ML113340410
| ML113340410 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/28/2011 |
| From: | NRC/RGN-II/DRS/OLB |
| To: | Progress Energy Florida |
| References | |
| 50-302/11-301 | |
| Download: ML113340410 (17) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: CRYSTAL RIVER 3 Date of Exam: SEPTEMBER 2011
ROK/ACaioyPcnts
SRO-Only_Points Tier Group K
K K
K K
KA A
A AG 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
L +/-
N/A 2_ j N/A 1
9 2
2 4
Evoluhons Tier Totals 5
4 5
5 4
4 27 5
5 10 1
23332232332 28 3
2 5
2.
Plant 2
Ill 11 101 111 10 0
2 1
3 Systems Tier Totals 3
4 4
4 3
3 3
3 4
4 3
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 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 / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
IRO SRO 007EK3.01 Reactor Trip
- Stabilization
- Recovery 4
4.6 El El El El El El El El El El Actions contained in EOP for reactor trip
/1 008AK3.02 Pressurizer Vapor Space Accident / 3 3.6 4.1 Why PORV or code safety exit temperature is below RCS or PZR temperature OO9EK1.01 Small Break LOCA /3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011 EK2.02 Large Break LOCA / 3 2.6 2.7 El Pumps 015AG2.4.46 RCP Malfunctions / 4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
025AK1.01 Loss of TRHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation 027AA2.14 Pressurizer Pressure Control System 2.8 2.9 RCP injection flow Malfunction / 3 029EK2.06 ATWS / 1 2.9 3.1 El El El El El El El El El El Breakers, relays, and disconnects.
038EA1.44 Steam Gen. Tube Rupture / 3 3.4 3.4 El El El El El El El El El El Level operating limits for S/Gs 040AG2.4.35 Steam Line Rupture
- Excessive Heat 3.8 4.0 El El El El El El El El El El Knowledge of local auxiliary operator tasks during Transfer / 4 emergency and the resultant operational effects 054AA1.04 Loss of Main Feedwater / 4 4.4 4.5 El El El El El El El El El El HPI, under total feedwater loss conditions Page 1 of 2 9/16/2010 9:49 AM
FORM ES-401-2 TOPIC:
Length of time for which battery capacity is designed Definition of saturation conditions implication for the systems Knowledge of EOP entry conditions and immediate action steps.
The cause of possible SWS loss Cause and effect of low-pressure instrument air alarm Voltatge regulator controls Facility s 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.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 055EK3.0l Station Blackout! 6 2.7 3.4 El 056AK1.04 Loss of Off-site Power! 6 3.1 3.2 058AG2.4.l Loss of DC Power! 6 4.6 4.8 El El El El El El El El El El {l 062AA2.02 Loss of Nuclear Svc Water! 4 2.9 3.6 El El El El El El El El El El 065AA2.0l Loss of Instrument Air! 8 2.9 3.2 El El El El El El El El El El 077AA1.03 Generator Voltage and Electric Grid 3.8 3.7 El El El El El El El El El El Disturbances! 6 BEO4EK2.2 Inadequate Heat Transfer
- Loss of 4.2 4.2 El El El El El El El El El El Secondary Heat Sink ! 4 Page 2 of 2 9!16!2010 9:49AM
ES-401, REV 9 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:
Reset of demand position counter to zero 2.9 3.8 Bases for power limit for rod misalignment 3.4 3.4 CVCS 2.7 3.1 Power supplies, including proper switch positions 3.8 4.2 Guidance contained in EOP for loss of containment integrity 3.4 3.2 Operating behavior characteristics of the facility.
3.3 3.7 J
Normal, abnormal and emergency operating procedures associated with (Flooding).
3.5 4
Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
003AK3.06 Dropped Control Rod / 1 2.7 3
OO5AK1.06 028AA1.02 032AK2.0l 069AK3.01 BAO2AA1.2 BA07AK1.2 BE03EA2.2 Inoperable/Stuck Control Rod /1 Pressurizer Level Malfunction / 2 Loss of Source Range NI / 7 Loss of CTMT Integrity / 5 LossofNNl-X/7 Flooding / 8 Inadequate Subcooling Margin / 4 BEO9EG2.4.30 Natural Circ. /4 Page 1 of 1 9/16/2010 9:49AM
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:
Seal injection flow Understanding of interface with LRS Relationship (dependence) of time available to perform system isolation surveillance test to time for decay heat to reach high limit Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).
Valves normally isolated from their control power Monitoring quench tank temperature Method of forming a steam bubble in the PZR CCW pump, including emergency backup Loads cooled by CCWS RCS pressure Bypass-block circuits RO SRO
003A3.0l Reactor Coolant Pump 3.3 3.2 004K1.35 Chemical and Volume Control 2.5 2.8 El El El El 005A1.06 Residual Heat Removal 2.7 3.1 El El El El El El l El El El El 005A4.05 Residual Heat Removal 2.8 2.8 El El El El El El El El El El 006K4.18 Emergency Core Cooling 3.6 3.7 El El El l El El El El El El El 007A1.03 Pressurizer Relief/Quench Tank 2.6 2.7 El El El El El El El El El El 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 El El El El El El El El El El 008K2.02 Component Cooling Water 3.0 3.2 El El El El El El El El El El 008K3.Ol Component Cooling Water 3.4 3.5 El El ] El El El El El El El El 010A1.07 Pressurizer Pressure Control 3.7 3.7 El El El El El El El El El El 012K6.04 Reactor Protection 3.3 3.6 El El El El El El El El El El Page 1 of 3 9/16/2010 9:49AM
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 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022K2.0l Containment Cooling 3.0 3.1 Containment cooling fans 026K1.01 Containment Spray 4.2 4.2 fl j ECCS 026K4.02 Containment Spray 3.1 3.6 Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray 039A2.03 Main and Reheat Steam 3.4 3.7 Indications and alarms for main steam and area radiation monitors (during SGTR) 059A3.03 Main Feedwater 2.5 2.6 Feedwater pump suction flow pressure 061 K2.0l Auxiliary/Emergency Feedwater 3.2 3.3 AFW system MOVs 062K3.03 AC Electrical Distribution 3.7 3.9 DC system 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 063K4.01 DC Electrical Distribution 2.7 3.0 Manual/automatic transfers of control 064A3.02 Emergency Diesel Generator 3.4 3.7 Minimum time for load pickup Page2of 3 9/16/2010 9:49AM
T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 k6 Al A2 A3 A4 G RO SAC 3.2 3.3 ES-401, REV 9 KA NAME / SAFETY FUNCTION:
064K6.08 Emergency Diesel Generator 073A4.03 Process Radiation Monitoring 3.1
3.2 TOPIC
Fuel oil storage tanks FORM ES-401-2 073G2.4.3 Process Radiation Monitoring 3.7 3.9 076G2.l.28 Service Water 4.1 4.1 Check source for operability demonstration 078A4.Ol Instrument Air 3.1 3.1 Ability to identify post-accident instrumentation.
103A2.05 Containment 2.9 3.9 Knowledge of the purpose and function of major system components and controls.
Pressure gauges Emergency containment entry Page 3 of 3 9/16/2010 9:49AM
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 K5.88 Control Rod Drive 2.9 3.4 Effects of boron on temperature coefficient 011 K3.03 Pressurizer Level Control 3.2 3.7 PZR PCS 014K4.06 Rod Position Indication 3.4 3.7 Individual and group misalignment 01 7A4.01 In-core Temperature Monitor 3.8 4.1 Actual in-core temperatures 027G2.4.6 Containment Iodine Removal 3.7 4.7 Lj j
Knowledge symptom based EOP mitigation strategies.
029K1.04 Containment Purge 3.0 3.1 Purge system 034A2.03 Fuel Handling Equipment 3.3 4.0 Mispositioned fuel element 041 A3.05 Steam Dump/Turbine Bypass Control 2.9 2.9 Main steam pressure 068K6.l0 Liquid Radwaste 2.5 2.9 Radiation monitors 075K2.03 Circulating Water 2.6 2.7 Emergency/essential SWS pumps Page 1 of 1 9/16/2010 9:49 AM
LI LI LI LI LI LI LI LI AbUity to use plant computer to evaluate system or component status.
4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
3.8 4.8 Ability to manage the control room crew during plant transients.
2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.
4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
2.9 4.1 Knowledge of pre-and post-maintenance operability requirements.
3.8 4.3 Ability to control radiation releases.
3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
ES-401, REV 9 RO SAC KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
G2.1.19 Conductof operations 3.9 3.8 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 G2.1.23 G2.l.6 G2.2.17 G2.2.2 G2.2.21 G2.3.1 1 G2.3.7 G2.4.4 G2.4.47 Conduct of operations Conduct of operations Equipment Control Equipment Control Equipment Control Radiation Control Radiation Control Emergency Procedures/Plans Emergency Procedures/Plans Page 1 of 1 9/16/2010 9:49AM
ES-401, REV 9 SRO 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 007EA2.04 Reactor Trip
- Stabilization
- Recovery 4.6 4.4 If reactor should have tripped but has not done so, I 1 manually trip the reactor and carry out actions in ATWS EOP 038EG2.4.20 Steam Gen. Tube Rupture / 3 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.
057AA2.06 Loss of Vital AC Inst. Bus! 6 3.2 3.7 AC instrument bus alarms for the inverter and alternate power source 062AG2.2.36 Loss of Nuclear Svc Water / 4 3.1 4.2 E D LI LI LI Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 077AG2.2.37 Generator Voltage and Electric Grid 3.6 4.6 Ability to determine operability and/or availability of safety Disturbances / 6 related equipment Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BEO5EA2.l Steam Line Rupture
- Excessive Heat Transfer / 4 3
4.2 Page 1 of 1 9/16/2010 9:49 AM
ES-401, REV 9 KA 003AA2.05 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RD SRO 2.5 3.2 3.3 4.0 3.9 4.1 BAO5AG2.2.12 Emergency Diesel Actuation! 6 3.7 4.1 Knowledge of surveillance procedures.
NAME / SAFETY FUNCTION:
Dropped Control Rod / 1 TOPIC:
005AG2.4.18 Inoperable/Stuck Control Rod / 1 051AA2.02 Loss of Condenser Vacuum / 4 FORM ES-401-2 Interpretation of computer in-core TC map for dropped rod location Knowledge of the specific bases for EOPs.
Conditions requiring reactor and/or turbine trip Page 1 of 1 9/16/2010 9:49AM
FORM ES-401-2 SRO T2G1 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 2.9 4.6 ED DDE DDDDDDDDL1 D
TOPIC:
Knowledge of the emergency action level thresholds and classifications.
Heater failures ES-401, REV 9 KA NAME / SAFETY FUNCTION:
008G2.4.41 Component Cooling Water 010A2.Ol Pressurizer Pressure Control 3.3 3.6 022A2.02 Containment Cooling 2.3 2.6 026A2.09 Containment Spray 2.5 2.9 059G2.l.25 Main Feedwater 3.9 4.2 Fan motor vibration Radiation hazard potential of BWST Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
Page 1 of 1 9/16/2010 9:49AM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 015A2.05 Nuclear Instrumentation 3.3 3.8 Core void formation 029A2.Ol Containment Purge 2.9 3.6 Maintenance or other activity taking place inside containment 071 G2.2.38 Waste Gas Disposal 3.6 4.5 Knowledge of conditions and limitations in the facility license.
Page 1 of 1 9/16/2010 9:49 AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
G2.1.15 Conduct of operations G2.1.31 Conduct of operations G2.2.19 Equipment Control G2.2.7 Equipment Control G2.3.4 Radiation Control G2.4.34 Emergency Procedures/Plans G2.4.8 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.4 3.6 3.7 4.1 4.5 FORM ES-401-2 RO
2.7 4.6 2.3 2.9 3.2 4.2
3.8 TOPIC
Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
Knowledge of maintenance work order requirements.
Knowledge of the process for conducting special or infrequent tests Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Page 1 of 1 9/16/2010 9:49AM
ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-1 (JPM Admin Outline)
NRC 2011 Rev 0.docx ES-301 Facility:
Crystal River Unit #3 Date of Exam:
09/12/11 thru 09/29/11 Examination Level:
1 (NRC)
Administrative Topic (See Note)
Type Code*
Describe activity to be performed Conduct of Operations M, R RO & SRO - (CO1) - Perform an RCS boron change calculation.
K/A - G2.1.37 RO 4.3 SRO 4.6 OP-304 Conduct of Operations D, R RO & SRO - (CO2) - Calculate SDM with a misaligned rod.
K/A - G2.1.7 RO 4.4 SRO 4.7 SRO Only - After completing the SDM calculation determine required ITS actions, if any.
K/A - G2.2.40 SRO 4.7 SP-421 Equipment Control M, R RO & SRO - (EC1) - Perform a QPTR calculation.
K/A - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the QPTR calculation determine required ITS actions, if any.
K/A - G2.2.40 SRO 4.7 SP-303 Radiation Control D, R RO & SRO - (RC1) - Determine stay times using survey maps.
K/A - G2.3.4 RO 3.2 SRO 3.7 DOS-NGGC-0004 Emergency Procedures
/ Plan D, P, R SRO Only - (EP1) - Determine Emergency Action Level and Protective Action Recommendations.
K/A - 2.4.41 SRO 4.6 K/A - 2.4.44 SRO 4.4 EM-202 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, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 1 of 1K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301 Facility:
Crystal River Unit #3 Date of Exam: 09/12/11 thru 09/23/11 Exam Level: RO SRO-I SRO-U Operating Test Number:
1 (NRC)
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.
CRDS - Perform actions of AP-504 K/A - 001A4.15 RO 3.1 SRO 3.1 (AP-504)
[RO]
D, S 1
- b.
ESFAS - Respond to an ES Actuation
[SRO-U]
K/A - BW/E03EA1.1 RO 4.1 SRO 3.8 (EOP-3)
[RO, SRO-I]
A, EN, N, S 4
Primary
- c.
PPCS - Respond to a stuck open PZR spray valve K/A - 010A4.01 RO 3.7 SRO 3.5 (AP-520)
[RO, SRO-I]
A, D, L, P, S
3
- d.
EFW - Establish Auxiliary Feedwater flow K/A - 061G2.1.20 RO 4.6 SRO 4.6 (EOP-04)
[RO, SRO-I]
N, S 4
Secondary
- e.
CSS - Initiate Reactor Building Spray
[SRO-U]
K/A - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)
[RO, SRO-I]
A, L, M, S 5
- f.
EDG - Synchronize Off-Site Power with EDG-1A K/A - 064A4.09 RO 3.2 SRO 3.3 (AP-770)
[RO, SRO-I]
D, S 6
- g.
CWS - Start CWP-1C While at Power
[SRO-U K/A - 075G2.1.31 RO 4.2 SRO 3.9 (OP-604)
[RO, SRO-I]
A, D, P, S 8
- h.
WGS - Respond to a Waste Gas Header leak K/A - 060AA2.05 RO 3.7 SRO 4.2 (AP-250)
[RO, SRO-I]
A, D, S 9
SPARE MU - Restart a MUP following an RCS leak isolation K/A - 002A2.01 RO 4.3 SRO 4.4 (AP-520)
D, S 2
In-Plant Systems* (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- i.
ECCS - Respond to a CFT Low Pressure condition
[SRO-U]
K/A - 006A1.13 RO 3.5 SRO 3.7 (AP-404)
[RO, SRO-I]
D, E, L, R 3
- j.
HRPS - Place a Hydrogen Analyzer in Service K/A - 028A4.03 RO 3.1 SRO 3.3 (EOP-14)
[RO, SRO-I]
A, D, E, L 5
- k.
WGDS - Perform a Waste Gas Release to the RB
[SRO-U]
K/A - 071G2.3.11 RO 3.8 SRO 4.3 (OP-412A)
[RO, SRO-I]
D, R 9
SPARE FS/OTSG - Transfer excess secondary inventory to FST K/A - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)
D, E 8
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 (control room system)
- / - / > 1
> 1 / > 1 / > 1
> 2 / > 2 / > 1 (randomly selected)
< 3 / < 3 / < 2
> 1 / > 1 / > 1
ES-301, Rev. 9, Supp. 1 Control Room / In-Plant Systems Outline Form ES-301-2 Page 2 of 2K:\\scandocs\\Operator Licensing\\Capehart\\Crystal River 2011-301\\Draft Exam\\Form ES-301-2 (JPM MCR-Plant Outline) NRC 2011 Rev 3.docx ES-301