ML102870160
| ML102870160 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/12/2010 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-424/10-301, 50-425/10-301, ES-401, Rev 9 | |
| Download: ML102870160 (21) | |
Text
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:
Date of Exam:
RO K/A Category Points SRO-Only Points Tier Group
KKKKKKAAAAIG A2 G*
Total 1
2 3
4 5
6 1
2 3 41*
Total
=
=
1.
1 333 33 3
18 3
3 6
Emergency &
2 E
2 1
1 9
2 2
4 Abnormal Plant
N/A NIA
Evolutions Tier Totals 5
=
=
5 4
=
4 27 5
5 10 1
33232323223 28 3
2 5
2.
2 11 1
11 1
1 101 1
10 2
1 3
Plant
Systems Tier Totals 4
4 3
4 3
4 3
4 2
3 4
38 5
3 8.
=
=
=
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
3 2
2 2
2 1
2 1.
Ensure that at least two topIcs from every applicable KIA 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 KJA 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 +/- I 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 that are not included on the outlIne should be added. Refer to ES-401, Attachment 2, 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 (lR) 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 I and 2 from the shaded systems and K/A categories.
7*
generic (G) K/As In Tiers I 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.
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 I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 007EG2.4.31 Reactor Trip
- Stabilization
- Recovery 4.2 4.1 Knowledge of annunciators alarms, indications or I 1 response procedures OO8AAI.04 Pressurizer Vapor Space Accident! 3 2.8 2.5 Feedwater pumps 009EK2.03 Small Break LOCA /3 3
3.3 Li LI LI LI LI LI LI LI LI LI S/Gs 011 EG2.2.38 Large Break LOCA / 3 3.6 4,5 LI LI LI LI LI LI LI LI LI LI Knowledge of conditions and limitations in the facility license.
01 5AK2.07 RCP Malfunctions /4 2.9 2.9 LI
[]
[]
}
( )
RCP seals 022AK1.01 Loss of Rx Coolant Makeup / 2 2.8 3.2 J
[
Consequences of thermal shock to RCP seals 025AA1.19 Loss of RHR System / 4 2.6 2.4 LI LI LI LI LI LI LI LI LI Block orifice bypass valve controller and indicators 027AA1.05 Pressurizer Pressure Control System 3.3 3.2 LI LI LI LI LI LI LI LI LI LI Transfer of heaters to backup power supply Malfunction / 3 038EK1.04 Steam Gen. Tube Rupture / 3 3.1 3.3 J LI LI LI LI LI LI LI LI LI LI Reflux boiling 054AK1.01 Loss of Main Feedwater / 4 4.1 4.3 LI LI LI LI LI LI LI LI LI LI MFW line break depressurizes the S/G (similar to a
steam line break) 055EG2.4.2 Station Blackout /6 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Page 1 of 2 9/9/2009 8:59 AM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES4O1-2 Normal, abnormal and emergency operating procedures associated with (Loss of Secondary Heat Sink).
KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 056AK3.0l Loss of Off-site Power / 6 3.5 3.9 D E D LI Order and time to initiation of power for the load sequencer 057AA2.05 Loss of Vital AC Inst. Bus /6 3.5 3.8 SIG pressure and level meters 062AA2.02 Loss of Nuclear Svc Water! 4 2.9 3.6 LI The cause of possible SWS loss 065AA2.03 Loss of Instrument Air / 8 2.6 2.9 LI Location and isolation of leaks 077AK3.02 Generator Voltage and Electric Grid 3.6 3.9 LI LI LI LI LI LI LI LI LI LI Actions contained in abnormal operating procedures for Disturbances / 6 voltage and grid disturbances WE04EK2.2 LOCA Outside Containment / 3 3.8 4.0 LI LI LI L] LI LI LI LI [1 LI Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WEO5EK3.2 3.7 4.1 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Page 2 of 2 9/9/2009 8:59 AM
ES-401, REV 9 Ti G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
JR Ki K2 1(3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003AK3.1O Dropped Control Rod /1 3.2 4.2 LI LI RIL and PDIL 032AA2.07 Loss of Source Range NI / 7 2.8 3.4 LI Maximum allowable channel disagreement O51AA1.04 Lossof Condenser Vacuum/4 2.5 2.5 LI LI LI [1 LI Rodposition 060AG2.I.25 AccidentalGaseousRadwasteRel./9 3.9 4.2 LI LI Abilityto interpret reference materials such as graphs, monographs and tables which contain performance data.
061 AK2.01 ARM System Alarms! 7 2.5 2.6 Detectors at each ARM system location 068AK3.02 Control Room Evac. / 8 3.7 4.1 J LI System response to turbine trip WE01 EK1.2 Rediagnosis! 3 3.4 4
[] U LI [] LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection /
Rediagnosis).
WE13EA1.1 Steam Generator Over-pressure /4 3.1 3.3 LI LI LI LI LI LI LI LI LI LI Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE16EKI.1 High Containment Radiation/9 2.7 3.0 LI LI LI LI LI LI LI LI LI LI Components, capacity, and function of emergency systems.
Page 1 of 9/9/2009 8:59 AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003G2.4.35 Reactor Coolant Pump 3.8 4.0 LI
[] []
[] LI Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 004G2.l.23 Chemical and Volume Control 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
004K6.31 Chemical and Volume Control 3.1 3.6 Seal injection system and limits on flow range 005K2.03 Residual Heat Removal 2.7 2.8 LI LI LI LI LI LI LI LI LI LI RCS pressure boundary motor-operated valves 005K6.03 Residual Heat Removal 2.5 2.6 LI LI LI LI L]
RHR heat exchanger 006K6.02 Emergency Core Cooling 3.4 3.9 J LI LI LI LI Core flood tanks (accumulators) 007K1.03 Pressurizer Relief/Quench Tank 3.0 3.2 ] LI LI LI LI LI LI LI LI LI LI RCS 007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 LI LI LI LI LI LI LI LI LI LI Quench tank cooling 008K2.02 Component Cooling Water 3.0 3.2 LI LI LI LI LI LI LI LI LI LI CCW pump, including emergency backup 01 OK1.08 Pressurizer Pressure Control 3.2 3.5 LI fl fl LI LI LI LI LI LI LI PZR LCS 012K1.05 Reactor Protection 3.8 3.9 ESFAS Page 1 of 3 9/9/2009 8:59 AM
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:
RD SRO 01 2K5.01 Reactor Protection 3.3 3.8 J
DNB 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022A1.01 Containment Cooling 3.6 3.7
[] []
[] [
Containment temperature 022A2.03 Containment Cooling 2.6 3.0
[]
[] {
Fan motor thermal overload/high-speed operation 026A3.02 Containment Spray 3.9 4.2 Verification that cooling water is supplied to the containment spray heat exchanger 039A2.01 Main and Reheat Steam 3.1 3.2 Li Li Flow paths of steam during a LOCA 059A3.02 Main Feedwater 2.9 3.1 Li Li Li Li fl Li Li Li Programmed levels of the S/G 061A1.01 Auxiliary/Emergency Feedwater 3.9 4.2 Li Li Li Li Li Li j Li Li Li Li SIG level 062G2.1.27 AC Electrical Distribution 3.9 Li Li Li Li Li Li Li Li Li Li Knowledge of system purpose and or function.
063K2.0l DC Electrical Distribution 2.9 3.1 Li Li Li Li LI Li Li Li Li Li Major DC loads 063K4.02 DC Electrical Distribution 2.9 3.2 Li Li Li Li Li Li Li Li Li Li Breaker interlocks, permissives, bypasses and cross-ties.
Page 2 of 3 9/9/2009 8:59 AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES4O1-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 064A2.13 Emergency Diesel Generator 2.6 2.8 Consequences of opening auxiliary feeder bus (EDIG sub supply) 073A4.02 Process Radiation Monitoring 3.7 3.7 Radiation monitoring system control panel 073K3.O1 Process Radiation Monitoring 3.6 4.2 Radioactive effluent releases 076K3.02 Service Water 2.5 2.8 D []
[J [( [] [] [] []
Secondary closed cooling water 078K4.O1 Instrument Air 2.7 2.9 El El H Manual/automatic transfers of control 1 03A4.03 Containment 2.7 2.7 LI LI LI El H H H H H l H ESF slave relays Page 3 of 3 9/9/2009 8:59 AM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001 K2.05 Control Rod Drive 3.1 3.5 WG sets 002A2.03 Reactor Coolant 4.1 4.3 fl Loss of forced circulation 016K1.08 Non-nuclear Instrumentation 34 3.4 J PZR PCS 028K5.01 Hydrogen Recombiner and Purge 3.4 3.9 fl fl Explosive hydrogen concentration Control 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems 035G2.2.40 Steam Generator 3.4 4.7 lJ Ability to apply technical specifications for a system.
055K3.01 Condenser Air Removal 2.5 2.7 Main condenser 071 K4.06 Waste Gas Disposal 2.7 3.5 fI Sampling and monitoring of waste gas release tanks 079A4.01 Station Air 2.7 2.7 EJ j Cross-tie valves with lAS 086K6.04 Fire Protection 2.6 2.9 Fire, smoke and heat detectors Page 1 of 1 9/9/2009 8:59 AM
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
Knowledge of shift or short term relief turnover practices.
Knowledge of procedures, guidelines or limitations associated with reactivity management Knowledge of surveillance procedures.
Knowledge of tagging and clearance procedures.
Ability to recognize system parameters that are entry-level conditions for Technical Specifications Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to aprove release permits Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RD SRO G2.1.l5 Conduct of operations 2.7 3.4 LI LI LI LI LI LI LI LILILI G2.1.3 Conduct of operations 3.7 3.9 LI LI LI LI LI LI LI LI LI LI II G2. 1.37 Conduct of operations 4.3 4.6 LI LI LI LI LI LI LI LI LI LI G2.2.12 Equipment Control 3.7 4.1 LI LI LI LI LI LI LI LI LI LI I G2.2.13 Equipment Control 4.1 4.3 LI LI LI LI LI LI LI LI LILI I]
G2.2.42 Equipment Control 3.9 4.6 LI LI LI LI LI LI LI LI LI LI G2.3.13 Radiation Control 34 3.8 LI LI LI LI LI LI LI LI LI LI I G23.6 Radiation Control 2.0 3.8 LI LI LI LI LI LI LI LI LI LI (I G2.4.30 Emergency Procedures/Plans 2.7 4.1 LI LI LI LI LI LI LI LI LI LI l?i G2.4.35 Emergency Procedures/Plans 3.8 4.0 LI LI LI LI LI LI LI LI LI LI II Page 1 of 9/9/2009 8:59 AM
SRO T1G1 PWR EXAMINATION OUTLINE IR KIK2K3K4K5K6AIA2A3A4G RO SRO DLI LI LI LH DEED DDE LiD EDDEDDD LID DDDDDL1l DEED LHL] LID ES-401, REV 9 KA NAME / SAFETY FUNCTION:
008AA2.28 Pressurizer Vapor Space Accident /3 O11EG2.4.11 LargeBreakLOCA/3 4.0 4.2 FORM ES-401-2 025AG2.4.31 Loss of RHR System 14 4.2
4.1 TOPIC
Safety parameter display system indications 056AA2.73 Loss of Off-site Power / 6 3.5 3.6 LI Knowledge of abnormal condition procedures.
065AG2.1.30 Loss of Instrument Air /8 4.4 4.0 Li WEO4EA2.1 LOCA Outside Containment /3 3.4 4.3 Knowledge of annunciators alarms, indications or response procedures PZR heater on/off Ability to locate and operate components, including local controls.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Page 1 of 1 9/9/2009 8:59AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
003AG2.l.30 Dropped Control Rod/i 028AG2.4.20 Pressurizer Level Malfunction / 2 068AA2.03 Control Room Evac. / 8 WEIOEA2.l Natural Circ. With Seam Void/ 4 SRO T1G2 PWR EXAMINATION OUTLINE IR ki K2 K3 K4 KS K6 Al A2 A3 A4 G RO SRO 4.4 4.0 DDEEIDL1D 3.8 4.3 4
4.2 3.2 3.9 FORM ES-401-2 TOPIC:
Ability to locate and operate components, including local controls.
Knowledge of operational implications of EOP warnings, cautions and notes.
T-hot, T-cold and in-core temperatures Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Page 1 of 1 9/9/2009 8:59 AM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-40I-2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RD SRO 003G2.4.41 Reactor Coolant Pump 2.9 4.6 j
Knowledge of the emergency action level thresholds and classifications.
007A2.03 Pressurizer Relief/Quench Tank 3.6 3.9 D
fl Overpressurization of the PZFI 010G2.1.20 Pressurizer Pressure Control 4.6 4.6 EJ Abilityto execute procedure steps.
026A2.03 Containment Spray 4.1 4.4 LI fl fl Failure of ESF 073A2.02 Process Radiation Monitoring 2.7 3.2 LI Detector failure Page 1 of 1 9/9/2009 8:59 AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
034G2.4.20 Fuel Handling Equipment 072A2.03 Area Radiation Monitoring O79A2O1 Station Air SRO T2G2 PWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 3.8 4.3 2.7 2.9 2.9 3.2 FORM ES4O1-2 TOPIC:
Knowledge of operational implications of EOP warnings, cautions and notes.
Blown power-supply fuses Cross-connection with lAS Page 1 of 1 9/9/2009 8:59AM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.1.35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs Gal.40 Conduct of operations 2.8 3.9 J
Knowledge of refueling administrative requirements G2.2.19 Equipment Control 2.3 3.4 D
Knowledge of maintenance work order requirements.
G2.2.35 Equipment Control 3.6 4.5 Ability to determine Technical Specification Mode of Operation G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.4.27 Emergency Procedures/Plans 3.4 3.9 Knowledge of fire in the plant procedures.
G2.4.39 Emergency Procedures/Plans 3.9 3.8 El El El LI El [l Knowledge of the ROs responsibilities in emergency plan implementation.
Page 1 of 1 9/9/2009 8:59 AM
ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 DraJ Facility:
Plant Vogtle Date of Examination: 02/22/2010 Examination Level:
RO Operating Test Number: 2010-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
R, D, P
Title:
Critical Safety Function Status Tree Evaluation
==
Description:==
Students will be provided a listing of plant parameters. This Conduct of Operations will require manually evaluating each status tree to determine the challenges to each tree and identify the highest priority challenge.
K/A: G2.1.7 (RO 4.4)
Title:
Perform QPTR Calculation (QPTR)
Conduct of Operations R, N
==
Description:==
Perform Quadrant Power Tilt Ration (QPTR) Calculation, both the top and bottom sections will be out of spec high.
K/A: G2.1.37 (RO 4.3)
Title:
Construct Tagout for Unit 2 # 4 Nuclear Service Cooling Water (NSCW) Pump Equipment Control R, D
==
Description:==
Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.
Identification of K-2 links to clear control room alarms is not required.
K/A: G2.2.13(R04.1)
Title:
Not applicable.
==
Description:==
Not applicable.
Radiation Control K/A: Not applicable.
Title:
Emergency Recall & Roll Call for Security Emergency Procedures/Plan S, N Emergency
==
Description:==
An emergency recall and roll call is required to be performed for a security emergency. This requires the use of a different recall scenario.
K/A: G2.4.43 (RO 3.2)
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)
Administrative Topics Outline Facility:
Vogtle Date of Examination: 02/22/2010 Examination Level:
SRO Operating Test Number: 2010-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
R, M, P
Title:
Perform Emergency Boration Flow Path Verification Conduct of Operations
==
Description:==
The plant will be in Mode 4 with the SI pumps common suction valve HV-8806 tagged shut and a sustained loss of instrument air to the unit. This will require the student to evaluate the effect of the loss of air on the boric acid flow paths in addition to the tagged component.
K/A: G2.1.7 (SRO 4.7)
R, N
Title:
Determine Active License Status
==
Description:==
The SRO will have to evaluate the status of 3 ROs to Conduct of Operations determine their license status for sitting the control board position.
K/A: G2.1.4 (SRO 3.8)
R, D
Title:
Construct Tagout for Unit 2 # 4 Nuclear Service Cooling Water (NSCW) Pump Equipment Control
==
Description:==
Determine the appropriate hold points and required positions of components to safely isolate NSCW pump 2-1202-P4-004.
K/A: G2.2.13 (SRO 4.3)
R, N
Title:
Emergency Exposure Limits Calculation and Authorization Radiation Control
==
Description:==
Historical data will be provided for individuals to receive an emergency exposure during a declared event. Data will be provided requiring a calculation to determine the exposure to be received, the student must determine the appropriate dose limit based on the expected dose.
K/A: 02.3.4 (SRO 3.7)
Title:
Upgrade - Emergency Classification (From Alert to Site Area Emergency)
Emergency Procedures/Plan R, N
==
Description:==
New data will be provided to the candidate to determine if an upgrade to a declared emergency is required. Once it is determined an upgrade is required, the ENN Notification Form will be required to be completed. This will be a time critical JPM.
K/A: G2.4.41 (SRO 4.6)
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: random Iv selected)
ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2 ZDraJ-z Facility:
Vogtle Date of Examination: 02/22/2010 Exam Level (circle one): RO / SRO-l I SRO-U Operating Test No.: 201 0-301 Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. Dropped Rod Recovery in Model (RO/SRO-l)
S, M, A A dropped rod will be recovered lAW AOP-1 8003-C, Rod Control Malfunction Section A for Dropped Rods in Mode 1. During the recovery, the rod being retrieved will not move. This will require reconfiguring the rod control system back to its previous state prior to attempting the dropped rod recovery.
K/A: 003M2.01 (RO 3.7 / SRO 3.9)
- b. Respond to Failure of PRZR Level Instrument (RO / SRO-I) 5, D, A 2
A PRZR level instrument will fail low requiring entry into AOP-18001 Section D. After to candidate attempts to place letdown back in service, a letdown isolation valve will NOT open requiring Excess Letdown to be placed into service.
K/A: 028AA1.05 (RO 3.7 / SRO 3.6)
- c. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train S, D, A, P 3
A Components Fail to Align (RO / SRO-I)
EN, L During alignment of ECCS to Hot Leg Recirculation, multiple Train A components will fail to align requiring the use of the RNO column.
K/A: 006A4.05 (RO 3.9 / SRO 3.8)
- d. Respond To RHR Pump Trip in Mode 4 (RO / SRO-l) 5, N, A, L 4P An RHR pump will trip in Mode 4 requiring entry into AOP-1 801 9, Section A, Loss of RHR Capability in Mode 4. The flow path through the procedure will require the candidate to start an RCP.
K/A: 025G2.4.9 (RO 3.8 / SRO 4.2)
- e. Dilute Containment with Service Air in accordance with 19010-S, D, L 5
C, E-l, Loss of Reactor or Secondary Coolant, Step 29. (RO /
SRO-l)
The student will be required to use SOP 13130-1, section 4.4.2 to align service air to containment to dilute the hydrogen.
K/A: 028A4.01 (RO 4.0 / SRO 4.0)
ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2 D ra4
- f. Synchronize Main Generator to the Grid. Field amps not S, D, A, P 6
indicated on one phase requires Main Turbine trip. (RO)
After synchronizing the main generator the student must recognize that one phase does not show any current, requiring opening of the generator output breaker to prevent damage to the generator.
K/A: 062A4.07 (RO 3.1)
- g. Respond to Fuel Handling Building High Radiation (ROISRO-l)
S, D, A 7
High Radiation will occur due to dropped rod in FHB but auto actuation fails, manual system alignment is required.
K/A: O61AA1.01 (RO 3.6 / SRO 3.6)
- h. Transfer Steam Dumps to Steam Pressure Mode (RO I SRO-l)
S, N, A, L 4S The student will be required to transfer steam dumps to the steam pressure mode using step 14 of AOP 1 8009-C. The steam dumps will not work, the student must shift the temperature control to the SG ARVs.
K/A: 041A4.08 (RO 3.0/ SRO 3.1)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Bypass CNMT HI-I Bistables Following Loss of Heat Sink D, E, L, P 7
Bistables must be bypassed using the BTI equipment in order to align a feedwater flow path to the SGs during a loss of secondary heat sink. This will also require knowledge of how / where to obtain multiple BTI keys to bypass 2 trains of equipment (RO / SRO-l)
K/A: 012A4.03 (3.6 / 3.6)
- j. Locally Start the TDAFW Pump D, E, L 8
Following a Control Room evacuation, the TDAFW pump is required to be locally started at Shutdown Panel C. Local transfer switches must be manipulated, the T & T valve checked for proper status, and throttling of AFW flow from the local panel is required using available flow indications.
K/A: 068AA1.02 (RO 4.3 / SRO 4.5)
During a loss of All AC power, the RCP seals are required to be isolated.
Included on Attachment E is opening the breakers to the SG ARVs in preparation for local operation.
K/A: 055G2.4.34 (RO 4.2/ SRO 4.1)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-l / SRO-U
ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2
..DraJ (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank
<91<81<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> I (P)revious 2 exams
< 3 / < 3 / < 2 (randomly selected)
(R)CA
>11>11>1 (S)imulator
ES-301, Rev. 9E Control Roomlln-Plant Systems Outilne Form ES-301-2 Facility:
Vogtle Date of Examination: 02/22/2010 Exam Level (circle one): RO I SRO-I / SRO-U Operating Test No.: 201 0-301 Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. Dropped Rod Recovery in Model (RO/SRO-l)
S, M, A A dropped rod will be recovered lAW AOP-1 8003-c, Rod control Malfunction Section A for Dropped Rods in Mode 1. During the recovery, the rod being retrieved will not move. This will require reconfiguring the rod control system back to its previous state prior to attempting the dropped rod recovery.
K/A: 003AA2.01 (RO 3.7/ SRO 3.9)
- b. Respond to Failure of PRZR Level Instrument (RO / SRO-l)
S, D, A 2
A PRZR level instrument will fail low requiring entry into AOP-1 8001 Section D. After to candidate attempts to place letdown back in service, a letdown isolation valve will NOT open requiring Excess Letdown to be placed into service.
K/A: 028AA1.05 (RO 3.7 / SRO 3.6)
- c. Transfer ECCS Pumps to Hot Leg Recirculation. Multiple Train S, D, A, P 3
A Components Fail to Align (RO / SRO-l)
EN, L During alignment of ECCS to Hot Leg Recirculation, multiple Train A components will fail to align requiring the use of the RNO column.
K/A: 006A4.05 (RO 3.9 / SRO 3.8)
S, N, A, L 4P An RHR pump will trip in Mode 4 requiring entry into AOP-1 8019, Section A, Loss of RHR capability in Mode 4. The flow path through the procedure will require the candidate to start an RCP.
K/A: 025G2.4.9 (RO 3.8 / SRO 4.2)
- e. Dilute Containment with Service Air in accordance with 19010-S, D, L 5
C, E-1, Loss of Reactor or Secondary Coolant, Step 29. (RO /
SRO-l)
The student will be required to use SOP 13130-1, section 4.4.2 to align service air to containment to dilute the hydrogen.
K/A: 028A4.01 (RO 4.0 / SRO 4.0) f.
N/A N/A N/A
ES-301, Rev. 9E Control Roomlln-Plant Systems Outline Form ES-301-2
- g. Respond to Fuel Handling Building High Radiation (RO/SRO-I)
S, D, A 7
High Radiation will occur due to dropped rod in FHB but auto actuation fails, manual system alignment is required.
K/A: 061AA1.01 (RD 3.6 / SRD 3.6)
- h. Transfer Steam Dumps to Steam Pressure Mode (RO I SRO-l)
S, N, A, L 4S The student will be required to transfer steam dumps to the steam pressure mode using step 14 of ADP 1 8009-C. The steam dumps will not work, the student must shift the temperature control to the SG ARVs.
K/A: 041A4.08 (RD 3.0 / SRD 3.1)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i. Bypass CNMT HI-I Bistables Following Loss of Heat Sink D, F, L, P 7
Bistables must be bypassed using the BTI equipment in order to align a feedwater flow path to the SGs during a loss of secondary heat sink. This will also require knowledge of how/ where to obtain multiple BTI keys to bypass 2 trains of equipment (RD / SRD-l)
K/A; 012A4.03 (3.6/3.6)
- j. Locally Start the TDAFW Pump D, F, L 8
Following a Control Room evacuation, the TDAFW pump is required to be locally started at Shutdown Panel C. Local transfer switches must be manipulated, the T & T valve checked for proper status, and throttling of AFW flow from the local panel is required using available flow indications.
K/A: 068AA1.02 (RD 4.3 / SRD 4.5)
During a loss of All AC power, the RCP seals are required to be isolated.
Included on Attachment E is opening the breakers to the SG ARVs in preparation for local operation.
K/A: 055G2.4.34 (RD 4.2/ SRD 4.1)
© All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RD I S RD-I I SRD-U (A)Iternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank
<91<81<4 (E)mergency or abnormal in-plant
? I I 1 I 1
(EN)gineered Safety Feature
- I I> 1 (control room system)
(L)ow-Power / Shutdown
> 1 /> 1 I> I (N)ew or (M)odified from bank including 1(A) 2 /
2 /
1 (P)revious 2 exams
< 3 I < 3 I < 2 (randomly selected)
(R)CA
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