ML120470096
| ML120470096 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/10/2012 |
| From: | NRC/RGN-II |
| To: | |
| Mark Bates | |
| Shared Package | |
| ML120470109 | List: |
| References | |
| Download: ML120470096 (26) | |
Text
ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Robinson Date of Exam: 201 1-302 RO K/A Category Points SRO-OnIy Points Tier Group ]
KIK K K K K A AAA G A2 G* Total 112 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 2 1 N/A 1 2 N/A 2 9 2 2 4 Plant Evolutions TierTotals 4 5 4 4 5 5 27 5 5 10 1 22323332323 28 3 2 5 2.
Plant 2 11111110111 10 2 1 3 Systems TierTotals 33434442434 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 2 2 1 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 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 En 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 SRO 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 SAC 038EG2.4.1 1 Steam Gen. Tube Rupture /3 4.0 4.2 Knowledge of abnormal condition procedures.
054AG2.4.1 1 Loss of Main Feedwater / 4 4.0 4.2 Knowledge of abnormal condition procedures.
055EA2.01 Station Blackout / 6 3.4 3.7 Edsting valve positioning on a loss of instrument air system 058AA2.03 Loss of DC Power / 6 DC loads lost; impact on ability to operate and monitor plant systems weO4EG2.4.3 LOCA Outside Containment /3 3.7 3.9 Ability to identify post-accident instrumentation.
WEO5EA2.1 Inadequate Heat Transfer Loss of
- Facility conditions and selectkn of appropriate Secondary Heat Sink / 4 procedures during abnormal and emergency operations.
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ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:
RO SRO OO1AG2.1.28 Continuous Rod Withdrawal/i 4.1 4.1 Knowledge of the purpose and function of major system components and controls.
068AG2.4.2 Control Room Evac. /8 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
076AA2.05 High Reactor Coolant Activity / 9 2.2 2.5 CVCS letdown flow rate indication WEO9EA2.1 Natural Circ. / 4 3.1 3.8 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
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ES-401, REV 9 SRO 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 003A2.03 Reactor Coolant Pump 2.7 3.1 Problems associated with RCP motors, including faulty motors and current, winding and bearing temperature problems 007A2.05 Pressurizer Relief/Quench Tank 3.2 3.6 Exceeding PRT high-pressure limits 022G2.4.50 Containment Cooling 4.2 4.0 U Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
059A2.03 Main Feedwater 2.7 3.1 Overteeding event 064G2.4.46 Emergency Diesel Generator 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
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ES-401, REV 9 SRO 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:
RD SRO 011 G2.2.38 Pressurizer Level Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.
045A2.1 1 Main Turbine Generator 2.4 2.9 Control problems in primary, e.g. axial flux imbalance; need to reduce load on secondary 056A2.04 Condensate 2.6 2.8 Loss of condensate pumps Page 1 of 1 6/2/2011 2:18PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:
RO SRO G2.1.31 Conduct of operations 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
G2.1 .41 Conduct of operations 2.8 3.7 Knowledge of the refueling processes G2.2.35 Equipment Control 3.6 Ability to determine Technical Specification Mode of Operation G2.2.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.43 Emergency Procedures/Plans 3.2 3.8 Knowledge of emergency communications systems and techniques.
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ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 007EG2.4. 11 Reactor Trip Stabilization
- - Recovery 4.0 4.2 Knowledge of abnormal condition procedures.
008AK2.03 Pressurizer Vapor Space Accident! 3 2.5 2.4 Controllers and positioners 009EK2.03 Small Break LOCA /3 3 3.3 j fJ S/Gs 011 EK1 .01 Large Break LOCA /3 4.1 4.4 Natural circulation and cooling, including reflux boiling.
015AK2.08 RCP Malfunctions! 4 2.6 2.6 J [J [] [ [] CCWS 022AA2.03 Loss of Rx Coolant Makeup / 2 3.1 3.6 El El El El El El El [ Failures of flow control valve or controller 025AK3.0l Loss of RHR System / 4 3.1 3.4 Shift to alternate flowpath 027AA1 .05 Pressurizer Pressure Control System 3.3 3.2 Malfunction / 3 LI El LI Transfer of heaters to backup power supply 029EG2.4.49 ATWS / 1 4.6 4.4 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
038EK1 .04 Steam Gen. Tube Rupture / 3 3.1 3.3 El El El El El El El El El El Reflux boiling 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 Pagelof2 6/2/2011 2:17PM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 055EG2.l .31 Station Blackout! 6 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
OS6AK1 .03 Loss of Offsite Power! 6 3.1 3.4 Definition of subcooling: use of steam tables to determine it 057AA2.04 Loss of Vital AC Inst. Bus /6 3.7 4 LI ESF system panel alarm annunciators and channel status indicators 058AA1 .02 Loss of DC Power! 6 3.1 3.1 Li Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector 065AA2.05 Loss of Instrument Air! 8 3.4 4.1 Li When to commence plant shutdown if instrument air pressure is decreasing WEO5EK3.1 Inadequate Heat Transfer Loss of 3.4 3.8 Secondary Heat Sink! 4 Li Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.
WE12EK3.3 Steam Line Rupture Excessive Heat 3.5 3.7 Manipulation of controls required to obtain desired Transfr / 4 operating results during abnormal and emergency situations.
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ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 005AK2.02 Inoperable/Stuck Control Rod / 1 2.5 2.6 Breakers, relays, disconnects and control room switches 028AA2.04 Pressurizer Level Malfunction / 2 2.6 3.1 Ammeters and running indicators for CVCS charging pumps 032AA2.09 Loss of Source Range NI / 7 2.5 2.9 Effect of improper HV setting 033AG2.2.44 Loss of Intermediate Range NI / 7 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 O6OAK1 .02 Accidental Gaseous Radwaste Rel. /9 2.5 3.1 . Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels 067AA1 .06 Plant Fire On-site / 8 3.5 3.7 Fire alarm 076AK2.01 High Reactor Coolant Activity / 9 2.6 3 Process radiation monitors weO8EG2.4.2 RCS Overcooling - PTS / 4 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
WE1OEK3.1 Natural Circ. With Seam Void/4 3.4 3.7 J Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure and reactivity changes and operating limitations and reasons for these operating characteristics.
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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 003A1 .07 Reactor Coolant Pump 3.4 3.4 RCS temperature and pressure 004K5.30 Chemical and Volume Control 3.8 4.2 Relationship between temperature and pressure in CVCS components during solid plant operation 004K6.14 Chemical and Volume Control 2.7 3.0 Recirculation path for charging pumps 005K3.Ol Residual Heat Removal 3.9 4.0 RCS 006K5.lO Emergency Core Cooling 2.5 2.9 Theory of thermal stress 007A1 .01 Pressurizer Relief/Quench Tank 2.9 3.1 Maintaining quench tank water level within limits 007K3.0l Pressurizer Relief/Quench Tank 3.3 3.6 Containment 01 OK1 .03 Pressurizer Pressure Control 3.6 3.7 RCS 010K4.0l Pressurizer Pressure Control 2.7 2.9 Spray valve warm-up 012A3.05 Reactor Protection 3.6 3.7 [] Single and multiple channel trip indicators 013K2.0l Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control Pagelof3 6/2/2011 2:17PM
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 022A3.0l Containment Cooling 4.1 4.3 Initia tion of safeguards mode of operation 022A4.03 Containment Cooling 3.2 3.2 Dampers in the CCS 026K1 .01 Containment Spray 4.2 4.2 ECCS 026K3.02 Containment Spray 4.2 4.3 Recirculation spray system 039K4.06 Main and Reheat Steam 3.3 3.6 Prevent reverse steam flow on steam line break 059A2.04 Main Feedwater 2.9 3.4 Feeding a dry S/G 059A3.02 Main Feedwater 2.9 3.1 Programmed levels of the S/G 061 K5.01 Auxiliary/Emergency Feedwater 3.6 3.9 Relationship between AFW flow and RCS heat transfer 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps 062A2.l0 AC Electrical Distribution 3.0 3.3 U U U U U U U Effects of switching power supplies on instruments and controls U U U U Battery capacity as it is affected by discharge rate 063A1 .01 DC Electrical Distribution 2.5 3.3 U U U U U U Page2of3 6/2/2011 2:17PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 063G2.4.41 DC Electrical Distribution 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
064K6.07 Emergency Diesel Generator 2.7 2.9 Air receivers 073G2.212 Process Radiation Monitoring 3.7 4.1 J Knowledge of surveillance procedures.
Li Li Li Li Li Li Knowledge of the specific bases for EOPs.
076G2.4.18 Service Water 3.3 4.0 Li Li Service water 076K2.0l Service Water 2.7 2.7 Li Li Li Li Li Li Li Li Li Li Li Containment vacuum system 103A4.09 Containment 3.1 3.7 Li Li Li Li Li Li Li Li Li Page3of3 6/2/2011 2:17PM
ES-401, REV 9 T2G2 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 A3.05 Control Rod Drive 3.5 3.5 Individual vs. group rod position 011 K2.02 Pressurizer Level Control 3.1 3.2 PZR heaters 015K6.0l Nuclear Instrumentation 2.9 3.2 Sensors, detectors and indicators 016K3.09 Non-nuclear Instrumentation 3.5 3.7 ESFAS 028A4.02 Hydrogen Recombiner and Purge 3.7 3.9 Location and interpretation of containment pressure Control indications 041 G2.4.l 1 Steam Dump/Turbine Bypass Control 4.0 4.2 Knowledge of abnormal condition procedures.
071 Ki .05 Waste Gas Disposal 2.7 2.8 Meteorological tower 072K5.0l Area Radiation Monitoring 2.7 3.0 Radiation theory, including sources, types, units and
. effects 079K4.0l Station Air 2.9 3.2 Cross-connect with lAS 086A1 .05 Fire Protection 2.9 3.1 LI LI LI LI LI LI LI FPS ineups Pagelofi 6/2/2011 2:17PM
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:
. I--I G2.l.15 Conduct of operations 27 3A Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.
G2.l.17 Conductof operations 3.9 4.0 Li Li Li Li Li Li Li Li Li Li i Ability to make accurate, clear and concise verbal reports.
G2.l.27 Conductof operations 3.9 4 Li Li Li Li Li Li Li Li Knowledge of system purpose and or function.
G22.6 Equipment Control 3.0 3.6 j jj Knowledge of the process for making changes to procedures G2.2.7 Equipment Control 2.9 3.6 Knowledge of the process for conducting special or infrequent tests G2.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 Li Li Li Li Li Li Li Li Li Knowledge of radiation exposure limits under normal and emergency conditions G2.4.25 Emergency Procedures/Plans 3.3 3.7 Li Li Li Li Li Li Li Li Li Li .
Knowledge of fire protection procedures.
G2.4.40 Emergency Procedures/Plans 2.7 4.5 Li Li Li Li Li Li Li Li Li Li Knowledge of the SROs responsibilities in emergency plan implementation.
G2.4.9 Emergency Procedures/Plans 3.8 4.2 Li Li Li Li Li Li Li Li Li Li Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
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ES-301 Administrative Topics Outline Form ES-301-1 Facility: H B Robinson Date of Examination: 1 1/28/1 1 Examination Level: RO X SRO Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note) Code*
M, R Perform OMM-024 Rod Position Channel Conduct of Operations Check Conduct of Operations D, R Calculate the boron addition required prior to initiating a natural circulation cooldown to CSD Perform Section 8.2.3 of OST-020, Shiftly M, R Surveillances Equipment Control N, R Calculate the maximum permissible stay time Radiation Control with emergency dose limits Emergency N/A Procedures/Plan 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)
2011-2 NRC RO Admin JPM Summary 2011-2 NRC JPM Admin RO Al-I Perform OMM-024 Rod Position Channel Check G2.1.20 Ability to interpret and execute procedure steps (CFR: 41.10 /43.5 /45.12)
RD 4.6, SRO 4.6 The plant has experienced a load reduction due to a disturbance on the electrical grid. 2 control rods did not move as the remainder of the bank automatically inserted into the core. The plant computer (ERFIS) failed during the transient which resulted in manual logs having to be taken due to the loss of monitoring function. The candidate will be expected to review the individual control rod positions and determine that 2 of the control rods are out of alignment with the bank.
2011-2 NRC JPM Admin RO A1-2 Calculate the boron addition required prior to initiating a natural circulation cooldown to CSD G2.1 .25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
(CFR: 41.10/43.5 / 45.12) RD 3.9, SRO 4.2 The candidate will be expected to calculate the boron addition needed for the plant to be placed in the cold shutdown condition while in natural circulation. This boration includes calculating the change in boric acid storage tank level.
2011-2 NRC JPM Admin RO A2 Perform Section 8.2.3 of DST-020, Shifty Surveillances G2.2.37 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7 /43.5 /45.12) RD 3.6, SRO 4.6 The candidate will be directed to complete DST-020, Shiftly Surveillances, Section 8.2.3. Several instruments will be out of tolerance for the parameters measured. The candidate will be expected to identify the out of tolerance instruments and make the appropriate log entries to identify the failures.
2011-2 NRC JPM Admin RO A3 Calculate the maximum permissible stay time with emergency dose limits G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
(CFR:41.12143.4145.1O) R03.2,SRO3.7 The candidate will be given specific tasks to be performed inside the Containment Vessel during a declared emergency event. He will be expected to calculate the dose to be received and apply the proper emergency dose limits to the allowed dose.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: H B Robinson Date of Examination: 11/28/11 Examination Level: RO SRO X Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note) Code Conduct of Operations M, R Heat Stress Work Limits Conduct of Operations N, R Complete Equipment Inoperable Record Perform Section 8.2.3 of OST-020, Shiftly Equipment Control M, R Surveillances Radiation Control Calculate emergency dose exposure time M, R limits Emergency Procedures/Plan M, R Classify an Emergency Event 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)
2011-2 NRC SRO Admin JPM Summary
/
2011-2 NRC JPM Admin SRO Al-I Heat Stress Work Limits G2.1 .26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
(CFR: 41.10/45.12) RO 3.4, SRO 3.6 The candidate will be expected to evaluate the heat stress work limits lAW AP-020. This determination will include the type of work to be performed, stay time and recovery time period.
2011-2 NRC JPM Admin SRO A1-2 Complete Equipment Inoperable Record G2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (CFR: 41.10 /45.12 /45.13) RO 3.6, SRO 3.8 The candidate will be expected to complete the OMM-007, Equipment Inoperable Record, for Component Cooling Water Pump B being inoperable. He will complete the necessary attachments, determine the allowed time to Modes 3 and 5, and determine whether a safety function determination is required for the equipment failure.
2011-2 NRC JPM Admin SRO A2 Perform Section 8.2.3 of OST-020, Shiftly S u rvei I lances G2.2.37 Ability to determine operability and/or availability of safety related equipment.
(CFR: 41.7 /43.5 /45.12) RO 3.6, SRO 4.6 The candidate will be directed to complete OST-020, Shiftly Surveillances, Section 8.2.3. Several instruments will be out of tolerance for the parameters measured. The candidate will be expected to identify the out of tolerance instruments and make the appropriate log entries to identify the failures. Once the out of tolerance instruments are identified, the candidate will be required to identify the applicable Technical Specification action statements for the affected instruments.
V 2011-2 NRC JPM Admin SRO A3 Calculate emergency dose exposure time limits.
G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
(CFR: 41.12/43.4 / 45.10) RO 3.2, SRO 3.7 The candidate will be given specific tasks to be performed and will be expected to apply the appropriate emergency exposure limits to the specified jobs.
2011-2 NRC JPM Admin SRO A4 Classify an Emergency Event.
G2.4.41 Knowledge of the emergency action level thresholds and classifications.
(CFR: 41.10 /43.5 /45.11) RO 2.9, SRO 4.6 The candidate will be given the necessary plant conditions to classify that an emergency event has occurred. This classification is required to be determined within 15 minutes of the onset of the event. Once the classification is communicated to the examiner, the candidate will be expected to fill out the Emergency Notification Form for communication to the state and counties within 15 minutes. Both portions of this JPM are time critical with a 15 minute completion criteria on each section.
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: H B Robinson Date of Examination: 1 1/28/11 Exam Level: RD X SRO-l X SRO-U X Operating Test No.:
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. Withdrawing Control Rod Shutdown Bank B A, M, S 1
- b. Align SI System for Cold Leg Recirculation (Time Critical) D EN L S 2
- c. PZR Pressure Control Malfunction A, D, S 3
- d. Transfer from Bypass to Main Feedwater Regulating Valves A M 4S
- g. Remove Source Range Instrument From Service D, L, S 7
- h. Respond to a Loss of CCW to the RCP Motor Coolers D, S 8 In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. Align Deepwell Pump D to Supply Cooling Water to EDGB D E
- j. Startup of Dedicated Shutdown UPS Inverter lAW N 6 OP -602
- k. Respond to Control Room Inaccessibility D, E, L, R 2
@ All RO and SRO-l 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 RD I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 I 23 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant 1 I 1 I 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/ 2 I -1 (P)revious 2 exams 3 /- 3 1 2 (randomly selected)
(R)CA (S)imulator JPM A: Withdrawing Control Rod Shutdown Bank B K/A 003 AK3.04 Knowledge of the reasons for the following responses as they apply to the Dropped Control Rod: Actions contained in EOP for dropped control rod.
(CFR: 41.5/41.10/45.6/45.13)
(Control Rod Drive System / 001) The candidate will be directed to withdraw Shutdown Bank B rods to support the upcoming reactor startup.
Once the control rods reach 70 steps withdrawn, Group 2 of Shutdown Bank B (4 control rods) will drop into the core. The candidate will be expected to enter AOP-001, Malfunction of Reactor Control System, and take the actions for dropped rods while the plant is in Mode 3. This will require that the remaining shutdown bank rods be driven into the core.
(CR-044 Bank JPM modified to drop the 4 control rods during withdrawal).
JPM B: Align SI System for Cold Leg Recirculation K/A 006 A4.05 Ability to manually operate and/or monitor in the control room: Transfer of ECCS flowpaths prior to recirculation.
(CFR: 41.7/45.5 to 45.8)
(Emergency Core Cooling System (ECCS) / 006) Candidate will transfer to cold leg recirculation lAW EPP-9, Transfer to Cold Leg Recirculation. This JPM is time critical. (CR-007 Bank JPM)
JPM C: PZR Pressure Control Malfunction K/A 010 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures.
(CFR: 41.5/43.5 /45.3/45.13)
(Pressurizer Pressure Control System (PZR PCS) / 010) Plant is operating in Mode 1 with the candidate directed to respond to plant conditions. The Auxiliary Spray valve will fail open, causing PZR pressure to lower. The candidate will be expected to take the immediate actions of AOP-01 9, Malfunction of RCS Pressure Control, and enter the procedure to analyze and respond to the lowering pressure. Once the failure is recognized, actions will be taken to isolate letdown and charging flow to isolate the auxiliary spray flow into the PZR. (CR-099 Bank JPM)
JPM D: Transfer from Bypass to Main Feedwater Regulating Valves K/A 045 Al .05 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of primary plant parameters (temperature and pressure) following TIG trip. (CFR: 41.5 I 45.5)
(Main Turbine Generator (MTIG) System I 045) Plant is in Mode I with the turbine at a low load and is ready for the Main Feedwater Regulating valves to be placed in service due to the capacity of the Feedwater Regulating Bypass valves. Once the feedwater transfer has been completed, a spurious turbine trip will occur and entry into AOP-007, Turbine Trip Below P-8, will be expected. The actions will reduce reactor power to less than 10% by manual or automatic rod insertion, along with the actions to ensure that the secondary plant is stabilized. AOP-007 and the turbine trip were recently changed so that an automatic reactor trip will not occur unless reactor power is above the P-8 setpoint of 40% power. (CR-045 Bank JPM modified with the turbine trip actions)
JPM E: Respond to RHR Leakage with the unit on RHR Cooling K/A 025 AA2.02 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere. (CFR: 43.5 /45.13)
(Loss of Residual Heat Removal System (RHRS) / 005) Plant is currently in Mode 5 with RHR supplying core cooling. When the RHR pumps are swapped, the RHR discharge relief valve lifts and fails to reseat. This results in a loss of RCS inventory and requires entry into AOP-020, Loss of Residual Heat Removal (Shutdown Cooling). The actions of AOP-020 will require that the RHR Pumps and Reactor Coolant Pumps be secured, along with the isolation of the RHR system. (CR-030 Bank JPM modified to change the leak location from an RCS pipe break to the RHR relief valve).
JPM F: Restore PRT to Normal Operating Conditions (RO ONLY)
K/A 007 Al .01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: maintaining quench tank water level within limits.
(CFR: 41.5/45.5)
(Pressurizer Relief Tank / Quench Tank System (PRTS) / 007) Candidate will restore level in the PRT to the normal operating band lAW OP-i 03, Pressurizer Relief Tank Control System. When securing the PRT fill lineup, Primary Water valve RC-519B will develop a hydraulic lock and will not close when demanded. This will require that actions be taken to relieve the hydraulic pressure using the appropriate section of OP-i 03.
(CR-056 Bank JPM)
JPM G: Remove Source Range Instrument from Service K/A 015 A4.03 Ability to manually operate and/or monitor in the control room: Trip bypasses. (CFR: 41.7 /45.5 to 45.8)
(Nuclear Instrumentation System (NIS)/ 015) The plant is in Mode 3 when a failure occurs on Source Range Channel N-31. The candidate will be directed to remove the failed channel from service using OWP-01 1, Nl-5.
This will remove the channel from scan on the ERFIS computer, bypass the channel trip signal and align the audio count rate channel to the operable Source Range channel. (CR-062 Bank JPM)
JPM H: Respond to a Loss of CCW to the RCP Motor Coolers K/A 008 K3.03 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: RCP. (CFR: 41.7)
(Component Cooling Water System (CCWS) I 008) Candidate will respond to a loss of CCW flow to the Containment when supply valve CC-716B inadvertently closes. Attempts to re-open the valve will be unsuccessful and will lead to entry into AOP-014, Component Cooling Water System Malfunction, and result in manually tripping the reactor and securing the Reactor Coolant Pumps. (2008 NRC exam JPM)
JPM I: Align Deepwell Pump D to Supply Cooling Water to EDG B K/A 076 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS.
(CFR: 41.5/43.5 /45.3 /45.13)
(Service Water System (SWS) / 076) Candidate will be directed to simulate establishing Deepwell Pump B flow to EDG B lAW EPP-28, Loss of Ultimate Heat Sink. This will require that EDG A be locally tripped, power supply for Deepwell Pump D aligned to 480V Bus E-2 (Train B) and flow manually established to EDG B through manual alignment of alternate cooling water valves. (lP-163 Bank JPM)
JPM J: Startup of Dedicated Shutdown UPS Inverter lAW OP-602 K/A 062 G2. 1.20 Ability to interpret and execute procedure steps: AC Electrical Distribution System (AC Electrical Distribution System / 062) Candidate will simulate placing the Dedicated Shutdown UPS Inverter back in service following maintenance activities. (New JPM written for 2011-2 NRC Exam)
JPM K: Respond to Control Room Inaccessibility K/A 068 AAI .06 Ability to operate and/or monitor the following as they apply to the Control Room Evacuation: Charging pump.
(CFR: 41.7 / 45.5 /45.6)
(Chemical and Volume Control System I 004) Candidate will simulate performing the breaker manipulations and local controls for inventory control lAW AOP-004, Control Room Inaccessibility, Attachment 1.