ML101270196
| ML101270196 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/08/2010 |
| From: | NRC Region 4 |
| To: | |
| References | |
| 50-313/10-03, 50-368/10-03 | |
| Download: ML101270196 (30) | |
Text
ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ____ANO-1_________________
Date of Examination: __3-8-2010__
Examination Level: RO X SRO Operating Test Number: _2010-1_
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations A1. 2.1.25 (Imp 3.9)
N/R A1JPM-NRC-ADMINCURV Ability to interrupt Rod insertion limits per COLR for operability Conduct of Operations A2. 2.1.19 (Imp 3.9)
D/P/S A1JPM-NRC-ADMINPMS3 Ability to use plant computer to enable CRD temperature point alarms Equipment Control A3. 2.2.12 (Imp 3.7)
N/R A1JPM-NRC-ADMINSURV5 Identify errors in a completed surveillance for the A RB Spray Pump P35-A Radiation Control A4. 2.3.7 (Imp 3.6)
N/R A1JPM-NRC-ADMINRWP1 Locate various dose-reduction items in a radiation work permit for a pre-job brief Emergency Procedures/Plan A5.
N/A N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Page 1 of 2 ES-301 Control Room/In-Plant Systems Outline Revision 1 Form ES-301-2 Facility: ____ANO-1 Date of Examination: __3-8-2010_
Exam Level: RO X SRO-I SRO-U Operating Test No.: __2010-1____
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
A1JPM-RO-EOP26 Emergency Boration 024 AK3.01 (RO 4.1/SRO 4.4)
N/E/A/S 1
Reactivity Control
- b.
A1JPM-RO-EOP25 Start Standby HPI pump after OP HPI trip 006 A4.02 (RO 4.0/SRO 3.8)
N/EN/A/S 2
Reactor Coolant System Inventory Control
- c.
A1JPM-RO-LTOP1 Establish LTOP Protection during cool down of the RCS 006 A4.11 (RO 4.2/SRO 4.3)
M/A/L/S 3
Reactor Pressure Control
- d.
A1JPM-RO-HYD04, Initiate RB Hydrogen Sampling B&W E14 EA1.1 (RO 3.8/SRO 3.6)
C/D/EN/P/S 5
Containment Integrity
- e.
A1JPM-RO-EOP23 Re-energize A1, A2, H1, and H2 during Degraded power 062 A2.05 (RO 2.9/SRO 3.3)
A/D/P/S 6
Electrical
- f.
A1-JPM-RO-ARM01, Respond to Area Radiation Monitor alarm 072 A4.01 (RO 3.0/SRO 3.3)
C/D/S 7
Instrumentation
Page 2 of 2
- g.
A1JPM-RO-AOP28 Respond to lo-lo Instrument Air pressure 065 AK3.08 (RO 3.7/SRO 3.9)
D/S 8
Plant Service Systems
- h.
A1JPM-RO-AOP19 Loss of Decay Heat Removal 025 AA1.02 (RO 3.8/SRO 3.9)
D/L/S 4
Heat Removal From Reactor Core (Primary)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
A1JPM-RO-EFW01 Reset EFW pump after over speed trip 061 A2.04 (RO 3.4/SRO 3.8)
D/E/R/EN 4
Heat Removal From Reactor Core (Secondary)
- j.
A1JPM-RO-EDO30, Place battery charger D-03B in service.
2.1.30 (RO 4.4/SRO 4.0)
D/A/EN 6
Electrical
- k.
A1JPM-RO-LRW01 Liquid Radiation waste release 2.3.11 (RO 3.8/SRO 4.3)
N/A/R 9
Radioactivity Release All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Administrative Topics Outline Revision 0 Form ES-301-1 Facility: ____ANO-1_________________
Date of Examination: __3-8-2010__
Examination Level: RO SRO X Operating Test Number: _2010-1_
Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations A1. 2.1.23 (Imp 4.3)
N/R A1JPM-NRC-ADMINSFPMU1 Review spent fuel pool makeup calculation Conduct of Operations A2. 2.1.34 (Imp 3.5)
D/P/R A1JPM-NRC-ADMINCHEM1 Review secondary chemistry package for out of specification feedwater chlorides and respond Equipment Control A3. 2.2.12 (Imp 3.7)
N/R A1JPM-NRC-ADMINSURV6 Identify errors in a completed surveillance for the A RB Spray Pump P35-A; determine operability Radiation Control A4. 2.3.7 (Imp 3.6)
N/R A1JPM-NRC-ADMINRWP1 Determine stay time in T-36 valve gallery using RWP information Emergency Procedures/Plan A5. 2.4.41 (Imp 4.6)
N/S A1JPM-NRC-ADMINEAL14 Determine Emergency Action level NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Page 1 of 2 ES-301 Control Room/In-Plant Systems Outline Revision 1 Form ES-301-2 Facility: ____ANO-1 Date of Examination: __3-8-2010_
Exam Level: RO SRO-I X SRO-U Operating Test No.: __2010-1____
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a.
A1JPM-RO-EOP26 Emergency Boration 024 AK3.01 (RO 4.1/SRO 4.4)
N/E/A/S 1
Reactivity Control
- b.
A1JPM-RO-EOP25 Start Standby HPI pump after OP HPI trip 006 A4.02 (RO 4.0/SRO 3.8)
N/EN/A/S 2
Reactor Coolant System Inventory Control
- c.
A1JPM-RO-LTOP1 Establish LTOP Protection during cool down of the RCS 006 A4.11 (RO 4.2/SRO 4.3)
M/A/L/S 3
Reactor Pressure Control
- d.
A1JPM-RO-HYD04, Initiate RB Hydrogen Sampling B&W E14 EA1.1 (RO 3.8/SRO 3.6)
C/D/EN/P/S 5
Containment Integrity
- e.
A1JPM-RO-EOP23 Re-energize A1, A2, H1, and H2 during Degraded power 062 A2.05 (RO 2.9/SRO 3.3)
A/D/P/S 6
Electrical
- f.
A1-JPM-RO-ARM01, Respond to Area Rad Monitor alarm 072 A4.01 (RO 3.0/SRO 3.3)
C/D/S 7
Instrumentation
- g.
A1JPM-RO-AOP28 Respond to lo-lo Instrument Air pressure 065 AK3.08 (RO 3.7/SRO 3.9)
D/S 8
Plant Service Systems
Page 2 of 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
A1JPM-RO-EFW01 Reset EFW pump after over speed trip 061 A2.04 (RO 3.4/SRO 3.8)
D/E/R/EN 4
Heat Removal From Reactor Core (Secondary)
- j.
A1JPM-RO-EDO30, Place battery charger D-03B in service.
2.1.30 (RO 4.4/SRO 4.0)
D/A/EN 6
Electrical
- k.
A1JPM-RO-LRW01 Liquid Radiation waste release 2.3.11 (RO 3.8/SRO 4.3)
N/A/R 9
Radioactivity Release All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Page 1 of 2 ES-301 Control Room/In-Plant Systems Outline Revision 1 Form ES-301-2 Facility: ____ANO-1 Date of Examination: __3-8-2010_
Exam Level: RO SRO-I SRO-U X Operating Test No.: __2010-1____
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- b.
A1JPM-RO-EOP25 Start Standby HPI pump after OP HPI trip 006 A4.02 (RO 4.0/SRO 3.8)
N/EN/A/S 2
Reactor Coolant System Inventory Control
- c.
A1JPM-RO-LTOP1 Establish LTOP Protection during cool down of the RCS 006 A4.11 (RO 4.2/SRO 4.3)
M/A/L/S 3
Reactor Pressure Control
- d.
A1JPM-RO-HYD04, Initiate RB Hydrogen Sampling B&W E14 EA1.1 (RO 3.8/SRO 3.6)
C/D/EN/P/S 5
Containment Integrity In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
A1JPM-RO-EFW01 Reset EFW pump after over speed trip 061 A2.04 (RO 3.4/SRO 3.8)
D/E/R/EN 4
Heat Removal From Reactor Core (Secondary)
- j.
A1JPM-RO-EDO30, Place battery charger D-03B in service.
2.1.30 (RO 4.4/SRO 4.0)
D/A/EN 6
Electrical All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Page 2 of 2
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
Simulator Scenario Scenario I
Appendix D Scenario Outline Form ES-D-1 Facility:
ANO-1 Scenario No.: 1-RI Op-Test No.: 2010-I Examiners:
Operators:
Initial Conditions:
Recall 30% IC C28A IA compressor is out of service for overhaul.
EFIC failed (IMF FW621)
A1/2 and H1/2 powered from Unit Aux transformer Caution tag P26B, P27B, P28B, B MFP turning gear Turnover:
30% Power (Power reduced for TV/GV testing)
Rod index 180% with equilibrium Xenon RCS boron 68Oppm A MFP I/S B MFP repairs in progress C28A IA compressor is out of service for overhaul.
Perform add N2 to B CFT to 585# +1-3# per 1104.001 step 11.0.
Escalate power to 35% following N2 add and hold till B MFP available per 1102.004 Power Operations step 7.5. (Procedure in progress)
Event MaIf. No.
Event Event No.
Type*
Description 1
N/A N-(SRO)
Add N2 to B CFT to raise pressure to 585#
N-(BOP)
Following N2 add commence raising power to 35%
A RCS Pressure transmitter PT-i 021 fails LO (TS)
I-(SRO)
C-(SRO) 4 SW121 SW pump bearing heatup and trip C-(BOP)
DO_K2AA 5
DO_K2AW C-(SRO)
A MFP oil reservoir leak K06F2 6
FW074 C-(ALL)
A MFP loss of LO and trip CONTINUED Page 1
of 14
Appendix D Scenario Outline Form ES-D-1 Facility:
ANO-1 Scenario No.: 1-Ri Op-Test No.: 201 0-1 Initial Conditions Continued 7
FW621 C-(ATC)
EFIC fails to actuate (TS) (ATC-CT)
C-(SRO) 8 N/A M-(ALL)
RX trip 9
M5134 M-ALL B SG steam leak in pent house down stream of the MSIV (ATC-CT) (CBO-CT)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 2
of 14
Appendix D Scenario Outline Form ES-D-1 Scenario #1-RI Objectives 1)
Evaluate individual ability to per 1104.001 step 11.0 for adding N2tothe CFT.
2)
Evaluate individual ability to raise RX power with ICS in automatic.
3)
Evaluate individual ability to recognize and respond to A RCS Pressure transmitter PT-i 021 fails LO.
4)
Evaluate individual ability to recognize and respond to a SW pump bearing heatup and trip.
5)
Evaluate individual ability to swap operating SW pumps.
6)
Evaluate individual ability to recognize and respond to an oil leak from the A MFP oil reservoir.
7)
Evaluate individual ability to recognize and respond to the loss of all feedwater and the need to trip the reactor.
8)
Evaluate individual ability to recognize and respond to EFIC failing to actuate EFW.
9)
Evaluate individual ability to recognize and respond to a main steam line rupture up stream of the MSIV and outside the reactor building.
Page 3
of 14
Appendix D Scenario Outline Form ES-D-I SCENARIO #1-RI NARRATIVE The crew will assume responsibility for the plant at 30% power. Power is low following TV/GV testing and awaiting thrust bearing repairs to the B MFP. The MFP is expected back later today. The plant has been at 30% for 2 days and xenon is at equilibrium. C28A IA compressor is OOS for motor cleaning and is not expected back till 8pm today.
The crew will be allowed to brief adding N2 to the B CFT and raising power to -35% prior to entering the control room. Power Operations procedure will be in progress and provided to the crew as well as a RHOBAL. Rx engineering direction is to use group 7 rods to raise power.
The CRS will direct adding N2 to the B CFT as soon as they have responsibility for the plant.
The CBO will perform 1104.001 Core Flood System Operating Procedure to raise CFT pressure 10 psig.
As soon as the CFT pressure is raised the CRS should direct the power escalation. The ATC will use the ULD and raise to 315 Mwe at <35%/Hr.
At -35% power controlling RCS pressure transmitter PT-i 021 will fail low resulting in a SASS mismatch and RCS low pressure alarms. All PZR heaters will fail on and the Spray Valve will remain closed. The CRS will use 1203.012H for SASS Mismatch and direct the Y instrument be selected for control. (TS)
(TS) LCO 3.3.I.A Four channels of RPS instrumentation for each Function in Table 3.3.1-I shall be OPERABLE.
The A SW pump bearing will overheat bring in K10-C4 SW PUMP MTR WDG TEMP HI. The CRS will enter 1203.0121 ANNUNCIATOR K10 CORRECTIVE ACTION and direct starting the B SW pump. The A SW pump may trip before the standby pump is started.
The A MFP lube oil system will develop a leak on the common pump discharge piping. Alarm K06-F2 T34 A/B LEVEL HI/LO will occur and the CRS should reference 1202.012E ANNUNCIATOR K06 CORRECTIVE ACTION. The AC will report the leak is quite large. The pump will trip 5 minutes after the initial alarm on loss of LO. The crew may elect to manually trip the RX and the MFP.
After the RX trip the crew should recognize EFIC failure to actuate EFW upon the second MFP trip. The ATC should manually actuate EFW (ATC-CT) (TS).
(CT-EFW should be actuated before RCS Thot reaches 580°F)
A main steam line leak will occur in the pent house upstream of the MSIV. The CRS should direct operation per the overcooling EOP. The crew should manually actuate MSLI to stop the overcooling. (ANY-CT)
(CT-MSLI should be actuated before RCS temperature reaches 430°F)
Page 4 of 14
Appendix D Scenario Outline Form ES-D-1 (TS) LCO 3.3.13 Trains A and B of each Logic Function shown below shalt be OPERABLE:
- a. Main Steam Line Isolation; and
(TS) LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable.
EAL 3.1 Uncontrolled OTSG Depressurization Resulting in MSLI Actuation The scenario can be terminated when RCS pressure and temperature are stabilized.
Page 5
of 14
Simulator Scenario Scenario 2
Appendix D Scenario Outline Form ES-D-1 Facility:
ANO-1 Scenario No.: 2-RI Op-Test No.: 2010-1 Examiners:
Operators:
Initial Conditions:
Recall 80% IC C28A IA compressor is out of service for overhaul.
A1/2 and H1/2 powered from Unit Aux transformer C03 Rx trip P/B is failed P7B fails to auto start EFW Flow control valve CV-2645 failed open Turnover:
80% Power due to grid disturbances C28A IA compressor is out of service for overhaul.
Engineering requests operations perform Generator Ground Test per Power Operations 1104.002 step 8.11 Zinc injection system is secured j Event Maif. No.
(
Event Event L No.
1.
Type]
Description 1
N/A N-(SRO)
Perform Generator Field Ground test N-(BOP) 2 CO_264A C-(SRO)
Generator Field Ground alarm K04C6 C-(BOP)
B5148 R-(ATC)
Loss of 500Kv line and Dispatcher directs power B5122 N-(SRO) reduction to 600Mw net 4
CO C5A C-(BOP)
C5A Vacuum Pump Trip C-(SRO) 5 TR592 l-(SRO)
A EFIC pressure transmitter for A SG fails low. (TS) l-(ATC)
K02C4 Hi neg seq alarm 6
CO_P32A C-(ALL)
A RCP Trip RC466 M-(ALL)
Reverse Rotation Dl ICCOO2O Reactor Trip
C-(ATC)
Shunt trip P/B (TS) (ATC-CT) 8 N/A Manual feed of A SG (ATC-CT) 9 N/A Natural Circulation Cooling (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1
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Appendix D Scenario Outline Form ES-D-1 Scenario #2-RI Objectives 1)
Evaluate individual ability to perform Generator Ground Test per Power Operations 1104.002 step 8.11 2)
Evaluate individual ability to recognize and respond to Generator Field Ground alarm.
3)
Evaluate individual ability to perform a controlled power reduction.
4)
Evaluate individual ability to recognize and respond to a condenser vacuum pump trip.
5)
Evaluate individual ability to recognize and respond to a B EFIC level transmitter to A SG fails low.
6)
Evaluate individual ability to recognize and respond to an HI neg seq alarm and A RCP Trip.
7)
Evaluate individual ability to recognize and respond to and RCP reverse rotation.
8)
Evaluate individual ability to recognize the failure of the RX trip P/B.
9)
Evaluate individual ability to perform a manual RX trip.
10)
Evaluate individual ability to recognize the need to manually feed of A SG.
11)
Evaluate individual ability to perform a natural circulation cooling.
Page 2
of 14
Appendix D Scenario Outline Form ES-D-1 SCENARIO #2-RI NARRATIVE The crew will assume responsibility for the plant at 80% power due to dispatcher ordered power reduction as a result of grid disturbances caused by severe weather in Tennessee.
The crew will be allowed to brief performing a Generator Ground Test prior to entering the control room.
The CRS will direct the CBO to perform 1104.002 step 8.11 Generator Ground Test per the request of system engineering. The initial test will bring in a generator ground alarm and associated light on C02. The CRS will enter 1203.012 C Annunciator Corrective Actions for the ground alarm and direct the alarm be reset and a second test conducted. The second test will not produce an alarm. The crew will check for other ground indications and inform relay and Operations Manager of the alarm.
After the Generator Ground Test two switchyard breakers will open resulting in a loss of the Mablevale 500Kv line. The dispatcher should be called and he will direct a power reduction to 600Mw net in 10 minutes. Power should be lowered using the ULD in manual per 1203.045 Rapid Plant Shutdown. The crew may decide to leave the Heater Drain Pumps in service.
During the power reduction the operating condenser vacuum pump will trip due to a motor fault.
Vacuum will begin to lower. The CRS should enter 1203.012 Annunciator Corrective Actions for Vacuum Pump Trip and 1203.016 Loss of Condenser Vacuum AOP if vacuum continues to lower. The standby vacuum pump should be started and vacuum monitored for recovery. Plant power should be stabilized at 600Mwe or when vacuum recovers.
The A EFIC Pressure transmitter to A SG (PT-261 8A) will fail low resulting in a half trip of EFW and MSLI for the A SG. The crew should recognize the half trip is due to an instrument failure. The CRS should enter 1203.012D AANNUNCIATOR CORRECTIVE ACTiON for EFIC System Trouble.
(TS)
LCO 3.3.11 The EFIC System instrumentation channels for each Function in Table 3.3.11-1 shall be OPERABLE.
An alarm will be received on the Hi bus for Neg Seq Overvoltage. The CRS should direct operations per 1203.012B ANNUNCIATOR CORRECTIVE ACTION and direct an AO to the Hi bus. The AO will report RCP amps to the CRS and the crew should determine the need to secure the A RCP.
The A RCP will experience a reverse rotation as indicated on PMS. The CRS should direct operations per 1203.031 Reactor Coolant Pump and Motor Emergencies Reverse Rotation Section. The crew should trip the reactor the remaining running RCPs. The ATC should recognize a failure of the RX trip push button and trip the reactor using the shunt trip push buttons. The CRS will enter 1202.001 Reactor Trip EOP.
(CT-The reactor should be tripped within 3 minutes of tripping the RCP.)
(TS)
LCO 3.3.2.A The RPS Manual Reactor Trip Function shall be OPERABLE.
CONTINUED Page 3
of 14
Appendix 0 Scenario Outline Form ES-D-1 The ATC should use 1202.012 step 5 to control EFW system. The crew should recognize P7B failed to auto start and may start P7B. The EFW flow control valve for P7B to A SG CV-2646 will be Vector Closed as a result of the EFIC SC Pressure Instrument failure. CV-2645 P7A to A SG is failed open requiring the crew to manually control EFW flow to the A SC using CV-2646 in vector override or by throttling CV-2627 in manual.
(CT-Manual control of EFW should be taken before SG level reaches 410.)
The scenario is complete when the crew establishes natural circulation core cooling and stabilizes RCS temperature and pressure.
Page 4 of 14
Simulator Scenario Scenario 3
Appendix D Scenario Outline Form ES-D-1 Facility:
ANO-1 Scenario No.: 3-Ri Op-Test No.: 2010-1 Examiners:
Operators:
Initial Conditions:
Recall 100% IC C28A IA compressor is out of service for overhaul
- 1 EDG Normal Stop P/B is failed Turnover:
100% power C28A IA compressor is out of service for overhaul
- 1 EDG surveillance is in progress to the point of paralleling the EDG to A3. Perform 1104.036 Supp 1 step 2.13 F Event 1 MaIf. No.
Event 1
Event
[
No.
]____________
Type*
]
Description N(BOP)
Parallel #1 EDG to A3 using 1104.036 Supp I Step I
N/A N-(SRO) 2.13 DI DG1_GV-C-(BOP)
RA C(BOP) be tripped using by going to Lockout. (TS)
C-(SRO)
I-(ATC)
Controlling PZR level transmitter will fail low over I 3
TR149 minute requiring selection of the other instrument. (TS)
I-(SRO)
IA Leak will occur resulting in IA pressure lowering to 4
lAl7O R-(ATC) between 45# and 60# requiring a power reduction.
5 Delete 1A170 N-(SRO, At 70% the IA leak will be patched. IA pressure will ATC) recover and plant power should be stabilized.
RD304 Two group 7 rods will drop into the core requiring a 6
RD279 M-(ALL) manual reactor trip. (ATC-CT)
A loss of off site power will occur resulting in a 7
ED1 83 M-(ALL) degraded power condition with only A4 energized.
N-(BOP)
U2 will report the AAC Generator is available for loading to power the A3 bus. (CBO-CT) 8 & 9 N/A N-(SRO)
The WCO will report an oil leak on P7A EFW pump C-(ATC)
C-(SRO) and is expected to lose oil in 10 minutes.
(ATC-CT)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1
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Appendix D Scenario Outline Form ES-D-I Scenario #3-RI Objectives 1)
Evaluate individual ability to recognize and respond to #1 EDG picking up requiring the EDG to be tripped using by going to Lockout..
2)
Evaluate individual ability to recognize and respond to an IA Leak requiring a power reduction.
3)
Evaluate individual ability to stop the power reduction and stabilize the plant.
4)
Evaluate individual ability to recognize and respond to two group 7 rods dropping into the core requiring a manual reactor trip.
5)
Evaluate individual ability to recognize and respond to a loss of off site resulting in a degraded power condition with only A4 energized.
6)
Evaluate individual ability to recognize and respond to an oil leak on P7A EFW pump.
7)
Evaluate individual ability to parallel #1 EDG to the A# bus using 1104.036 Supplement 1.
8)
Evaluate individual ability to recognize and respond to input signal failures to the pressurizer level control system.
9)
Evaluate individual ability to perform a rapid power reduction in accordance with plant abnormal operating procedures.
10)
Evaluate individual ability to recognize and respond to abnormal conditions associated a loss of oil to P7A Turbine Driven EFW pump to regain power to A3 for P7B Motor Driven EFW pump.
11)
Evaluate individual ability to energize the vital A3 bus from the Alternate AC Generator.
12) valuate individual ability to start P7B EFW pump and secure P7A EFW pump.
Page 2
of 13
Appendix 0 Scenario Outline Form ES-D-I SCENARIO #3-RI NARRATIVE The crew will assume responsibility for the plant at 100% power and ICS in full automatic. No major plant equipment will be out of service. 1104.036 Supplement 1 EDG #1 monthly surveillance will be complete up to step 2.10. This step will parallel the EDG to the A3 bus. The CBO should conduct a short brief of this task and parallel the EDG to the bus. When the CBO adjusts the EDG governor to raise load the control switch will fail in the raise position resulting in the EDG continuously picking up load. The CBO should recognize the loss of control and trip the EDG before the EDG auto trips. The EDG can be stopped by either going to lockout or depressing the trip pushbutton. Technical Specification 3.8.1.B (One DG Inoperable) applies requiring the performance of SR 3.8.1.1 within I hour and entry into a 7 day time clock.
(TS) 3.8.1.B Two diesel generators (DGs) each capable of supplying one train of the onsite Class I E AC Electrical Power Distribution System.
The controlling pressurizer level transmitter will fail low over 1 minute. This will cause the pressurizer level control valve to travel full open resulting in actual pressurizer level rising and makeup tank level lowering. The crew should recognize the failure and enter 1203.015 Pressurizer Systems Failure, section 4. Manual control of CV-1235 pressurizer level control valve may be necessary to control pressurizer level. The alternate level transmitter should be verified correct and then selected for indication and control. Once the good transmitter is selected the pressurizer level control valve should be returned to automatic. Technical Specification 3.3.15 Post Accident Monitoring Instrumentation is applicable and requires entry into a 30 day time clock per 3.3.15.A (TS)3.3.15 The PAM instrumentation for each Function in Table 3.3.15-1 shall be OPERABLE.
An Instrument Air (IA) header leak will develop on the main IA header in the turbine building basement. The leak will result in a lowering IA pressure to between 45# 60#. The operators should enter 1203.024 Loss of Instrument Air and commence a rapid plant shutdown. At 70% power the field operators and/or maintenance will be successful in temporarily patching the leak resulting in IA pressure recovering to normal. The crew should stop the power reduction and stabilize plant power.
The crew should recognize two dropped control rods and the ATC operator should trip the reactor (CT Reactor should be tripped before Tcold reach 540°F).
10 minutes after the trip a grid disturbance created by the trip will result in a loss of offsite power.
The #2 EDG will automatically energize the A4 bus. The A3 bus will remain de-energized as the #1 EDG is faulted. Unit 2 should be contacted to start the AACG and supply the Uniti vital bus.
Emergency Feedwater (EFW) using the turbine driven EFW will supply both SGs and provide decay heat removal capability.
15 minutes post trip the WCO will call the control room and report EFW pump P7A has an oil leak on its in board pump bearing and is expected to be out of oil in 10 minutes.
CONTINUED Page 3
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Appendix D Scenario Outline Form ES-D-1 The crew should communicate with U2 for the availability of the Alternate AC Generator (AACG).
The AACG will be available to supply the Ui cross tie bus. The CBO should energize A3 from the AACG in order to supply the electric EFW pump P7B. (CT A3 should be energized before P7A trips)
P7B should be started or allowed to start and P7A secured. (CT P78 should be started before P7A trips)
The scenario can be terminated after P7B is supplying both SGs and P7A is secured or as directed by the lead evaluator.
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Simulator Scenario Scenario 4
Appendix D Scenario Outline Form ES-D-1 Facility:
ANO-1 Scenario No.: 4-Ri Op-Test No.: 2010-1 Examiners:
Operators:
Initial Conditions:
Recall 100% IC C28A IA compressor is out of service for overhaul.
RPS is failed Turnover:
100% power C28A IA compressor is out of service for overhaul.
Swap operating EH oil pumps following maintenance on the standby pump for a 30mm run PMT. The AO has been briefed and is standing by the EH pump.
Event Maif. No.
Event Event No.
Type*
Description 1
N/A N(BOP, Swap the operating EH oil pumps FW086 C(SRO, P8A heater drain pump winding failure and trip.
2 & 3 N/A Power reduction 4
TR580 I (ALL)
Controlling Header Pressure fails low 5
COP14A C (BOP)
Or EH pump will trip Dl PB92O1 p
C (SRO, RPS is failed (TS) 6 RP246,7,8,9 ATC)
M (ALL)
Manual reactor trip (ATC-CT)
RCOO2 M (ALL) 210 GPM tube leak in the B SG (TS) (BOP-CT) 7&8 N/A N (ATC)
Plant cooldown and depressurization 9
IMF CVO6I C (ALL)
Operating HP! pump trip (TS) (CBO-CT)
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1
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Appendix D Scenario Outline Form ES-D-1 Scenario #4-RI Objectives 1)
Evaluate individual ability to swap running EH oil pumps.
2)
Evaluate individual ability to recognize and respond to a heater drain pump trip.
3)
Evaluate individual ability to perform a rapid plant power reduction.
4)
Evaluate individual ability to recognize and respond to a turbine header pressure instrument failing low.
5)
Evaluate individual ability to recognize and respond to the loss of the operating EH oil pump and resultant turbine trip.
6)
Evaluate individual ability to recognize and respond to a reactor protection system failure to complete an automatic trip.
7)
Evaluate individual ability to recognize and respond to a steam generator tube leak.
8)
Evaluate individual ability to commence a reactor coolant system cool down and depressurization.
9)
Evaluate individual ability to recognize and respond to the operating HPI pump trip.
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Appendix D Scenario Outline Form ES-D-I SCENARIO #4-RI NARRATIVE The crew will assume the watch with the plant at 100% power. C2A IA compressor is out of service for overhaul.
The turn over sheet will direct the crew to swap operating turbine electro-hydraulic pumps per 1106.012 Electro-Hydraulic Oil System Operation Section 14 for a 30 minute run PMT. (SRO-N)
(BOP-N).
P8A heater drain pump will experience a winding failure causing a high temperature alarm and P8A trip (SRO-C) (BOP-C). The CRS should reference 1203.012E Annunciator Corrective Action P8AIP8B FLOW LO and CONDENSATE PUMP AUTOSTART.
A plant power reduction is required to maintain suction pressure. The CRS should direct the power reduction per 1203.045 Rapid Plant Shutdown (ATC-R) (SRO-N).
The controlling Turbine Header Pressure instrument will fail low. (SRO-C) (ATC-C) (BOP-C)
This will result in the turbine lowering demand to raise header pressure. The reactor and feedwater will rise as a result of the header pressure error. A SASS mismatch alarm will be received. The CRS will direct operations per 1203.012F Annunciator Corrective actions for SASS mismatch alarm and 1203.001 ICS Abnormal Operation. The crew should verify the turbine in manual control SGIRX master and both turbine bypass valves in manual. Once the plant is stable the crew will verify the alternate instrument is good and select the good it on C04.
The crew should return ICS to automatic.
After the power reduction the operating EH oil will trip. The standby pump will not start (BOP-C).
The loss of both EH pumps will result in a turbine trip. (Crew may complete a manual RX trip prior to the turbine trip) The reactor will fail to trip do to a failure of RPS (ATC-C) (TS). The ATC should manually trip the reactor using the shunt trip breakers (ATC-CT) (ATC-M) (BOP-M)
(SRO-M).
TS 3.3.1 Condition C TS 3.3.2 Condition A (CT The reactor should be manually tripped before the pressurizer goes solid.)
EAL ALERT 6.2 RPS Failure to Complete an Automatic Trip A 2lOgpm tube leak will occur in the B SG (ATC-M) (BOP-M) (SRO-M) (TS). The CRS should direct operation per 1202.006 Tube Rupture. The leak will be large enough to require HPI be initiated (BOP-CT). An RCS depressurization and cooldown should be started (ATC-N).
TS 3.4.13 Condition B (CT HPI should be initiated before SCM is lost.)
EAL NUE 3.2 SIG Tube Leak > Tech. Spec. Limits The Operating HPI pump breaker trips due to a motor fault. (SRO-C) (ATC-C) (BOP-C) The CRS should direct operations per 1203.026 Loss of Reactor Coolant Makeup section 1 Loss of HPI Pump. The crew should diagnose the pump trip as a breaker fault and start the standby HPI pump. HPI should be restarted using the standby pump or raised using the ES pump. (BOP-CT)
TS 3.5.2 Condition A (CT HPI should be started or raised on the ES pump before SCM is lost.)
The scenario may be terminated when HPI has been restarted or at the direction of the lead evaluator.
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ES-301 Transient and Event Checklist Rev I Form ES-301-5 Facility: ANO-1 Date of Exam:
3/8/2010 Operating Test No.: 2010-1 A
E Scenarios P
1 2
3 M
L N
CREW_POSITION CREW_POSITION CREW_POSITION T
N I
T C
A T
U S
A B
S A
B S
B A
R T
0 R
T 0
R T
A M(*)
N 0
C P
a c
P C
p L
R iu T
RX 3
1 110 RO NOR 1,2 9
3 1
1 1
R2, R5, I/C 5, 6, 7, R8
,6 8
6 442 MAJ 8,9 7
3 221 TS 0022 f?j(
5 1
110 RO NOR 1,2 1
6 4
1 1
1 R6 I/C 4,6 2,4,6 4,9 7
4 4
2 MAJ 8, 9 7
7, 8 5
2 2
1 TS 0022 RX 2
1110 NOR 1,9 2
1 1
1 R1R7 I/C 3, 6, 7 2, 3 5
4 4
2 MAJ 8, 9 7, 8 4
2 2 1 TS 0022 RX 5
1110 NOR 1
6 2
lii R3R9 I/C 2,4,6 4,9 5
4 4
2 MAJ 7
7,8 3
221 TS 0022 RX 2
1110 NOR 1
1,9 3
iii I/C 3,6,7 2,4,6 2,3 8
4 4
2 MAJ 8, 9 7
7, 8 5
2 2
1 TS 0022 Instructions:
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
3.
Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Transient and Event Checklist Rev I Form ES-301-5 Facility: ANO-1 Date of Exam:
3/8/2010 Operating Test No.: 201 0-1 A
E Scenarios P
1 2
3 M
L N
CREW_POSITION CREW_POSITION CREW_POSITION T
N I
T o
C A
T u
A R
T 0
R T
0 R
C o
Mo N
0 C
P 0
C P
0 P
L R
lU T
E RX 5
1110 NOR 1,2 1,3,9 6
6 1
1 1
SRO-l I/C 3, 4, 5, 2, 4, 5, 4 9 12 4
4 2
Ii 6,7 6,8 MAJ 8, 9 7
7, 8 5
2 2
1 TS 3,7 5,7 4
0 2
2 RX 3
1110 NOR 1,2 9
1,6,9 6
1 1
1 SRO-l I/C 3,4, 5, 5, 6, 7, 2,,,
13 4
4 2
12 6,7 8
9 MAJ 8, 9 7
7, 8 5
2 2
I TS 3,7 2,3 4
0 2
2 RX 2
1110 NOR 1,3,9 3
! i +/-
SRO-U i/C 3 6 7 2, 4,,
8 4
4 2
13
6,8 MAJ 8,9 7
3 221 TS 5,7 2
022 RX 0110 NOR 1,2 1,3,9 1,6,9 8
1 1 1 SRO-U i/C 3, 4, 5, 2, 4, 5, 2, 3,,
14 4
4 2
U1,U2 6,7 6,8 9
MAJ 8, 9 7
7, 8 5
2 2 1 TS 3,7 5,7 2,3 6
0 2
2 Instructions:
3.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. RO5 must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
4.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
3.
Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.