ML14351A054
| ML14351A054 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/17/2014 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| Shared Package | |
| ML14351A112 | List: |
| References | |
| ES-401, ES-401-2 50-348/OL-14, 50-364/OL-14 | |
| Download: ML14351A054 (18) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 L Facility:
FARLEY Date of Exam:
OCTOBER 2014
K/A CatpojyPoints_
SRO-Only_Points Tier Group KKKKKKAAAAG A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total 1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
Abnormal 2
.1. i N/A 2
I N/A 9
2 2
4 Evolutions Tier Totals 4
4 5
5 4
5 27 5
5 10 1
32332232233 28 3
2 5
2.
Plant 2
lIlLilif 110 10 0
2 I
3 Systems Tier Totals 4
3 4
4 3
3 4
3 3
4 3
38 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 I
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 KIA 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 0.1.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 trom 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 0.1.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 (If) 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 3RD-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 (If) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
Knowledge of less than one hour technical specification action statements for systems.
057AA1 05 Loss of Vital AC Inst. Bus / 6 3.2 3.4 iLiDcIrlLIDHr:rln Backup instrument indications ES-401, REV 9 T1G1 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 007EK2.02 Reactor Trip
- Stabilization
- Recovery 2.6 2.8 F] ] F] F] LI F] F] [] [] F] F]
Breakers, relays and disconnects
/1 008AK2 01 Pressurizer Vapor Space Accident! 3 2 7 2 7 v Li Li Li Li C F]
F]
Valves 01 5AK1.01 RCP Malfunctions / 4 4.4 4.6 LI [1 LI H Li F]: F] F] F] []
Natural circulation in a nuclear reactor power plant 025AK3.0l Loss of RHR System / 4 3.1 3.4
[] LI ii F] F] F] F] F] F] F] F]
Shift to alternate flowpath 026AA1.07 Loss of Component Cooling Water /8 2.9 3
F] F] Li LI [I Li
] Fl [1 F].
Flow rates to the components and systems that are serviced by the CCWS; interactions among the components 027AK1.02 Pressurizer Pressure Control System 2.8 3.1 Li LI H H [I Li El F] F] F]
Expansion of liquids as temperature increases Malfunction / 3
038EG2.4.11 Steam Gen. Tube Rupture /3 4.0 4.2 F] F] F] F] F] F] F] El [] [1 Knowledge of abnormal condition procedures.
054AA2.03 Loss of Main Feedwater /4 4.1 4.2 LI F] F] F] F] F] F] i flF] F]
Conditions and reasons for AFW pump startup 055EA2.01 Station Blackout! 6 3.4 3.7 F fl LI LI F] F] Li j [] IF] F]
Existing valve positioning on a loss of instrument air system 3.9 4.5 056AG2.2.39 Loss of Oft-site Power / 6 F]F]LIHDF]F]F]LZF]
Page 1 of 2 12/09/2013 11:09AM
ES-401, REV 9 T1G1 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 058AK3.02 Loss of DC Power! 6 4
4.2 LI LI Li Li Li Li [J Li C]
Actions contained in EOP for loss of do power 062AA2.03 Loss of Nuclear Svc Water / 4 2.6 2.9 C] C] Li Li Li Li ] Li Li Li The valve lineups necessary to restart the SWS while
bypassing the portion of the system causing the abnormal condition 065AK3.04 Loss of Instrument Air / 8 3
3.2 Li Li [ Li Li Li Li LI LI Li Li Cross-over to backup air supplies Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 AbiIy-to-dontif JkcL,L
-LftqO f,),
Cb.1II1I ç,
c2 f4O Components, capacity, and function of emergency systems.
WE11EA1.1 Loss of Emergency Coolant Recirc. /4 3.9 4.0 LiLiLILiL1L]i[..i EflLi Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
077AG2.4.
Generator Voltage and Electric Grid Z,13) Disturbances! 6
- _3.
LLt t.j ELiLiLILiLiLiEiLiLi WEC4EK2.2 LOCA Outside Containment / 3 3.8 4.0 Li J Li [1 Li Li Li LI Li C] 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.
WEO5EK1.1 3.8 4.1 LiLiLiLiLiLILiLJ Li Page2of2 12/09/2013 11:09AM
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 001 AG2.4.6 Continuous Rod Withdrawal / 1 3.7 4.7
[U [J LI Knowledge symptom based EOP mitigation strategies.
036AA1 02 Fuel Handling Accident/B 31 35 J E Li Z El v UI Li C fl ARM system 037AA2 07 Steam Generator Tube Leak / 3 3 1 3 6 E C C UI LI UI i EU L El Flowpath for dilution of ejector exhaust air 051 AK3.0l Loss of Condenser Vacuum / 4 2.8 3.1 12 LI Li LI Li Li Li Li C Li Loss of steam dump capability upon loss of condenser vacuum 068AK3.18 Control Room Evac. / 8 4.2 4.5 ri [1 i El [UI Li LI LI Li LI LI Actions contained in EOP for control room evacuation emergency task WEO3EK2.2 LOCA Cooldown
- Depress. / 4 3.7 4.0 LI LI LI LI LI LI [] LI Li i]
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.
weO6EG2.1.20 Degraded Core Cooling / 4 4.6 4.6 LI LI LI LI LI LI LI LI LI LI Ability to execute procedure steps.
- WEO8EA1.1 RCS Overcooling-PTS / 4 3.8 3.8
[J El 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.
WE15EK1.2 Containment Flooding! 5 2.7 2.9 rI Li Li LI LI LI Li [1 LI E.
Normal, abnormal and emergency operating procedures associated with (Containment Flooding).
Page lof 1 12/09/2013 11:09AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003K6.02 Reactor Coolant Pump 2.7 3.1 LI LI LI LI LI Lj LI LI LI LI RCP seals and seal water supply 004A1.07 Chemical and Volume Control 2.7 3.1 F] c] LI LI LI LI J LI LI LI []
Maximum specified letdown flow 004K1.06 Chemical and Volume Control 3.1 3.1 Li H LI F] LI LI LI Li Li F]:
Makeup system to VCT 005K5.02 Residual i-teat Removal 3.4 3.5 F]
Need for adequate subcooling 006A4.01 Emergency Core Cooling 4.1 3.9
[
LI Pumps 007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 F] LI LI F] L
. Li [J F] H Quench tank cooling 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 ri F] LI F]:
LI LI LI LI Li Li Method of forming a steam bubble in the PZR 008K3.03 Component Cooling Water 4.1 4.2 F] LI )) LI F] LI LI Li C] LI LI RCP 01 0A4 03 Pressurizer Pressure Control 4 0 3 8 F] El CI Li H LI LI F] Li El PORV and block valves 010K6.01 Pressurizer Pressure Control 2.7 3.1 LI LI LI F]I LI i Li LI LI LI F]
Pressure detection systems 012A2 03 Reactor Protection 34 37 J
[
F] F] F] F] j [] ] F]
Incorrect channel bypassing Pagelof3 12/09/2013 11:09AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki 1<2 1<3 K4 1<5 K6 Al A2 A3 A4 G TOPIC:
RO SRQ 013K2.0l Engineered Safety Features Actuation 3.6 3.8 fi H fi H j H H H H Li ESFAS/safeguards equipment control 022A2.01 Containment Cooling 2.5 2.7 Li [] E Li Li Li Li ij Fj H H Fan motor over-current 0261<1 01 Containment Spray 42 42 Li Li Li Ti 1
[ L ECCS 0261<3.02 Containment Spray 4.2 4.3 Li [T Li Li IF] F)) Li Li Li Li Recirculation spray system 039K4.02 Main and Reheat Steam 3.1 3.2 Li Li [ L Li Li fl[] Li [F]
Utilization of T-ave. program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits 059A4.08 Main Feedwater 3.0 2.9 E Li Li Li H H Ti H H li Li Feed regulating valve controller 059K3.03 Main Feedwater 3.5 3.7. { H j Li Li Li H Li* F)) [F] F]
S/GS 061A1.02 Auxiliary/Emergency Feedwater 3.3 3.6 fl L.. Li H H Li [i Li H [1 F))
S/G pressure 061 G2.1.23 Auxiliary/Emergency Feedwater 4.3 4.4
[1 H Li Li H H Li H Li H [1 Ability to perform specific system and integrated plant
procedures during all modes of plant operation.
062A1.03 AC Electrical Distribution 2.5 2.8 fi [F] H H H H j Li Li H Effect on instrumentation and controls of switching power supplies 063A3.01 DC Electrical Distribution 2.7 3.1 H H [1 Ti H H H Li Li Meters, annunciators, dials, recorders and indicating lights Page 2 of 3 12/09/2013 11:09AM
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ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR 1(1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001A3,06 Control Rod Drive H H H H H H H H ti Fl H RCS temperature and pressure 0151(2.01 Nuclear Instrumentation 3.3 3.7
[F]
H [1 F] L1 H [1 F] F] F]
NIS channels, components and interconnections 0171(6.01 In-core Tem perature Monitor 2.7 3.0 Fl H H H: H
[F] [] [j H [F]
Sensors and detectors 0271(1.01 Containment Iodine Removal 3.4 3.7 Es H H Fl H H F] [1 H H CSS 029A1 02 Containment Purge 3 4 3 4 H H H F] El F]
J
[
[
Radiation levels 035A4.06 Steam Generator 4.5 4.6 H H H H F] El H H H ii H S/G isolation on steam leak or tube ruptur&leak 0411(5.02 Steam Dump/Turbine Bypass Control 2.5 2.8 ] H LI H l H H H H H [F]
Use of steam tables for saturation temperature and pressure 045A2.12 Main Turbine Generator 2.5 2.8 F]
F] L LI H H i H H LI Control rod insertion limits exceeded (stabilize secondary) 055K3.01 Condenser Air Removal 2.5 2.7 H H [i Li H H H H LI H H Main condenser 0681(4.01 Uquid Radwaste 3.4 4.1 H H LI 1 Ti H H H1 H H H Safety and environmental precautions for handling hot, acidic and radioactive liquids Page 1 of 1 12/09/2013 11:09AM
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.18 Conduct of operations 3.6 3.8 LI Ability to make accurate, clear and concise logs, records, status boards and reports.
G2.l.5 Conduct of operations 2.9 3.9 H
L H L1 H fl fl Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
G2.2.42 Equipment Control 3.9 4.6 LI El LI LI LI LI LI [] [J LI J Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.2.44 Equipment Control 4.2 4.4
[]
Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions G2.3.11 Radiation Control 3.8 4.3 El LI LI LI LI LI LI LI LI LI [1 Ability to Control radiation releases.
G2.3.12 Radiation Control 3.2 3.7 LI LI LI LI LI LI LI LI LI LI Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.5 Radiation Control 2.9 2.9 LI LI LI LI LI LI LI LI LI LI [Zi Ability to use radiation monitoring systems G2 437 Emergency Procedures/Plans 3 0 4 1 H H H H H H LI H Li Knowledge of the lines of authority during implarnentation
of an emergency plan.
G2.4.49 Emergency Procedures/Plans 4.6 4.4 LI LI LI H LI LI LI LI LI LI [I Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
G2.4.9 Emergency Procedures/Plans 3.8 4.2 LI LI LI LI LI LI LI [IL LI I
Knowledge of low power) shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
Page 1 of 1 12/09/2013 11:09AM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-40i-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SPO
- 007EG2.4.18 Reactor Trip
- Stabilization
- Recovery 3.3 4.0 Li LI [] LI
[1 Li []
Knowledge of the specific bases for EOPs.
/1 009EG2.2.4 Small Break LOCA /3 3.6 3.6 H H LI Li ri H ri ri Li fl (multi-unit) Abitty to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
027A32.2.25 Pressurizer Pressure Control System 3.2 4.2
[1 H Li H H Li H H H [1 Knowledge of the bases in Technical Specifications for Malfunction / 3
limiting conditions for operations and safety limits.
029EA2.05 ATWS / 1 3.4 3.4 Li Li Li LI Li Li LI Li Li Li System component valve position indications 057AA2.16 Loss of Vital AC Inst. Bus / 6 3
3.1 Li El Li LI Li Li Li &i Li [1 LI Normal and abnormal PZR level for various modes of
plant operation 062AA2.01 Loss of Nuclear Svc Water / 4 2.9 3.5 Li Li LI LI Li Li Li i Li Li Li Location of a leak in the SWS Page 1 of 1 12/09/2013 11:09AM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003AG2.2.22 Dropped Control Rod! 1 4.0 4.7 r] Li LI LI LI LI [1 LI ri fl []
Knowledge of limiting conditions for operations and safety limits.
028AG2.l.32 Pressurizer Level Malfunction / 2 3.8 4.0
[LI Li LI LI EL Li Li J LI L I
Ability to explain and apply all system limits and precautions.
068AA2.08 Control Room Evac. /8 3.9 4.1 Fl [F [F
[] [ [F j fl LI [F SIG pressure WE1OEA2.2 Natural Circ. With Seam Void/4 3.4 3.9
[1 LI LI Li Li Li Li i Li LI LI Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
Page 1 of 1 12/09/2013 11:09AM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003G2.4.2 Reactor Coolant Pump 4.5 4.6 Li Li Li Li LI Li Li Li Li Li [
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
006A2.13 Emergency Core Cooling 3.9 4.2 fl fl Li Li Li rj Fl Li Li hadvertent Sf6 actuation 008G2.4.50 Component Cooling Water 4.2 4.0 Li fi LI Li Li Li [I Li L Li :
Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
012A2.05 Reactor Protection 3.1 3.2 Li LI Li Li LI Li Li
. Li LI H Faulty or erratic operation of detectors and function generators 073A2.02 Process Radiation Monitoring 2.7 3.2 Li Li Li Li Li Li Li l [I Li Li Detector failure Page 1 of 1 12/09/2013 11:09AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
034G2.4.30 Fuel Handling Equipment 072A2.03 Area Radiation Monitoring 079A2.0l Station Air SRO T2G2 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.7 4.1 2.7 2.9 DDfl.[][jr 2.9 3.2 DEL][ZCHL1[]r FORM ES-401-2 TOPIC:
Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
Blown power-supply fuses Cross-connection with lAS Page 1 of 1 12/09/2013 11:09AM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNC11ON:
IR Ki K2 K3 K4 1<5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.1.41 Conduct of operations 2.8 3.7 F] F] F] F] [] F] F] F] F] F]
Knowledge of the refueling processes G2 238 Equipment Control 3 6 45
[J J J U [J J J
[ []
Knowledge of conditions and limitations in the faciIi, license.
G2.2.41 Equipment Control 3.5 3.9 F] Li Li rI [1 F] [] F] F] F] j Ability to obtain and interpret station electrical and mechanical drawings G2.3.14 Radiation Control 3.4 3.8
[1 [1 F] F] Li F] F] [J F] F] [j Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.6 Radiation Control 2.0 3.8 F] F] LI F] F] F] F] F] F] F] i Ability to aprove release permits G2.4.26 Emergency Procedures/Plans 3.1 3.6 F] F] F] F] F] [] F] [1 F] F] Ti Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
G2.4.32 Emergency Procedures/Plans 3.6 4.0 F] F] F] [J LI LI LI Li [.1 F] i1 Knowledge of operator response to loss of all annunciators.
Page 1 of 1 12/09/2013 11:09AM
ES-301-1 Administrative Topics Outline Facility: Farley Nuclear Plant Date of Examination: October 6, 2014 Examination Level: RO X Operating Test Number: FA2014-301 Administrative Topic (see Note)
Type Code*
Describe activity to be performed
- a. A.1.a Conduct of Operations RO ONLY R, N
Title:
Determine load limitations with a 500 kV transmission line out of service.
G2.1.20 - 4.6 / 4.6 G2.1.25 - 3.9 / 4.2
Title:
Perform a Shutdown Margin Calculation in modes 1 & 2 (STP-29.5).
G2.1.20 - 4.6 / 4.6 G2.1.23 - 4.3 / 4.4
- c. A.2 Equipment Control RO ONLY R, M
Title:
Complete selected sections of completed STP-1.0, Operations Daily and Shift Surveillance Requirements.
G2.2.12 - 3.7 / 4.1 G2.2.42 - 3.9 / 4.6
Title:
Calculate the Maximum Permissible Stay Time within Dose Limits.
G2.3.4 - 3.2 / 3.7
- e. A.4 Emergency Procedures/Plan N/A NONE SELECTED 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 4
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) 0 (N)ew or (M)odified from bank ( 1) 4 (P)revious 2 exams ( 1; randomly selected) 0
ES-301-1 Administrative Topics Outline Facility: Farley Nuclear Plant Date of Examination: October 6, 2014 Examination Level: SRO X Operating Test Number: FA2014-301 Administrative Topic (see Note)
Type Code*
Describe activity to be performed
- a. A.1.a Conduct of Operations SRO ONLY R, N
Title:
Determine DG fuel level.
G2.1.25 - 3.9 / 4.2
Title:
Perform a Shutdown Margin Calculation in modes 1 & 2 (STP-29.5).
G2.1.20 - 4.6 / 4.6 G2.1.23 - 4.3 / 4.4
- c. A.2 Equipment Control SRO ONLY R, D
Title:
Review selected sections of STP-1.0, Operations Daily and Shift Surveillance Requirements and identify any required actions.
G2.2.40 - 3.4 / 4.7 G2.2.42 - 3.9 / 4.6
Title:
Calculate the Maximum Permissible Stay Time within Dose Limits.
G2.3.4 - 3.2 / 3.7
- e. A.4 Emergency Procedures/Plan SRO ONLY R, M
Title:
Determine Protective Action Recommendations.
G2.4.44 - 2.4 / 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 5
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) 1 (N)ew or (M)odified from bank ( 1) 4 (P)revious 2 exams ( 1; randomly selected) 0
ES-301-2 Control Room/In-Plant Systems Outline Facility:
Farley Nuclear Plant Date of Examination: October 6, 2014 Exam Level: RO SRO-I SRO-U-Operating Test No.:
FA2014 301 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.
CRO-065B: Inadvertent cooldown requires boration per AOP-27, Emergency Boration.
024AA2.05 3.3/3.9 A, L, M, S 1
- b.
CRO-NEW: Establish HHSI flow for Bleed and Feed during FRP-H.1.
013A4.01 - 4.5 / 4.8 013A4.02 - 4.3 / 4.4 013A4.03 - 4.5 / 4.7 A, EN, L, N, S (SRO-U) 2
- c.
CRO-076: Raise the A Accumulator Pressure.
006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8 D, S 3
- d.
CRO-336B: Check Feedwater status in response to a Reactor trip and Safety Injection.
059A3.04 - 2.5 / 2.6 059A3.06 - 3.2 / 3.3 059A4.08 - 3.0 / 2.9 061A3.01 - 4.2 / 4.2 A, D, L, S (SRO-U) 4S
- e.
CRO-066D: Borate the RHR System to prepare for RCS Cooldown.
005K1.04 2.9/3.1 D, L, S 4P
- f.
CRO-MOD: Perform actions of ESP-0.1. (Step 1.6 of ).
062A2.04 - 3.1 / 3.4 062A4.01 - 3.3 / 3.1 056AA1.31 - 3.3/3.3 056AA1.37 - 3.4/3.5 A, M, S 6
- g.
CRO-127A - Perform actions of AOP-100 for a NI-42 failure.
015A2.01 - 3.5 / 3.9 015A3.02 - 3.7 / 3.9 015A4.03 - 3.8 / 3.9 D, P, S (RO ONLY) 7
- h.
CRO-346: Align the Containment Spray (CS) system for the post-accident recirculation phase of operation.
026A4.01 4.5/4.3 A, M, L, S (SRO-U) 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
SO-351A (modified): Start 2C DG from DGLCP in Mode
- 4.
064A4.01 4.0/4.3 064A4.02 3.3/3.4 064A4.06 3.9/3.9 E, L, M (SRO-U) 6
- j.
SO-Fire Pump: Start a Motor Driven Fire Pump (MDFP) and Diesel Driven Fire Pump (DDFP) locally.
086A4.01 - 3.3 / 3.3 D, E, P 8
- k.
SO-95B, Align the Recycle Holdup Tank (RHT) to Drain to Waste Holdup Tank U2.
068K1.07 - 2.7 / 2.9 D, R (SRO-U) 9 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 (5/5/3)
(0) 9 / 8 / 4 (6/5/2) 1 / 1 /1 (2/2/1)
- / - / 1 (control room system)
(-/-/1) 1 / 1 / 1 (6/6/4) 2 / 2 / 1 (5/5/3) 3 / 3 / 2 (randomly selected)
(2/1/0) 1 / 1 / 1 (1/1/1)
(8/7/3)