ML091480100
| ML091480100 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/28/2009 |
| From: | Division of Nuclear Materials Safety II |
| To: | Southern Nuclear Operating Co |
| References | |
| Download: ML091480100 (17) | |
Text
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:,'::;,"I-",V Date of Exam: A/!:rY-Z &;1' r RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 3
2 4
3 3
3 18 3
3 6
Emergency &
2 2
2 1
1 2
1 9
2 2
4 Abnormal Plant N/A N/A Evolutions Tier Totals 5
4 5
4 5
4 27 5
5 10 1
3 2
2 3
3 3
2 3
2 2
3 28 2
3 5
- 2.
1 1
1 1
1 1
Plant 2
1 1
1 0
1 10 1
2 3
Systems Tier Totals 4
3 3
4 4
4 3
4 3
2 4
38 3
5 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 I
1 I
2 I
3 I
4 I
7 I
Categories 3
2 2
3 1
2 2
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 ofthe 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA 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 KIAs 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 KIA categories.
- 7.
- The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8.
On the following pages, enter the KIA 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. LimitSRO selections to KIAs that are linked to 10 CFR 55.43.
ES-401, REV 9 T1 G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G 007EA2.01 00BAK2.03 009EK3.16 RO SRO Reactor Trip - Stabilization - Recovery 4.1 4.3 0 0 0 0 0 0 0 Ii'l 0 0 0
/ 1 Pressurizer Vapor Space Accident / 3 2.5 2.4 0 Ii'l 0 0 0 0 0 0 0 0 0 Small Break LOCA / 3 3.B 4.1 0 0 Ii'l 0 0 0 0 0 0 0 0 015AG2.4.50 RCP 4
4.2 4.0 0 0 0 0 0 0 0 0 0 0 Ii'l 025AA2.05 Loss of RHR System /4 3.1 3.5 0 0 OOOOIi'lOOO 026AK3.03 Loss of Component Cooling Water / B 4
4.2 0 0 Ii'l 0 0 0 0 0 00 027AG2.4.6 Pressurizer Pressure Control System 3.7 4.7 0 0 0 0 0 0 0 0 0 0 Ii'l Malfunction / 3 029EK1.05 ATWS/1 2.B 3.2 Ii'l 0 0 0 0 0 0 0 000 03BEA 1.34 Steam Gen. Tube Rupture / 3 4.2 4.3 n 0 0 0 0 0 Ii'l 0 0 0 0 040AK2.02 055EK3.02 Steam Line Transfer / 4 Station Blackout / 6
- Excessive Heat 2.6 2.6 0 Ii'l 0 0 0 0 0 0 0 0 0 4.3 4.6 0 0 Ii'l 0 0 0 0 0 0 0 0 Page 1 of 2 FORM ES-401-2 TOPIC:
Decreasing power level from available indications Controllers and positioners Containment temperature, pressure, humidity and level limits Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Limitations on LPI flow and temperature rates of change Guidance actions contained in EOP for Loss of CCW Knowledge of EOP mitigation strategies.
definition of negative temperature coefficient as applied to large PWR coolant systems Obtaining shutdown with natural circulation Sensors and detectors Actions contained in EOP for loss of offsite and onsite power
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
056AG2.4.1 Loss of Off-site Power / 6 057AK3.01 Loss of Vital AC Inst. Bus / 6 058AK1.01 Loss of DC Power / 6 062AA 1.07 Loss of Nuclear Svc Water /4 065AA2.03 Loss of Instrument Air / 8 077 AK1.01 Generator Voltage and Electric Grid Disturbances / 6 WE04EA 1.1 LOCA Outside Containment / 3 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.6 4.8 0 0 0 0 0 0 0 DD~
4.1 4.4 0 0 ~
0 0 0 0 0 0 0 2.8 3.1
~ 0 0 0 0 0 0 0 0 o
2.9 3
nOD 0 0 0 ~ 0 0 0 0 2.6 2.9 0 0 0 0 0 0 0 ~ 0 0 0 3.3 3.5
~ 0 0 0 0 0 0 0 0 0 0 4.0 4.0 0 0 0 0 0 0 ~ 0 0 0 0 Page 2 of 2 FORM ES-401-2 TOPIC:
Knowledge of EOP entry conditions and immediate action steps.
Actions contained in EOP for loss of vital ac electrical instrument bus Battery charger equipment and instrumentation Flow rates to the components and systems that are serviced by the SWS; interactions among the components Location and isolation of leaks Definition of the terms: volts, watts, amps, VARS, power factor Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 001AK3.02 Continuous Rod Withdrawal / 1 3.2 4.3 D D ~ D D D D D D D D 003AK2.05 Dropped Control Rod / 1 2.5 2.8 D ~ D D D D D D D D D 059AG2.4.49 Accidental Liquid RadWaste ReI. / 9 4.6 4.4 D D D D D D D D D D ~
060AA2.03 Accidental Gaseous Radwaste ReI. /9 3.2 3.9 D D D D D D D ~ D D D 061AK2.01 ARM System Alarms / 7 2.5 2.6 D ~ D D D D D D D D D 076AA 1'.04 High Reactor Coolant Activity / 9 3.2 3.4 D D D D D D ~ D D D D WE03EK1.2 LOCA Cooldown - Depress. /4 3.6 4.1
~ D D D D D D D D D D WE08EK1.2 RCS Overcooling - PTS / 4 3.4 4.0
~ D D D D D D D D D D WE15EA2.1 Containment Flooding / 5 2.7 3.2 D D D D D D D ~ D D D
. Page 1 of 1.
FORM ES-401-2 TOPIC:
Tech-Spec limits on rod operability Control rod drive power supplies and logic circuits Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
The steps necessary to isolate a given radioactive-gas leak, using P&IDs Detectors at each ARM system location Failed fuel-monitoring equipment Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
Normal, abnormal and emergency operating procedures associated with (Pressurized Thermal Shock).
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
003K5.01 Reactor Coolant Pump 004A3.02 Chemical and Volume Control 004K6.02 Chemical and Volume Control 005K5.05 Residual Heat Removal 005K6.03 Residual Heat Removal 006K1.08 Emergency Core Cooling 007G2.1.7 Pressurizer Relief/Quench Tank 008K4.09 Component Cooling Water 010M.01 Pressurizer Pressure Control 010K1.05 Pressurizer Pressure Control T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.9 D D D D ~ D D D D D D 3.6 3.6 DDDDDD
~DD 2.5 2.6 D D D D D ~ D D D D D 2.7 3.1 D D D D ~ D D D D D D 2.5 2.6 D D D D D ~ D D 3.6 3.9
~ D D D D D D D D D D 4.4 4.7 D D D D DDD~
2.7 2.9 D D D ~ D D D D D D D 3.7 3.5 D D D D D D D D D ~ D 3.4 3.6
~ D D D D D D D D D D Page 1 of 3 FORM ES-401-2 TOPIC:
The relationship between the RCPS flow rate and the nuclear reactor core operating parameters (quadrant power tilt, imbalance, ONB rate, local power density, difference in loop T-hot pressure)
Letdown isolation Oem ineralizers and ion exchangers Plant response during "solid plant": pressure change due to the relative incompressibility of water heat exchanger CVCS Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
The "standby" feature for the CCW pumps PZR spray valve PATS
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 012K3.02 Reactor Protection 3.2 3.3 0 0 Ii'] 0 0 0 0 0 0 0 0 013A2.01 Engineered Safety Features Actuation 4.6 4.8 0 0 0 0 0 0 0 Ii'] 0 0 0 013K5.02 Engineered Safety Features Actuation 2.9 3.3 0 0 0 1i']000000 022A2.01 Containment Cooling 2.5 2.7 0 0 0 0 0 0 Ii'] 0 00 022G2.4.20 Containment Cooling 3.8 4.3 0 0 0 0 0 0 0 0 0 0 Ii']
026K3.02 Containment Spray 4.2 4.3 0 0 Ii'] 0 0 0 0000 039A4.04 Main and Reheat Steam 3.8 3.9 0 0 0 0 0 0 0 0 0 Ii'] 0 059A3.03 Main Feedwater 2.5 2.6 0 0 0 0 0 0 0 0 Ii'] 0 0 061K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 0 0 0 0 0 Ii'] 0 0 0 0 0 062K4.01 AC Electrical Distribution 2.6 3.2 0 0 0 Ii'] 0 0 0 o
Page 2 of 3 FORM ES-401-2 TOPIC:
T/G LOCA Safety system logic and reliability Fan motor over-current Knowledge of operational implications of EOP warnings, cautions and notes.
Recirculation spray system Emergency feedwater pump turbines Feedwater pump suction flow pressure Controllers and positioners Bus lockouts
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
062K4.03 AC Electrical Distribution 063K2.01 DC Electrical Distribution 064A1.02 Emergency Diesel Generator 073A2.02 Process Radiation Monitoring 076A1.02 Service Water 076K2.08 Service Water 078K1.03 Instrument Air 103G2.4.4 Containment T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.8 3.1 0 0 0 ~ 0 0 0 0 0 0 0 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 2.5 2.8 0 0 0 0 0 0 ~ 0 0 0 0 2.7 3.2 0 0 0 0 0 0 0 ~ 0 0 0 2.6 2.6 0 0 0 0 0 0 ~ 0 0 0 0 3.1 3.3 0 ~ 0 0 0 0 0 0 0 0 0 3.3 3.4
~ 0 0 0 0 0 0 0 0 0 0 4.5 4.7 DOD 0 0 0 0 0 0 0 ~
Page 3 of 3 FORM ES-401-2 TOPIC:
Interlocks between automatic bus transfer and breakers Major DC loads Fuel consumption rate with load Detector failure Reactor and turbine building closed cooling water temperatures.
ESF-actuated MOVs Containment air Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:
RO SRO 002A2.04 Reactor Coolant 4.3 4.6 D D D D D D D ~ D D D Loss of heat sinks 011 K2.01 Pressurizer 3.1 3.2 D ~ D D D D D D D Charging pumps 015K6.01 Nuclear Instrumentation 2.9 3.2 D D D D D ~ D D D D D Sensors, detectors and indicators 027G2.1.27 Containment Iodine Removal 3.9 4
D DDD~
Knowledge of system purpose and or function.
029K4.02 Containment Purge 2.9 3.1 DDD~DDDDDDD Negative pressure in containment 035A3.01 Steam Generator 4.0 3.9 DDDDDDDD~DD S/ G water level control 041A1.01 Steam DumpfTurbine Bypass Control 2.9 2.9 DDDDDD~DDDD T-ave. verification above lOW/low setpoint 055K3.01 Condenser Air Removal 2.5 2.7 DD~DDDDDDDD Main condenser 056K1.03 Condensate 2.6 2.6
~DDDDDDDDDD MFW 071K5.04 Waste Gas Disposal 2.5 3.1 DDDD~DDDDDD Relationship of hydrogen/oxygen concentrations to flammability Page 1 of 1
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.17 Conduct of operations G2.1.21 Conduct of operations G2.1.36 Conduct of operations G2.2.13 Equipment Control G2.2.17 Equipment G2.3.15 Radiation Control G2.3.4 Radiation Control G2.4.26 Emergency Procedures/Plans G2.4.28 Emergency Procedures/Plans G2.4.5 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.0 0 0 0 0 0 0 0 0 0 0 ~
3.5 3.6 DOD 0 0 DDDD~
3.0 4.1 0 0 0 0 0 0 0 0 0 0 ~
4.1 4.3 0 DDD~
2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~
2.9 3.1 0 0 0 0 0 0 0 0 D~
3.2 3.7 0 0 0 0 DDDDD~
3.1 3.6 0
DDDDDDDD~
3.2 4.1 0 0 0 0 0 0 0 0 0 0 ~
3.7 4.3 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Ability to make accurate, clear and concise verbal reports.
Ability verify the controlled procedure copy.
Knowledge of procedures and limitations involved in core alterations Knowledge of tagging and clearance procedures.
Knowledge of the process for managing maintenance activities during power operations.
Knowledge of radiation monitoring systems Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
Knowledge of procedures relating to emergency response to a security event (non-safeguards information).
Knowledge of the organization of the operating procedures network for normal, abnormal and emergency evolutions.
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO OOBAG2.2.4 Pressurizer Vapor Space Accident / 3 3.6 3.6 0 0 0 0 0 0 0 0 0 0 ~
011EA2.10 Large Break LOCA / 3 4.5 4.7 0
~DDD 025AA2.02 Loss of RHR System /4 3.4 3.B 0 0 0 0 0 0 0 ~ 0 0 0 056AG2.2.40 Loss of Off-site Power / 6 3.4 4.7 0 0 0 0 DDDDD~
065AA2.06 Loss of Instrument Air / B 3.6 4.2 0 0 0 0 0 0 0 ~ DOD we04EG2.1.7 LOCA Outside Containment / 3 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~
Page 1 of 1 FORM ES-401-2 TOPIC:
(multi-unit) Ability to explain the variations in control board / control room layouts, systems, instrumentation and procedural actions between units at a facility.
Verification of adequate core cooling Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere Ability to apply technical specifications for a system.
When to trip reactor if instrument air pressure is de-creasing Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 028AG2.4.8 Pressurizer Level Malfunction / 2 3.8 4.5 D D D D D D D D D D ~
068AA2.02 Control Room Evac. /8 3.7 4.2 D D D D D D D ~ D D D 076AG2.1.32 High Reactor Coolant Activity / 9 3.8 4.0 D D D D D D D D D D ~
WE10EA2.1 Natural Circ. With Seam Void! 4 3.2 3.9 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
Local boric acid flow Ability to explain and apply all system limits and precautions.
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
012G2.4.2 Reactor Protection 039G2.4.1 Main and Reheat Steam 062G2.2.36 AC Electrical Distribution 063A2.02 DC Electrical Distribution 103A2.02 Containment SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.S 4.6 D D D D D D D D D D ~
4.6 4.8 D D D D D D D D D D ~
3.1 4.2 D D D D D D D D D D ~
2.3 3.1 D
DDDDD~DDD 2.2 3.2 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Knowledge of EOP entry conditions and immediate action steps.
Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Loss of ventilation during battery charging Necessary plant conditions for work in containment
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
028A2.01 Hydrogen Recombiner and Purge Control 055G2.1.19 Condenser Air Removal 071 G2.1.20 Waste Gas Disposal SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.6 D D D D D D D ~ D D D 3.9 3.8 D D D D D D D D D D ~
4.6 4.6 D D D D DDDDD~
Page 1 of 1 FORM ES-401-2 TOPIC:
Hydrogen recombiner power setting, determined by using plant data book Ability to use plant computer to evaluate system or component status.
Ability to execute procedure steps.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.3 Conduct of operations G2.2.1 Equipment Control G2.2.15 Equipment Control G2.3.6 Radiation Control G2.3.7 Radiation Control G2.4.35 Emergency Procedures/Plans G2.4.38 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.7 3.9 D D D D D DDDD~
4.5 4.4 DDDDDDDDDD~
3.9 4.3 DDDDDDDDDD~
2.0 3.8 DDDDDDDDDD~
3.5 3.6 D D D D D D D D D D ~
3.8 4.0 D D DDDDDDD~
2.4 4.4 D D D D D D D D D D ~
Page 1 of 1 FORM ES-401-2 TOPIC:
Knowledge of shift or short term relief turnover practices.
Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
Ability to determine the expected plant configuration using design and configuration control documentaion Ability to aprove release permits Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects to take actions called for in the facility emergency supporting or acting as emergency
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Farley Nuclear Plant Date of Examination: Oct 27, 2008 Examination Level: SRO + RO Operating Test Number: FA2008301 Administrative Topic (see T;;ree Describe activity to be performed Note)
Co e
Conduct of Operations Al.1 Makeup to the RWST SOP-2.3 sect 4.2.3 and R/N determine the Tech specs that are applicable with the out of SRO spec reading given.
006Al.02 (3.0/3.6)
Conduct of Operations Al.2. CRO-122 Perform A Quadrant Power Tilt Ratio SRO+RO RID Calculation STP-7.0 015Al.04 RO-3.5 SRO-3.7 A2 Complete STP-9.0, DETERMINE RCS LEAK RATE, Equipment Control RIM Appendix 1, and identify conditions that do not meet acceptance criteria. CRO-035 RO 004A2.22 RO-3.2 SRO-3.1 A2 Complete STP-9.0, DETERMINE RCS LEAK RATE, Equipment Control RIM Appendix 1, and identify conditions that do not meet acceptance criteria. Then apply Tech specs for the SRO conditions that exist. CRO-035 004A2.22 RO-3.2 SRO-3.1 Radiation Control RIM A3 Determine if a job assigned can be accomplished based SRO+RO on Admin limits and RWP requirements given. G2.3.4 (3.2/3.7)
RIM A4 A Site Area emergency exists. Plant and SROONLY meteorological conditions have changed. Evaluate as the ED whether a follow-up message or an upgrade to a GE is required and fill out applicable forms for notification. An upgrade to a GE will be required and PAR recommendations will be required lAW NMP-EP-109.
G2.4.44 (4.4) Time critical JPM
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes) [1/1]
(N)ew or (M)odified from bank (~1) [3/4]
(P)revious 2 exams << 1; randomly selected) [0/0]
Parley OCT 2008 NRC ADMIN exam outline Page 1 of 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Farley Nuclear Plant Date of Examination:
October 27, 2008 Exam Level (both): RO SRO-I SRO-u Operating Test No.: FA2008301 Control Room Systems (8 for RO; 7 for SRO-i; 2 or 3 for SRO-U)
System / JPM Title Type Safety Code*
Function
- a.
CRO-NEW PERFORM CORRECTIVE ACTIONS IN S/ N / A 1
RESPONSE TO A MALFUNCTION OF THE ROD SRO-U CONTROL SYSTEM FOR A CONTINUOUS ROD WITHDRAWAL 001AA2.05 RO-4.4 SRO-4.6
- b.
CRO- 066D (modified) Borate the RHR system to S/ M/ AI L 2
prepare for RCS cooldown SRO-U 004A2.10 R03.9 SRO 4.2
- c.
CRO-333A (modified) Perform the Required Actions S/ M/ AI L 3
for Cold Leg Recirculation starting at step 7 OF ESP-SRO-U 1.3.
011 EA1.11 RO-4.2 SRO-4.2
- d.
CRO-358B, Place a SGFP on service while in FRP-S / D/ L 4
H.1 W/E05 EA1.1 RO-4.1 SRO-4.0
- e.
CRO-406E Two Train Verification of ECCS equipment S/ 0/ A 6
064A4.06 RO-3.9 SRO-3.9
- f.
CRO-328B Restore Instrument Air to Containment S/ AI D/ P 8
065AA1.03 RO-2.9 SRO-3.1
- g.
CRO-NEW Respond to a FH5, SFP AREA RE25A OR S/ N / A 9
B HI RAD, alarm 060AA1.02 RO-2.9 RO-3.1
- h.
RO ONLY CRO-343H Align R-11 /12 to normal in S/ D /L 7
response to a spurious 81 RO 073A4.02 RD-3.7 SRO-3.7 ONLY In-Plant Systems (3 for RO: 3 for SRO-i; 3 or 2 for SRO-U)
System / JPM Title Type Safety Code*
Function
- i.
SO - 130 Make Up To SFP From the RWST D/ R 8
033A1.01 RO-2.7 SRO-3.3 SRO-U
- j.
SO-311 Shift Auxiliary Feed Pump Suction D/ E/ L 4S Emergency Supply (NRAB)
SRO-U 061A1.04 RO-3.9 SRO-3.9
- k.
SO-090 Place 'A' BAT OIS & 'B' BAT O/R D/R 1or2 004K1.16 RD-3.3 SRO-3.5 Parley October 2008 NRC JPM exam Page 1 of2
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Ali 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-i/ SRO-U [ACTUAL]
(A)lternate path 4-6/4-6/2-3
[6/6/3]
(C)ontrol room (D)irect from bank
- 5:.9/:5:.8/:5:. 4
[7/6/2]
(E)mergencyor abnormal in-plant
- 1/;
- ::1/;:::1
[1 ]
(L)ow-Power / Shutdown
- 1/;
- ::1/2:. 1
[5/4/3]
(N)ew or (M)odified from bank including 1 (A)
- 2/2
- . 2 /2:. 1
[4/4/3]
(P)previous 2 exams
' :5:. 3 / :5:. 3 / :5:. 2 (randomly selected) [1/1/0]
(R)CA 2:. 1 /2:. 1 /;:::1
[2]
(S)imulator Farley October 2008 NRC JPM exam Page 2of2