ML032591147
| ML032591147 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  (NPF-014, NPF-022) |
| Issue date: | 08/01/2003 |
| From: | Roush K Susquehanna |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-387/03-301, 50-388/03-301 | |
| Download: ML032591147 (82) | |
Text
L Event No.
1 2
3 4
5 II Appendix D Scenario Outline Form ES-D-I Malf. No.
Event Event Type*
Description N/A N
Perform ARI surveillance N/A R
10% Power reduction to 90%
IMF RL02:E411 K17 I
HPCl CST low level switch failure IMF AV04:Tv11016B 0 I
B Recirc pump MG set HYD FLUID CTRL TCV (TIC-11016B) failed closed. B Reactor Recirc Pump trip (Auto trips at 210°F as a result of TIC-11016B failure).
IMF TC193016 130 M
TURBINE EHC PRESSURWFLOW GAIN UNIT FAILURE (130%) - MSlV Closure IMF RD155017 M
Hydraulic ATWS Facility: SSES Scenario No.: PCOl7-I 02 Op-Test No.:
7 1
8 Examiners:
IMF SL153001A C
SBLC Squib valves fail to fire.
IMF SL153001 B IMF MV06:HV155F006 C
HPCl injection Auto ODen failure Operators:
Initial Conditions: IC-20 Both Units at 100% Power EOL Turnover: B Service Air Compressor out of service for Dreventative maintenance. The compressor will not be returned to service this shift. Decrease Dower to 90% for rod adiustments IAW OP-AD-338 (Attachment C) then call Reactor Enaineerinq. Prior to starting power reduction perform SO-155006. QUARTERLY ARI MANUAL TRIP CHANNEL FUNCTIONAL TEST.
11 6
I bat RPB.HYDAlWS-1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021 Draft Rev. 9 2003 NRC Exam Rev. 1 Susquehanna Facsimile
PP&L-S USQU EHAN NA TRAINING CENTER SIMULATOR SCENARIO Scenario
Title:
NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration: 90 Minutes Scenario Number: PCOl7-102 Revision/Date:
Rev 0, 5/1/2003
~~
Course:
PC017, Senior Reactor Operator License PC018, Reactor Operator License Operational Activities:
1 Surveillance Activity 2 Power Change 3 HPCl CST Level Switch Failure 4 MG B HYD Fluid TCV Fail Closed 11 Prepared By:
Reviewed By:
Approved By:
5 Turbine EHC System Malfunction 6 ATWS 7 SBLC Squib Valve Fail to Fire 8 HPCl F006 Auto Logic Failure Instructor Nuclear Operations Training Supervisor Supervising Manager/Shif? Supervisor Date Date Date Form STCP-QAG12A Rev. 0, (C4/98)
Page 1 of 15 2003 NRC Exam Rev. 1 File No. RI 1-3
Page 2 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 Form STCP-QA-612A Rev. 0, (04/98)
Page 2 of 23 2003 NRC Exam Rev. 1 THIS PAGE IS INTENTIONALLY LEFT BLANK File No. Rll-3
Page 3 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 SCENARIO
SUMMARY
11 The scenario begins with the plant operating at 100% power. The "BI Service Air Compressor is out of service for preventive maintenance and will not be returned to service this shift. Unit 2 is in MODE 1 at 100%
power.
After assuming the shift, the crew will perform a surveillance activity on the Alternate Rod Insertion system.
Upon completion of the surveillance the crew will commence a power decrease requested by Reactor Engineering for a rod pattern adjustment. While meeting this request, a HPCl system CST low level switch fails; HPCl suction source will swap to the suppression pool and Technical Specifications will be addressed.
Upon resumption of the power decrease a failure of the " B Reactor Recirc MG set lube oil TCV-1 I01 6B occurs; the valve will fail shut, resulting in elevated lube oil temperatures to the MG set. This will cause "BI reactor recirc pump to eventually trip. The crew will take actions IAW General, Off-Normal and Operating procedures as well as address Technical Specifications for Single-Loop operation.
Following crew response to the tripped recirculation pump, the EHC Pressure/Flow Gain Unit will fail, causing all Main Turbine Bypass and Control valves to open. Reactor pressure will rapidly decrease to cause a MSlV isolation and reactor scram signal. When the reactor scram signal is received, one Scram Discharge Volume will become blocked, resulting in a hydraulic ATWS.
The crew will enter the LeveVPower Control procedure to mitigate the ATWS. The crew will initiate SLC, but the Squib valves will fail to fire, requiring alternate SLC injection with RCIC. Since initial ATWS power level is above 5%, the crew will lower RPV level and stabilize in the target band of -60" to -1 IO". When HPCl is initiated the injection valve will fail to open, placing the control switch to open will allow injection flowpath. As RPV water level is being maintained between -60" and -1 IO" crew attempts to insert control rods manually and by resetting/rescramming will be successful. The crew should exit LeveVPower Control and re-enter RPV Control to slowly restore and maintain level between + I 3" to +54".
I When all control rods are inserted and actions are in progress to restore RPV water level to +13" to +54", the scenario will be terminated.
F o
~
STCP-QA-61%
Rev. 0, (04/98)
Page 3 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Form STCP-QA-612A Rev. 0, (04/98)
Page 4 of 23 2003 NRC Exam Rev. 1 Page 4 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 File No. R I M
Page 5 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 L
SCENARIO OBJECTIVES The SRO will:
I. Ensure initiation of ESF equipment if automatic operation was not properly initiated (00.AD.131).
- 2. Inform other shift members and plant management of changes in plant status, potential plant problems or limitations (00.AD.I 31).
- 3. Ascertain the need to notify the Duty Manager when a plant event develops and ensure the notification is made (00.AD.131).
- 4. Implement Loss of Reactor Recirculation Flow (64.ON.010).
- 5. Implement Turbine EHC Malfunction (93.0N.005).
- 6. Implement Main Turbine Trip (93.0N.006).
- 7. Implement Scram (00.ON.018).
- 8. Implement RPV Control (00.E0.026).
- 9. Implement LeveVPower Control (00.E0.031).
I O. Implement Primary Containment Control (00.E0.027).
- 11. Implement Boron Injection Via RClC (50.E0.009).
- 13. Ensure required actions per Technical Specifications are met when a LCO is not met (00.TS.002).
- 1. Perform normal operation of RHR in the Suppression Pool Cooling Mode (49.0P.003).
- 2. Perform automatic/manual startup of RClC system (50.0P.010).
- 3. Perform manual startup of HPCl (52.0P.012).
- 4. Perform maximizing CRD flow (55.0P.001).
- 5. Perform initiation of Standby Liquid Control System (53.0P.003).
- 6. Perform inserting manual scram with CRD system in service (55.0P.006).
- 7. Perform shutdown of Recirculation Pump for Single Loop operation (64.0P.002).
- 8. Perform inhibiting ADS (83.0P.005).
- 9. Implement Loss of Reactor Recirculation Flow (64.ON.010).
I O. Implement Turbine EHC Malfunction (93.0N.005).
- 11. Implement Main Turbine Trip (93.0N.006).
- 12. Implement Scram (00.ON.018).
- 13. Implement RPV Control (00.E0.026).
- 14. Implement LeveVPower Control (00.E0.031).
- 15. Implement Primary Containment Control (00.E0.027).
- 16. Implement Boron Injection Via RClC (50.E0.009).
The ROs will:
\\-
Form STCP-QA-612A Rev. 0. (04/98)
Page 5 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 6 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 Form STCP-QA-612A Rev. 0, (04/98)
Page 6 of 23 2003 NRC Exam Rev. 1 File No. R l l - 3
Page 7 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 I*
I CRITICAL TASKS 03 ATWS 06 LEVEL / POWER CONTROL
,Lowers RPV level to <-60" but >-161".
Manually opens HPCl injection HV-I 55-FOO6.
Inserts control rods IAW EO-100-1 13 Sht. 2.
Denotes Simulator Critical Task Form STCP-QA-612A Rev. 0. (04/98)
Page 7 of 23 2003 NRC Exam Rev. 1 File No. RI 1-3
Page 8 Scenario PCOl7-102 Rev. 0, 5/1/2003 THIS PAGE IS INTENTIONALLY LEFT BLANK 1
ll Form STCP-QA-612A Rev. 0. (04/98)
Page 8 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 9 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 SCENARIO REFERENCES
- 1. SURVEILLANCE ACTIVITY SO-I 55-006 OP-AD-004 QUARTERLY ARI MANUAL TRIP CHANNEL FUNCTIONAL TEST, REV. 8 OPERATIONS STANDARDS FOR ERROR AND EVENT PREVENTION, REV. 5
- 2. POWER CHANGE GO-I 00-01 2 POWER MANEUVERS, REV. 17 NDAP-QA-338 REACTIVITY MANAGEMENT AND CONTROLS PROGRAM, REV. 6 OP-AD-001 OP-AD-338 OPERATIONS STANDARDS FOR SYSTEM AND EQUIPMENT OPERATION, REV.5 COMMUNICATION REQUIREMENTS FOR REACTIVITY MANIPULATIONS, REV. 1
- 3. HPCl SYS CST LO LEVEL SWITCH FAILURE AR-114-EO1 CST LO WATER LEVEL, REV. 22 STANDARDS FOR SHIFT OPERATIONS, REV. 9 TS 3.3.5.1 NDAP-QA-0702 ECCS INSTRUMENTATION, AMENDMENTS 178 & 204 OP-AD-002 ACTION REQUEST AND CONDITION REPORT PROCESS, REV. 12
- 4. MG B HYD FLUID TEMP CONTROL VALVE FAIL CLOSED / RRP B TRIP AR-102-C05 AR-102-C06 AR-102-BO5 RECIRC MG SET A/B BRG OR FLUID DRIVE OIL HI TEMP, REV. 21 RECIRC MG B FLUID DRIVE OIL HI-LO TEMP, REV. 21 RECIRC MG B DRIVE MTR TRIP, REV. 21 ON-164-002 LOSS OF REACTOR RECIRCULATION FLOW, REV. 20 TS 3.4.1 TR 3.2 RECIRCULATION LOOPS OPERATING, AMENDMENT 178 COLR SECTION 8, 3/15/02 GO-I 00-009 SINGLE RECIRCULATION LOOP OPERATION, REV. 13
- 5. TURBINE EHC SYSTEM MALFUNCTION / MSlV ISOLATION ON-I 56-001 ON-I 93-001 UNEXPLAINED REACTIVITY CHANGE, REV. 14 TURBINE EHC SYSTEM MALFUNCTION, REV. 10
- 6. ATWS / LEVEUPOWER CONTROL / RPV CONTROL ON-I 00-1 01 EO-I 00-1 02 EO-I 00-1 13 ES-150-002 ES-158-002 EP-PS-1 00 SCRAM, REV. 9 RPV CONTROL, REV. 1 BORON INJECTION VIA RCIC, REV. 13 RPS AND ARI TRIP BYPASS, REV. 4 LEVEL-POWER CONTROUCONTROL ROD INSERTION, REV. 1 EMERGENCY PLANT POSITION-SPECIFIC (ED), REV. 16 Continued on next page:
Form STCP-QAB12A Rev. 0. (04198)
Page 9 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page I O Scenario PCOl7-I 02 Rev. 0, 5/1/2003
- 7. PRIMARY CONTAINMENT CONTROL L-EO-I 00-1 03 PRIMARY CONTAINMENT CONTROL, REV. 2
- 8. OTHER BWROG SIMULATOR SCENARIO DEVELOPMENT GUIDELINE, TEMPLATE RPV-6 Form STCP-QA-612A Rev. 0. (04/98)
Page 10 of 23 2003 NRC Exam Rev. 1 File No. R1 1-3
Page 11 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 MALFS 63 : 63 SCENARIO SPECIAL INSTRUCTIONS REMFS OVRDS TRIGS I
3:3 0
- 1. Initialize the simulator to IC-20 (Both Units 100% Power, EOL).
- 2. Set up the simulator for the scenario by performing the following:
Place the "B" Service Air Compressor control switch on 1 C668 to OFF.
- 3. Type restorepref YPP.PCO17-I 02; verify the following pre-inserts and Program Button assignments:
Verify the Environment Window:
IOR ZAlM2J115HD5 15 MCFL POT AT 100%
MRF PM091 K108B OUT "Bv SERVICE AIR COMPRESSOR BKR RACKED OUT IMF RD155017 PARTIAL SCRAM (BROWNS FERRY EVENT)
+IMF MV07:PV146F003 8.7 CRD PRESS VLV F003 FAILED, 8.7% <-
IMF MV06:HVl55F006 AUTO LOGIC FAILURE TO OPEN IMF SL153001A IMF SL153001B SQUIB VALVE XV-C41-F004A FAILS TO FIRE SQUIB VALVE XV-C41-F004B FAILS TO FIRE bat RP B. HY DAMIS-1
[P-I] IMF RL02:E411Kl7
[P-21 IMF AV04:TV11016B 0
[P-31 IMF TC193016 130 HPCl SYS CST LO LEVEL SWITCH FAILURE MG B HYD FLUID CTRL TCV (TIC-I 1016B) FAILED CLOSED TURBINE EHC PRESSURE/FLOW GAIN UNIT FAILURE (130%)
[PA] MRF RD155017 0 146F034 CRD CHARGING WTR IS0 VLV CLOSED
[P-5] bat RPB.DISABLARI OPENS ARI BKRS IAW ES-158-002
[P-61 bat RPB.ES158002 BYPASSES RPS IAW ES-158-002
[P-81 bat RBP.HYATW-CLR DELETE HYD ATWS
[P-71 DMF RD155017 PARTIAL SCRAM - DELETED
- 4. Prepare a turnover sheet indicating:
- a. "Bv Service Air Compressor out of service for preventive maintenance. The system will not be returned to service this shift.
- b. Decrease power to 90% for rod adjustments IAW OP-AD-338 (Attachment C) then call RE.
- c. Prior to starting power reduction perform SO-155-006, QUARTERLY ARI MANUAL TRIP CHANNEL FUNCTIONAL TEST.
- d. Unit 2 is in MODE 1 at 100% power.
- 5. Prepare a power change with Recirc (form OP-AD-338, Attachments A & C) indicating power to be reduced to 90% at l%/min.
- 6. Prepare a copy of SO-155-006, QUARTERLY ARI MANUAL TRIP CHANNEL FUNCTIONAL TEST and a su rvei I Ian ce covers heet.
- 7. Make a copy of shift assignments.
Form STCP-QA-612A Rev. 0, (04/98)
Page 11 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 12 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 THIS PAGE IS INTENTIONALLY LEFT BLANK 1
II Form STCP-QAB12A Rev. 0, (04198)
Page 12 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 13 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 EVENT 1
2 SCENARIO EVENT DESCRIPTION FORM TIME DESCRIPTION 05 SURVEILLANCE ACTIVITY 20 POWER CHANGE
--+-
3 Initial Conditions: Initialize the Simulator to IC-20. Place the Simulator to RUN. Ensure the Program Buttons are assigned as indicated on the Special Instructions sheet via the appropriate Preference File. Assign Shift positions. Direct the start of the 5-minute panel walk down.
25 HPCl SYSTEM CST LO LEVEL SWITCH FAILURE 5
55 TURBINE EHC SYSTEM MALFUNCTION / MSlV ISOLATION II 4
7 I
35 I MG B HYD FLUID TEMP CONTROL VALVE FAIL CLOSED / RRP B TRIP 65 SBLC SQUIB VALVE FAIL TO FIRE 8
II 75 HPCl INJECTION F006 AUTO LOGIC FAILURE TO OPEN I
60 I ATWSILEVEL POWER CONTROURPV CONTROL II I
90 I TERMINATIONCUE Form STCP-QA-61%
Rev. 0. (04/98)
Page 13 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 14 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 POSITION SCENARIO EVENT FORM TIME STUDENT ACTIVITIES Event No:
I, 233 Brief
Description:
Surveillance Activity / Power Change / HPCl Sys CST Lo Level Switch Failure us PCOP us PCOM PCOP c-
~
~
Reviews and authorizes performance of SO-I 55-006.
Performs SO-I 55-006.
Reviews and approves the Reactivity Manipulation Package.
Conduct a reactivity briefing in accordance with OP-AD-338.
Commences power decrease at I
% per minute with Reactor Recirculation Flow Control in accordance with OP-AD-338 and GO-100-012.
Reports CST LO WATER LEVEL alarm.
Refers to AR-114-EOI.
Verifies PUMP SUCT FROM SUPP POOL HV-155-F042 OPENS.
Verifies PUMP SUCT FROM CST HV-155-F004 CLOSES.
Checks CST A level on OC653, LR-00812.
I Reports CST A level is not low.
Dispatch Plant Operator to investigate.
us I Contacts Work Week Manager concerning CST level switches.
I I Refers to TS 3.3.5.1, Table Function 3.d, enters Condition A & D.
I Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATION.
~
Identifies a CR is required.
- Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0, (04/98)
Page 14 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 15 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 i-INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
1Y2Y 3 Brief
Description:
Surveillance Activity / Power Change I HPCl Sys CST Lo Level Switch Failure INSTRUCTOR ACTIVITY:
When reactor power is reduced -2%, insert HPCl system CST low level switch failure, Depres P-I:
[P-I] IMF RL02:E411Kl7 CST LO WTR LEVEL LSLL-E41-1N002 FAILURE NOTE: Monitor sim diagram MW3 to report local CST A level from OC518A.
ROLE PLAY:
As Plant Operator sent to HPCl CST low level switches, wait -2 mins. and report there is no visible indication of either switch having a problem.
As Plant Operator sent to CST A, wait -2 mins. and report there is no visible leakage or loss of CST level.
~.-
.~
As FIN Team/l&C sent to investigate the level switch problem, wait - 5 mins. and report LSLL-E41-1N002 has failed, it will take -6 hours to replace and calibrate the switch.
Form STCP-QA-61ZA Rev. 0, (04/98)
Page 15 of 23 2003 NRC Exam Rev. 1 File No. Rl1-3
Page 16 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 TIME SCENARIO EVENT FORM
.A Event No:
4 Brief
Description:
MG B HYD Fluid Temp Control Valve Fail Closed I RRP B Trip STUDENT ACTIVITIES Recognizes/reports AR-102-C05, RECIRC MG SET N B BRG OIL FLUID DRIVE HI TEMP, and AR-102-C06, RECIRC MG B FLUID DRIVE OIL HI-LO TEMP alarms.
Attempts manual control of TIC-1 100166; reports failure of TV-110016B.
Recognizesh-eports loss of "6" Recirc pump.
Depress 6 MG drive motor breaker stop pushbutton, HS-14001 B per the AR.
Performs actions of ON-164-002, LOSS OF REACTOR RECIRCULATION FLOW.
Evaluate Power/Flow Mau.
\\_.-
POSITION PCOM I Dispatches NPO to investigate TV-11016B; may direct opening TV bypass valve 110038.
us 1 Directs Work Week Manager about failure of TV-110016B.
I Directs actions of ON-164-002.
I Contacts Reactor Engineer.
Refers to GO-1 00-012, POWER MANEUVERS and GO-1 00-009, SINGLE RECIRCULATION LOOP OPERATION.
Refers to T.S. 3.4.1, Recirculating Loops Operating and COLR section 8.0 in TRM section 1
1 3.2.
1 Directs I&C to perform Flow-Bias Scram setpoint changes for Single Loop operation.
I I Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.
Identifies a Condition Report is required IAW NDAP-QA-702, ACTION REQUEST AND CONDITION REPORT PROCESS.
- Denotes Critical Task F
o
~
STCP-QA-61%
Rev. 0, (04198)
Page 16 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 17 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:
4 Brief
Description:
MG B HYD Fluid Temp Control Valve Fail Closed I RRP B Trip INSTRUCTOR ACTIVITY:
When power reduction is resumed, wait one minute then activate the failure of TIC-I 1016B: (Ensure this malfunction is entered prior to reaching -95% power, this will subsequently ensure the power level for ATWS actions later), Depress P-2:
[P-21 IMF AV04:TV11016B 0 MG B HYD FLUID CTRL TCV (TIC-I 1016B) FAIL CLOSED NOTES:
0 0
0 Refer to Simulator P&ID SW3 for W-110016B status; refer to P&ID RR6 for "B" Recirc MG Set Oil temperatures.
RECIRC MG B BRG OR FLUID DRIVE OIL HIGH TEMP alarm (AR-102-C05,140°F) takes -2 minutes to annunciate.
RECIRC MG B FLUID DRIVE OIL HIGH TEMP alarm (AR-102-C06, 190°F) takes -5 minutes to annunciate.
The MG Set trips at 210°F in -6 minutes.
If crew elects to take OP-164-001 Single Loop actions and is subsequently required to manually scram the reactor due to operation in Region I of the Power/Flow map, perform the next event via [P-31 as outlined on page 19 BEFORE the crew places the Mode Switch to Shutdown.
ROLE PLAY:
- 1. As RE, direct crew to insert control rods per OP-AD-338 Attachment E in CRC Book. You will run the core monitor and report results shortly.
- 2. If directed as NPO to investigate n/-11016B, wait -2 minutes and report that the valve is closed; the valve stem appears to be bent.
- 3. If directed to bypass TV-I 1016B by opening 110038, wait -2 minutes and report that the valve is stuck; you can not get the valve open.
- 4. If directed as FIN Team to investigate failure of TV-I1016B, wait -5 minutes and report that the valve is jammed on it's closed seat; it will take some time to free the valve. You have no time estimate for completion of repairs at this time.
- 5. As 1&C directed to perform Flow-Bias Scram setpoint changes for Single Loop operation, acknowledge the order and perform no further actions.
Form STCP-QA-612A Rev. 0. (04/98)
Page 17 of 23 2003 NRC Exam Rev. 1 File No. Rl l -3
Page 18 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 POSITION TIME STUDENT ACTIVITIES NOTES:
PCOM NOTE 1: This event is classified as a SITE AREA EMERGENCY due to ATWS/SLC failure IAW I Observes TCVs and BPVs open and SCRAM.
I Recognizes failure of all control rods to fully insert.
Performs ON-100-101, SCRAM:
0 0
Tripsherifies tripped "A" Recirc Pump.
Place Mode Switch to S/D.
Arm and Depress manual scram pushbuttons.
PCOP I Recognize/reports MSlV closure.
I initiates ARI.
us Enters EO-I 00-1 02, RPV CONTROL and exits to EO-I 00-1 13, LEVEL/POWER CONTROL.
I Directs initiating SLC and inhibiting ADS.
PCOP NOTE 1 I Attempts to initiate SLC, notifies US of SLC Squib valves failure.
us I Directs alternate SLC injection IAW ES-150-002.
PCOP I Inhibits ADS as directed.
- Denotes Critical Task I1 I)
Form STCP-QA-612A Rev. 0, (04/98)
Page 18 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 19 Scenario PCOl7-I 02 Rev. 0, 5/1/2003 I/
INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:
5, 637 Brief
Description:
Turbine EHC System Malfunction I MSlV Isolation I ATWS I Squib Valve Failure INSTRUCTOR ACTIVITY:
- 1. When the actions for the loss of "B" Recirc pump are complete (pump tripped and single loop operations discussed), fail the in service EHC pressure transmitter, Depress P-3:
[P-31 IMF TC193016 130 TURBINE EHC PRESSURE/FLOW GAIN UNIT FAILURE (130%)
NOTE: Boron injection via RClC will not be done in this scenario.
ROLE PLAY:
- 1. As NPO dispatched to investigate SLC, wait -3 minutes and report that the SLC pumps are running and the discharge relief valves are chattering. Pump discharge pressure on the local gage is cycling between -1250 psig and 1450 psig.
- 2. As FUS, acknowledge direction to perform ES-150-002, Boron Injection Via RClC but take no further action. If the crew requests a status update role play as necessary since boron injection is not going to be permitted.
Form STCP-QA-612A Rev. 0. (04198)
Page 19 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 20 Scenario PCOl7-I 02 Rev. 0, 5/1/2003
- COP PCOP SCENARIO EVENT FORM Establishes RPVlevel in target band of -60" to -110" using RCIC & HPCI.
Reports HPCI Injection F006 failure to open.
Manually OPENS HPCl Injection valve F006.
Maintains RPV pressure between 800 and 1087 psig using SRVs in alphabetical order.
Event No:
638 Brief
Description:
ATWS I Level Power Control I RPV Control I HPCl F006 Auto Logic Failure POSITION
?tUS TIME STUDENT ACTIVITIES Directs RPVIevel lowered to <-60" but >-I61 ".
Directs establishing RPVIevel target band of -60" to -110" Directs controlling RPV pressure between 800 and a 0 8 7 psig.
Directs PCOM to insert control rods IAW EO-100-113 Sht. 2, CONTROL ROD INSERTION.
Directs implementation of ES-158-002.
/
Directs bypassing RSCSIR WM and manually inserting control rods.
,fit Lowers and controls RPVlevel to G60" but >-kI" using available injection systems.
I I
Lowers RCIC speed controller j, Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0. (04198)
Page 20 of 23 2003 NRC Exam Rev. 1 File No. R1 1-3
Page 21 Scenario PCOl7-I 02 Rev. 0, 5/1/2003
--.4 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:
6 8 Brief
Description:
ATWS / Level Power Control / RPV Control / HPCl F006 Auto Logic Failure INSTRUCTOR ACTIVITY:
I. When the PCOM directs closing 146F034 to isolate the CRD Charging header, wait =2 minutes and Depress P-4:
[P-41 MRF RD155017 0 146F034 CRD CHARGING WTR IS0 VLV CLOSED ROLE PLAY:
As NPO directed to close CRD Charging Water Isolation Valve 146F034, report the valve has been closed.
INSTRUCTOR ACTIVITY:
- 2. When the PCOM has manually inserted -10 control rods and RPV water level has been stabilized between -60" and -1 IO", call the Unit Supervisor on the page and ask permission to open ARI breakers 1 D614006 & 1 D624016 IAW ES-158-002 wait -2 minutes, Depress P-5:
[P-5] bat RPB.DISABLARl OPENS ARI BKRS IAW ES-158-002 ROLE PLAY:
As FUS, report that the ARI breakers have been opened IAW ES-158-002. You are continuing with bypassing RPS at this time.
INSTRUCTOR ACTIVITY:
- 3. After disabling ARI above, call the Unit Supervisor on the page and ask permission to bypass RPS trips IAW ES-158-002 wait -3 minutes and complete ES-158-002 Depress P-6:
[P-61 bat RPB.ES158002 BYPASSES RPS IAW ES-158-002 ROLE PLAY:
As FUS, report that RPS has been bypassed and ES-158-002 is now completed.
Form STCP-QA-612A Rev. 0. (04/98)
Page 21 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 22 Scenario PCOI 7-1 02 Rev. 0, 5/1/2003 SCENARIO EVENT FORM Event No:
6 Brief
Description:
ATWS I Level Power Control I RPV Control POSITION
- COM us PCOP PCOP TIME STUDENT ACTIVITIES Inserts control rods IA W 0-100-173 Sheet 2.
Bypasses RSCS/R WM.
0 0
Resets scram.
Directs 146FO34 closed, as necessary.
Commences manual control rod insertion.
Drains SDV and inserts another scram.
Verifies and reports all control rods in.
Acknowledges all control rods inserted.
Exits EO-1 00-1 13 and re-enters EO-1 00-1 02.
Directs RPV water level be restored to +13" to +54".
Enters EO-1 00-1 03, PRIMARY CONTAINMENT CONTROL.
Directs Suppression Pool Cooling maximized.
Places both loops of RHR in Suppression Pool Cooling.
Restores RPV water level to +13" to +54".
TERMINATION CUE:
All control rods are inserted and actions are in progress to restore RPV water level to +13" to +54".
- Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0. (04198)
Page 22 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 23 Scenario PCOI 7-1 02 Rev. 0. 5/1/2003 b-INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
6 Brief
Description:
ATWS I Level Power Control I RPV Control INSTRUCTOR ACTIVITY:
[P-71 DMF RD155017 PARTIAL SCRAM - DELETED
[P-81 bat RBP.HYAMI-CLR DELETES HYD ATWS NOTE: It takes -7 minutes for RPS AI/A2 (BI/B2) SCRAM DSCH VOL HI WTR LEVEL TRIP annunciators (AR-I03/104-F02) on IC651 to clear. Monitor P&ID Display RD-5 for SDV status.
ROLE PLAY:
As necessary.
.\\--
TERMINATION CUE:
All control rods are inserted and actions are in progress to restore RPV water level to +13 to +54 Form STCP-QA-612A Rev. 0. (04198)
Page 23 of 23 2003 NRC Exam Rev. 1 File No. R11-3
N/A IMF RD7550043823 Appendix D Scenario Outline Form ES-D-1 N
R Facility:
IMF PM03:OP504A SSES Scenario No.:
C PCOI 7-1 03 IMF MV07:HV144F100 100 Op-Test No.:
C Examiners:
Operators:
Initial Conditions: IC423 Unif 7 30% Power OL.(#) Unit 2 stat--up in proqress, - 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from svnchronizinq to the qrid.
Turnover: HPCI is ouf of service for repairs to oil pump breaker and oil chan_qeout.(5) The svstem will not be returned to service this shift. Mechanical vacuum Dump is out of service for a seal reriacement. The svstem will not be returned to service this shift. Perform SO-054-AO3. QUARTERLY ESW FLOW VERIFICATION LOOP A. Maintenance is standinn by for vibration data.
Event No.
1 2
3 Malf. No.
Event (NONE 0 20) 5 IMF DSl04001A (NONE 10 0)
C IMF CUI61007 100 4:OO IMF MV07:HV144Fl06 IMF MVO9:HV144FOOI (004) 98 (102) 100 IMF RC150011 IMF BR05:1A10104 (204)
M M
Event Description Perform A ESW Loop Surveillance Rod 38-23 driffs to position 38 (6)
A ESW pump trips during surveillance Loss of 1A ESS bus/Loss of RPS/Loss of CRD RWCU F007 (7) VLV FAILED-OPEN Unisolable break on RWCU line inside Secondary Containment Loss of all High pressure feed. (Leads to loss of adequate core cooling, requiring rapid depressurization)
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021 Draft Rev. 9 2003 NRC Exam Rev. 1 Susquehanna Facsimile
PP&L-SUSQUEHANNA TRAINING CENTER Prepared By:
Instructor Reviewed By:
Nuclear Operations Training Supervisor SIMULATOR SCENARIO Date Date
~
~
Scenario
Title:
NRC INITIAL LICENSE OPERATOR EXAMINATION Scenario Duration: 90 Minutes Approved By:
Supervising ManagerIShift Supervisor Scenario Number: PCOl7-103 Date Revision/Date:
Rev 0; 5/1/03 Course:
PC017, SENIOR REACTOR OPERATOR LICENSE PC018, REACTOR OPERATOR LICENSE Operational Activities:
1 Surveillance Activity 5 Control Rod Drift 2 Inoperable ESW Pump 6 RWCU Break Inside Sec Containment 3 Loss of 1A ESS Bus 7 Loss of High Pressure Feed 4 RWCU Fool Failure to Close J
Form STCP-QA612A Rev. 0. (04198)
Page 1 of 15 2003 NRC Exam Rev. 1 File No. R11-3
Page 2 Scenario PCOl7-I 03 Rev. 0, 5/1/03 Form STCP-QA4IZA Rev 0. (04/98)
Page 2 of 23 2003 NRC Exam Rev. 1 IS E IS INTEN LLY L K
File No. R11-3
Page 3 Scenario PCOI 7-1 03 Rev. 0, 5/1/03 The scenario begins with the plant operating at 30% power. HPCl is out of service for governor repair work and the Mechanical Vacuum Pump is out of service for seal replacement. A quarterly surveillance test of the "A" ESW Loop is scheduled for this shift. Unit 2 start-up is in progress, -1 hour from synchronizing to the grid.
The first event will be a control rod will drift in to position 38. The crew will insert the rod to position 00.
Then a failure of the 1A ESW Pump when started for the "A" ESW Loop Flow Surveillance. The crew will address Technical Specifications and declare the pump inoperable as well as terminate the ESW Surveillance. A loss of ESS Bus I A will occur as a result of breaker problems with the ESW Pump. The crew will respond to the loss of the bus per Off-Normal procedures and rack-out the failed ESW pump breaker; (the bus will not be recovered for the duration of the scenario). Other actions required by the crew will include restoring CRD and resetting the RPS half-scram.
Shortly after responding to the ESS Bus fault, an unisolable break will occur on the RWCU suction piping located in Secondary Containment. The break will cause one area of SC to approach maximum safe temperature, requiring the crew to manually scram the reactor. Upon initiating the manual scram FWLC will fail, causing RPV water level to drop. When the Main Turbine trips, the Aux Buses will fail to transfer and cannot be manually transferred resulting in a loss of Condensate/Feedwater. Main Turbine BPVs will fail shut, requiring pressure control with SRVs. RClC will trip when initiated either automatically or manually, and will be unavailable for the rest of the transient. The only high pressure sources remaining, SLC and CRD, will not be able to keep up with the rate of inventory loss from the RWCU system break and from actuating SRVs for pressure control. When RPV level can no longer be maintained above TAF, the crew will perform Rapid Depressurization and restore RPV level with low pressure systems.
When the reactor has been rapidly depressurized, RPV level has been restored to +13" to 54" and actions are in progress to initiate Suppression Pool Cooling, the scenario will be terminated.
Form STCP-QA-612A Rev. 0, (04/98)
Page 3 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 4 Scenario PCOl7-I 03 Rev. 0, 5/1/03 Form STCP-QA-612A Rev. 0. (04/98)
Page 4 of 23 2003 NRC Exam Rev. 1 THIS PAGE IS INTENTIONALLY LEFT BLANK File No. R11-3
Page 5 Scenario PCOl7-I 03 Rev. 0, 5/1/03 SCENARIO OBJECTIVES The SRO will:
- 1. Inform other shift members and plant management of changes in-plant status, potential plant problems or limitations.
- 2. Implement Loss of 4KV Bus (04.ON.011).
- 3. Implement Loss of CRD System Flow (55.0N.014).
- 4. Implement Scram (00.ON.018).
- 5. Implement RPV control (00.E0.026).
- 6. Implement Primary Containment Control (00.E0.027).
- 7. Implement Secondary Containment Control (00.E0.028).
- 8. Implement Rapid Depressurization (00.E0.030).
- 9. Ensure that required actions per Technical Specificationsflechnical Requirements are met when a LCO/TRO is entered (00.TS.003).
I O. Shutdown the reactor when it is determined reactor safety is in jeopardy, or when operating parameters exceed any RPS setpoint and scram does not occur.
The ROs will:
- 1. Perform LPCl injection through heat exchanger (49.0P.013).
- 2. Perform manual operation of Core Spray (51.OP.OOl).
- 3. Perform maximizing CRD System flow (55.0P.001).
- 4. Perform ESW system manual startup (54.0P.004).
- 6. Perform Scram (00.ON.018).
- 7. Perform RPV Control (00.E0.026).
- 8. Perform Primary Containment Control (00.E0.027).
- 9. Perform Secondary Containment Control (00.E0.028).
I O. Perform Rapid Depressurization (00.E0.030).
\\ - 5. Perform Loss of 4KV Bus (04.ON.011).
Form STCP-QA-6lZA Rev. 0. (04/98)
Page 5 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 6 Scenario PCOl7-I 03 Rev. 0, 5/1/03 THIS PAGE IS INTENTIONALLY LEFT BLANK 1
11 Form STCP-QAS12A Rev. 0. (04/98)
Page 6 of 23 2003 NRC Exam Rev. 1 FileNo. R11-3
Page 7 Scenario PCOI 7-1 03 Rev. 0, 5/1/03
-u CRITICAL TASKS 13 SECONDARY CONTAINMENT CONTROL Manually scram the reactor before any RWCU area temperature reaches Max Safe Temperature.
11 RAPID DEPRESSURIZATION Perform Rapid Depressurization when RPV level drops to -161.
Denotes Simulator Team Critical Task Form STCP-QA-612A Rev. 0. (04198)
Page 7 of 23 2003 NRC Exam Rev. 1 File No. R113
Page 8 Scenario PCOI 7-1 03 Rev. 0, 5/1/03
-\\_--
Form STCP-QA-612A Rev. 0, (04/98)
Page 8 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 9 Scenario PCOl7-I 03 Rev. 0, 5/1/03 SCENARIO REFERENCES
- 1.
SURVEILLANCE ACTIVITY-INOPERABLE ESW PUMP SO-054-001 AR-016-AlO QUARTERLY ESW FLOW VERIFICATION LOOP A, REV. 2 ESW PUMP A, B, C, D TRIP, REV. 35 TS 3.7.2 EMERGENCY SERVICE WATER SYSTEM, AMENDMENT 178 NDAP-QA-702ACTlON REQUEST AND CONDITION REPORT PROCESS, REV. 12 OP-AD-002 STANDARDS FOR SHIFT OPERATIONS, REV. 9
- 2.
LOSS OF ESS BUS 1A TS 3.8.7 TS 3.6.1.3 PCIVs, AMENDMENT 195 ON-104-201 LOSS OF ESS BUS IA, REV. 5 DISTRIBUTION SYSTEMS OPERATING, AMENDMENT 178
- 3.
LOSS OF CRD/LOSS OF RPS/RWCU Fool FAILURE ON-155-007 ON-158-001 LOSS OF CRD SYSTEM FLOW, REV. 16 LOSS OF RPS, REV. 6
- 4.
ROD DRIFT AR-104-HO5 ROD DRIFT, REV. 17 ON-155-001 CONTROL ROD PROBLEMS, REV. 18
- 5.
RWCU BREAK INSIDE SECONDARY CONTAINMENT AR-101-A02 AR-101-A03 AR-101-BO2 AR-101-BO2 EO-I 00-1 04 ON-100-101 SCRAM, REV. 9 RWCU LEAK DET IS0 LOGIC A HI TEMP, REV. 29 RWCU LEAK DET IS0 LOGIC B HI TEMP, REV. 29 RWCU LEAK DET IS0 LOGIC A HI LEAKAGE, REV. 29 RWCU LEAK DET IS0 LOGIC B HI LEAKAGE, REV. 29 SECONDARY CONTAINMENT CONTROL, REV. 1
- 6.
LOSS OF HIGH PRESSURE FEED EO-I 00-1 02 RPV CONTROL, REV. 1
- 7.
LOSS OF ADEQUATE CORE COOLING EO-I 00-1 12 RAPID DEPRESSURIZATION, REV. 1
- 8.
PRIMARY CONTAINMENT CONTROL EO-I 00-1 03 OP-149-005 PRIMARY CONTAINMENT CONTROL, REV. 2 RHR SUPPRESSION POOL COOLING, REV. 20
- 9.
OTHER BWROG SIMULATOR SCENARIO DEVELOPMENT GUIDELINE, TEMPLATES SC-1 AND RPV-1 Form STCP-QAB12A Rev. 0. (04/98)
Page 9 of 23 2003 NRC Exam Rev. 1 File No. RII-3
Page 10 Scenario PCOl7-I 03 Rev. 0, 5/1/03 Form STCP-QA-6lZA Rev. 0. (04/98)
Page 10 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 11 Scenario PCOl7-I 03 Rev. 0, 5/1/03 MALFS 12 :I2 REMFS OVRDS TRIGS 8
2:2 5
- 1. Set-up the simulator for the scenario by performing the following:
- a.
- b.
Initialize the simulator to IC-I8 (100% Power, EOL).
Close and status control pink tag the HPCl F002 and F003 valves, place the HPCl controller in MAN set at 0%. Also, depressurize the steam supply header by opening the F054, steam trap bypass; then reclose the valve.
- 2. Take a snapshot to a saved IC at 30% Power
- 3. Initialize the simulator to IC-123.
- 4. Type restorepref YPP.PCOl7-I 03; verify the following pre-inserts and Program Button assignments.
Verify the Environment Window:
TRG E l BAAA26409 EVENT TRIGGER: MODE SWITCH TO SHUTDOWN TRG E l = IMF RN145011 FWLC MASTER CTLR FAILS LOW WHEN E l TRUE TRG E l = IMF TC193001 MAIN TURBINE TRIP WHEN E l TRUE TRG E2 GAAA00214 EVENT TRIGGER: RClC TURBINE SPEED Xi00 RPM TRG E2 = IMF RC150011 RClC TURBINE TRIP WHEN E2 TRUE TRG E3 CAAA00706 EVENT TRIGGER: "A" ESW PUMP START SWITCH DEPRESSED TRG E3 = IMF PM03:OP504A "A" ESW PUMP TRIP WHEN E3 TRUE TRG E3 = IMF DS104001A (NONE I O 0) ESS 1A LOCKOUT WHEN E3 TRUE, 10 SEC. TD bat HPCIOOS SIMULATES HPCl 00s bat YPB.EVAL505A REMOVES MECHANICAL VACUUM PUMP FOR MAINTENANCE IMF CN03:LICC32R600 0 FWLC MASTER CONTROLLER FAILURE IN MAN IMF TC193025 ALL TURBINE BPVs FAIL CLOSED IMF MV09:HV144FOOI 98 RWCU INLET IB IS0 VALVE BINDING IMF MV09:HVl44F004 98 RWCU INLET OB IS0 VALVE BINDING u
IMF BRO5~lAl0104 TIE BUS TO 11A BKR FAILS AS-IS IMF BR05:lAl0204 TIE BUS TO 11 B BKR FAILS AS-IS IMF MV07:HVl44Fl00 100 RWCU FIOO VLV FAILED-OPEN IMF MV07:HVl44Fl06 100 RWCU F106 VLV FAILED-OPEN IMF MV07:HV144F102 IO0 RWCU F102 VLV FAILED-OPEN
[P-I] MRF PC125001 OPEN IA - CIG 90# HEADER CROSS-TIE VLVS OPEN
[P-2] IMF RD1550043823 (NONE 0 20) 5 ROD 3823 DRIFT TO POS. 38
[P3] MRF RM179024
[P4] MRF RM179026 A MSL RAD MON RESET C MSL RAD MON RESET
[P-5] MRF PM140P504A OUT A ESW PUMP BKR 1A20108 RACKED-OUT
[P-61 IMF CUI61007 I00 4:OO RWCU SUCTION PIPING BREAK OUTSIDE CTMT
[P-71 IMF TR02:RITl3708 48 5:OO 1.997 RWCU PUMP ACCESS ARM INCREASES Form STCP-QA-612A Rev. 0. (04/98)
Page 11 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 12 Scenario PCOl7-I 03 Rev. 0, 5/1/03 Continued on next page:
F o
~
STCP-QA-61%
Rev. 0. (04/98)
Page 12 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 13 Scenario PCOl7-I 03 Rev. 0, 5/1/03 L.
- 5. Prepare a turnover sheet indicating:
- a.
HPCl is out of service for repairs to oil pump breaker and lube oil changeout. The system will not be returned to service this shift.
- b.
Mechanical Vacuum Pump is out of service for a seal replacement. The system will not be returned to service this shift.
- c.
Perform SO-054-AO3, QUARTERLY ESW FLOW VERIFICATION LOOP A. Maintenance is standing by for vibration data.
- d.
Unit 2 start-up in progress, -1 hour from synchronizing to the grid.
- 6. Prepare an LCO Sheet: HPCl has been out of service for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to repair a governor control-oil leak.
- 7. Copy the procedure SO-054-A03, QUARTERLY ESW FLOW VERIFICATION LOOP A and prepare a surveillance coversheet.
- 8. Make a copy of shift assignments.
- 9. Place the Simulator in RUN.
Form STCP-QA-612A Rev. 0. (04/98)
Page 13 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 14 Scenario PCOI 7-1 03 Rev. 0, 5/1/03 EVENT SCENARIO EVENT DESCRIPTION FORM TIME DESCRIPTION 2
1 1
I SURVEILLANCE ACTIVITY ROD DRIFT 4
3 1
LOSS OF 1A ESS BUS / LOSS OF CRD / LOSS OF RPS 1 INOPERABLE ESW PUMP 6
RWCU BREAK INSIDE SECONDARY CONTAINMENT 5
I I RWCU Fool FAILURE 7
~
LOSS OF HIGH PRESSURE FEED / LOSS OF ADEQUATE CORE COOLING TERMINATION CUE Form STCP-CIA-61%
Rev. 0, (04/98)
Page 14 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 15 Scenario PCOl7-I 03 Rev. 0, 5/1/03 POSITION SCENARIO EVENT FORM v
Event No:
192,334, 5 Brief
Description:
Surveillance Activity I Rod Drift In INOP ESW Pump I Loss of 1A ESS Bus I Loss of CRD Loss of RPS I RWCU Fool Failure TIME STUDENT ACTIVITIES
\\---
PCOM Reports rod drift alarm.
PCOP I
I Commences SO-054-AO3, QUARTERLY ESW FLOW VERIFICATION LOOP A.
us Directs performance of ON-1 55-001, CONTROL ROD PROBLEMS.
PCOM Depress Display Rods Drifting button for Full Core Display.
Determines rod 38-23 is drifting.
Depress Display Scram Valves Open button for Full Core Display.
Determines scram valves are not open.
Selects rod 38-23 on RMCS rod select matrix.
Reports rod 38-23 position.
Inserts rod 38-23 to position 00.
us I Contacts Reactor Engineering.
PCOP us Continues SO-054-A03, QUARTERLY ESW FLOW VERIFICATION LOOP A.
Directs performance of ON-104-201, LOSS OF ESS BUS 1A.
I Starts A ESW pump, responds to AR-Ol6-AlO ESW PUMPS A,B,C,D TRIP annunciator.
Directs NPO to investigate A ESW Pump and breaker.
us 1 Directs termination of SO-054-AO3.
Contacts Work Week Manager about A ESW Pump trip.
~~~
~
Checks Technical Specifications, declares 7 day LCO IAW T.S. 3.7.2 C-1 for loss of A ESW pump.
PCOP I
Recognizes/reports loss of 1A ESS Bus.
I I
I Reports half-scram, loss of CRD, failure of RWCU Fool valve.
Form STCP-QAS12A Rev. 0. (04/98)
Page 15 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 16 Scenario PCOl7-I 03 Rev. 0, 5/1/03 x
Directs performance of ON-1 58-001, LOSS OF RPS.
I Directs performance of ON-155-007, LOSS OF CRD SYSTEM FLOW.
II I
I Directs performance of ON-117-001, LOSS OF INSTRUMENT BUS.
Refers to T.S. 3.8.7 A-1, declares 8-hour LCO for loss of ESS Bus IA. May also refer to T.S. 3.6.1.3 for containment isolation valve (Fool) failure.
- Denotes Critical Task NOTES:
Form STCP-QA-61PA Rev. 0, (04/98)
Page 16 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 17 Scenario PCOl7-I 03 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:
1,2,3,4,5 Brief
Description:
Surveillance Activity / Rod Drift In INOP ESW Pump / Loss of I A ESS Bus / Loss of CRD Loss of RPS / RWCU F001Failure INSTRUCTOR ACTIVITY:
- 1. As soon as ESW surveillance has begun and BEFORE crew starts "A" ESW pump insert control rod 38-23 drift in, Depress P-2:
[P-21 IMF RD1550043823 (NONE 0 20) 5 ROD 38-23 DRIFT IN TO POS 38 When the crew starts "A" ESW pump for S0-054-AO3, verify the Event Triggers activate to cause:
- 2. An instantaneous overcurrent trip of "A" ESW pump, AND 10 sec. later
- 3. A lockout-trip of 1A ESS Bus.
ROLE PLAY:
- 1. If spray pond level is requested, report level as 678' 6.
- 2. When directed as AS0 to investigate "A" ESW Pump, wait -1 min. and report that the pump is not running; it otherwise appears to be normal.
-\\---
- 3. When directed as NPO to investigate "A" ESW Pump breaker I N 0 1 08, wait -2 mins. and report that the breaker has a 50/51 device flag (instantaneous overcurrent). You also smell an burnt odor in the vicinity of the breaker.
- 4. As NPO dispatched to investigate 1A ESS Bus, report that both the Primary and Backup Lockout Relays (86A-201 and 86A1-201), are tripped. If asked to reset the lockouts, report that they will not reset.
- 5. As FIN Team dispatched to investigate "A" ESW Pump and 1A ESS Bus, wait -3 mins. and report that breaker 1A20108 for the "A" ESW Pump has failed, which was the cause for the ESS Bus I A Lockout trip. The ESS Bus will require extensive investigation and testing prior to attempting re-energization. Also, request ESW PUMP 1 A 4.16kv breaker racked out.
Form STCP-QA-612A Rev. 0, (04/98)
Page 17 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 18 Scenario PCOI 7-1 03 Rev. 0, 5/1/03 POSITION us PCOP SCENARIO EVENT FORM TIME Event No:
1,2,3,4,5 Brief
Description:
Surveillance Activity / INOP ESW Pump / Loss of 1A ESS Bus / Loss of CRD Loss of RPS / RWCU FOOlFailure I Rod Drift In I
- Denotes Critical Task STUDENT ACTIVITIES Directs cross-tying Instrument Air and the CIG 90# Header.
Evaluator Note:
STAs would normally be available to support the monitoring functions for the ESW pumps
~
~
~~
~
~~
~
~
~~
Dispatches NPO to cross-tie IA and the CIG 90# Header.
Starts 2 ESW Pumps to support auto start of A Diesel Generator.
Starts " 6 CRD pump, restores CRD system IAW ON-1 55-007, LOSS OF CRD SYSTEM FLOW.
Transfers RPS "A" to ALT IAW ON-I 58-001.
NOTES:
Form STCP-QA-61ZA Rev. 0. (04198)
Page 18 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 19 Scenario PCOl7-I 03 Rev. 0, 5/1/03
-v-INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
1.2.3.4. 5 I
Brief
Description:
Surveillance Activity / INOP ESW Pump I Loss of 1A ESS Bus I Loss of CRD Loss of RPS / RWCU FOOI Failure I INSTRUCTOR ACTIVITY:
[P-I] MRF PC125001 OPEN IA - CIG 90# HEADER CROSS-TIE VLVS OPEN ROLE PLAY:
As NPO directed to cross-tie IA and CIG, report valves 126167 and 126172 are open and the headers have been cross-tied.
- 3. When directed to reset MSL rad monitors, wait - 2 mins. and Depress P-3 and P-4:
[P-3] MRF RM179024 RESET A MSL RAD MON RESET
[P-41 MRF RM179026 RESET C MSL RAD MON RESET ROLE PLAY:
As NPO directed to reset MSL rad monitor A & C, call on the plant page and report MSL rad monitors A & C are reset.
NOTE:
- 1. If directed to reset other Area and Process Rad Monitors, type: RFI RM and reset Rad Monitors as directed.
Form STCP-QA-61%
Rev. 0, (04/98)
Page 19 Of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 20 Scenario PCOI 7-1 03 Rev. 0, 5/1/03 POSITION us PCOP PCOM SCENARIO EVENT FORM TIME STUDENT ACTIVITIES Directs reviewing ON-104-201, LOSS OF ESS BUS 1A for impact of loss of ESS bus Dispatches NPO to rack-out "A" ESW Pump breaker lA20108.
Reviews ATACHMENTS B, D, and E of ON-104-201 and checks equipment availability for crew during sustained power loss.
Recognizes/reports RWCU Fool valve indication lost.
Dispatches NPO to investigate RWCU FOOI valve and MOV breaker 1 B236053.
Event No:
I, 2,39495 Brief
Description:
Surveillance Activity I INOP ESW Pump I Loss of 1A ESS Bus / Loss of CRD
~
NOTES:
Loss of RPS / RWCU F001Failure I Rod Drift In I Contacts Work Week Manager concerning RWCU Fool Denotes Critical Task Form STCP-QA-612A Rev. 0. (04/98)
Page 20 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 21 Scenario PCOl7-I 03 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
1233,495 Brief
Description:
Surveillance Activity / INOP ESW Pump I Loss of 1A ESS Bus I Loss of CRD Loss of RPS / RWCU F001Failure I Rod Drift In INSTRUCTOR ACTIVITY:
When directed to rack-out breaker 1A20108, wait -2 mins. and Depress P-5:
EP-51 MRF PM140P504A OUT A ESW PUMP BKR 1A20108 RACKED-OUT ROLE PLAY:
- 1. As NPO directed to rack-out breaker I N 0 1 08, report that the breaker is racked-out.
.\\I--.
Form STCP-QA-61ZA Rev. 0, (04/98)
Page 21 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 22 Scenario PCOl7-I 03 Rev. 0, 5/1/03 POSITION SCENARIO EVENT FORM TIME STUDENT ACTIVITIES Event No:
6 Brief
Description:
RWCU Break Inside Sec Containment us PCOM
- US Enters EO-1 00-1 04, SECONDARY CONTAINMENT CONTROL.
Directs starting of ESW, and all Room Coolers.
Directs commencing reactor shutdown due to area temps. > max normal.
NOTE 1 Reports RWCU has failed to isolate; reports loss of indication on RWCU F004 valve.
Directs scram-imminent actions, enters 0-700-702 RPV CONTROL and directs manual scram before any RWCU temperature reaches max safe.
PCOM I
I Recognizes/reports indications of RWCU system leak.
I I Responds to AR-IOl-A02/A03, RWCU LEAK DET IS0 LOGIC N B HI TEMP.
I I Responds to AR-101-B02/B03, RWCU LEAK DET IS0 LOGIC N B HI LEAKAGE.
Reports RWCU FOO4 valve is isolating.
Evacuates area and notifies Health Physics.
PCOM I
I Runs-back Recirc flow to 65 Mlbs/hr.
I Starts MSOP, TGOP.
1 Manually scrams reactor before any RWCU temperature reaches max safe.
pcop I Attempts to transfer house loads to Aux Buses; reports failure of Tie Bus to 11A and 11 B breakers.
-k Denotes Critical Task 1
NOTES:
I NOTE 1 : This event is classified as a SITE AREA EMERGENCY based on RWCU leak IAW EP-PS-100-6, EAL 18.3.
Form STCP-QA-612A Rev. 0, (04198)
Page 22 of 23 2003 NRC Exam Rev. 1 File No. R113
Page 23 Scenario PCOl7-I 03 Rev. 0, 5/1/03 L-INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
6 Brief
Description:
RWCU Break Inside Sec Containment INSTRUCTOR ACTIVITY:
- 1. -1 min. after reporting breaker 1A201108 has been racked out, insert an unisolable RWCU leak, Depress P-6 and P-7:
[P-61 IMF CUI61007 100 4:OO RWCU SUCTION PIPING BREAK OUTSIDE CTMT
[P-71 IMF TR02:RIT13708 48 5:OO 1.997 RAMPS UP RWCU PUMP AREA RADS
- 2. When Mode Switch is placed in SHUTDOWN, verify event triggers activate to cause the following:
0 FWLC Master Controller output fails low, resulting in RPV level shrinking to -40 to -50 The Main Turbine trips, causing the Aux Buses to subsequently de-energize.
ROLE PLAY:
- 1. As NPO directed to investigate RWCU FOOI, wait -2 mins. and report that breaker 18236053 is tripped-open. If asked to resetheclose the breaker, report that it immediately tripped-open again.
- 2. As NPO directed to investigate RWCU F004, wait -2 mins. and report that breaker 1 D274042 is tripped-open. If asked to resetheclose the breaker, report that it immediately tripped-open again.
- 3. As FIN Team dispatched to investigate the RWCU FOOl/F004 problems, wait -3 mins. and report that the breakers functioned properly; the problem may be with the associated valves motor-operator.
- 4.
If contacted as Security to report status of blowout panels; inform the crew that steam is visible above the Unit 1 CST area.
Form STCP-QA-6lZA Rev. 0, (04/98)
Page 23 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 24 Scenario PCOl7-I 03 Rev. 0. 5/1/03 POSITION SCENARIO EVENT FORM TIME STUDENT ACTlVlTl ES Event No:
7 Brief
Description:
Loss of High Pressure Feed / Loss of Adequate Core Cooling us Dispatches NPO to investigate RClC trip.
Directs RPV level maintained +I 3" to -161" with CRD/SLC.
Contacts Work Week Manager concerning RCIC.
PCOM I
PCOP us I Reports failure of FWLC Master Controller output.
Maximizes CRD and initiates SLC if directed.
Directs RHR and CS systems started and lined-up for injection.
[ Reports loss of FeedwaterlCondensate Pumps when Turbine trips.
PCOM/P us Initiates both loops of CS and RHR.
I Directs RPV water level restored to +I 3" to +54" with RCIC.
I Contacts Work Week Manager concerning Aux Buses failing to transfer.
PCOP I
I Reports RClC tripped when started.
- Denotes Critical Task NOTES:
F O n STCP-QA-612A Rev. 0. (0498)
Page 24 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 25 Scenario PCOl7-I 03 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTOR'S PERSONAL NOTES Event No:
7 Brief
Description:
Loss of High Pressure Feed I Loss of Adequate Core Cooling INSTRUCTOR ACTIVITY:
None.
ROLE PLAY:
- 1. As FIN Team dispatched to investigate the Aux Buses, wait -3 mins. and report that the Transfer logic has failed. It will take time to troubleshoot the exact cause for the failure. You will call back when you have a better idea of repair strategy and time estimates.
- 2. As NPO directed to investigate the RClC trip, wait -2 mins. and report that the RClC overspeed trip mechanism is tripped and the linkage is bent. You cannot reset the overspeed trip.
i--
Form STCP-QA-612A Rev. 0, (04198)
Page 25 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 26 Scenario PCOl7-I 03 Rev. 0, 5/1/03 SCENARIO EVENT FORM
-L--
Event No:
7 Brief
Description:
Loss of High Pressure Feed I Loss of Adequate Core Cooling POSITION I TIME PCOM/P I
- us I
- PCOIwP I
PCOM/P I
=I= PCOM/P STUDENT ACTIVITIES Informs US that RPV level has reached -161".
Performs Rapid Depressurization when RPV level drops to -161".
Enters EO-100-1 12, RAPID DEPRESSURIZA TION.
Verifies Suppression Pool level >5:
Directs Rapid Depressurization by opening 6 ADS valves.
Initiates Rapid Depressurization by opening 6 ADS valves.
Directs restoring RPV level to +13" to +W with RHR and CS.
Restores RPV level to +13" to +54" with RHR and CS.
Enters EO-1 00-1 03 due to high Suppression Pool temperature.
Directs maximizing Suppression Pool Cooling.
Places both loops of RHR in Suppression Pool Cooling IAW OP-149-005, RHR SUPPRESSION POOL COOLING.
TERMINATION CUE:
Rapid Depressurization has been completed, RPV level has been restored to +I 3" to
+54", and actions are in progress to initiate Suppression Pool Cooling.
- Denotes Critical Task Form STCP-QA-612A Rev. 0, (04/98)
Page 26 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 27 Scenario PCOI 7-1 03 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
7 Brief
Description:
Loss of High Pressure Feed I Loss of Adequate Core Cooling INSTRUCTOR ACTIVITY:
None.
ROLE PLAY:
As necessary.
TERMINATION CUE:
Rapid Depressurization has been completed, RPV level has been restored to +13 to +54, and actions are in progress to initiate Suppression Pool Cooling.
Form STCP-QA-612A Rev. 0. (04198)
Page 27 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Appendix D Scenario Outline Form ES-D-1 Event No.
1 2
11 Facility: SSES Scenario No.: PCOI 7-1 04 Op-Test No.:
Malf. No.
Event Event Type*
Description NIA N
Place C Reactor Feed Pump in service.
N/A R
Raise reactor power (power increase enough to cause stuck rod indications for event 3 below)
IMF RD1550063407 12 0 12 C
Stuck Rod (34-07)
I 3
bat FWB.PCO17-I 04A Examiners:
Operators:
I Initial Conditions: IC-16 Unit 1 50% Power EOL. Unit 2 100% power EOL MRF DC102140 OPEN bat FWB.CPTRIP bat RRB.PCOl7-104B 5
6 Turnover B2 Start-up Sequence was suspended at step 539. Power ascension was suspended while BOP equipment is placed into service. Place C RFP in service IAW GO-100-102 step 6.71.3 then continue rod withdrawal to 75% reactor power.
C C
M
~
IMF RLOl:E411 K2 IMF RH149004A (4B) 20 8
~~
C II I
I 4:00 I
C
- (N)ormal, (R)eactivity, (I)nstrument, (C)oml Loss of extraction steam to 3B feedwater heater (HTR 3B LEVEL CONTROL FAILURE)
Dual Reactor Recirc Pump Trip Loss of all condensate pumps Instrument line Ref Leg Break & Bottom Head Leak inside the Drywell HPCl Auto Start Failure RHR Suction line leak
- onent, (M)ajor NUREG 1021 Draft Rev. 9 2003 NRC Exam Rev. 1 Susquehanna Facsimile
PP&L-SUSQUEHANNA TRAINING CENTER Prepared By:
Instructor Reviewed By:
Nuclear Operations Training Supervisor SIMULATOR SCENARIO Date Date I
Scenario
Title:
NRC INITIAL LICENSE OPERATOR EXAMINATION Approved By:
Supervising ManagedShift Supervisor Scenario Duration: 90 Minutes Date
~
~~
Scenario Number: PCOl7-104 RevisionlDate:
Rev 0; 5/1/03 Course:
PC017, SENIOR REACTOR OPERATOR LICENSE PC018, REACTOR OPERATOR LICENSE Operational Activities:
1 Place C RFP In Service 6 Loss of Condensate Pumps 2 Raise Power by Rod Withdrawal 7 lnstr Line Break Inside DW 3 Stuck Control Rod 8 HPCl Auto Start Failure 4 Loss of Extraction Steam 3B 9 RHR Suction Line Leak 5 Dual RRP Trip Form STCP-QA-6IZA Rev. 0. (04198)
Page 1 of 15 2003 NRC Exam Rev. 1 File No. R11-3
Page 2 Scenario PCOl7-104 Rev. 0. 5/1/03 Form STCP-QA-61%
Rev. 0, (04/98)
Page 2 of 23 2003 NRC Exam Rev. 1 THIS PAGE IS INTENTIONALLY LEFT BLANK File No. R11-3
Page 3 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 SCENARIO
SUMMARY
Unit 1 is 50% power EOL, Unit 2 is 100% power EOL. Power ascension is in progress on Unit 1.
The crew will place RFP C in service then continue raising power by withdrawing control rods. After several rods are withdrawn control rod 34-07 will fail to move. An Off-Normal procedure will direct the crew to raise drive water d/p at which time rod motion will continue.
An instrument failure will cause a level control problem in feedwater heater 3B resulting in an automatic extraction steam isolation to heater 36. An Off-Normal procedure will require the crew to manually isolate extraction steam to feedwater heaters 4B and 5B. Technical Specification for MCPR is impacted by the loss of extraction steam. After addressing the actions for loss of extraction steam a dual Recirc MG A & 6 drive motor breaker trip occurs resulting from a 125 VDC breaker trip. Immediate Operator action is to place the Mode Switch to Shutdown, no other equipment is affected by the 125 VDC breaker trip.
When the reactor mode switch is placed in shutdown a loss of all condensate pumps occurs resulting in a loss of feedwater injection. The crew will respond by establishing RPV level control with HPCl and RCIC.
An auto start failure in the HPCI system will require a component by component startup to allow injection.
Shortly after the reactor scram an instrument line break inside the drywell will result in a loss of numerous reactor water level and pressure instruments in Division 1. Drywell pressure and temperatures will increase and require Emergency Operating Procedure entry which will direct initiation of Suppression Chamber Spray initially. The RHR loop chosen to initiate containment spray will experience a suction line leak requiring Emergency Operating Procedure entry which will direct shutdown and isolation of the RHR system discharging into the Secondary Containment. The crew will successfully isolate the RHR leakage and perform containment sprays with the other loop of RHR. This delay in starting sprays will result in Suppression Chamber pressure exceeding 13 psig, requiring the crew to initiate drywell sprays.
Containment parameters will improve following spray initiation.
L-After Drywell Sprays have been initiated and RPV water level is maintained + I 3 to +54 the scenario will be terminated.
Form STCP-QA-612A Rev. 0, (04/98)
Page 3 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Form STCP-QA-6lZA Rev. 0. (04/98)
Page 4 of 23 2003 NRC Exam Rev. 1 Page 4 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 File No. R11-3
Page 5 Scenario PCOl7-I 04 Rev. 0, 5/1/03 SCENARIO OBJECTIVES The SRO will:
- 1. Ensure initiation of ESF equipment if automatic operation was not properly initiated.
- 2. Inform other shift members and plant management of changes in-plant status, potential plant problems or limitations.
- 3. Implement Appropriate Portions of Condition Report (00.AD.267)
- 4. Implement Appropriate Portions of Plant Startup, Heatup and Power Operation (OO.GO.013)
- 5. Respond to a Stuck control Rod (55.0N.016)
- 6. Implement Scram (00.ON.018).
- 7. Implement RPV control (00.E0.026).
- 8. Implement Primary Containment Control (00.E0.027).
- 9. Implement Secondary Containment Control (00.E0.028).
IO. Implement Loss of Feedwater Heating (Extraction Steam) (47.0N.005) 1 1. Implement Loss of Recirc Flow (64.0N.010)
- 12. Ensure that required actions per Technical Specifications/Technical Requirements are met when a
- 13. Shutdown the reactor when it is determined reactor safety is in jeopardy, or when operating parameters LCO/TRO is entered (00.TS.003).
exceed any RPS setpoint and scram does not occur.
The ROs will:
- 1. Perform Feeding With Additional Reactor Feed Pump (45.0P.010)
- 2. Implement HWC Operation When Placing a Third Reactor Feed Pump In Service (45.0P.025)
- 3. Implement Appropriate Portions of Plant Startup, Heatup and Power Operation (00.G0.013)
- 4. Respond to a Stuck control Rod (55.0N.016)
- 5. Implement Loss of Feedwater Heating (Extraction Steam) (47.0N.005)
- 6. Implement Loss of Recirc Flow (64.0N.010)
- 7. Perform Scram (00.ON.018).
- 8. Perform RPV Control (00.E0.026).
- 9. Perform HPCl Component by Component Start-up (52.0P.002)
I O. Perform Primary Containment Control (00.E0.027).
- 11. Perform Secondary Containment Control (00.EO.028).
- 12. Perform RHR Containment Spray (49.0P.005)
- 13. Perform Manual Component by Component Startup of RClC (50.0P.015)
Form STCP-QA-612A Rev. 0. (04/98)
Page 5 of 23 2003 NRC Exam Rev. 1 File No. Rl l -3
Page 6 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 THIS PAGE IS INTENTIONALLY LEFT BLANK FOm STCP-QA-6lZA R w. 0, (04/98)
Page 6 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 7 Scenario PCOl7-I 04 Rev. 0, 5/1/03 L--
CRITICAL TASKS 21 LOSS OF RECIRC FLOW Manually scram the reactor due to a dual Recirc Pump trip.
@{
PP P
+
b#
0 06 PRIMARY CONTAINMENT CONTROL Isolates RHR System discharging into the Secondary Containment.
- 0.
Sprays the Drywell when Suppression Chamber pressure exceeds 13 psig. ytT e (J Limits Drywell Spray flow to between 1000 and 2800 gpm for the first 30 seconds.
3 Denotes Simulator Team Critical Task L-Form STCP-QA-6lZA Rev. 0. (04/98)
Page 7 of 23 2003 NRC Exam Rev. 1 File No. Rl l-3
Page 8 Scenario PCOl7-I 04 Rev. 0, 5/1/03 Form STCP-QA-612A Rev. 0. (04/98)
Page 8 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 9 Scenario PCOl7-I 04 Rev. 0, 5/1/03 L-.
SCENARIO REFERENCES
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
PLACE C RFP IN SERVICE GO-100-002 OP-145-001 OP-145-002 PLANT STARTUP, HEATUP AND POWER OPERATION, REV. 40 RFP AND RFP LUBE OIL SYSTEM, REV. 32 HYDROGEN WATER CHEMISTRY, REV. 4 INCREASE POWER BY ROD WITHDRAWAL CORE REACTIVITY CONTROL BOOK, REV. 1 OP-AD-338 OP-AD-001 COMMUNICATION REQUIREMENTS FOR REACTIVITY MANIPULATIONS, REV. 1 OPERATIONS STANDARDS FOR SYSTEM AND EQUIPMENT OPERATION, REV.
5 CONTROL ROD COUPLING / FULL IN INDICATOR CHECKS, REV. 8 SO-156-007 STUCK ROD ON-I 55-001 CONTROL ROD PROBLEMS, REV. 18 NDAP-QA-702 ACTION REQUEST AND CONDITION REPORT PROCESS, REV. 12 LOSS OF EXTRACTION STEAM TO 38 HEATER ON-147-001 AR-120-H07 AR-120-DO7 LOSS OF FEEDWATER HEATING EXTRACTION STEAM, REV. 13 FW LOOP B PANEL IC102 TROUBLE, REV. 12 FW HTR STRING B DUMP VLV OPEN, REV. 1 TS 3.2.2 MCPR, AMENDMENT 178 DUAL REACTOR RECIRC PUMP TRIP AR-102-BO2 AR-102-BO5 OP-AD-055 RECIRC MG A DRIVE MTR TRIP, REV. 21 RECIRC MG B DRIVE MTR TRIP, REV. 21 OPERATIONS PROCEDURE PROGRAM, REV. 0 ON-164-002 LOSS OF REACTOR RECIRCULATION FLOW, Rev. 20 ON-I 00-1 01 EO-100-102 RPV CONTROL, REV. 1 SCRAM, REV. 9 LOSS OF ALL CONDENSATE PUMPS INSTRUMENT LINE BREAK INSIDE DRYWELL EO-I 00-1 03 OP-149-004 PRIMARY CONTAINMENT CONTROL, REV. 2 RHR CONTAINMENT SPRAY, REV. 17 HPCl AUTO START FAILURE OP-152-001 HPCl SYSTEM, REV. 28 RHR SUCTION LINE BREAK EO-I 00-104 SECONDARY CONTAINMENT CONTROL, REV. 1 Form STCP-QA-612.4 Rev. 0, (04198)
Page 9 of 23 2003 NRC Exam Rev. 1 File No. R113
Page 10 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 Form STCP-QAB12A Rev. 0. (04/98)
Page 10 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 11 Scenario PCOl7-I 04 Rev. 0, 5/1/03 MALFS 2:2 L-SC E N ARI 0 SPECIAL INSTRUCTIONS REMFS OVRDS TRIGS 0
2:2 1
- 1. Set-up the simulator for the scenario by performing the following:
- a. Initialize the simulator to IC-16. Unit 1 at 50% Power EOL. Unit 2 is 100% power EOL.
- b. Place Condensate Demin E & F in service.
- c. Start Condensate Pump D.
- d. Place Circ Water Pump D in service.
- 2. Take a snapshot to a saved IC.
- 3. Initialize to IC-124.
- 4. Type restorepref YPP.PCO17-I 04; verify the following pre-inserts and Program Button assignments.
Verify the Environment Window:
IMF RD1550063407 12 0 12 ROD 3407 STUCK AT POSITION 12 IMF RLOI:E411K2 HPCl AUTO START FAILURE TRG E l BAAA26409 MODE SWITCH TO S/D TRG El = bat FWB.CPTRIP TRIP ALL CONDENSATE PUMPS HTR 3B LEVEL CONTROL FAILURE DUAL REACTOR RECIRC PUMP TRIP
\\
[P-I] DMF RD1550063407 DELETE STUCK ROD 34-07 u
[P-21 bat FWB.PCO17-I 04A
[P-4] bat RRB.PCO17-104B REF LEG BREAK & BOTTOM HEAD LEAK J
I
[P-5] IMF RHl49004A 20 4:OO RHR LOOP A SUCTION BREAK 1..
p
\\-
, ? :
c?
LJ r
b
[P-31 MRF DC102140 OPEN
[P-61 IMF RH149004B 20 4:OO RHR LOOP B SUCTION BREAK II I,
i c
$ / )7 L P t
- 5. Prepare a turnover sheet indicating:
- a. Unit 1 is at 50% power, Unit 2 is in MODE 1 at 100% power EOL.
- b. Using B2 Startup Sequence at step 539.
- c. Power ascension was suspended while BOP equipment is placed into service.
reactor power.
Continued on next page:
F o
~
STCP-(24-613 Rev. 0. (04/98)
Page 11 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 12 Scenario PCOl7-I 04 Rev. 0, 5/1/03
- 6. Ensure the B2 Startup Sequence CRC Book is placed in the simulator and remove the B2 Shutdown Sequence.
- 7. Prepare a marked up copy of page 23 from the Start-up Control Rod Sequence B2. Sign off all steps up to step 539.
- 8. Make copies of pages 24 and 24A from the Start-up Control Rod Sequence B2 to use as page replacements following the scenario.
- 9. Copy GO-100-002 completed up to step 6.71. Signoff confirmation for the following steps; 6.71.I, 6.71 2, 6.71 5, and 6.71.6.
IO. Copy SO-I 56-007 signed off to support rod withdrawal starting at step 539. Prepare a surveillance coversheet.
- 11. Copy OP-145-001 signed of to step 2.5.5 to have C RFP warmed and on mini-flow
- 12. Make a copy of shift assignments.
- 13. Place the Simulator in RUN.
Form STCP-QA-612A Rev. 0, (04/98)
Page 12 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 13 Scenario PCOl7-I 04 Rev. 0, 5/1/03 SCENARIO EVENT DESCRIPTION FORM Initial Conditions: Initialize the simulator to IC-124. Ensure the Preference File is executed per the Special Instructions Sheet. Assian Shift positions. Direct the Crew to begin a five minute panel walk down.
TERMINATION CUE Form STCP-QA-612A Rev. 0, (04/98)
Page 13 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 14 Scenario PCOl7-I 04 Rev. 0, 5/1/03 POSITION TIME STUDENT ACTIVITIES I Directs implementation of OP-145-001, RFP AND RFP LUBE OIL SYSTEM.
Establish RFP discharge pressure 50-1 00 psig below Reactor pressure.
Increases RFP speed using SIC-C32 1 R601C.
1 PCoM
~
Maintains RFP minimum flow on FI-10604C greater than minimum flow setpoint FI-1061 2C by manually throttling FIC-10604C.
ll Verifies RFP C discharge temperature is - equal to RFP A & B discharge temperature on TR-10608.
Direct Plant Operator to align Hydrogen Water Chemistry System for placing C RFP IAW OP-145-002, HYDROGEN WATER CHEMISTRY.
II I Raise RFP speed using SIC-C32-1 R601 C until injection flow just begins.
Slowly reduce RFP C minimum flow by depressing CLOSE button On FIC-10604C while observing:
0 0
0 CLOSE minimum flow valve.
RFP C minimum flow decreasing.
RFP C discharge flow increasing.
RFP A & B discharge flow decreasing to match RFP C flow increase.
Match RFP C output meter (horizontal) with the demand meter (vertical) by adjusting SIC-C32-1 R601 C.
II I
I Place RFP C SIC-C32-1 R601 C to AUTO.
Adjust RFP A & B flows using bias thumbwheel until discharge flows on 3 RFPs are -
equal.
Place FIC-10604C in AUTO when discharge flow is > 1.5 mlbm/hr.
Directs Plant Operator to close 1061 55, RFP C OB Seal Drain Ctl Vlv Bypass.
I Directs STA to select LEFM in PlCSY for Calc of Core Thermal Power.
Directs Plant Operator to establish automatic flow balancing for condensate filters.
-k Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0. (04198)
Page 14 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 15 Scenario PCOl7-I 04 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
1 Brief
Description:
PLACE C RFP IN SERVICE INSTRUCTOR ACTIVITY:
As necessary.
ROLE PLAY:
- 1.
- 2.
- 3.
- 4.
As Plant Operator sent to align HWC System for placing RFP C in service, wait - 5 mins. and report HWC System is aligned support placing RFP C is service. (OP-145-002, flow is reduced to -3 until RFP placed in service ten ramped back to -38 SCFH)
As Plant Operator sent to close 106155, wait 2 mins. and report 106155 is closed.
As STA directed to select LEFM in PlCSY for calculation of core thermal power acknowledge the direction and take no further action.
As Plant Operator directed to establish automatic flow balancing for the condensate filters acknowledge the direction and take no further action.
Form STCP-QA-612A Rev. 0. (04/98)
Page 15 of 23 2003 NRC Exam Rev. 1 File No. R l l - 3
Page 16 Scenario PCOl7-104 Rev. 0, 5/1/03 POSITION TIME us SCENARIO EVENT FORM STUDENT ACTIVITIES Conduct Reactivity Manipulation Briefing for the upcoming power increase.
Direct the power increase.
Direct implementation of Reactor Engineer Instruction in the CRC Book.
Event No:
293 Brief
Description:
INCREASE POWER I STUCK ROD Direct implementation of GO-I 00-002, PLANT STARTUP, HEATUP AND POWER OPERATION.
Increase reactor power as directed by the US and CRC Book.
PCOM I Plots power change on the power to flow map.
I Maintains load set -100 MWe above existing load.
Notifies GCC before the power increase begins.
PCOP Identifies control rod 34-07 failed to move after a withdraw command.
PCOM Directs implementation of ON-I 55-001, CONTROL ROD PROBLEMS.
us I
I Notifies Reactor Engineering.
~
~~
I Makes notifications IAW OP-AD-002, STANDARDS FOR SHIFT OPERATIONS.
Identifies a CR is required IAW NDAP-QA-0702, ACTION REQUEST AND CONDITION REPORT PROCESS.
- Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0. (04/98)
Page 16 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 17 Scenario PCOl7-I 04 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
233 Brief
Description:
INCREASE POWER I STUCK ROD INSTRUCTOR ACTIVITY:
NOTE: Stuck rod 34-07 is a pre-inserted malfunction.
As necessary.
ROLE PLAY:
As Reactor Engineer notified about stuck rod 34-07, acknowledge the condition and state no further notification is necessary if the rod moves during implementation of procedure actions.
Form STCP-QA-61 2A Rev. 0. (04198)
Page 17 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 18 Scenario PCOl7-I 04 Rev. 0, 5/1/03 SCENARIO EVENT FORM Event No:
2,3 Brief
Description:
INCREASE POWER I STUCK ROD Jc Denotes Critical Task STUDENT ACTIVITIES
~~
Confirms rod position using any 3 of the following:
0 0
FULL-IN/FULL-OUT DISPLAY pushbutton 0
Alarm logger System Event Display(SED)
CRT and SIP 4 ROD DISPLAY OD-7(RWM)
Depress withdraw rod pushbutton and simultaneously momentarily depress the continuous insert pushbutton. Release continuous insert pushbutton and check for single notch withdrawal.
Confirms rod position again using available rod position indications - determines no movement.
Attempt to move control rod as follows:
0 Completes rod data on Attachment A.
0 Increase drive water pressure in 50 psid increments to a max of 350 psid.
0 Withdraw rod one notch while observing drive water flow.
Records drive water pressure and flow required to move rod.
Return drive water pressure to -250 psid.
Continues power increase by rod withdrawal.
NOTES:
F o n STCP-QA-612A Rev. 0. (04/98)
Page 18 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 19 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
233 Brief
Description:
INCREASE POWER I STUCK ROD INSTRUCTOR ACTIVITY:
After the ON-I 55-001 actions are implemented to raise drive water d/p, permit continued rod movement, Depress P-I :
[P-I] DMF RD1550063407 DELETE STUCK ROD 34-07 ROLE PLAY:
As necessary.
Form STCP-QA-612A Rev. 0. (04/98)
Page 19 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 20 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 us PCOM SCENARIO EVENT FORM Directs implementation of ON-147-001, LOSS OF FEEDWATER HEATING EXTRACTION STEAM.
Plot position on power to flow map.
Event No:
4 Brief
Description:
LOSS OF EXTRACTION STEAM TO 38 HEATER PCOP POSITION Checks MSL and Offgas Pretreatment Log radiation monitors on 1 C600.
Notifies US MCPR LCO 3.2.2 is applicable. (2hr LCO, Decrease <25% pwr)
PCOP TIME STUDENT ACTIVITIES Reports HTR 38 LP EXTR IS0 HV-10240B is closing.
Dispatch a Plant Operator to 1 C102 to investigate heater problem.
Checks heater levels on 1C668 and determines FW HTR 103B and 104B have high level indication.
us I
I Refers to TS 3.2.2.
Notifies Reactor Engineering.
PCOP Notify PCOM to be aware of lower feedwater temperatures as valves are being closed.
I I CLOSES MSEP A DRN TO HTR 4B HV-102138.
CLOSES MSEP 8 DRN TO HTR 4B HV-10216B.
PCOM Monitors reactor power as feedwater heating is reduced.
- Denotes Critical Task NOTES:
Form STCP-QA-61ZA Rev. 0. (04/98)
Page 20 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 21 Scenario PCOI 7-1 04 Rev. 0, 5/1/03
-L:
INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
4
~
Brief
Description:
LOSS OF EXTRACTION STEAM TO 3B HEATER INSTRUCTOR ACTIVITY:
After actions for stuck rod 34-07 are complete and rod 34-07 is being moved to its bank position insert a loss of extraction steam to heater 3B, Depress P-2:
[P-21 bat FWB.PCO17-104A HTR 36 LEVEL CONTROL FAILURE NOTE: Heater 3B extraction steam isolates in -3.5 minutes.
Monitor LP1 C102 for heater alarms and indications.
ROLE PLAY:
- 1. As Plant Operator sent to IC102 wait - 1 min. and report you have:
HTR 38 & 48 HI LEVEL ALARMS HTR 4B DUMP VALVE NOT 100% CLOSED ALARM HTR 4B level is controlling on the dump valve.
.--*I
- 2. As Plant Operator sent to determine valve status at 1 C102 on heater string B, report the normal and emergency drain valves are closed on heater 3B, the normal drain outlet from heater 46 is closed, and the emergency dump valve on heater 4B is open.
\\--
Form STCP-QA-612A Rev. 0. (04/98)
Page 21 of 23 2003 NRC Exam Rev. 1 File No. Rll-3
Page 22 Scenario PCOl7-I 04 Rev. 0, 5/1/03 POSITION SCENARIO EVENT FORM TIME Event No:
495, 6 Brief
Description:
LOSS OF EXTRACTION STEAM TO 3B HEATER I DUAL RRP TRIP I LOSS OF CONDENSATE PUMPS STUDENT ACTIVITIES CLOSES HTR 4B LP EXTR IS0 HV-10241 B.
CLOSES HTR 5B HP EXTR IS0 HV-102428.
If feedwater heating is not restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, isolate feedwater string B.
Directs Plant Operator to check normal and emergency drain from heater 3B OPEN and drain inlet from heater 48 CLOSED.
PCOM I
Report Recirc MG A & B Drive Motor Trip.
kPCOM
- Place Reactor Mode Switch to SHUTDOWN due to a dual Recirc Pump Trip.
Performs actions of ON-I 00-1 01, SCRAM:
0 0
Reports all control rods are fully inserted
- us 1
Directs Reactor Mode Switch to Shutdown due to a dual Recirc Pump Trip.
Enters EO-1 00-1 02, RPV CONTROL Directs implementation of ON-100-1 01, SCRAM.
~
~~
~
Directs a panel walkdown for Isolations, ECCS Initiations, and D/G Starts.
Directs RPV level restored and maintained +13" to +54" with HPCl and RCIC.
Directs RPV pressure stabilized 4087 psig.
PCOM I
Reports loss of Condensate and Feedwater pumps.
PCOP I I Performs panel walkdown and reports status for Isolations, ECCS Initiations and D/G starts.
- Denotes Critical Task Form STCP-QA-612A Rev. 0. (04198)
Page 22 of 23 2003 NRC Exam Rev. 1 File No. R I 1-3
Page 23 Scenario PCOl7-I 04 Rev. 0, 5/1/03
\\-
INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
495, 6 Brief
Description:
LOSS OF EXTRACTION STEAM TO 3B HEATER I DUAL RRP TRIP I LOSS OF CONDENSATE PUMPS INSTRUCTOR ACTIVITY:
- 1. When actions are complete for loss of extraction steam, insert a dual Reactor Recirc pump trip, Depress P-3:
[P3] MRF DC102140 OPEN BREAKER ID61419 TRIP ROLE PLAY:
As Plant Operator sent to Recirc MG A & B drive motor breakers, wait -2 mins. and report breaker 1 AI 01 10 and 1 A I 021 0 are tripped and there are no flags for any protective relays.
- 2. When the Mode Switch is placed to Shutdown verify event trigger 1 activates a trip of all condensate pumps.
TRG E l = bat FWB.CPTRIP TRIP ALL CONDENSATE PUMPS
- 3. When EO-I02 is entered, insert an instrument line break inside drywell, Depress P-4:
[P-4] bat RRB.PCOl7-1048 REF LEG BREAK & BOTTOM HEAD DRAIN LEAK Form STCP-QA-613 Rev. 0. (04/98)
Page 23 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 24 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 POSITION SCENARIO EVENT FORM Event No:
6, 738 Brief
Description:
LOSS OF CONDENSATE PUMPS I INSTR LINE BREAK INSIDE DRYWELL HPCl AUTO START FAILURE TIME STUDENT ACTIVITIES PCOP PCOM/P us Contacts Work Week Manager concerning loss of all condensate Pumps.
Reports HPCl auto start failure.
Performs HPCl component by component startup IAW OP-I 52-001, HPCI SYSTEM.
Controls HPCl injection to restore and maintain RPV water level +13" to +54".
NOTE 1 Reports drywell pressure and temperature rising.
Reports loss of division 1 level and pressure indicators.
Verifies RPV level using redundant level indicators.
1 Contacts Work Week Manager concerning Recirc MG A & B drive motor breaker trips.
us Enters EO-I 00-1 03, PRIMARY CONTAINMENT CONTROL when drywell pressure exceeds 1.72 psig Re-enters EO-I 00-1 02 when drywell pressure exceeds 1.72 psig.
Directs suppression chamber sprays placed in service.
-k Denotes Critical Task II I
II NOTES:
I NOTE1 : This event is classified as an ALERT based on reactor coolant leakage rate greater than 50 gpm IAW EP-PS-100, EAL 12.2.
Form STCP-QA-61ZA Rev. 0. (04/98)
Page 24 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 25 Scenario PCOl7-I 04 Rev. 0, 5/1/03 L.
INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
Brief
Description:
6, 7, 8 LOSS OF CONDENSATE PUMPS I INSTR LINE BREAK INSIDE DRYWELL HPCl AUTO START FAILURE INSTRUCTOR ACTIVITY:
As necessary.
ROLE PLAY:
- 1. As FIN Team sent to investigate the Recirc MG A & B drive motor breaker trip, wait -10 mins. and report a trip signal from RPT breakers 3A (20501) and 3B (20601) is present. We will continue to investigate.
- 2. As FIN Team sent to investigate the Condensate pumps, wait -10 mins. and report a trip signal is present from the Plant Aux Load Shed circuit. Further trouble shooting is required, when anything new develops we will notify you in the control room, Form STCP-QA-61%
Rev. 0. (04198)
Page 25 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 26 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 POSITION TIME SCENARIO EVENT FORM STUDENT ACTIVITIES Event No:
799 Brief
Description:
INSTR LINE BREAK INSIDE DRYWELL I RHR SUCTION LINE BREAK
- PCOIWP L
Note 1 Isolates RHR system discharging into the Secondary Containment.
Stops RHR pump.
NOTES:
PCOM/P NOTE 1 : The RHR suction break will occur on which ever RHR loop is initially started for sprays.
Sprays the Suppression Chamber IAW OP-149-004, RHR CONTAINMENT SPRAY.
Places RHRSW in service IAW OP-I 16-001, RHRSW SYSTEM.
I Note 1 Reports RHR LOOP A(B) ROOM FLOODED alarm. (AR-109(111)-H08)
I I Verifies Suppression Pool level dropping.
Dispatches Plant Operator to investigate room flooding.
~
us
- us Note 1 Enters EO-I 00-1 04, SECONDARY CONTAINMENT CONTROL.
Directs isolating RHR system discharging into the Secondary Containment.
Directs start of ESW and unit coolers with a cooling source.
Re-enter EO-I 00-103, PRIMARY CONTAINMENT CONTROL due to suppression pool level ~22.
Closes H V-151 -FO04A(B) and HV-l51-H)04C(D).
Reports Suppression Pool level has stopped dropping.
PCOM/P Starts ESW and unit coolers with a cooling source.
Directs other loop of RHR placed in Suppression Chamber sprays.
- Denotes Critical Task Form STCP-QA-612A Rev. 0. (04/98)
Page 26 of 23 2003 NRC Exam Rev. 1 File No. Rl l-3
Page 27 Scenario PCOI 7-1 04 Rev. 0, 5/1/03 k-INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
799 Brief
Description:
INSTR LINE BREAK INSIDE DRWELL I RHR SUCTION LINE BREAK INSTRUCTOR ACTIVITY:
Which ever loop of RHR is chosen to initiate sprays will incur a failure, monitor for the loop chosen to insert the correct failure below.
- 1. If the A loop of RHR is placed in service; immediately after either A or C pump is started, initiate s suction line break, Depress P-5:
[P-5] IMF RH149004A 20 4:OO RHR LOOP A SUCTION BREAK
- 2. If the B loop of RHR is placed in service; immediately after either B or D pump is started, initiate s suction line break, Depress P-6:
[P-61 IMF RH1490048 20 4:OO RHR LOOP B SUCTION BREAK
.U ROLE PLAY:
As NPO dispatched to investigate RHWCS Pump rooms, wait -2 minutes and report you are unable to enter either RHR because something is blocking the door; you hear a loud noise like water rushing into the room.
If asked, report you are unable to determine water levels in the rooms.
Form STCP-QA-612A Rev. 0. (04/98)
Page 27 of 23 2003 NRC Exam Rev. 1 File No. R11-3
Page 28 Scenario PCOl7-I 04 Rev. 0, 5/1/03 POSITION PCOM/P SCENARIO EVENT FORM TIME STUDENT ACTIVITIES c-
- us
- us Event No:
739 Brief
Description:
INSTR LINE BREAK INSIDE DRYWELL I RHR SUCTION LINE BREAK Directs Spraying the DW when Supp Chmbr pressure exceeds 13 psig.
Directs DWspray flow limited to between 1000 and 2800 gpm for the first 30 seconds.
Directs terminating DW Sprays before DW pressure drops to 0 psig.
I I
Places RHR in Supp Chmbr Sprays with 2500 gpm spray flow.
us I
I Directs terminating Supp Chmbr Sprays before Supp Chmbr pressure drops to 0 psig.
- PCO/wP I
I Sprays the DW when Supp Chmbrpressure exceeds 13 psig.
- PCOIwP I I Limits DWspray flow to between 1000 and 2800 gpm for the first 30 seconds.
Establishes 9500 gpm spray flow before throttling.
Reports DW pressure and temperature dropping.
Terminates DW Sprays before DW pressure drops to 0 psig.
Terminates Supp. Chmbr. Sprays before Supp. Chmbr. pressure drops to 0 psig.
TERMINATION CUE:
Drywell sprays have been initiated and RPV water level is maintained +I 3 to
+54 the scenario can be terminated.
I I
- Denotes Critical Task NOTES:
Form STCP-QA-612A Rev. 0. (04198)
Page 28 of 23 2003 NRC Exam Rev. 1 File No. Rl l -3
Page 29 Scenario PCOl7-I 04 Rev. 0, 5/1/03 A--
INSTRUCTOR ACTIVITIES, ROLE PLAY, AND INSTRUCTORS PERSONAL NOTES Event No:
739 Brief
Description:
INSTR LINE BREAK INSIDE DRYWELL I RHR SUCTION LINE BREAK INSTRUCTOR ACTIVITY:
As necessary.
ROLE PLAY:
As necessary.
TERMINATION CUE:
Drywell sprays have been initiated and RPV water level is maintained +I 3 to +54 the scenario can be terminated.
Form STCP-QA-612A Rev. 0, (04/98)
Page 29 of 23 2003 NRC Exam Rev. 1 File No. R11-3