ML051890202
| ML051890202 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/18/2005 |
| From: | Mccall K AmerGen Energy Co |
| To: | D'Antonio J Operations Branch I |
| Conte R | |
| References | |
| 50-289/05-301, ES-D-1 50-289/05-301 | |
| Download: ML051890202 (55) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility:
Three Mile Island Scenario No.:
1 OpTestNo.:
NRC Examiners:
Operators:
Initial Conditions:
80% power, MOC
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0 AH-E-1A is tagged out of service.
0 CRD Aux Programmer out of service for maintenance Turnover:
Continue 80% power operation.
Critical Tasks:
Cross Tie LPI Loops and balance LPI flows Trip RCPs within 1 minute following loss of subcooling Event Malf.
Event No.
Event Description 1
I RCOGA I ICRS I Pressurizer temperature instrument failure (high).
I URO 2
CHOl B TS CRS AH-E-1 B RB Air Handling Unit Trip. (TS) 3 MU19D C CRS RCP Seal #1 failure.
4 RDlOC N CRS Manual reactor power reduction due to ICs-CRDS interface 5
RF DH32 TS CRS BWST Low Level Alarm Condition (TS)
C URO R, URO problem.
50 gpm RCS leak (TS) requires plant shutdown.
I I 1 t;;
I Large Break LOCA.
ITHWA 8
1 DHOlB I E I LPI Pump failure.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Amendix D Scenario Outline Form ES-D-1 THREE MILE ISLAND MAY 2005 NRC EXAM SIMULATOR SCENARIO #I GENERAL DESCRIPTION The crew will take the watch with reactor power at 80% and ICs in Full Automatic.
On cue from the Lead Evaluator, initiate the Pressurizer temperature instrument failure. The crew should respond to alarm G-2-5, PZR LEVEL HI/LO, and 1202-29, Pressurizer System Failure, transferring Pressurizer level control to manual, selecting valid instrumentation for automatic control, and then returning level control to automatic. An EQUIPMENT DEFICIENCY TAG should be applied to the pressurizer temperature selector pushbutton, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
Afler the failed Pressurizer temperature instrument is declared inoperable, and an Equipment Deficiency Tag is applied, the Lead Evaluator can cue the RB Cooling Fan failure. The crew should respond to alarms 8 - 2 4 480V ES MOTOR OVERLOAD, and B-1-5,480V ES Motor TRIP. Since there is no standby air handling unit to start, the SRO should evaluate for Technical Specification compliance (7-day TS time clock.) An EQUIPMENT DEFICIENCY TAG should be applied to the AH-E-IB control switch, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
Afler the SRO has declared the 7-day TS time clock, the Lead Examiner can cue initiation of the RCP Seal failure.
Seal leakoff rate will be set to exceed 1203-16 entry conditions (> 6 GPM), but negate the (>8 GPM) requirement to trip the reactor if power is reduced to less than the required limit within 5 minutes. Based on these conditions 1203-16 will require the crew to reduce power to less than 75%, shutdown the affected pump using OP-TM-226-154, SHUTDOWN RC-P-1 D, and isolate seal #1 leak-off. During the power reduction the CRD system will fail to respond to automatic insert signals. Operators should take MANUAL control of the Diamond Rod Control Panel and additional ICs controls to effect the power reduction in accordance with requirements of OP-TM-621-471, ICs MANUAL CONTROL.
On cue from the Lead evaluator following the power reduction and RCP seal isolation, the Borated Water Storage tank (BWST) level will be reduced to activate MAP E-3-4, BWST TEMP/LVL HVLO. The crew should confirm the validity of the low level alarm using redundant control room and plant computer indications, and perform the actions described in the alarm response procedure for MAP E-3-4. The SRO should determine that conditions do not satisfy T.S. 3.3.1.l.a. If BWST level is not restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, T.S. 3.0.1 requires initiation of plant shutdown and the plant must be placed in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. If BWST is still not restored, the plant must be placed in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Makeup to the BWST is not required to proceed with the scenario.
Shortly after BWST level reduction the Lead Evaluator can cue initiation of the 50 gpm RCS leak. The SRO is required to recognize the (TS 3.1.6.1) 1 gpm unidentified and the (TS 3.1.6.2) 10 gpm total RCS leakage limits are exceeded, and announce requirements to place the reactor in hot shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The SRO should announce the more restrictive time limits to initiate plant shutdown with 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and reach HOT STANDBY within the time limits of T.S. 3.0.1.
Afler the leakage tech spec evaluation, the Lead Examiner can cue initiation of the large break LOCA with delayed trip of one LPI Pump. The crew should enter OP-TM-EOP-001, REACTOR TRIP, perform the immediate manual actions and recognize loss of RCS subcooled margin. Actions of RULE 1 should be completed, followed by transitions to OP-TM-EOP-002, LOSS OF SUBCOOLED MARGIN, and then to OP-TM-EOP-006, LOCA COOLDOWN. Among other actions the team will perform the following high level activities: trip all operating RCPs, verify HPI actuation and EFW actuations, raise OTSG levels to 75-85%, cross-tie Train A and Train B LPI systems and balance LPI flows between the two systems in response to trip of DH-P-1A afler the ES actuation.
The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated
Appendix D Scenario Outline Form ES-D-1 Simulator Scenario #I 4
Event Description Procedure Support 1
Pressurizer temperature instrument Failure (high).
OP-TM-MAP-G0205, Pzr level Hi/Lo./OP-TM Map-GO1 05 1202-29, Pressurizer System Failure.
TS 3.5.5, Accident Monitoring Instrumentation.
MAP B-1-5, 480V ES Motor Trip.
TS 3.3.1.3, 3.3.2, and 3.3.3.
1203-16, RCP #1 Failures. F-l-3/F-1-6 Maps in.
2 AH-E-1 B RB Air Handling Unit Trip (TS) 3 RCP Seal #1 failure.
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OP-TM-226-154, Shutdown RC-P-1 D.
4 Manual reactor power reduction due to ICS-CRDS interface problem.
OP-TM-621-417, ICs Manual Control.
OP-TM-622-471, Manual Control Rod Operations.
5 BWST Level Low Condition.
MAP E-3-4, BWST Temp/Lvl Hi/Lo.
TS 3.1.6, Leakage.
1102-4, Power Operations.
6 50 gpm RCS leak (TS) requires plant shutdown.
7 Large Break LOCA.
OP-TM-EOP-001, Reactor Trip.
OP-TM-EOP-002, Loss of Subcooled Margin.
OP-TM-EOP-006, LOCA Cooldown.
OP-TM-EOP-010, Emergency procedure Rules, Guides and Graphs.
a OP-TM-EOP-010 Guide 3, LPI Failure.
LPI Pump failure.
NRC Scenario 1 Setup Page 1
ACTION I
COMMENTS / INSTRUCTIONS I
DESCRIPTION I
Initialization IC-I6 Console Right AH-E-1A PTL INFO Tag Diamond Control Panel Remote Functional CHR05 Malfunction RCOGA Malfunction CHOI B Malfunction MU-19D Malfunction RDIOC Remote Function RF DH32 Malfunction THO3A Malfunction THWA Malfunction DHOI B 80% Power MOC AH-E-1A Tagged 00s AH-E-1A Tagged 00s Breaker OPEN INFO Tag stating Aux Programmer 00s for maintenance Value:
OUT When:
IMMEDIATELY Value:
Insert SEV. - 99.ayo When:
Event 1 RAMP 10 Sec Value:
Insert When:
Event 2 Value:
Insert SEV. - 9%
When :
Event 3 RAMP 120 sec.
Value:
Insert When:
Event 4 Value:
Insert SEV. 93%
When:
Event 5 Value:
Insert SEV. 30%
When:
Event 6 RAMP 360 sec.
Value:
Insert SEV. 4.75%
When:
Event 7 RAMP 300 sec Value:
Insert When :
Event 8 XENON Equilibrium MOL Scenario Support Scenario Support ScenarioSupport Pressurizer Temp INST FAILS HIGH AH-E-1 B R. B. Air Handling Unit Trip RC-P Seal #1 FAILURE ICs - CRD Interface Problem BWST Low Level Alarm Condition
= 50 gpm RCS Leak Requires Plant Shutdown Large Break LOCA LPI Pump Failure
CRS Appendix D Operator Action Form ES-D-2 Directs entry to OP-TM-MAP-G0205.
Op Test No.:
1 Scenario #
1 Event#
1 Page 5 of 19 Event
Description:
Pressurizer Temperature Instrument Failure (High) x-Time
[
Position I
Applicant's Actions or Behavior I FLOOR OPERATOR:
When directed by the Lead Examiner, enter Event 1.
EXAMINER'S NOTE:
When OP-TM-MAP-GO105 and OP-TM-MAP-GO205 actuate, CRS can REVIEW the associated procedures or go directly to 1202-29.
OBSERVE:
Pressurizer level recorder RC-1 LR a
MU-V-17 position indication a
RC-LI-777A u
IF PZR level indication is not valid, then PERFORM the I
URo I following:
PLACE MU-V-17 in Hand and control PZR level.
I I
a a
PLACE MU-V-17 in AUTO.
SELECT a valid level signal.
END Of OP-TM-MAP-GO205 I
I CRS I Direct entry into OP-TM-MAP-GO105 I
I URO I INITIATE Guide 9 to control Pressurizer level.
I I
URO
]OBSERVE:
PZR Level 0
MU-V-17 Position a
MU-Flow
ADDendix D ODerator Action Form ES-D-2
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Op Test No.:
1 Scenario #
1 Event#
1 Page 6 of 19 Event
Description:
Pressurizer Temperature lnstnrment Failure (High)
Time I
Position I
Applicant's Actions or Behavior I
CRS 1
URO I VERIFY Hi-Hi Level as follows:
0 0
PLACE MU-V-17 in hand IAW OP-TM-211-472.
SELECT other PZR Level Instruments (this checks for instrument problems).
End of MAP G0105.
Direct entry into 1202-29 MONITOR the following:
0 Pressurizer level (RC-LI-777NRCl -LR) (CC) 0 RCS Pressure (RC3-PR (CC) / RC-PI-949A (PCL).
0 Makeup Flow (MU24A-FI) (CC).
PLACE MU-V-17 (CC) in HAND by pressing White HAND PB and PERFORM the following:
0 VERIFY White HAND light is Lit on (CC).
0 MAINTAIN Pressurizer level as required (RC-LI-777A / RC1-LR) using toggle switch.
If indication fails high:
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0 TAKE MU-V-17 under hand control AND ADJUST makeup flow to equal letdown flow minus seal injection to maintain makeup tank as constant as possible.
0 SELECT alternate pressurizer level transmitter 0
SELECT alternate pressurizer temperature transmitter.
Appendix D Operator Action Form ES-D-2 CRS Op Test No.:
I Scenario #
1 Event#
1 Page 7 of 19 I
v Review TS for applicability:
Event
Description:
Pressurizer Temperature Instrument Failure (High)
Time I
Position I Applicant's Actions or Behavior NUMBER OF CHANNELS INSTRUMENTS MINIMUM NUMBER OF CHANNELS I
I I
I I
I Pressurizer Level I 2
I 1
I CRS I Have URO attach EDT Tan to FAILED lnst I
I When directed by Lead Examiner, proceed to Event 2
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event#
2 Page 8 of 19 Event
Description:
AH-E-1 B RB Air Handling Unit Trip Time I
Position I Applicants Actions or Behavior 1 FLOOR OPERATOR:
When directed by the Lead Examiner, enter Event 2.
CRS CREW Directs entry to OP-TM-MAP-BO105.
Should review response to alarm.
Observation (Control Room):
0 Tripped fan disagreement light (ambedgreen).
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Review TS for Reactor Building Emergency Cooling System for applicability:
The following components must be OPERABLE:
Two reactor building emergency cooling fans and associated cooling units (one in each train). Specification 3.0.1 applies.
Maintenance or testing shall be allowed during reactor operation on any component(s) in the RB emergency cooling water, systems which will not remove more than one train from service.
One reactor building cooling fan and associated cooling unit shall be permitted to be out-of-service for seven days.
Declare 7-Day Time Clock per T.S. 3.3.3.
Instruct Crew to apply EDT Tag to AH-E-1 B.
When directed by Lead Examiner, proceed to Event 3.
v CRS CRS CRS Appendix D Operator Action Form ES-D-2 Directs entry to OP-TM-MAP-FO103.
I M T Seal Number 1 Leak-Off Flow (SLO) is > 6 gpm, then GO TO 1203-16, RC Pump Seal Failures.
Direct entry to OP-TM-FO106.
Page 9
of 19 I Op Test No.:
1 Scenario #
1 Event#
3 I
Event
Description:
RCP Seal #1 Failure Time I
Position I Applicants Actions or Behavior FLOOR OPERATOR:
EXAMINERS NOTE:
When directed by the Lead Examiner, enter Event 3.
Crew may review alarms. If Entry conditions to 1203-16 are verified Crew may enter 1203-1 6 directly.
EXAMINERS NOTE:
This alarm procedure may be reviewed. Guidance is the same as OP-TM-MAP-FO103. OP-TM-MAP-FO103 also directs Crew to 1203-16.
I CRS I Manual Actions Required:
Observe the following:
RC-18-DPI-1/2/4 (CC) 0 0
MU-42-FI (CC), Seal Injection Flow MU-24-FI (CC), RCS Makeup Flow Seal Number 1 Leak-Off Flow (SLO)
I CRS I Direct entry to 1203-16.
I I
URO RAISE Seal injection flow, as necessary to attempt to maintain lab seal DP positive on each RC pump. Adjust SI Flow H/A station setpoint or place MU-V-32 in manual. IF lab seal DP indication is not available, then maximize seal injection flow.
Do not exceed 60 GPM.
Appendix D Operator Action Form ES-D-2 c
Op Test No.:
1 Scenario #
1 Event#
3 Page 10 of 19 Event
Description:
RCP Seal #I Failure Time I
Position I
Applicant's Actions or Behavior Event REDUCE reactor power IAW 1102-4 to within the appropriate limit based on shutdown of the affected RC pump.
0 For 3 RC pumps operating, reactor power must be less than 75%.
CRS/URo CRS CRS I
1 2 / 1 RCP Combination - 75% NI Power INITIATE OP-TM-226-154 to shutdown the affected RC pump.
VERIFY Reactor Power the following for the final RCP Combination:
VERIFY Turbine Load the following for the final RCP I
CRS I Combination:
URO I 0 2 / 1 RCP Combination - 665 MWE PLACE RC-P-1 D in Pull-To-Lock.
NOTE:
A 2 / 1 RCP combination with OTSG levels > LLLs will require a re-ratio (= 70% I 30%) of Feedwater flow to A I B OTSG.
I URO I PLACE at least one each of the following in Normal-After-Start:
0 RC-P-2D-1, Oil Lift Pump AC HP (CC), or RC-P-2D-2, Oil Lift Pump DC HP (CC)
RC-P-3D2, Backstop Oil Pump #2 (CC) 0
Op Test No.:
1 Scenario #
1 Event#
3 Page 11 of 19 URO Event
Description:
RCP Seal #1 Failure Time I
Position I
Applicants Actions or Behavior When the affected RC Pump stops rotating CLOSE MU-V-33D.
URO 1
URO 1 Place RC-P-3D-2 and RC-P-30-1 in Pull-To-Lock.
Place RC-P-2D-2 and RCP-2D1 in Pull-To-Lock.
Appendix D Operator Action Form ES-D-2 Event
Description:
Manual Reactor Power Reduction Due to ICs-CRDS interface Problem Time I
Position I Applicant's Actions or Behavior I
URO Op Test No.:
PRESS AUTO/MAN pushbutton on Diamond Panel.
- 1) VERIFY MAN lamp Lit.
I Scenario #
I Event#
4 Page 19-1 FLOOR OPERATOR:
EXAMINER'S NOTE:
When directed by the Lead Examiner, enter Event 4.
Event 4 should be entered immediately prior to the power reduction to run in tandem with Event 3.
CRS Directs entry to OP-TM-621-471.
URO ENSURE ULD in HAND.
I URO 1 PLACE SGIREACTOR DEMAND station in HAND.
I URO I VERIFY alarm H-2-1 "ICs in Track actuated.
I ACO I PLACE SG A/B LOAD RATIO AT^) station in HAND.
ACO PLACE SG A FW DEMAND station in HAND.
I ACO I PLACE SG B FW DEMAND station in HAND.
I URO I PLACE REACTOR DEMAND station in HAND.
EXAMINER'S NOTE:
Slow crew response time may result in meeting entry conditions for OP-TM-AOP-070.
When Event 3 4 actions are complete, the Lead Examiner, can cue Event 5.
Appendix D Operator Action Form ES-D-2 L.
Op Test No.:
I Scenario #
1 Event#
5 Page 13 of 19 Event
Description:
BWST Low Level Alarm Condition (TS)
Time I
Position I Applicant's Actions or Behavior I FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 5.
CRS URO lndicationslcues available:
BWST TEMPlLVL HllLO alarm Directs entry to OP-TM-MAP-E0304 If level is LO:
v CRS Dispatch A 0 to check drain to tank is closed and check for leaks.
Review for applicability T.S. 3.3.1.1.a.
0 Makeup to tank to maintain level (refer to 1104-29C).
0 Check console indication and ES Panel to verify DH-V-6NB are closed. If either indicate open: Immediately close DH-V-5A or 58, and close DH-V-6A and B.
If the BWST volume is not within limits, restore the BWST to OPERABLE within one hour. Specification 3.0.1 applies.
When directed by Lead Examiner, proceed to Event 6.
CREW
-v Leakage - If time allows perform OS-24, Leak Rate.
Appendix D Operator Action F
o
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ES-D-2 Op Test No.:
1 Scenario #
I Event#
6 Page 14 of 19 Event
Description:
50 GPM RCS Leak (TS) Requires Plant Shutdown Time I
Position I
Applicants Actions or Behavior CRS FLOOR OPERATOR:
When directed by Lead Evaluator, initiate Event 6.
Direct Crew to initiate Plant S/D IAW 11 02-4.
EXAMINERS NOTE:
Crew may elect to place RB Emergency Cooling in service or to initiate a manual reactor trip.
CRS If any reactor coolant leakage exists through a nonisolable fault in an RCS strength boundary (such as the reactor vessel, piping, valve body, etc., except the steam generator tubes), the reactor shall be shutdown, and a cooldown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection. (T.S. 3.1.6.1 and T.S. 3.1.6.2)
~~
When directed by Lead Examiner, proceed to Events 7 and
- 8.
Appendix D Operator Action Form ES-D-2 Op Test No.:
I Scenario #
1 Event #
718 Page 15 of 19 Event
Description:
LPI Pump Failure Time I
Position I
Applicants Actions or Behavior CRS Directs entry to OP-TM-EOP-001.
URo I
TRIP the Reactor by depressing the Reactor Trip and DSS pushbuttons.
I URO I VERIFY the reactor is shutdown.
URO TRIP the Turbine.
1 URO I VERIFY the turbine stop valves are closed.
CRSURo IAAT a symptom exists, then immediately treat the symptom using the following priority:
SCM 25°F GO TO OP-TM-EOP-002.
CRS URO IAAT SCM I
URo I Rule 1 OP-TM-EOP-010 25°F and reactor is shutdown, then perform Direct transition to OP-TM-EOP-002.
PERFORM Rule 1, SCM.
- 1. VERIFY it has been more than two minutes since RCP I
I URo I
start.
Critical Task I
I URO
- 2. ENSURE RCPs are shutdown (stops RC-P-IA, 1 B, 1 C).
I I
URO I 3. ENSURE 1600 # ESAS has been actuated.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
1 Event #
718 Page 16 of 19 Event
Description:
LPI Pump Failure Time I
Position I
Applicant's Actions or Behavior I URO/ARO I 4. ENSURE EFW has actuated.
URo I condition.
- 6. Initiate Guide 15 and Feed available OTSG's to 75% to 85% operating range level.
ARO ENSURE announcement of reactor trip and EFW actuation over the plant page and radio.
CRS CRS ENSURE performance of an alarm review.
CRS REQUEST SM evaluate Emergency Action Levels (EALs).
IAAT RCS pressure GO TO OP-TM-EOP-006.
185 psig and LPI flow > 1250 GPM, then CRS VERIFY PORV is closed (Tailpipe DP indicator, Alarm G-1-7, I CRS'URo I A0517).
INITIATE Attachment 1, Isolation of Possible Sources of Leakage.
CRS/URo CRS/URO VERIFY all RC Pumps are shutdown.
CRS VERIFY one of the following exists:
0 Two (2) HPI trains in ES operation I
I 1 0 SCM>25"F 0
lncore temperature stable or reducing.
Appendix D Operator Action Form ES-D-2 CRS CRS I
I IAAT RCS > 25°F superheat, then GO TO OP-TM-EOP-008.
IF primary-to-secondary heat transfer is excessive, then GO TO OP-TM-EOP-003.
Op Test No.:
1 Scenario #
1 Event #
718 Page 17 of 19 Event
Description:
LPI Pump Failure Time I
Position I Applicant's Actions or Behavior CRS IAAT RM-A-1 high alarm or 4 psig ESAS have actuated, then Radiological Event Operations".
OP-TM-826-901, "Control Building Ventilation System
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VERIFY cooldown rate > 40"F/hr or primary-to-secondary heat transfer exists.
CRS CRS VERIFY OTSG tube leakage VERIFY SCM > 25°F is being maintained without use of MU-V-217 or HPI.
1 GPM.
URO URo 1 EXAMINER'S NOTE:
Enter Event 8 prior to Crew transition to OP-TM-EOP-006.
ENSURE HPI and LPI are operated per RULE 2.
IAAT an ES Actuation setpoint is reached, then ENSURE all ES components have actuated.
I I
CRS I GO to OP-TM-EOP-006, LOCA Cooldown.
I URO I Initiate Guide 3, LPI Failures.
Appendix D Operator Action Form ES-D-2 I
Scenario #
1 Event#
718 Page 18 I OP Test No.: -
Event
Description:
LPI Pump Failure Time I
Position I
Applicant's Actions or Behavior Critical Task URO CRS/URO CRS/URO CRS/URO CRS CRS CRS CRS CRS URO If one LPI Pump fails, and all other LPI equipment is operable then:
0 CLOSE DH-V-4 on the train with the inoperable pump 0
OPEN DH-V-38A and B (Aux. Bldg. 281' El.)
0 THROTTLE DH-V-4A and B to balance LPI flow between the two trains while maximizing total LPI flow within limits (RULE 2). (21250 gpm through each injection line and total flow 53300 gpm)
ENSURE CF-V-1A and CF-V-1B (PCR) are OPEN.
VERIFY RB temperature e 130°F and RB pressure < 2 psig.
IAAT RM-A-1 high alarm or 4 psig ESAS have actuated, then INITIATE OP-TM-826-901, "Control Building Ventilation System Radiological Event Operations".
IAAT RCS > 25°F superheat, then GO TO OP-TM-EOP-008.
ENSURE performance of an alarm review.
REQUEST SM evaluate Emergency Action Levels (EALs).
VERIFY Emergency Diesel Generators are in ES standby or loaded on bus.
INITIATE Guide 20, "PRIOR to Transfer to RB Sump".
INITIATE Rule 5, "Emergency Boration"
Appendix D Operator Action Form ES-D-2 Page 19 of Op Test No.:
1 Scenario #
1 Event#
718 19 Event
Description:
LPI Pump Failure Time I
Position I
Applicant's Actions or Behavior Terminate scenario when Crew has had opportunity to perform BOTH designated critical tasks, or at Lead Examiner's discretion.
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Appendix D Scenario Outline Form ES-D-1 Facilrty:
Three Mile Island Scenario No.:
2 Op Test No.:
NRC Examiners:
Operators:
initial Conditions:
lOO%power,EOC AH-E-1A tagged 00s.
DC-P-1A is operating in accordance with OP-TM-543401 to support chemistry sampling.
CRD Aux Prwrammer out of service for maintenance Turnover:
Maintain 100% power operations.
Critical Tasks:
Manually actuate ES Train B Throttlefrenninate HPI flow to the RCS OTSG - 1A Isolation Event No.
1 2
3 4
5 6
7 8
Malf. No.
RCR42 RCR43 MU01 B cco2A RC08B 110 Override TCOl MSWA MSWB IC26 110 Override ESOlB Event Description I CRS I URO C CRS C URO C CRS C URO I CRS I URO Pressurizer Spray Valve Failure.
Makeup Pump Trip, Loss of RCS Makeup and Seal Injection.
Decay Heat Closed Cooling Pump Failure. (TS)
N CRS I Manual Power Reduction Due to Heat Balance Calculation Error. (TS)
R URO M CRS Main Turbine Trip.
M URO
_ _ _ ~
C CRS I Stuck Open Main Steam Safety Valves with Excessive FW Flow C URO I CRS I URO ES Train B Actuation Failure.
(N)ormal. (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 THREE MILE ISLAND MAY 2005 NRC EXAM SIMULATOR SCENARIO #2 GENERAL DESCRIPTION The crew will take the watch with reactor power at 100% and ICs in Full Automatic.
On cue from the Lead Evaluator, the Pressurizer spray valve failure will be activated. The crew should respond to alarm G-3-8, RCPRESS NARROW RNG HVLO or indications in accordance with 1202-29, PRESSURIZER SYSTEM FAILURE. Spray valve control should be shifted Manual, and the valve closed. From this point forward, OP-TM-220-503. MANUAL CONTROL OF PRESSURIZER PRESSURE, will be applicable. An EQUIPMENT DEFICIENCY TAG should be applied to the pressurizer spray valve AutoManual control selector, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
When ready, the Lead Evaluator can cue initiation of the Makeup Pump failure. The crew should respond to alarms B-2-2,4KV ES MOTOR OVERLOAD, and 8-1-2, 4KV ES MOTOR TRIP, and implement 1203-15, LOSS OF R.C.
MAKEUP/SEAL INJECTION. Following completion of 1203-1 5 immediate manual actions, MU-P-1A will be started with cooling water established either from DCCS or the NSCC system. An EQUIPMENT DEFICIENCY TAG should be applied to the failed Makeup Pump control switches, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
When ready, the Lead Examiner can cue initiation of DC-P-1A trip. The crew should respond to alarms 8 - 2 4 480V ES MOTOR OVERLOAD, and 8-1-5,480V ES MOTOR TRIP. If not performed with startup of MU-P-1A previously, OP-TM-543-439, SWAPPING MU-P-IA COOLING TO NS, will provide guidance to re-establish cooling to MU-P-1 A.
The SRO should review TS 3.3 to determine that a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TS time clock has been started, with possible plant shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. An EQUIPMENT DEFICIENCY TAG should be applied to the DC-P-1A control switch, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
After the SRO has declared the TS for the ECCS, the Lead Evaluator can cue the RCS cold leg RTD failure. The crew should respond to alarm H-3-2, SASS MISMATCH, in accordance with OP-TM-MAP-H0302, to select an alternate instrument. An EQUIPMENT DEFICIENCY TAG should be applied to the affected Tcold selector pushbutton, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
When cued by the Lead Examiner the SOS will call the control room to direct the CRS to reduce reactor power by 5%
due to discovery of an error in the Plant Computer heat balance calculation. The SRO will apply T.S. 1. I and direct a power reduction in accordance with 11024, POWER OPERATION. During the power reduction the operators will be required to take MANUAL control of the ICs to effect the power reduction, using OP-TM-621-471, ICs MANUAL CONTROL, and OP-TM-622471, MANUAL CONTROL ROD OPERATIONS.
Shortly after the reduction to 95% power, the Lead Evaluator can cue the Main Turbine trip, which will result in an automatic reactor trip. OTSG I A safety valves will stick open and FW-P-1A will not respond in automatic to cause RCS overcooling conditions. The crew should respond in accordance with OP-TM-EOP-001, REACTOR TRIP, followed by OP-TM-EOP-003, EXCESSIVE PRIMARY-TO-SECONDARY HEAT TRANSFER. Once the crew enters OP-TM-EOP-003, among other actions they will perform the following high level activities: isolation of OTSG 1A feed and steam pathways, manual actuation of HPI Train B (simulator malfunction blocks automatic actuation), HPI throttling, and actions required to prevent RCS reheat and repressurization following isolation of the OTSG.
The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated.
Appendix D Scenario Outline Form ES-D-1 Simulator Scenario #2 Event Description Procedure Support I
Initial Set-up.
I OP-TM-543-401, Operating DC-P-1A For Other Than Decay Heat Removal Operations.
OP-TM-MAP-G0308, RC Press Narrow Rng Hi/Lo.
1 1
Pressurizer Spray Valve Failure.
1202-29, Pressurizer System Failure.
I I
OP-TM-220-563, Manual Control of Pressurizer Pressure.
MAP 8-2-2, 4KV ES Motor Overload.
I 2
Makeup Pump Trip.
I 1203-15, Loss of R.C. MakeupISeal Injection.
I MAP 8-2-5, 480V ES Motor Overload.
I 3
DC-P-1A Trip (TS)
MAP 8-16, 480V ES Motor Trip.
OP-TM-543-439, Swapping MU-P-1A Cooling To NS.
TS 3.3 Emergency Core Cooling, Reactor Building Emergency Cooling and Reactor Building Spray Systems.
OP-TM-MAP-H0302, SASS Mismatch.
I OP-TM-621-471, ICs Manual Control.
I Manual Reactor Power Reduction.
Main Turbine Trip.
OP-TM-622-471, Manual Control Rod Operations.
I OP-TM-EOP-001, Reactor Trip.
I OP-TM-EOP-010 Rule 3, Excessive Heat Transfer. I Excessive PSHT due to Stuck Open MSSVs with Excessive FW Flow.
I OP-TM-EOP-003, Excessive Primary to Secondary Heat Transfer.
OP-TM-EOP-010, Emergency Procedure Rules, Guides and Graphs.
8 ES Train B actuation failure.
OP-TM-EOP-010 Guide 9, RCS Inventory Control. I
NRC Scenario 2 Setup Page c
ACTION I COMMENTS / INSTRUCTIONS I DESCRIPTION I
L Initialization IC-1 7 Console Right Remote Function CHRO5 INFO Tag Diamond Control Panel Console Center Main Console AH-E-1A PTL DC-P-1A N.A.S.
Remote Function RCR342 Remote Function RCR43 Malfunction MU01 B Malfunction CC02A Malfunction RC08B Override DI ZDllCSlMCSl(3)
Override DI ZDllCSlMCSl(4)
Malfunction TCOl
\\
02A4A37 -
02A4A37 -
Malfunction MS04A Malfunction MS04B Malfunction IC 26 Override DI 36AMCS(4)
Malfunction MSlOAA 01 A5A03 - ZDl 1 CS Malfunction MSlOAB Malfunction ESOl B 100% HFP, ICs Full AUTO AH-E-1A Tagged 00s Value:
OUT When:
Immediately INFO Tag stating Aux Programmer 00s for maintenance DC-P-1A Operating IAW OP-TM-543-401 for Chemistry Robust Barriers applied IAW Risk Document AH-E-1A PTUAH-E-1A BKR OPEN Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
Value:
When:
2125 Event 1 2000 Event 1 Insert Event 2 Insert Event 3 Insert Sev..001%
Event 4 RATE 300 sec.
OFF Event 5 OFF Event 5 Insert Delay 3 sec.
Event 6 Insert Sev. 100%
Event 6 Delay 15 sec.
Insert Sev. 100%
Event 6 Delay 15 sec.
Insert Event 6 OFF Event 6 Insert Event 6 Insert Event 6 Insert Event 6 Equilibrium X2N00 Scenario Support Scenario Support Scenario Support Scenario Support Scenario Support Pressurizer Spray Valve Failure Pressurizer Spray Valve Failure Make-up Pump 1 B Trip Decay heat Closed Pump 1A Trip RCS Cold Leg RTD Failure Disable ULD SG/RX Master Required Disable ULD SGlRX master Required Main Turbine Trip Stuck Open MSSV A OTSG Stuck Open MSSV A OTSG A Main Feedwater Pump Fails to Respond in AUTO FWD-1A Toggle Switch (Lower) Disabled SGA Train A Low Pressure MFW ISOL SGA Train B Low Pressure MFW ISOL ES Train B Actuation Failure
NRC Scenario 2 Setup Page I
ACTION I
COMMENTS / INSTRUCTIONS I DESCRIPTION I
Appendix D Operator Action Form ES-D-2 CRS Op Test No.:
1 Scenario#
2 Event#
1 Page 6 of 20 Event
Description:
L Pressurizer Spray Valve Failure Time I
Position I
Applicant's Actions or Behavior Directs entry to OP-TM-MAP-G0308.
~
URO I MANUAL ACTIONS REQUIRED
~
PZR level (strip recorder) and PZR temperature varying
~ _ _ _
I OBSERVEthe followingat Console CC:
URO OBSERVE the following at Console CR:
0 Narrow range pressure indications varying (possible SASS 1
mismatch)
URO URO 0
T Average varying 0
Power channels varying 0
VERIFY RC-RV-2 PORV is Closed 0
CLOSE RC-V-2 as required.
I 0 Steam generator level and feedwater flow varying URO CRS I
Makeup tank level varying I
I 0
ENSURE CLOSE RC-V-1 PZR Spray Control Valve Directs entry to 1209-29, Pressurizer System Failure.
I 0 Pressurizer heater control and indicating lights URO I IF RCS pressure is Lo, then PERFORM the following:
Appendix D Operator Action Form ES-D-2 URO I
Op Test No.:
1 Scenario#
2 Event#
1 Page 7 of 20 MONITOR pressurizer level and RCS temp.
Event
Description:
Pressurizer Spray Valve Failure I
Time I
Position I
Applicants Actions or Behavior EXAMINERS NOTE:
1202-29 should be entered for Event 1.
I CRS I Enter Section C - Decreasing or LOW RCS Pressure VERIFY PORV and Code Safeties are closed.
I URO IF press.C 2155 psig, THEN VERIFY PZR spray valve (RC-V-1) is shut.
I URO If RC-V-1 failed open then CLOSE RC-V-3 VERIFY pressurizer heaters energize at setpoint OR manually TURN ON additional heaters as necessary to maintain RCS pressure at 2 2135.
+
IF PZR spray valve has failed open, THEN perform the following:
0 AITEMPT control spray valve (RC-V-1) with manual pushbuttons.
I I
EXAMINERS NOTE:
Crew can refer to OP-TM-220-503, Manual Control of Pressurizer Pressure for Pressure Control.
I I Go to Event 2
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
2 Event#
2 Page -
8 of 20 Event
Description:
Makeup Pump Trip, Loss of RCS Makeup and Seal Injection I
Time I
Position I Applicant's Actions or Behavior FLOOR INSTRUCTOR: When directed by Lead Examiner, enter Event 2.
EXAMINER'S NOTE:
Crew may enter any of the alarm responses below or directly into 1203-1 5.
c/15 I
URO I
CRS t CRS URO CRS Directs entry into OP-TM-MAP-FO105.
Manual Actions Required 0
OBSERVE the following:
MU-42-FI (CC)
IC-5-FI (CR) > 550 gpm 0
MU-41-DPI (CC), Seal INJ Filters D/P indication, 50 psid MU-V-20 (CC) Open MU-43-FR (PC), RCP Leak off flow 0
IAAT unable to maintain SI flow > 22 gpm from Control Room, then GO TO 1203-15, Loss of RC Makeup / Seal Injection.
~ _ _ _ ~
~
Directs entry to OP-TM-MAP-BO202 Observation (Control Room)
- 1. Disagreement Light (amberhed)
- 2. Computer readout Directs entry to OP-TM-MAP-BO102 Observation (Control Room)
- 1. Disagreement indication (greedamber)
- 2. Computer Printouts and Alarms Directs entry to 1203-15, Loss of R.C. MakeupISeal Injection
Appendix D Operator Action Form ES-D-2 URo Page 9
of 20 Op Test No.:
1 Scenario#
2 Event#
2 If RC makeup is not likely to be quickly restored, place MU-V-17 control station to manual and close.
Event
Description:
Makeup Pump Trip, Loss of RCS Makeup and Seal Injection Time I
Position I Applicants Actions or Behavior URo URO
~~
-1 URO
~
1 Determine cause for loss of R.C. MakeupEeal Injection Verify IC flow to RCPs by flow on IC-5 FI between 650-1300 gpm. (Located on Console CR).
Place MU-V32 control station to manual and close.
0 Running Makeup Pump trips (Green and amber control switch light)
Direct URO Performance of Follow-up Action 1
URO Close MU-V-3 as required to maintain pressurizer level above 150 inches.
URO
+--
I EXAMINERS NOTE:
If seal injection cannot be restored in less than several ( ~ 3 )
minutes, close MU-V-33A-D on any RCP with seal leak off greater than 8 gpm or seal inlet water temperature approaching 225°F in order to minimize the temperature transient at the seal area.
~~-
~~
-~
May not be applicable based on timing of response.
1 URO If RCP Seal No. 1 inlet water temperature or radial bearing temperature exceeds 225F, reduce power 50 - 75 percent and trip the affected pump.
EXAMINERS NOTE:
May not be applicable based on timing of response.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
2 Page 10 of 20 Event
Description:
Makeup Pump Trip, Loss of RCS Makeup and Seal Injection Time I
Position I
Applicant's Actions or Behavior EXAMINER'S NOTE:
Due to rise in ICCW temp caused by Loss of Seal Injection, MU-V-3 mav close isolating letdown. If this occurs crew should recover letdown per OP-TM-211-950. See Final Step in Event 2.
URO URO URO URO URO URO URO URO EXAMINER'S NOTE:
Verify markeup tank level and pressure within the normal operating band.
Compare redundant makeup tank level indications, (LI-778A and MU14-LR on Console Center and PPC points A0498 and A0426).
Opedverify open MU-V-12 OR open BWST supply valve, MU-V-14A/B, if MU-V-12 cannot be opened or Make-up Tank inventory is questionable.
Start standby Makeup Pump and ensure cooling water supplied.
Slowly re-establish RCP Seal injection flow at a rate so seal water temperature at the bearing is decreasing less than 1 "F/min, (Computer points A0521 to A0524).
When a flow rate of 38 gpm is established place MU-V32 control station in AUTO.
If isolated, restore pressurizer level gradually and return MU-V-17 control station to AUTO.
If isolated, restore letdown flow gradually IAW OP RM-211-950 to minimize letdown cooler thermal shock.
Letdown restoration may not be required.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
2 Page 11 of 20 I
Event
Description:
Makeup Pump Trip, Loss of RCS Makeup and Seal Injection Time I
Position I
Applicant's Actions or Behavior Go to Event 3
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
3 Page -
12 of 20 I I
Event
Description:
Decay Heat Closed Cooling Pump Failure (TS)
I Time I
Position I
Applicants Actions or Behavior FLOOR INSTRUCTOR: When directed by Lead Examiner, enter Event 3.
EXAMINERS NOTE:
This alarm should alert the operators to DC-P-lA Failure.
They then should initiate OP-TM-543 439 to place NSCC on MUP-1 A.
I CRS I Directs entry to OP-TM-MAP-BO105 I
CRS I Observation (Control Room):
I I 1. Tripped pump disagreement light (ambedgreen)
I I 2. Computer printout and CRT Directs entry to OP-TM-543-439, Swapping MU-P-1 A Cooling 1
CRS 1 toNS If required to shift MU-P-1A cooling to NS, then PERFORM the I
CRS I following:
I 1 0 NOTIFY Control Room to monitor the following:
DC-T-1A level (DC-LI-109) (CR).
NS-T-1 level (NS-LI-800 / NS-LI-801) (CC).
I 0 CLOSE the following valves: (Locked Valve entry)
DC-V41A DC-V-45A I 0 OPEN the following valves:
I NS-V-80 NS-V-81 IC0 NOTE:
When directed by crew to do steps 4.2.2 and 4.2.3 go to CCR 12 and select NS.
I CRS I Refer to T.S. Section 3.3
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
3 Page 13 of 20 Event
Description:
Decay Heat Closed Cooling Pump Failure (TS)
Time I
Position I
Applicant's Actions or Behavior Two decay heat removal coolers and their cooling water I
CRS I supplies are OPERABLE T.S. 3.3.1.1.d.
Two decay heat closed cycle cooling water pumps must be I
CRS I OPERABLE T. S. 3.3.1.4.c Maintenance or testing shall be allowed during reactor operation on any component(s) in the decay heat, RB spray, cooling water systems which will not remove more than one train of each system from service. Components shall not be removed from service so that the affected system train is inoperable for more than 72 consecutive hours. If the system is not restored to meet the requirements of Specification 3.3.1 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the reactor shall be placed in a HOT SHUTDOWN condition within six hours.* T.S. 3.3.2 Go to Event 4
Appendix D Operator Action Form ES-D-2 CRS Op Test No.:
1 Scenario#
2 Event#
4 Page 14 of 20 Event
Description:
RCS Cold Leg RTD Failure Time I
Position I Applicants Actions or Behavior Directs entry into OP-TM-MAP-H0302.
URo If plant control is not stable Validity of selected instrument is unknown or suspect, then PLACE affected-stations in Hand IAW associated manual operations procedure to balance plant parameters.
I I 0 DETERMINE which inwt is bad.
URO CRS 0
ENSURE valid instrument selected IAW OP-TM-621-451, Selecting Alternate Instrument Inputs to ICs.
Instruct URO to place EDT Tag on failed instrument.
Appendix D Operator Action Form ES-D-2 CRS Op Test No.:
1 Scenario #
2 Event#
6 Page 15 of 20 Event
Description:
Main Turbine Trip Time I
Position I
Applicant's Actions or Behavior FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 5.
Uses 1102-4 to reduce power 5%.
CRS Directs entry to OP-TM-621-471, ICs Manual Control.
I CRS I Establish manual SG/REACTOR Control as follows:
CRS 0
0 PLACE SG/REACTOR DEMAND station in HAND.
VERIFY alarm H-2-1 "ICs in Track" actuated.
ENSURE ULD in HAND.
If necessary to maintain reactor power or control rods within limits or if a power change is being conducted IAW 1102-4, then ADJUST SGIREACTOR DEMAND as follows:
- 1.
If maintaining stable reactor power or a slow planned power change, then RAISE or LOWER in discrete steps to keep neutron error between +2% and -2%.
EXAMINER'S NOTE:
If plant was previously placed in Full ICs Manual Control per OP-TM-621471 neutron error will remain at 0. CRS will give RCS temp and pressure bands to maintain during power reduction.
Go to Event 6
Appendix D Operator Action Form ES-D-2 1
Scenario#
2 Event#
6,7and8 Page 16 of 20 I OP Test No.: -
Event
Description:
Main Turbine Trip; Stuck Open Main Steam Safety Valves with Excessive FW Flow; ES Train B Actuation Failure I
Time I
Position I
Applicants Actions or Behavior FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 6.
I CRS Directs entry to OP-TM-EOP-001, Reactor Trip.
TRIP the Reactor by depressing the Reactor Trip and DSS pushbuttons.
VERIFY the reactor is shutdown.
TRIP the Turbine.
~
~~
~
~
VERIFY the turbine stop valves are closed.
Perform symptom check.
IAAT a symptom exists, then immediately treat the symptom using the following priority:
XHT GO TO OP-TM-EOP-003.
EXAMINERS NOTE:
CRS transitions to OP-TM-EOP-003.
EXAMINERS NOTE:
Event 7 is driven off completion of Reactor Trip.
Appendix D Operator Action F O I ~
ES-D-2 Op Test No.:
1 Scenario#
2 Event#
8 Page 17 of 20 Event
Description:
ES Train B Actuation Failure Time I
Position I Applicants Actions or Behavior Critical Task actions on next URO CRS CRS URO/ARO Initiate Rule 3. Either ARO or URO can perform Rule 3.
IAAT MFW flow is excessive and Reactor is shutdown, then:
0 VERIFY FW Flow is controlled by ICs.
0 ADJUST M W Pumps and MI regulating valves to control OTSG level and valve DP.
IAAT Primary to Secondary Heat Transfers excessive and Reactor is shutdown, then:
0 PERFORM Phase 1 Isolation of the affected OTSG(s).
0 VERIFY OTSG level and pressure stabilizes.
PERFORM Phase 2 Isolation of the affected OTSG(s).
VERIFY steam leak is not in R6 or Intermediate Building.
0 INITIATE Guide 12, RCS stabilization following OTSG Isolation.
Initiate Guide 9, Inventory Control.
EXAMINERS NOTE:
Rule 3 and Guide 9 can be performed together.
EXAMINERS NOTE:
Event 8 will occur shortly after initiation of Guide 9.
Appendix D Operator Action Form ES-D-2 I
i Op Test No.:
1 Scenario#
2 Event#
8 Page 18 of 20 L-Event
Description:
ES Train B Actuation Failure Time I
Position I
Applicant's Actions or Behavior Critical Task UROIARO EXAMINER'S NOTE:
~
~
Phase 1 Isolation OTSG A MS-V-1A MS-V-1 B MS-V-16A FW-V-1 7A FW-V-SA FW-V-92A M S-V-3D MS-V-3E MS-V-3F MS-V-4A FW-V-85A Phase 2 Isolation OTSG A EF-V-30A EF-V-30 D MS-V-2A IF OTSG pressure DEFEAT HSPS LO-LO Pressure MFW Isolation.
750 psig and can be controlled, then Based on the size of the overcooling Event 8 should occur here. 6 side HPI will not AUTO initiate.
Critical I URO Task Manually initiate B side HPI by depressing 160W manual push button.
UROIARO I---'
ADJUST OTSG pressure so that secondary TsAT is lower than RCS cold leg temperature.
Appendix D Operator Action F O I ~ ES-D-2 Op Test No.:
1 Scenario#
2 Event#
8 Page of 20 Event
Description:
ES Train B Actuation Failure Time I
Position I
Applicant's Actions or Behavior Critical Task
~
URO U ROIARO CRSIURO CRSIURO CRSIURO URO UROIARO UROIARO UROIARO URO
~
~
~
~
~
0 0
Verify SCM <250 "F 0
Verify at least one CRP is operating 0
When incore temperature is reducing and RCS e25 'F superheat and either of the following conditions exists:
0 SCM >25 'F 0
Verify MU Pump flows 5515 GPMlpump LPI 4250 gpm in each line then HPI may be throttled to e500 gpmlpump by manipulating MU-V-IGA, 6, C, D.
ADJUST OTSG pressure to stabilize RCS temperature.
REVIEW PTS Rule 6.
REVIEW Dry OTSG Guide 13.
REVIEW TSDT Limit Guide 14.
ENSURE announcement of reactor trip over the plant page and radio.
VERIFY at least one OTSG has stable pressure with level present.
ENSURE RCS temperature reduction has been terminated.
VERIFY primary to secondary heat transfer is being established.
VERIFY RCS Tcold > 525°F.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
2 Event#
8 Page 20 of 20 Event
Description:
ES Train B Actuation Failure Time I
Position I Applicant's Actions or Behavior EXAMINER'S NOTE:
Emergency Boration may be required based on TIC.
I I
CRS I ENSURE performance of an alarm review.
I I
CRS I REQUEST SM evaluate Emergency Action Levels (EALs).
CRS I VERIFY OTSG B is providing sufficient steam for Gland Steam.
CRS I VERIFY OTSG tube lealdrupture symptoms do not exist.
CRS I VERIFY RCS Tcold > 400°F.
CRS VERIFY RB Pressure 2 psig.
CRS VERIFY 30 psig RBI is RESET.
I CRS
~
1 INITIATE Attachment 1 CRS I Go to OP-TM-EOP-001, VSSV I The Lead Examiner can terminate the scenario.
I Appendix D Scenario Outline Form ES-D-1 1 Facility:
Three Mile Island Scenario No.:
3 OpTest No.:
NRC Examiners:
Operators:
Initial Conditions:
Reactor 5%. Plant startup in progress, MOC.
0 AH-E-1A tagged 00s.
0 ICs in Manual control due to startup operations.
0 CRD Aux Programmer out of service for maintenance Turnover:
Continue with plant startup Critical Tasks:
Initiate Manual Reactor Trip Reduce RCS Subcooled Margin Malf.
Event NO/Type' Event No.
Event Description 1
I/O I ICRS I Pressurizer Level Controller Failure.
Override I I URO Manual reactor power increase.
2 3
Stuck control rod. (TS) 4 DH06A ITSCRS Core Flood Tank Nitrogen Leak. (TS) 5 FW15A 1 M CRS Loss of Main Feedwater.
6 RD28 I CCRS RPS Auto Trip Failure (ATWS).
TH15A I MCRS OTSG Tube Leak.
7 8
Override "O
I CCRS Emergency Feedwater Pumps Fail.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D NUREG 1021 Revision 9
I Appendix D Scenario Outline Form ES-D-1 1 THREE MILE ISLAND MAY 2005 NRC EXAM SIMULATOR SCENARIO #3 GENERAL DESCRIPTION The crew will take the watch with reactor power at 5% power during plant startup. ICs is in manual due to startup operations.
When ready, the Lead Evaluator can cue initiation of the Pressurizer level controller malfunction. The crew will respond to MAP D-3-2, MRI TANK LEVEL HIILO, or indication of zero RCS makeup flow with lowering Pressurizer level. The team can implement any one of three following procedures to respond to the malfunction by establishing manual control of makeup valve MU-V-17: 1203-15, LOSS OF RCS MAKEUPISEAL INJECTION, OP-TM-211472.
MANUAL PRESSURIZER LEVEL CONTROL, or OP-TM-EOP-010, Guide 9, RCS INVENTORY CONTROL.
Diagnosis of the malfunction is not required to proceed with the scenario if manual control of MU-V-17 is established to control Pressurizer level. If diagnosed, An EQUIPMENT DEFICIENCY TAG should be applied to the MU-V-17 controller, but logging and documentation of configuration control procedures is NOT required to continue with the scenario.
On cue from the Lead Evaluator, the crew will be contacted by the Shift Operations Supervisor to begin raising reactor power from 5%. The crew will continue startup in accordance with 1102-1, Plant Startup, and 1102-4, Power Operations. The reactor power increase will be accomplished manually due to the low power condition.
When power is greater than 7%, the Lead Evaluator can cue initiation of the stuck control rod. If not diagnosed earlier, the crew should respond to alarm G-2-1, CRD PATERN ASYMMETRIC, in accordance with OP-TM-MAP-GO201 and/or indications of a stuck or asymmetric rod as described in 1202-8, CRD EQUIPMENT FAILURE symptoms. The team should implement 1202-8 immediate manual actions to determine the rod is stuck. The SRO should determine that TS 3.5.2.2.b is applicable, requiring verification of one percent delta WK shutdown margin, and exercising the remaining regulating and safety rods to verify operability. The SRO should recognize if the stuck rod becomes asymmetric reactor power will be restricted to 60% of the thermal power allowable based on RCP operating configuration.
v On cue from the Lead Evaluator, the Core Flood Tank nitrogen leak will begin to reduce CF-T-1A pressure. The crew should respond to alarm D-2-7, CF TANK 1A LEVEUPRESS HVLO. The SRO should review TS 3.3.1.2.a to determine tank pressure is lower than the Tech Spec LCO limit, and TS 3.0.1 is applicable. Tank pressure is not required to be restored to normal to proceed with the scenario.
After the SRO has reviewed the TS for Core Flood Tank pressure, the Lead Evaluator can cue the Main Feedwater Pump failure coupled with initiation of an OTSG tube leak. The crew should recognize the reactor should have tripped (ATWS) and initiate a manual reactor trip in accordance with OP-TM-EOP-001, REACTOR TRIP. Following completion of the immediate actions, the team should diagnose the existence of the OTSG Tube leak, and the SRO should make the transition to OP-TM-EOP-005, OTSG TUBE LEAKAGE.
Coincident with the Feedwater Pump trip Emergency Feedwater Pumps EF-P-2A and EF-P-2B will fail to automatically start. The crew should enter OP-TM-EOP-005, OTSG TUBE LEAKAGE, and, among other actions, perform the following high level activities: Manually start EF-P-2A and EF-P-2B, reduce RCS pressure to minimize RCS subcooled margin, and begin RCS Cooldown to Cold Shutdown.
The Lead Evaluator can terminate the scenario when all high level activities have been completed and the evaluators agree the crew can be properly evaluated.
Appendix D NUREG 1021 Revision 9
Simulator Scenario #3 Event Procedure Support MAP D-3-2, M/U Tank Level Hi/Lo.
Description Pressurizer level controller failure.
I
~~
1203-1 5, Loss of RCS MakeupiSeal Injection.
OP-TM-211-472, Manual Pressurizer Level Control.
OP-TM-621-471, ICs Manual Control.
OP-TM-622-471, Manual Control Rod Operations.
OP-TM-MAP-G0201, CRD Pattern Asymmetric.
2 Manual power increase 3
Stuck Control Rod. (TS) 1202-8, CRD Equipment Failure.
TS 3.5.2 Control Rod Group and Power Distribution Limits.
TS 4.7 Reactor Control Rod Tests.
OP-TM-MAP-D0207, CF Tnk 1A LeveVPress Hi/Lo.
4 Core Flood Tank nitrogen leak.
(TS)
TS 3.3.1.2 Core Flooding System.
OP-TM-EOP-001, Reactor Trip.
Loss of Main Feedwater.
OP-TM-EOP-010, Emergency Procedure Rules, Guides and Graphs.
6 OP-TM-EOP-001, Reactor Trip.
OP-TM-EOP-01 0, Emergency Procedure Rules, Guides and Graphs.
~~~
OTSG tube leak.
~
OP-TM-EOP-005, OTSG Tube Leakage.
OP-TM-EOP-01 0, Emergency procedure Rules, Guides and Graphs.
Emergency Feedwater Pump failure.
OP-TM-EOP-010 Guide 16.2, Failure of E F-P-2A or E F-P-2 B.
Appendix D NUREG 1021 Revision 9
NRC Scenario 3 Setup Page I
1 COMMENTS / INSTRUCTIONS I
DESCRIPTION ACTION I
Initialization IC-5% Power EOC Set letdown flow at 75 gpm IAW OP-TM-211-1 102-2 44 1 INFO Tag Diamond Control Panel 00s for maintenance Ensure continuous bleed path Maintain PZR level Ensure MF-P-1NB Placing letdown per Enclosure 2 of INFO Tag stating Aux Programmer Lineup bleed path to B RCBT Setting PZR level per Enclosure 2 of Verifv DP within range IAW OP-TM-2 1 1 -472 1 1 02-2 delta p 60-90 psig OVERRIDE IO 02A5A06 - ZAl RCLl C Malfunction RD0254 Malfunction DHO6A Malfunction FW15A v
Malfunction RD28 Malfunction TH15A Remote Function FWR 71 OVERRIDE LO ZLOEFP2A Test - ON 08A7DS01-Value:
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.01 Event 1 Insert Event 3 Insert SEV.
Event 4 Insert Event 5 Insert 3
IMMEDIATELY Insert SEV. 0.48%
Event 7 Ramp 300 secs Defeat Insert immediately ON Insert immediately XENON Free EOC Scenario setup Scenario Support Scenario setup Scenario setup Scenario setup Pressurizer Level Control Failure Stuck Rod Group 7 Core Flood Tank ?A Nitrogen Leak FWA-1A Trip RPS AUTO Trip Failure OTSG Tube Leak 40 gpm EFP-2A, EFP-2B Test Failure Failure of EF-P-A and B to start Appendix D NUREG 1021 Revision 9
Appendix D Operator Action Form ES-D-2 CRS Op Test No.:
1 Scenario#
3 Event#
1 Page 5 of 16 Direct entry into 1203-15.
Event
Description:
Pressurizer Level Controller Failure Time I
Position I Applicant's Actions or Behavior I FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 1.
I 1
URO 1 ManualAction I
0 Determine cause for loss of R.C. Makeup/Seal Injection MU-VI7 closed. (Zero flow on MU24FI with MU-PIB operating.)
I URO - 1 I
I URO I Action for makeup Pump Operating and MU-V17 failed closed. I 0
Shift MU-V17 MU flow control station to manual and restore pressurizer level.
I EXAMINER'S NOTE:
Crew may elect to enter OP-TM-211472.
I Go to Event 2
Appendix D Operator Action Form ES-D-2 I
1 CRS Page Of "I Op Test No.:
1 Scenario#
3 Event#
2 Event
Description:
Dropped Control Rod (TS)
Directs crew to raise power per 1102-2 Plant Start-up.
I Time I
Position I Applicant's Actions or Behavior I
FLOOR OPERATOR:
When directed by Lead Examiner, instruct crew to perform power increase at 20% per hour.
EXAMINER'S NOTE:
When Rod Group 7 is controlling and reactor power greater than the 7% FWP trip setpoint enter Event 3.
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario #
3 Event#
3 Page 7 of 16 Event
Description:
Stuck Control Rod (TS)
Time I
Position I Applicant's Actions or Behavior I FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 3.
I 1
CRS Directs entry to OP-TM-MAP-G0201, CRD Pattern Asymmetric.
Manual Actions Required.
If any rod is more than 7" from its Group Average Position, then GO TO 1202-8, CRD Equipment Malfunction.
EXAMINER'S NOTE: Based on indication, crew may elect to got 1202-8, Section A - Asymmetric Rod. Step 4.i directs crew to Section C - Stuck Rod.
Directs entry to 1202-8, CRD Equipment Failure. Section C Stuck Rod Direct Manual Actions CAUTION:
Only RUN speed should be used when attempting to move F
a stuck rod-This will minimize the possibility of overstressing the control rod assembly.
CRS Place the Diamond Rod Control Panel in manual IAW OP-TM-621-471. Attempt to first insert the rod a short distance and then attempt to withdraw it a short distance.
FLOOR OPERATOR: Enter Event 4 after the Diamond Rod Control Panel is placed in manual.
CRS Review if there is more than one inoperable rod as defined in Specification 4.7.1.2 and 4.7.1.3 in the safety or regulating rod banks then commence a reactor shutdown and be in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (T.S. 3.5.2.2.a).
Appendix D Operator Action Form ES-D-2 Op Test No.:
1 Scenario#
3 Event#
3 Page 8 of 16 Event
Description:
Stuck Control Rod (TS)
I Time I
Position I Applicants Actions or Behavior 1
Appendix D Operator Act ion Form ES-D-2 CRS Op Test No.:
1 Scenario#
3 Event#
4 Page 9 of 16 Event
Description:
Core Flood Tank Nitrogen Leak (TS)
Time I
Position I
Applicant's Actions or Behavior Two (2) core flooding tanks (CFTs) each containing 940 f 30 ft3 of borated water at 600 k25 psig shall be available.
Specification 3.0.1 applies.
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FLOOR OPERATOR:
Event 4 was entered during Event 3.
Directs entry to OP-TM-MAP-D0207, CF TNK 1A LeveVPress I
CRS I HI/LO.
EXAMINER'S NOTE:
@ 90% YALF Severity CFT PZR reduces 5 1.2 psi per min.
CRS Manual Actions Required:
I 0 MONITOR PPC Area 5 Group 26 for CF-Tank's para meters.
I 0 ADJUST level and/or pressure as required IAW OP-TM-213 series procedures.
0 If either CFT pressure indication is outside of 585 to 61 5 psig or level indication is outside of 1 1.29 to 1 1.87 ft and Reactor is critical, then REFER Tech. Spec. 3.3.1.2.a Action Statement.
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CRS Review Core Flooding System Go to Event 5/6
Appendix D Operator Action Form ES-D-2 Critical Task Op Test No.:
1 Scenario#
3 Event#
5 Page 10 of 16 Event
Description:
Loss of Main Feedwater Time I
Position I Applicant's Actions or Behavior TRIP the Reactor by depressing the "Reactor Trip" and "DSS" URo pushbuttons.
FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 5.
URo I
CRS I Directs entry to OP-TM-EOP-001, Reactor Trip.
IAAT a symptom exists, then immediately treat the symptom using the following priority:
I I
URO I VERIFY the reactor is shutdown.
I I
URO I TRIP the Turbine.
I I
URO I VERIFY the turbine stop valves are closed.
I I
- 11. SCMc25"F GO TO OP-TM-EOP-002
- 2. XHT GO TO OP-TM-EOP-003.
- 3. LOHT GO TO OP-TM-EOP-004.
- 4. OTSG tube leakage > 1 gpm GO TO OP-TM-EOP-005.
Go to Event 6 I
I I
Appendix D Operator Action Form ES-D-2 CRS I OpTest No.:
I Scenario #
3 Event#
6 Page 11 of 16 I Directs crew to OP-TM-EOP-010, Guide 15 - EFW Actuation Response.
Event
Description:
Time I
Position I
Applicant's Actions or Behavior I FLOOR OPERATOR:
Event 6 is triggered from Event 5.
URO I
URO EFW is actuation is required, then:
ENSURE EF-P-1, EF-P-2A, and EF-P-2B start
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0 DISPATCH an Auxiliary Operator (AO) to EF-V-30 area.
0 If ERN pump disch. Pressure OTSG pressure, then INITIATE Guide 16.
IAAT OTSG pressure is more than 100 psig below desired, then THROTTLE EFW flow if permitted by Rule 4.
ENSURE EF-V30ND and EF-V-30BK control OTSG level at setpoint (Rule 4).
IAAT an EFW failure occurs then initiate Guide 16 - EFW Failure 0
Initiates Guide 16.2 for EF-P-2A or EF-P-2B failure Verify voltage available on the associated bus Verify control power is available as indicated by the green indicator light at the control switch.
Obtain CRS concurrence immediately prior to initiating flow.
Appendix D Operator Action Form ES-D-2 URo Op Test No.:
1 Scenario#
3 Event#
6 Page 12 of 16 Obtain CRS concurrence and ensure ERN actuation enable-defeat switches (8) are in DEFEAT.
Event
Description:
Time I Position I Applicant's Actions or Behavior URO
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Starts EF-P-2A and EF-P-2B I
I 1 Go to Event 7
Appendix D Operator Action Form ES-D-2 L.
Op Test No.:
1 Scenario#
3 Event#
7 & 8 Page 13 of 16 Event
Description:
OTSG Tube Leak, Motor Driven Emergency Feedwater Pumps Fail Time I
Position I
Applicant's Actions or Behavior I FLOOR OPERATOR:
When directed by Lead Examiner, enter Event 7 CRS CRS Requests symptom check.
DETERMINE the affected OTSG as follows:
0 Request OTSG Steam line samples.
I I
URO I Performs symptom check.
CRS 1
CRS I Directs entry to OP-TM-EOP-005, OTSG Tube Leakage.
0 Observe OTSG levels and feed rates.
INITIATE Attachment 2.
1 CRS I NOTIFY RAC to begin offsite dose assessment.
I URO I INITIATE Guide 9, "RCS Inventory Control.
I CRS I VERIFY the reactor is critical.
v CRS GO TO Step 3.4.
CRS NOTIFY SM to evaluate Emergency Action Levels (EALs).
I I
1 0 Request Steam line Radiation Surveys.
Appendix D Operator Action FOIWI ES-D-2 Op Test No.:
1 Scenario#
3 Event#
7 & 8 Page 14 of 16 Event
Description:
OTSG Tube Leak, Motor Driven Emergency Feedwater Pumps Fail Time I
Position I
Applicant's Actions or Behavior CRS/URO I
IAAT OTSG pressure is approaching or is greater than 1000 psig, then ENSURE MS-V-2A(B) is open and OPEN TBVs or ADVs to maintain OTSG pressure 1000 psig.
CRSNRO 1 IAAT Aux. Steam is available, then URo CRS
- 1. OPEN AS-V-8 (TB 355' south of 6' stage drain collection 1
tank).
IAAT level is rising due to tube leakage in an available OTSG, then preferentially STEAM to maintain OTSG level 85%.
Review IAAT Step 3.16 and Step 3.17.
- 12. CLOSEGS-V-4.
And transfer operating FWPs to Aux Steam.
SLOWLY OPEN AS-V-5A.
SLOWLY OPEN AS-V-5B.
CRS I VERIFY the reactor is critical.
CRS I GO TO Step 3.10.
URO 1 PERFORM a SYMPTOM CHECK.
ENSURE announcement of reactor trip over the plant page and URo 1 radio.
URO I DISPATCH an Operator to check MSSV status.
CRS I ENSURE performance of an alarm review.
Appendix D Operator Action Form ES-D-2 I
I URO 1
Scenario #
3 Event#
7 & 8 Page 15 I OpTestNo.: -
Examiner Note: The critical task is to perform the Guide 8 steps and reduce RCS pressure to maintain SCM 230 F 570 O F.
IAAT EF-P-2A or EF-P-2B are running, then:
0 PLACE both trains of each EFW actuation in DEFEAT (eight switches).
I I Event
Description:
OTSG Tube Leak, Motor Driven Emergency Feedwater Pumps Fail I
Time I
Position I
Applicants Actions or Behavior I
Critical Task Directs entry to OP-TM-EOP-010, Guide 8, RCS Pressure Control CRS I URO INITIATE Guide 8 to MINIMIZE SCM 0
ENSURE HPI is throttled per (Rule 2) and control RCS inventory.
URO 1
URO I
0 VERIFY RCS temperature is stable or decreasing.
0 IF pressurizer steam bubble is controlling RCS pressure, then ENSURE Pressurizer Heaters are OFF URO I URO 0
VERIFY an RCP is operating.
URO ENSURE RC-V-3 is open.
URO I
0 OPEN RC-V-1 When RCS Pressure is in the desired range, then URo I
CLOSE RC-V-1.
I CLOSE MS-V-13A and MS-V-13B.
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I URO I IAAT of the following exist:
Op Test No.:
I Scenario #
3 Event#
7 8 8 Page 16 of 16 Event
Description:
OTSG Tube Leak, Motor Driven Emergency Feedwater Pumps Fail Time I
Position I Applicants Actions or Behavior I
RCS pressure -C 1750 psig 0
Then BYPASS ESAS (HPI Actuation).
RCS pressure is being controlled IAAT RM-A-? high alarm or 4 psig ESFAS have actuated, then INITIATE OP-TM-826-901, Control Building Ventilation System Radiological Event Operations.
URO 1
URO I INITIATE Emergency Boration IAW Rule 5.
When SCM has been minimized, then INITIATE plant cooldown I
URo I IAW 11 02-1 1.
EXAMINERS NOTE:
The Lead Evaluator can terminate the scenario at any time after SCM is minimized.