ML13347B120
| ML13347B120 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/11/2013 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| Download: ML13347B120 (20) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: VOGTLE Date of Exam:
MARCH 2012 RQK/ACajojyPoh,ts SRO-OnIy_Points Tier Group KKIKKKKAAAAG A2 G*
Total 1
213 4
5 6
1 2
3 4
Total 1.
1 13 3
3 3
3 3
18 3
3 6
Emergency &
Abnormal 2
1 1
2 N/A 1
N/A L
9 2
2 4
Plant Evolutions Tier Totals 4
4 5
5 5
4 27 5
5 10 1
3 2
3 3
3 3
2 3
2 2
2 28 3
2 5
2.
Plant 2
2+/-L LJ 10 0
2 1
3 Systems Tier Totals 4
3 4
4 4 1 2.. I 1.
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 1 0 1
2 3
4 7
Categories 2
3 3
2 1
2 2
2 Note:
1 Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7**
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 007EG2.4.2 Reactor Trip
- Stabilization
- Recovery 4.5 4.6 j j
Knowledge of system set points, interlocks and automatic I 1 actions associated with EOP entry conditions.
008AK3.04 Pressurizer Vapor Space Accident I 3 4.2 4.6
]
RCP tripping requirements 015AK2.1O RCP Malfunctions I 4 2.8 2.8 j j RCP indicators and controls 022AG2.2.42 Loss of Rx Coolant Makeup I 2 3.9 4.6 J
J Ability to recognize system parameters that are entry-level conditions for Technical Specifications 025AK2.03 Loss of RHR System I 4 2.7 2.7 j
J Service water or closed cooling water pumps 026AA1.03 Loss of Component Cooling Water I 8 3.6 3.6 SWS as a backup to the CCWS 029EK1.01 ATWS I 1 2.8 3.1 J
Reactor nucleonics and thermo-hydraulics behavior O4OAA1.20 Steam Line Rupture
- Excessive Heat 4.1 4.2 Containment pressure and temperature trends Transfer / 4 054AA2.02 Loss of Main Feedwater /4 4.1 4.4 j
Differentiation between loss of all MFW and trip of one MEW pump 055EA2.02 Station Blackout /6 4.4 4.6 RCS core cooling through natural circulation cooling to S/G cooling 056AK1.03 Loss of Off-site Power /6 3.1 3.4 EJ Definition of subcooling: use of steam tables to determine it Page 1 of 2 4/27/2011 8:34AM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 058AK3.Ol Loss of DC Power I 6 3.4 3.7 j
j j J J
Use of dc control power by DIGs 062AA2.03 Loss of Nuclear Svc Water I 4 2.6 2.9 j
j The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 065AK304 Loss of Instrument Air I 8 3
3.2 D El j j j
Cross-over to backup air supplies 077AK1.02 Generator Voltage and Electric Grid 3.3 3.4 Over-excitation Disturbances /6 WEO4EA1.3 LOCA Outside Containment /3 3.8 4.0 Desired operating results during abnormal and emergency situations.
WEO5EK2.l Inadequate Heat Transfer
- Loss of 3.7 3.9 El El El El El El El El El El Components and functions of control and safety systems, Secondary Heat Sink / 4 including instrumentation, signals, interlocks, failure modes and automatic and manual features.
well EG2.4.6 Loss of Emergency Coolant Recirc. /4 3.7 4.7 El El El El El El El El El El Knowledge symptom based EOP mitigation strategies.
Page 2of 2 4/27/2011 8:34AM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO OO1AA1.02 Continuous Rod Withdrawal I 1 3.6 3.4 j
j Rod in-out-hold switch 036AK3.03 Fuel Handling Accident I 8 3.7 4.1 j
j j J Guidance contained in EOP for fuel handling incident 037AK1.02 Steam Generator Tube Leak I 3 3.5 3.9 j j j Leak rate vs. pressure drop 051AA2.02 Loss of Condenser Vacuum I 4 3.9 4.1 j ]
Conditions requiring reactor and/or turbine trip 068AA2.lO Control Room Evac. / 8 4.2 4.4 j j j j j j Source range count rate 074EA1.25 mad. Core Cooling / 4 3.8 3.8 j
Atmospheric dump valve controllers and indicators WEO3EK2.l LOCA Cooldown
- Depress. /4 3.6 4.0 j J Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEO8EK3.4 RCS Overcooling
- PTS /4 3.4 3.7 Li LI LI LI El RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
wel5EG2.l.32 Containment Flooding / 5 3.8 4.0 LI LI LI LI El LI LI LI LI LI Ability to explain and apply all system limits and precautions.
Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 CCW pumps Excessive letdown flow, pressure and temperatures on ion exchange resins (also causes)
RCS temperature and pressure Closed cooling water flow rate and temperature (muW-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
Bubble formation in PZR Automatic actions associated with the CCWS that occur as a result of a safety injection signal Constant enthalpy expansion through a valve PZR sprays and heaters T/G KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
---F 003K2.02 ReactorCoolantPump 2.5 2.6 j
004A2.2l Chemical and Volume Control 2.7 2.7 j
004K3.06 Chemical and Volume Control 3.4 3.6
]
005A1.03 Residual Heat Removal 2.5 2.6 El El El 006G2.2.4 Emergency Core Cooling 3.6 3.6 E] El El El El 007A2.06 Pressurizer Relief/Quench Tank 2.6 2.8 El El El El El El El El El El 008A3.08 Component Cooling Water 3.6 3.7 El El El El El El El El El El 010K5.02 Pressurizer Pressure Control 2.6 3.0 El El El El El El El El El El 010K6.03 Pressurizer Pressure Control 3.2 3.6 El El El El El ] El El El El El Ol2Kl.06 Reactor Protection 3.1 3.1 El El El El El El El El El El 012K4.09 Reactor Protection 2.8 3.1 El El El El El El El El El El Separation of control and protection circuits Page 1 of 3 4/27/2011 8:34AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 013A4.Ol Engineered Safety Features Actuation 4.5 4.8 j
j j
ESFAS-initiated equipment which fails to actuate 022A4.Ol Containment Cooling 3.6 3.6 j
j CCS fans 026A1.02 Containment Spray 3.6 3.9 j
El E E D D Containment temperature 026K2.O1 Containment Spray 3.4 3.6 J
Containment spray pumps 039G2.l.25 Main and Reheat Steam 3.9 4.2 j
j Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
039K5.08 Main and Reheat Steam 3.6 3.6 El El El El El [
Effect of steam removal on reactMty 059K4.08 Main Feedwater 2.5 2.7 El El El El El El El El El El Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch) 061 A3.04 Auxiliary/Emergency Feedwater 4.1 4.2 El El El El El El El El El El Automatic AFW isolation 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 El El El El El El El El El El Pumps 062A2.l 1 AC Electrical Distribution 3.7 4.1 El El El El El El El il El El El Aligning standby equipment with correct emergency power source (D/G) 063K3.01 DC Electrical Distribution 3.7 4.1 ED/G Page 2of 3 4/27/2011 8:34AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 063K4.04 DC Electrical Distribution 2.6 2.9 J j Trips 064K6.07 Emergency Diesel Generator 2.7 2.9 Air receivers 073K5.03 Process Radiation Monitoring 2.9 3.4 El El El El El El El El El El Relationship between radiation intensity and exposure limits 076K1.09 Service Water 3.0 3.1 El El El El El El El El El El Reactor building closed cooling water 078K3.01 Instrument Air 3.1 3.4 El El El El El El El El El El Containment air system 103K1.07 Containment 3.5 3.7 El El El El El El El El El El Containment vacuum system Page 3of 3 4/27/2011 8:34AM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001A3.06 Control Rod Drive 3.9 3.9 j j j
RCS temperature and pressure 0111(2.01 Pressurizer Level Control 3.1 3.2 J
J Charging pumps Ol5G2.4.45 Nuclear Instrumentation 4.1 4.3 j ]
Ability to prioritize and interpretthe significance of each annunciator or alarm.
016K1.09 Non-nuclear Instrumentation 3.7 3.7 j j ESFAS 028A2.02 Hydrogen Recombiner and Purge 3.5 3.9 D
LOCA condition and related concern over hydrogen Control 041 K3.02 Steam DumplTurbine Bypass Control 3.8 3.9 El El El El RCS 071 Al.06 Waste Gas Disposal 2.5 2.8 El El El El El El El El El El Ventilation system 072K5.02 Area Radiation Monitoring 2.5 3.2 El El El El El El El El El El Radiation intensity changes with source distance 075K4.0l Circulating Water 2.5 2.8 El El El El El El El El El El Heat sink 086A4.06 Fire Protection 3.2 3.2 El El El El El El El El El El Halon system Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.29 Conduct of operations 4.1 4.0 j
j j j Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
G2.l.8 Conduct of operations 3.4 4.1 J J Ability to coordinate personnactivities outside the control room.
G2.2.1 Equipment Control 4.5 4.4 j
J Ability to perform pre-startup procedures for the facUity, including operating those controls associated with plant equipment that could affect reactivity.
G2.2.17 Equipment Control 2.6 3.8 j j j ]
j j
Knowledge ofthe process for managing maintenance activities during power operations.
G2.2.3 Equipment Control 3.8 3.9 j
(multunit license) Knowledge of the design, procedural and operational differences between units.
G2.3.l 1 Radiation Control 3.8 4.3 j E]
Ability to control radiation releases.
G2.3.13 Radiation Control 3.4 3.8 EJ El El Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.31 Emergency Procedures/Plans 4.2 4.1 El j j j El Knowledge of annunciators alarms, indications or response procedures G2.4.46 Emergency Procedures/Fans 4.2 4.2 El El El El El El El El El El Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 008AG2.l.19 Pressurizer Vapor Space Accident I 3 3.9 3.8 j El D D El LI i Ability to use plant computer to evaluate system or component status.
054AG2. 1.7 Loss of Main Feedwater I 4 4.4 4.7 j ]
j Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
055EA2.Ol Station Blackout /6 3.4 3.7 Existing valve positioning on a loss of instrument air system 058AG2.4.9 Loss of DC Power /6 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
077AA2.08 Generator Voltage and Electric Grid 4.3 4.4 Criteria to trip the turbine or reactor Disturbances / 6 WEO5EA2.2 Inadequate Heat Transfer
- Loss of Secondary Heat Sink /4 3.7 4.3 Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001 AA2.01 Continuous Rod Withdrawal / 1 4.2 4.2 Reactor tripped breaker indicator 037AA2.10 Steam Generator Tube Leak / 3 3.2 4.1 D E D LI El El il El J
Tech-Spec limits for RCS leakage weO6EG2.4.18 Degraded Core Cooling / 4 3.3 4.0 LI LI LI LI LI LI LI LI LI LI Knowledge of the specific bases for EOPs.
wel OEG2.4.47 Natural Circ. With Seam Void! 4 4.2 4.2 LI LI LI LI LI El LI LI LI LI Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 012G2.l.27 Reactor Protection 3.9 4
Knowledge of system purpose and or function.
039G2.l.28 Main and Reheat Steam 4.1 4.1 Knowledge of the purpose and function of major system components and controls.
063A2.O1 DC Electrical Distribution 2.5 3.2 El El El El El El El El El Grounds 076A2.02 Service Water 2.7 3.1 El El El El El El El El El El Service water header pressure 103A2.02 Containment 2.2 3.2 El El El El El El El El El El Necessary plant conditions for work in containment Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 KA 01 5A2.05 SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.3 3.8 3.4
4.0 TOPIC
Core void formation The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment Ability to perform specific system and integrated plant procedures during all modes of plant operation.
NAME / SAFETY FUNCTION:
Nuclear Instrumentation 028A2.03 071 G2.1.23 Hydrogen Recombiner and Purge Control Waste Gas Disposal FORM ES-401-2 Page 1 of 1 4/27/2011 8:34AM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.38 Conduct of operations 3.7 3.8 j
j j
J Knowledge of the stations requirements for verbal communication when implamenting procedures G2.2.13 Equipment Control 4.1 4.3 j j Knowledge of tagging and clearance procedures.
G2.2.18 Equipment Control 2.6 3.8 El El El El El Knowledge of the process for managing maintenance activities during shutdown operations.
G2.3.12 Radiation Control 3.2 3.7 j j j Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.12 Emergency Procedures/Plans 4.0 4.3 El El El El El El El El El El Knowledge of general operating crew responsibilities during emergency operations.
G2.4.37 Emergency Procedures/Plans 3.0 4.1 El El El El El El El El El El Knowledge of the lines of authority during implamentation of an emergency plan.
Page 1 of 1 4/27/2011 8:34AM
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Vogtle 1 & 2 Date of Examination:
4/20/12 Examination Level:
Administrative Topic Type Describe activity to be performed (see Note)
Code*
R P V-NRC-JP-14915-HL17 ConductofOperations
Perform AFD Monitoring
==
Description:==
With data provided, candidate will perform 14915 Data sheet 6 for AFD monitoring.
G2.1.37 (4.3/4.6)
V-NRC-JP-1 9001 -HL1 7 Conduct of Operations R, D Calculate Boron Addition with 3 Stuck Rods
==
Description:==
With data given, the candidate will calculate the amount of Boric Acid that is required to compensate for the stuck rods.
G2.1.25 (3.9/4.2)
V-NRC-JP-NMP-AD-003-HL1 7 Equipment Control R, N Determine Tagging Requirements
==
Description:==
candidate will determine appropriate fluid boundary points and their associated positions required for the Tagout of Containment Spray Pump 1A.
G2.2.13 (4.1 /4.3)
V-NRC-JP-00930-HL1 7 Radiation Control R, D Radiation Posting Requirements
==
Description:==
Candidate will determine the posting requirements for a room with a radioactive component temporarily stored in it.
G2.3.12 (3.2/3.8)
N/A Emergency Procedures/Plan R, D 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)
ES-301 Administrative Topics Outline Form ES-301-!
Facility: VoqtIe 1 & 2 Date of Examination:
3/26/12 4/20/12 Examination Level:
RO SRO SROU Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note)
Code*
R P V-NRC-JP-14915-HL17 Conduct of Operations Evaluate Inoperable AFD Monitor Alarm
==
Description:==
With data provided, candidate will select 14915 Data sheet 6 for AFD monitoring, evaluate data and take appropriate actions.
G2.1.37 (4.3 / 4.6)
V-NRC-JP-1 4005-HL1 7 Conduct of Operations R, D Calculate Shutdown Margin-Keff Determ nation for Shutdown Bank Withdrawal
==
Description:==
Reactor Startup in progress. candidate will determine Keff for Shutdown Bank withdrawal.
G2.1.25 (3.9 / 4.2)
V-NRC-JP-NMP-AD-003-HL1 7 Equipment Control R, N Determine Tagging Requirements
==
Description:==
candidate will determine appropriate fluid boundary points and their associated positions required for the Tagout of Containment Spray Pump 1A. The candidate must also determine any Tech Spec required actions to allow this system to be tagged.
G2.2.13(4.1 /4.3)
V-NRC-JP-00930-HL1 7 Radiation Control R, D Radiation Posting Requirements /Controls
==
Description:==
Candidate will determine the posting requirements for a room with a radioactive component temporarily stored in it. The candidate must state the Tech Spec Admin controls required to access the area.
G2.3.12 (3.7)
V-NRC-JP-NMP-EP-1 1 2-HL1 7 Emergency Procedures/Plan R, D Determine Offsite Protective Area Recommendations
==
Description:==
With a General Emergency declared, the candidate will determine the required offsite PARs with the data given.
G2.4.44 (4.4)
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)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: VogtIe 1 & 2 Date of Examination:
4/2O/12 Exam Level: RO SRO-l SRO-U Operating Test No.:
Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function a.
V-NRC-JP-14410-HL17 Perform Control Rod OperabilityTest-Alt A, M, S path (Two rods drop requiring a manual Reactor Trip).
==
Description:==
Candidate performs control rod operability test for Control bank A. This JPM is modified to drop two rods in a staggered sequence on CBA when CBB test is started. This will require a manual reactor trip per 1 8003-C, Rod Control System Malfunction.
001 A2.1 7 (3.3 I 3.8)
(RO/SROI)
Alternate a. V-NRC-JP-1 3009-HL1 7 Perform a Manual Makeup To A,M,S VCT( Alt-loss off boric acid flow)
==
Description:==
Candidate performs a manual makeup to VCT. This JPM is modified to simulate a blown control power fuse stops the running boric acid transfer pump requiring stopping the makeup.
004A4.12 (3.8 I 3.3)
(RO I SROI) b.
V-NRC-JP-19013-HL17 Transfer ECCS Pumps To Cold Leg A, EN, D, S 2
Recirc (Cold Leg Recirc path not available)
==
Description:==
Equipment failures will prevent cold leg recirculation. Candidate is required to identify a loss of emergency coolant recirculation.
006A4.05 (3.9 I 3.8)
(RO/SROI/SROU) c.
V-NRC-JP-19030-HL17 Depressurize RCS To Reduce Break A P 5 Flow to Ruptured SG (Normal Pressurizer Spray Not available
and 1 st PORV Block Valve fails to open)
==
Description:==
A SGTR has occurred. The candidate task is to Depressurize the RCS beginning with 1 9030-C step 34, until one termination criterion is met. Normal spray controllers will not function. Candidate should use a PORV with complications.
038EA1.04 (4.3 I 4.1)
(RO I SROI)
d.
V-NRC-JP-13003-HL17 Start a RCP with a Seal Failure A, D, L, S 4P
==
Description:==
Plant is in Mode 3 at 557°F, 2235 psig with three RCPs running. The candidate must start RCP 2 per SOP 13003-1
. On start, the #1 seal fails requiring pump shutdown.
003A2.02 (3.7 I 3.9)
(RO I SROI)
Alternate d. V-NRC-JP-1 301 1 -HL-1 7 Place an RHR Train In Service D,L,S 4P for RCS Cooldown
==
Description:==
The candidate must place a train of RHR in service for RCS cooldown per SOP 1 301 1 -1.
005A4.01 (3.6 I 3.4)
(RO I SROI) e.
V-NRC-JP-13610-HL17 Transfer AFW Suction Source to CST 2 D, EN, L, S 45
==
Description:==
The candidate must transfer the AFW suction source to CST 2 with AFW in service per SOP 1 361 0-1.
061 Al.04 (3.9 I 3.9)
(RO I SROI) f.
V-NRC-JP-l 31 30-HL1 7 Dilute Containment With Service Air P, S 5
==
Description:==
The candidate will be required to use SOP 1 31 30-1, section 4.4.2 to align service air to containment to dilute hydrogen.
028A4.0l (4.0 I 4.0)
(RO/SROI) g.
V-NRC-JP-13427-HL17 Energizing 4160v Bus 1AAO2 from N, S 6
Alternate Incoming Source (RAT B) using l3427A-l
==
Description:==
A loss of all AC power has occurred. The candidate must energize Train A 4160 V bus from the Train B RAT.
062A4.0l (3.3 I 3.1)
(RO/SROI/SROU) h.
V-NRC-JP-13301-HL17 Manually Actuate CAl Due to Smoke M, S RO ONLY
==
Description:==
A brush fire on site is causing smoke to enter the 8
control room air intakes. The candidate must perform a Control Room Isolation.
067AA1.05 (3.0/3.1)
(RO)
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
I.
V-NRC-JP-18019-HL17 Establish RWST Gravity Drain Through A, R, P 4P RHR Pumps to RCS Hot Legs (Cold Legs Not Available)
==
Description:==
During a loss of RHR at midloop level, establish gravity drain to the hot legs per AOP 1 801 9-C Attachment A section C.
025G2.1.20 (4.6 I 4.6)
(RO I SROI I SROU) j.
V-NRC-JP-1 8038-HL1 7 Establish Local Control of 1 E N, E 8
Switchgears
==
Description:==
The candidate must take local control of the 4160 V switchgear breakers and verify an ACCW pump in service per AOP 18038-1.
068AA1.20 (3.9 I 4.1)
(RO I SROI I SROU) k.
V-NRC-JP-1 8001 -HL1 7 Place Steam Pressure Bistables in the C, D 7
Tripped Condition
==
Description:==
The candidate must place 2PT-0524 bistables in the tripped condition per AOP 1 8001 -C.
012A4.04 (3.3/3.3)
(RO/SROI/SROU)
All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRQ-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 I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 1 2-3 (C)ontrol room (D)irectfrom bank 918/4 (E)mergency or abnormal in-plant 1 I 1 /
1 (EN)gineered safety feature
- I I 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1 (A) 2 I 2 I 1
(P)revious 2 exams 3 /
3 I 2 (randomly selected)
(R)CA (S)imulator