OATC/BOP will perform Rule 2 (Loss of Subcooling Margin) and the SRO will transfer to the LOSCM tab.
Page 15 of 18
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:
2 nd 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/DATC will perform Rule 2 (Loss of Subcooling Margin).
BOP/OATC Rule 2
- IAAT all the following exist:
~ Any SCM S OaF
~ Rx power S 1%
~ S 2 minutes elapsed since loss of SCM THEN Stop all RCPs. (CT-1, Trip All RCPs)
- Start all available HPI pumps.
- Verify at least two HPI pumps are operating using two diverse indications.
- IAAT the following limits are exceeded 1A & 1B HPI pumps operating with 1HP-409 open and Total flow of 950 gpm (incl. seal injection) THEN throttle HPI to maximize flow S flow limit.
- Establish 300 gpm to 1A and 1B 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)
Page 16 of 18
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:
2 nd dropped CR, ATWS, Main FDW Pumps Trip, PORV fails OPEN (M, ALL)
Time Position Applicant's Actions or Behavior Plant Response:
Loss of Subcooling Margin Crew Response:
The SRO will transfer to the LOSCM tab LOSCM tab SRO OATC/BOP
- Verify all of the following exist:
- NO RCPs operating
- 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: (CT-11 Control SG Pressure to Maintain RC Temperature)
- Close 1RC-4.
NOTE: 1 RC-4 will not close.
- Verify primary to secondary heat transfer exists.
- Initiate Enc15.16 (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 17 of 18
Appendix D Scenario Outline Form ES-D-2 March,2009 CRITICAL TASKS
- 1. CT-24, ATWS
- 2. CT-16, FW Flow Control
- 3. CT-1, Trip All RCPs
- 4. CT-11, Control SG Pressure to Maintain RC Temperature Page 18 of 18
Appendix D Scenario Outline March,2009 Facility: Oconee Scenario No.: 5 RO IS 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 1C HPI Pump fails to start Ob Pre-insert 1A RBCU fails to receive ES signal MPS350 1 Pressurize "A" CFT with N2 Override N, BOP, SRO 1N-298 (N2 Fill CFT 1A), fails OPEN (TS) 2 R, OATC, SRO Increase power to 3% and place ICS in AUTO
( 3 MPI150 I, OATC, 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 1B1 RCP Lower Seal Failure 6 Override C, OATC, SRO Continuous Rod Withdrawal 7 MPS400 M,ALL SBLOCA 1C HPI Pump fails to start requiring rapid RCS C/D due to degraded HPI 8 MPS400 M,ALL LBLOCA
- (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor
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; N21N-298 fails OPEN (N, BOP/SRO)
Time Position 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.
- 3. Monitor 1A CFT pressure
- 5. Determine 1N-298 has failed to close:
- Red "open" light lit
- CFT pressure continues to increase
- 6. Inform the SRO.
Note: If 1N-137 is not closed the CFT pressure will continue to increase, possibly outside of TS limits.
SRO 7. Verify 1A CFT pressure is stable.
When CFT pressurization is stopped or when directed by the lead examiner this event is completed.
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 Applicant's Actions or Behavior Crew response:
OP/1/A/1102l001 (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, 1HP-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).
SROIOATC
- Begin raising 1HP-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.
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)
Time Position Applicant's Actions or Behavior Plant response:
Statalarms:
- 1SA-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 1HP-120 to manual to control PZR level.
- Refer to Technical Specification 3.4.9, Pressurizer.
- Refer to Technical Specification 3.3.8, PAM Instrumentation.
o Condition H applies
- Refer to PT/1/A/0600/001 (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 1HP-120 returned to AUTO or when directed by the lead examiner.
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 Time Position Applicant's Actions or Behavior Plant response:
Statalarms:
Board indications:
- RC Makeup 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:
BOP Refer to ARGs: Refer to AP/14 SRO AP/14 (Loss of Normal HPI Makeup and/or RCP Seal Injection)
- Announce AP entry
- Verify any HPI pump operating (go to RNO)
~ Close 1HP-5 (Letdown Isolation)
~ Place 1HP-120 in HAND and closed
~ Place 1HP-31 in HAND and closed
~ Attempt to start the Standby HPIP (1 B HPIP starts)
- Slowly open 1HP-31 in small increments until == 8 gprnlRCP is achieved.
- Re-establish normal makeup through 1HP120.
- Reduce 1HP-7 demand to 0%.
- Close 1H P-6
- Open the following:
~ 1HP-1 (1A Letdown Cooler Inlet)
~ 1HP-2 (1 B Letdown Cooler Outlet)
~ 1HP-3 (1A Letdown Cooler Inlet)
~ 1HP-4 (1 B Letdown Cooler Outlet
Appendix 0 Scenario Outline Form ES-O-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; OATC, SRO) TS Time Position Applicant's Actions or Behavior
- Open 1HP-S
- Throttle open 1HP-7 for:::::: 20 gpm letdown flow.
- Open 1HP-6
- ,Adjust 1HP-7 for desired letdown flow.
- Place 1HP-31 in AUTO.
SRO Refer to Tech Spec 3.S.2 High Pressure Injection
- Condition "A"
- 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 1HP-31 is placed in AUTO or when directed by the Lead Examiner.
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)
Time Position Applicant's Actions or Behavior Plant response:
- 1SA-06/C-5, RC PUMP 1B1 CAVITY PRESS HI/LOW
- 1SA-06/C-6, RC PUMP 1 B1 SEAL RETURN FLOW HI/LOW Crew response:
BOP Refer to the ARGs Refer to AP/16 , Abnormal RCP Operations SRO
- IAAT the failure is identified, THEN GO TO the applicable section: 4A Seal Failure BOP
- Stop the affected RCP (1 B1)
- IAAT 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:
>- 1HP-20
>- 1 HP-21
- IAAT RCP has been shutdown for >30 minutes, THEN close the associated RCP motor cooler inlet/outlet valve (1 LPSW-9 & 10)
When the 1 B1 RCP has been secured or when directed by the lead Examiner, the event is complete.
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 6 Page 1 of 1
Event
Description:
Continuous Rod Withdrawal: (I, OATC)
Time Position 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 OATC 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 SPOC 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.
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 7 Page 1 of 6 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior Plant response:
Control board indications:
- 1SA-21D-3, RC PRESS HI/LOW
- RCS Pressure and PZR level decreasing
- ES 1-6 actuate
- RCS subcooling margin will indicate O°F Crew response:
IMAs (IAAT steps) from AP-2 give direction to close 1HP-5 if MU ALL flow is > 100 GPM with Pzr level decreasing, and to TRIP the Rx if MU is beyond "Normal Makeup Capability" (160 gpm) with 1HP-5 closed
- BOP/OATC may trip the reactor based on the above IAAT.
( OATC
- 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.
SRO 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
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Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 7 Page 2 of 6 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
- IAAT all the following exist:
>- Any SCM::; QOF
>- Rx power::; 1%
>- ::; 2 minutes elapsed since loss of SCM THEN perform Stop all RCPs
- Open 1HP-24/25
- Open 1HP-26/27
- Maximize HPI flow::; 475 gpm (including seal injection for A hdr)
- Dispatch two operators to align ADVs
- Notify CR SRO to:
>- Suspend Rule 3 until directed by LOSCM tab
>- Degraded HPI exists
- EXIT this rule
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.:5 Event No.: 7 Page 3 of 6 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior OATC OATC will perform Enclosure 5.1 (ES actuation)
Enclosure 5.1
- Verify all ES digital channels associated with actuation setpoints have actuated.
- Place HPI in Manual.
- Verify Rule 2 in progress or complete.
- Verify any RCP operating
- RNO: GO TO Step 8
- IAAT ES Channels 3 & 4 are actuated, THEN GO TO Step 12.
- Place the following in manual control:
~ 1A LPI PUMP
~ 1LP-17
~ 1B LPI PUMP
~ 1LP-18 CAUTION LPI pump damage may occur if operated in excess of 30 minutes against a shutoff head.
- IAAT any LPI pump is operating against a shutoff head, THEN at the CR SRO's discretion, stop affected LPI pumps. (Cn (Within 30 minutes)
- Start A and B OUTSIDE AIR BOOSTER FAN (CT-27) (30 minutes from the LOCA)
- Notify Unit 3 to start 3A and 3B OUTSIDE AIR BOOSTER FANS
- Verify the following are open:
~ 1CF-1
~ 1CF-2
- Verify 1HP-410 closed.
- Secure makeup to the LDST.
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 7 Page 4 of 6 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior OATC/BOP Enclosure 5.1 (Continued)
- Close 1 LPSW-139.
- Place the following in FAIL OPEN:
~ 1LPSW-251 FAIL SWITCH
~ 1LPSW-252 FAIL SWITCH
- Verify either of the following:
~ Three LPSW pumps operating
~ Two LPSW pumps operating when Tech Specs only requires two to be operable
- Open the following:
~ 1LPSW-4
~ 1LPSW-5
- Select DECAY HEAT LOW FLOW ALARM SELECT switch to ON.
- IAAT ES channels 5 & 6 have actuated, THEN perform Step 40.
- Verify all ES channel 5 & 6 components in the ES position. (1 A RBCU will not be in required - LOW speed)
- Notify U2 CR SRO that SSF is inoperable due to OTS1-1 open
Appendix 0 Scenario Outline Form ES-O-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 7 Page 5 of 6 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior SRO SRO will transfer to the LOSCM tab.
LOSCM tab
- Ensure Rule 2 (Loss of SCM) is in progress or complete.
- IAAT 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)
SRO/BOP/
- Start both MDEFWPs OATC
- Start the TDEFWP
- Establish 300 gpm to each of the SGs:
~ 1ASG
~ 1BSG
- 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))
- Trip Both Main FDW Pumps
- Ensure Rule 3 (Loss of Main or Emergency FDW ) is in progress or complete
Appendix D Scenario Outline Form ES-D-2 March,2009 Op-Test No.: _ _ Scenario No.: 5 Event No.: 7 Page 6 of 6 Event
Description:
SBLOCA: (M, ALL)
Time Position Applicant's Actions or Behavior SRO/BOP
- GO TO Step 37
- Close 1RC-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 OATC/BOP
- Initiate Enc15.9 (Extended EFDW Operation)
~ Perform the following to maintain UST level> 7.5':
o Makeup with demin water o Place CST pumps in AUTO
- Start TD EFDWP BEARING OIL COOLING PUMP.
When the SRO reaches the WHEN step above or when directed by the lead examiner this event is completed.
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)
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-B if not previously actuated will now actuate OATC/BOP Crew response:
- RO performing Encl. 5.1, ES Actuation, must recognize that the IAAT Step 14 will need to be performed and LPI Pumps restarted. (CT-4, Initiate LPI)
- RO performs Symptom Check
- Crew should recognize LOSCM IAAT Step 6 now exists.
LOSCM IAAT Step 6:
- IAAT 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 1LPSW-1B.
~ _Open 1LPSW-21.
~ _ Open 1LPSW-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 S 400°F, THEN continue in this procedure.
When transfer to LOCA Cooldown tab or when directed by the lead examiner, this event is completed
Appendix 0 Scenario Outline Form ES-O-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
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