ML15203A951
| ML15203A951 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 07/22/2015 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML15203A951 (24) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility:
MCGUIRE Date of Exam:
APRIL 2015
aoy_Pots_
S RD-Only Points Tier Group 1
1 K
KIK K
K K
A A
A AG A2 G*
Total 1
2f3 4
5 6
1 2
3 4
Total I
1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
Abnormal 2
L L I.
N/A
.1 N/A 9
2 2
4 Evoluons Tier Totals 5
4 4
5 4
5 27 5
5 10 1
22333233322 28 3
2 5
2.
Plant 2
11 111 11 101 1
10 0
2 1
3 ys ems Tier Totals 3
3 4
4 4
3 4
4 3
3 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 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 RD 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 RD 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 RD and SRO ratings for the RD 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 RD and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO OO7EA1.03 Reactor Trip Stabilization
- Recovery 4.2 4.1 RCS pressure and temperature 008AK2.01 Pressurizer Vapor Space Accident /3 2.7 2.7 Valves 009EA2.02 Small Break LOCA / 3 3.5 3.8 Possible leak paths 022AA1.07 Loss of Rx Coolant Makeup / 2 2.8 2.7 Excess letdown containment isolation valve switches and indicators 025AK2.01 Loss of RHR System / 4 2.9 2.9 RHR heat exchangers 027AG2.4.46 Pressurizer Pressure Control System 4.2 4.2 Ability to verify that the alarms are consistent with the Malfunction / 3 plant conditions.
029EG2.4.21 ATWS / 1 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions 038EK3.01 Steam Gen. Tube Rupture / 3 4.1 4.3 Equalizing pressure on primary and secondary sides of ruptured S/G 040AK3.04 Steam Line Rupture
- Excessive Heat 4.5 4.7 Actions contained in EOP5 for steam line rupture Transfer / 4 054AA2.03 Loss of Main Feedwater / 4 4.1 4.2 Conditions and reasons for AFW pump startup 055EK1.01 Station Blackout / 6 3.3 3.7 Effect of battery discharge rates on capacity Pagelof2 09/11/2014 10:19AM
ES-401, REV 9 T1GI 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 056AG2.4.47 Loss of Off-site Power / 6 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
057AA1.05 Loss of Vital AC Inst. Bus! 6 3.2 3.4 U LI LI U U U U U Li Li Backup instrument indications 058AA2.03 Loss of DC Power / 6 3.5 3.9 Li DC loads lost; impact on ability to operate and monitor plant systems 077AK1.03 Generator Voltage and Electric Grid 3.3 3.4 Under-excitation Disturbances / 6 WEO4EK3.4 LOCA Outside Containment / 3 3.6 3.8 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
WEO5EK1.3 Inadequate Heat Transfer
- Loss of 3.9 4.1 Annunciators and conditions indicating signals, and Secondary Heat Sink! 4 remedial actions associated with the (Loss of Secondary Heat Sink).
WE1 1 EK2.l Loss of Emergency Coolant Recirc. / 4 3.6 3.9 Li Li Li Li Li Li Li Li Li Li Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
Page 2 of 2 09/11/2014 10:19AM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 CRDS False indication of PZR level when PORV or spray valve is open and RCS saturated Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Effects of voltage changes on performance Area radiation monitors Time limit of long-term-breathing air system for control room Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Components, capacity, and function of emergency systems.
Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SAC 005AA1.01 Inoperable/Stuck Control Rod / 1 3.6 3.4 028AK3.03 Pressurizer Level Malfunction / 2 3.5 4.1 032AG2.2.36 Loss of Source Range NI / 7 3.1 4.2 033AK1.01 Loss of Intermediate Range NI / 7 2.7 3
060AA1.01 Accidental Gaseous Radwaste Rel. /9 2.8 3
067AA2.10 Plant Fire On-site/8 2.9 3.6 076AG2.4.50 High Reactor Coolant Activity / 9 4.2 4.0 El El El El El El El WEO8EK1.1 RCS Overcooling
- PTS / 4 3.5 3.8 El El El El El El El El El El WE1OEK2.l Natural Circ. With Seam Void/4 3.3 3.5 El El El El El El El El El El Page 1 of 1 09/11/2014 10:19AM
DEED DEED DEED EED DEED EED DEED DEED DEED EEJE DEED ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
d e
q u
a t
e cooling of RCP motor and seals Starting requirements RCS pressure and temperature Pressure transient protection during cold shutdown 003K4.04 Reactor Coolant Pump 2.8 3.1 E E E E E E 003K6.14 Reactor Coolant Pump 62 004A1.09 Chemical and Volume Control 3.6 3.8 005A2.02 Residual Heat Removal 3.5 3.7 005K5.02 Residual Heat Removal 3.4 3.5 E
E E 006A4.08 Emergency Core Cooling 4.2 4.3 006K5.04 Emergency Core Cooling 2.9 3.1 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 008A1.03 Component Cooling Water 2.7 2.9 010A4.02 Pressurizer Pressure Control 3.6 3.4 012K2.01 Reactor Protection 3.3 3.7 LI D E LI Need for adequate subcooling ESF system, including reset Brittle fracture, including causes and preventative actions Method of forming a steam bubble in the PZR CCW pressure PZR heaters RPS channels, components and interconnections Page 1 of 3 09/11/2014 10:19AM
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 013K3.03 Engineered Safety Features Actuation 4.3 4.7 Containment 022A3.01 Containment Cooling 4.1 4.3 Initia tion of safeguards mode of operation 025A2.02 Ice Condenser 2.7 2.5 High/low floor cooling temperature 026K1.01 Containment Spray 4.2 4.2 ECCS 039K4.06 Main and Reheat Steam 3.3 3.6 Prevent reverse steam flow on steam line break 059K3.04 Main Feedwater 3.6 3.8 RCS 061 K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 Controllers and positioners 062A1.01 AC Electrical Distribution 3.4 3.8 Significance of DIG load limits 062K3.01 AC Electrical Distribution 3.5 3.9 Major system loads 063G2.4.34 DC Electrical Distribution 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 064A3.07 Emergency Diesel Generator 3.6 3.7 Load sequencing Page2of3 09/11/2014 10:19AM
FORM ES-401-2 RO 3.1 2.7 2.7 4.4 2.7 3.9 ES-401, REV 9 KA NAME I SAFETY FUNCTION:
064K1.02 Emergency Diesel Generator 073A2.02 Process Radiation Monitoring 076K2.01 Service Water 078G2.1.30 Instrument Air 078K4.01 Instrument Air 1 03A3.01 Containment TOPIC:
DIG cooling water Detector failure system T2G1 PWR EXAMINATION OUTLINE IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.6 3.2 2.7 4.0 2.9 4.2 Service water Ability to locate and operate components, including local controls.
Manuallautomatic transfers of control Containment isolation Page 3 of 3 09/1112014 10:19AM
ES-401, REV 9 T2G2 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 001 K6.08 Control Rod Drive 2.9 3.2 Purpose and position switch of alarm for high flux at shutdown 002K4.07 Reactor Coolant 3.1 3.5 Contraction and expansion during heatup and cooldown 011K2.02 Pressurizer Level Control 3.1 3.2 LI PZR heaters 014K5.01 Rod Position Indication 2.7 3.0 Reasons for differences between RPIS and step counter 017A1.01 In-core Temperature Monitor 3.7 3.9 Core exit temperature 027A4.04 Containment Iodine Removal 2.8 2.9 LI LI LI LI LI LI LI LI El El Filter temperature 029G2.l.31 Containment Purge 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.
033K3.02 Spent Fuel Pool Cooling 2.8 3.2 LI El El El El El El El El El Area and ventilation radiation monitoring systems 035A2.05 Steam Generator 3.2 3.4 El El El El El El El El El El Unbalanced flows to the 5/Gs 068K1.07 Liquid Radwaste 2.7 2.9 El El El El El El El El El El Sources of liquid wastes for LRS Pagelofi 09/11/2014 10:19AM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
4.3 4.6 Knowledge of procedures, guidelines or limitations associated with reactivity management 5
3.4 Knowledge of new and spent fuel movement procedures 3.9 4.5 LI LI LI LI LI LI LI LI Knowledge of less than one hour technical specification action statements for systems.
3.6 3.6 LI j (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
4 3.8 LI Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 2.9 3.1 Knowledge of radiation monitoring systems 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions 3.4 4.1 Knowledge of EOP layout, symbols and icons.
3.1 3.6 LI Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
3.9 3.8 Knowledge of the ROs responsibilities in emergency plan implementation.
RO SRO G2.l.37 G2.1.42 G2.2.39 G2.2.4 G2.3.14 G2.3.15 G2.3.4 G2.4.l 9 G2.4.26 G2.4.39 Conduct of operations Conduct of operations Equipment Control Equipment Control Radiation Control Radiation Control Radiation Control Emergency Procedures/Plans Emergency Procedures/Plans Emergency Procedures/Plans Page 1 of 1 09/11/2014 10:19AM
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 SRO 007EG2.4.20 Reactor Trip
- Stabilization
- Recovery 3.8 4.3 Knowledge of operational implications of EOP warnings, I 1 cautions and notes.
009EG2.l.7 Small Break LOCA / 3 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
011 EG2.4.21 Large Break LOCA / 3 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions 026AA2.06 Loss of Component Cooling Water / 8 2.8 3.1 The length of time after the loss of CCW flow to a component before that component may be damaged 056AA2.73 Loss of Off-site Power! 6 3.5 3.6 PZR heater on/off 062AA2.04 Loss of Nuclear Svc Water! 4 2.5 2.9 The normal values and upper limits for the temperatures of the components cooled by SWS Page 1 of 1 09/11/2014 10:19AM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO Sf0 003AA2.03 Dropped Control Rod / 1 3.6 3.8 Dropped rod, using in-core/ex-core instrumentation in-core or loop temperature measurements 036AG2.2.37 Fuel Handling Accident / 8 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 037AA2.09 Steam Generator Tube Leak! 3 2.8 3.4 System status, using independent readings from redundant Condensate air ejector exhaust monitor 067AG2.l.23 Plant Fire On-site / 8 4.3 4.4 DDE DD Page 1 of 1 09/11/2014 10:19AM
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:
RD SRO 006G2.4.9 Emergency Core Cooling 3.8 4.2 LI Lj Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
022G2.4.35 Containment Cooling 3.8 4.0
[1 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 059A2.01 Main Feedwater 3.4 3.6 LI LI LI LI LI LI LI LI LI LI Feedwater actuation of AFW system 064A2.02 Emergency Diesel Generator 2.7 2.9 LI LI LI LI LI LI LI LI LI LI Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level temperatures 073A2.0l Process Radiation Monitoring 2.5 2.9 LI LI LI LI LI LI LI LI LI LI Erratic or failed power supply Pagelofl 09/11/2014 10:19AM
ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 001 A2.08 Control Rod Drive 2.9 3.3 El El El El El [] El El El Loss of CCW to CRDS 072A2.02 Area Radiation Monitoring 2.8 2.9 El El El El El El El El El El Detector failure 086G2.4.30 Fire Protection 2.7 4.1 ElElElElElElElElElEl Page 1 of 1 09/11/2014 10:19AM
ES-401, REV 9 SRO 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:
RO SRO G2.l.13 Conduct of operations 2.5 3.2 Knowledge of facility requirements for controlling vital!
controlled access.
G2.l.42 Conduct of operations 2.5 3.4 LI Knowledge of new and spent fuel movement procedures G2.2.12 Equipment Control 3.7 4.1 Knowledge of surveillance procedures.
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 G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.
G2.4.50 Emergency Procedures/Plans 4.2 4.0 LI LI LI LI LI LI LI LI LI LI Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Page 1 of 1 09/11/2014 10:19AM
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515)
Facility:
McGuire Date of Examination:
4/2015 Examination Level:
RO Operating Test Number:
N15-1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations M, R 2.1.37 (4.3)
Knowledge of procedures, guidelines or limitations associated with reactivity management JPM:
Perform an Estimated Critical Boron Concentration Conduct of Operations M, R 2.1.25 (3.9)
Ability to interpret reference materials, such as graphs, curves, tables, etc.
JPM:
Perform a Manual NC Leakage Calculation Equipment Control D, P, R 2.2.43 (3.0)
Knowledge of process used to track inoperable alarms.
JPM:
Partial Loss of Annunciators Radiation Control M, R 2.3.7 (3.5)
Ability to comply with radiation work permit requirements during normal or abnormal conditions.
JPM:
Evaluate Stay Time with Lowered SFP Level NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (4)
(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)
(N)ew or (M)odified from bank (> 1) (3)
(P)revious 2 exams ( 1; randomly selected) (1)
NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515)
RO Admin JPM Summary A1a This is a modified Bank JPM. The operator will be told that a Unit 1 startup in progress per OP/1/A/6100/001 (Controlling Procedure for Unit Startup), that all steps are complete up to determining the desired estimated critical rod height, and that the performance of the estimated critical rod height determination has resulted in the need to perform.1 (Estimated Critical Boron Concentration) of OP/0/A/6100/006 (Reactivity Balance Calculation). The operator will be provided with an initial set of plant /reactor conditions; and directed to perform an Estimated Critical Boron Concentration per.1 of OP/0/A/6100/006 (Reactivity Balance Calculation). The operator will be expected to determine that the Measured Critical Boron is 1810.5 PPM+/-1% (See attached KEY).
A1b This is a modified Bank JPM. The operator will be told that Unit 1 is at 100% power, the Unit 1 OAC point M1L4554 is out of service, and that PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations in accordance with the attached KEY, and identify that the Unidentified RCS Leakage Technical Specification has been exceeded.
A2 This is a Bank JPM. The operator will be told that while Unit 1 was operating at 100%
power, a lightning strike caused several of the Unit 1 Control Room Annunciators to fail requiring entry into PT/1/A4600/033 (Loss of Control Room Annunciators). The operator will be provided with a list of failed annunciators; and directed to continue with Enclosure 13.2 (Partial Loss of Annunciator Panels), and identify the affected Annunciators, if any, that have an Alternate Method for Surveillance that are applicable. The operator will be expected to determine that 11% of the Annunciators have failed in accordance with the attached Key, and identify five (5) specific annunciators that have an identified Alternative Method for Surveillance. This JPM was randomly selected from among the JPMs on the previous two NRC exams. It appeared on the 2013 NRC Exam.
A3 This is a modified Bank JPM. The operator will be told that a station wide accident has occurred due to an Earthquake, that Unit 1 is Mode 6 with a full core off-load, that the Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level, and that the crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature). They will also be told that there are no installed radiation monitors are operable in the Spent Fuel Building, that an RWP limit of 25 mrem has been placed on all personnel performing emergency tasks within the building, and that the operator has been assigned a repetitive task within Generic 2 which will require them to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The operator will be directed to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs.
Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times they will be able to perform this repetitive task before they must be replaced by another operator. The operator will be expected to use Enclosure 13 of AP/1/A/5500/41 to determine that the dose rate around the Spent Fuel Pool area is 25.2 NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515) mrem/hour and based on this the operator will determine that the repetitive task can be performed 19 times before another operator will need to perform the task. This JPM is identical to the N15 A3 SRO JPM.
NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515)
Facility:
McGuire Date of Examination:
4/2015 Examination Level:
SRO Operating Test Number:
N15-1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations D, P, R 2.1.37 (4.6)
Knowledge of procedures, guidelines or limitations associated with reactivity management JPM:
Perform an ECP Conduct of Operations M, R 2.1.25 (4.2)
Ability to interpret reference materials, such as graphs, curves, tables, etc.
JPM:
Perform/Review a Manual NC Leakage Calculation Equipment Control M, R 2.2.18 (3.9)
Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.
JPM:
Perform a Thermal Margin Determination Radiation Control M, R 2.3.7 (3.6)
Ability to comply with radiation work permit requirements during normal or abnormal conditions.
JPM:
Evaluate Stay Time with Lowered SFP Level Emergency Procedures/Plan N, R 2.4.44 (4.4)
Knowledge of emergency plan protective action recommendations.
JPM:
Provide an updated PAR NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (0) (S)imulator, (0) 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) (1)
NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515)
SRO Admin JPM Summary A1a This is a Bank JPM. The operator will be told that Reactor Startup is an hour away, and provided with a set of initial conditions. The operator will be asked to perform an Estimated Critical Position (ECP) in accordance with OP/0/A/6100/06, Reactivity Balance Calculation, Enclosure 4.2, Estimated Critical Rod Position. During the course of the ECP, the operator will be given a set of power history conditions, and asked to perform a Shutdown Fission Product Correction calculation in accordance with OP/0/A/6100/06, Reactivity Balance Calculation, Enclosure 4.8, Shutdown Fission Product Correction Calculation, in support of the ECP. The operator will be expected to calculate the Estimated Critical Rod Position Bank for No and Peak Xenon at time of Criticality per the attached KEY. This JPM was randomly selected from among the JPMs on the previous two NRC exams. It appeared on the 2013 NRC Exam.
A1b This is a modified Bank JPM. The operator will be told that Unit 1 is at 100% power, the Unit 1 OAC point M1L4554 is out of service, and that PT/1/A/4200/040 (Reactor Coolant Leakage Detection) has been completed showing that NCS Leakage is 1.6 gpm. The operator will be given Enclosure 13.2 (NC Leakage Determination Using Manual Calculations) of PT/1/A/4150/001B (Reactor Coolant Leakage Calculation) with the necessary raw data compiled on a Data Sheet; and directed to complete the calculations within the Enclosure. The operator will be expected to complete all calculations in accordance with the provided Key, identify any Technical Specification Limits that have been exceeded, and identify with all Technical Specification ACTION.
A2 This is a modified Bank JPM. The operator will be told that Unit 1 was shutdown 13 days ago for a mid-cycle outage after 200 days of operation, that Unit 1 is currently in Mode 5 with the NC system is 125°F and A Train ND in service; and that preparations are being made to lower NC system level to 60 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OP/1/A/6100/SD-20 (Draining the NC System). The operator will be directed to complete Attachment 12.6 of OMP 5-8 (Shift Supervision Turnovers) to determine the new thermal margin with NC system level at 67 inches above Hot Leg Centerline and make the appropriate notifications (Complete all paperwork). The operator will be expected to complete Attachment 12.6 (Thermal Margin Determination) of OMP 5-8 (Shift Supervision Turnovers) with a new thermal margin calculated and documented on 2.7 (Shutdown Assessment Status) in accordance with the provided KEY.
A3 This is a modified Bank JPM. The operator will be told that a station wide accident has occurred due to an Earthquake, that Unit 1 is Mode 6 with a full core off-load, that the Unit 1 Spent Fuel Pool level has lowered to 12.5 feet above the top of the fuel, and has stabilized at this level, and that the crew is implementing AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level) and EP/1/A/5000/G-1 Generic Enclosures), Enclosure 32 (Monitoring Unit 1 SFP Level and Temperature). They will also be told that there are no installed radiation monitors are operable in the Spent Fuel Building, that an RWP limit of 25 mrem has been placed on all personnel performing emergency tasks within the building, and that the operator has been assigned a repetitive task within Generic 2 which will require them to enter the Fuel Building and proceed to the area around the Spent Fuel Pool, and remain there for 3 minutes, before exiting the building.
The operator will be directed to use Enclosure 13 (Spent Fuel Pool Radiation Level Vs.
Water Level Above Fuel) of AP/1/A/5500/41 (Loss of Spent Fuel Cooling or Level), and determine the number of times they will be able to perform this repetitive task before they NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 (Rev_020515) must be replaced by another operator. The operator will be expected to use Enclosure 13 of AP/1/A/5500/41 to determine that the dose rate around the Spent Fuel Pool area is 25.2 mrem/hour and based on this the operator will determine that the repetitive task can be performed 19 times before another operator will need to perform the task. This JPM is identical to the N15 A3 RO JPM.
A4 This is a new JPM. The operator will be placed in a post-accident condition with a Large Break LOCA with a release from the Containment. The operator will be told that a General Emergency has been declared, and provided with the initial Protective Action Recommendation (PAR). The operator will be given a subsequent set of plant conditions and meteorological data, and asked to provide an updated PAR in accordance with.4 (Offsite Protective Recommendations) of RP/0/B/5700/029 (Notifications to Offsite Agencies from the Control Room), and then to complete the Emergency Power Plant Emergency Notification Form. The operator will be expected to determine the PAR for the current conditions and complete the Emergency Power Plant Emergency Notification Form as reflected on the provided KEY within 15 minutes.
NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_020515)
Facility:
McGuire Date of Examination:
4/2015 Exam Level (circle one):
Operating Test No.:
N15-1 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.
061 Auxiliary/Emergency Feedwater System [061 A2.04 (3.4/3.8)]
Operate the Turbine Driven CA Pump from the Control Room S, D, A, EN 4S B.
010 Pressurizer Pressure Control System [010 A4.03 (4.0/3.8)]
Place LTOP in Service and Respond to a Failed PORV S, N, A, L 3
C.
EPE 074 Inadequate Core Cooling [074 EA1.01 (3.7/3.8) ]
Align Alternate Makeup During Inadequate Core Cooling Conditions S, N 4P D.
013 ESF Actuation System [013 A4.01 (4.5/4.8)]
Respond to Failed ESF Actuation S, P, D, A 2
E.
APE 003 Dropped Rod [APE 003 AA1.02 (3.6/3.4)]
Retrieve a Dropped Control Rod S, M, A 1
F.
APE 026 Loss of Component Cooling Water [026 AA1.02 (3.2/3.3)]
Respond to High VCT Temperature S, D, A 8
G.
073 Process Radiation Monitoring System [073 A4.02 (3.7/3.7)]
Respond to the 1EMF-35 Trip 2 Alarm S, D 7
H.
APE 056 Loss of Off-Site Power [056 AA1.02 (4.0/3.9)]
Restore Normal Power to 1ETB and Unload the 1B EDG S, D 6
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I.
APE 069 Loss of Containment Integrity [069 AA1.03 (2.8/3.0)]
Start the Hydrogen Analyzers D, P, R, E 5
J.
EPE 055 Station Blackout [055 EA2.04 (3.7/4.1)]
Transfer of 1EMXA4 To SSF During A Loss Of All AC on Unit 1 M, R, E 6
K.
EPE E05 Loss of Secondary Heat Sink [E05 EA1.1 (4.1/4.0)]
Manually Fail Open 2SA-48ABC and 2SA-49AB D, E 4S NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_020515)
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 4-6 (5) /4-6 (5) / 2-3 (3)
(C)ontrol room (D)irect from bank 9 (7) / 8 (6) / 4 (2)
(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)
(EN)gineered Safety Feature
- / - / 1 (1) (Control Room System)
(L)ow-Power / Shutdown 1 (1) / 1 (1) / 1 (1)
(N)ew or (M)odified from bank including 1(A) 2 (4) / 2 (4) / 1 (3)
(P)revious 2 exams 3 (2) / 3 (2)/ 2 (1) (Randomly Selected)
(R)CA 1 (2 )/ 1 (2) / 1 (2)
(S)imulator JPM Summary JPM A This is a Bank JPM. The operator will be told that Unit 1 is operating at 98% power, that Maintenance has requested Operations to run the TD CA Pump to allow them to check vibration for pump retest, and that a normal start of the TD CA Pump is desired. The operator will be directed to start the TD CA Pump per OP/1/A/6250/002 Enclosure 4.4 (Manual Operation of #1 TD CA Pump) from the Control Room and run it in recirc for 10 minutes. During the pump run a bearing failure will occur (Alternate Path). The operator will be expected to start the #1 TD CA Pump in recirc from the Control Room and then diagnose a bearing failure has occurred, and stop the pump immediately.
JPM B This is a new JPM. The operator will be told that Unit 1 is in a cooldown and depressurization in accordance with OP/1/A/6100/SD-4, (Cooldown to 240 Degrees F),
that the 1B, 1C and 1D NCPs are operating, and that conditions have been established for placing LTOPs in service. The operator will be directed to place the LTOP System in operation beginning with Step 3.13.2 - of Enclosure 4.1 of OP/1/A/6100/SO-10 (Controlling Procedure for LTOP Operation) and monitor for proper operation. The operator will be expected to place LTOP in service by first placing 1NC-32B in service per procedure; and then respond to a failed open Pzr PORV (1NC-34A) by closing the failed open Pzr PORV Block Valve (Alternate Path).
JPM C This is a New JPM. The operator will be told that Unit 1 has had a LOCA, that all NV, NI and ND Pumps are either OOS, unavailable or have failed, that a Red Path exists on Core Cooling and that the crew has entered EP/1/A/5000/FR-C.1, Response to Inadequate Core Cooling; and that they are an available operator in the Control Room. The operator will be directed to try to establish flow from all available sources per Enclosure 3 (Alternate Makeup Sources) of FR-C.1, while the crew continues in the body of the procedure. The operator will be expected to perform Enclosure 3 of FR-C.1 and coordinate with the AO to start the Standby Makeup Pump; and then start the PD Pump in accordance with Generic 7.
JPM D This is a Bank JPM. The operator will be told that Unit 1 has experienced an ATWS and an inadvertent Train A Safety Injection actuation, and that the crew is presently performing EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS). The operator will NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_020515) be directed to perform Enclosure 3 (Subsequent S/I Actions) of EP/1/A/5000/FR-S.1 (Response to Nuclear Power Generation/ATWS), while the crew continues with the actions of EP/1/A/5000/FR-S.1. The operator will be required to manually actuate the B Train of SI which is expected to start the 1B RN Pump, the operator will observe that the 1B RN Pump has tripped (Alternate Path). The operator will be expected to complete the required actions of Enclosure 3 including manually actuating the Train B of SI and Phase A CIS, reset the Train B SIS and Sequencer and dispatch an operator to stop the B Diesel Generator using the Emergency Stop Pushbutton. This was previously used on the 2013 NRC Exam, randomly selected for use on the 2015 Exam.
JPM E This is a modified Bank JPM. The operator will be told that Unit 1 is operating at 30%
power with TAvg = TREF, that Control Rod H-8 in"D" Control Bank has dropped to the bottom of the core, that AP/1/A/5500/14 (Rod Control Malfunction) has been implemented and completed through step 17 of Enclosure 1 (Response to a Dropped Control Rod), and that IAE has repaired the cause of the dropped rod and has determined that rod realignment is permissible. The operator will be directed to complete Enclosure 1 of AP/1/A/5500/14 (Rod Control Malfunction), beginning at step 26, and recover the dropped rod. The operator will be expected to start to recover Control Rod H-8 such that when the operator is withdrawing Control Rod H-8, it is the only Control Rod in Bank D moving, and approaching indicated Control Bank D position; and then manually trip the reactor (Alternate Path) when a second dropped rod occurs.
JPM F This is a Bank JPM. The operator will told that Unit 1 was at 100% power when a leak developed in the KC System, that the crew entered AP/1/A/5500/21 (Loss of KC or KC System Leakage) and has completed the actions through Step 12. They will be told that MCB Annunciator 1AD-7, D1, VCT HI TEMP, has just alarmed, making Foldout Page item
- 5 applicable. The operator will be directed to perform the actions of Enclosure 4.6 of AP/1/A/5500/21 (Loss of KC or KC System Leakage), while the crew continues with the AOP. The operator will be expected to isolate Letdown, and attempt to start the PD Pump.
When the PD Pump fails to start (Alternate Path), and the operator will ultimately align the suction of the NV Pumps to the FWST JPM G This is a Bank JPM. The operator will be told that Unit 1 is at 100% power, and that Annunciator 1RAD2 A1, 1EMF-35 UNIT VENT PART HI RAD, has just alarmed. The operator will be directed to respond to this alarm. The operator will be expected to place the Aux Building Filtered Exhaust System in operation and the Train B Outside Air Pressure Filter Train in service.
JPM H This is a Bank JPM. The operator will be placed in a situation with both Unit 1 and Unit 2 involved in a Loss of Offsite Power. The operator will be told that both the 1A and 1B, as well as the 2A and 2B Diesel Generators automatically started and re-powered their respective essential busses. With the Off-Site power now restored, the operator will be directed to restore 1ETB to normal power and unload the D/G from the Control Room per OP/1/A/6350/002 (Diesel Generator), Enclosure 4.4 (1B D/G Shutdown). While 1ETB is being powered by the 1B D/G, the operator will be expected to parallel 1ETB, with 1ATD, and then unload the DG.
JPM I This is Bank JPM. The operator will be told that Unit 1 has tripped from 100% power due to an accident, that the crew is currently in EP/1/A/5000/FR-Z.1 (Response to High Containment Pressure), and that the crew is currently checking Containment Hydrogen Concentration. The operator will be directed to place the Hydrogen Analyzers in service NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (REV_020515) in accordance with Enclosure 5 (Placing H2 Analyzers In Service) of EP/1/A/5000/G-1 (Generic Enclosures). The operator will be expected to place the 1A Hydrogen Analyzer in service. This was previously used on the 2013 NRC Exam, randomly selected for use on the 2015 Exam.
JPM J This is a modified Bank JPM. The operator will be told that a Station Blackout has occurred at Unit 1, that the crew is currently in EP/1/A/5000/ECA-0.0 (Loss of All AC Power), and that the CRS has dispatched an operator to the SSF to complete Enclosure 2 (Unit 1 SSF ECA-0.0 Actions). The operator will be directed to perform Enclosure 3 (Unit 1 ETA and ETB Rooms - ECA-0.0 Actions). The operator will be expected to transfer 1EXMA-4 to its alternate power supply within 4 minutes from dispatch (Start of the JPM),
and identify that the 1ETA2 Lockout Relay has tripped.
JPM K This is a Bank JPM. The operator will be told that Unit 2 was at 100% power when a spurious Feedwater Isolation signal caused a Reactor trip, that the 2A CA pump is tagged out for motor replacement, that the 2B CA pump started and tripped on overload, that the crew has transitioned from EP/2/A/5000/E-0 to EP/2/A/5000/FR-H.1 (Response to Loss of Secondary Heat Sink), that the TDCA Pump is not running, and that both 2SA-48ABC and 2SA-49AB are closed. The operator will be directed to fail the air supplies to 2SA-48ABC and 2SA-49AB per EP/2/A/5000/FR-H.1, RNOs 7.d.1 and 7.d.2. The operator will be expected to fail the air supplies to 2SA-48ABC and 2SA-49AB per EP/2/A/5000/FR-H.1, RNOs 7.d.1 and 7.d.2.
NUREG-1021, Revision 9