ML112650097
| ML112650097 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 09/20/2011 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML112650097 (23) | |
Text
ES-401, Rev. 9 PWR Examination Outline 1)
Form ES-401-2 Facility: mcGuire Date of Exam: june 13, 2011 RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total 1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
2 2
1 2
1 2
9 2
2 4
Abnormal Plant
N/A N/A
Evolutions Tier Totals 5
4 4
5 4
5 27 5
5 10 1
32332323232 28 3
2 5
2.
2 1
1 1
11 1
011 1
1 10 1
1 1
3 Plant Systems Tier Totals 4
3 4
4 3
4 2
4 3
4 3
38 3
8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2
2 3
3 2
2 2
1 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 flier 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 4 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.l.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 KIA5 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 I and 2 from the shaded systems and K/A categories.
7* *fl generic (G) KIAs in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, butthe topics must be relevant to the applicable evolution or system. Refer to section D.1.b of ES-401 for the applicable KA5.
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 # I 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..
Steam Line Rupture
- Excessive Heat Transfer /4 ES-401, REV 9 TIGI 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 007EA1.01 Reactor Trip
- Stabilization
- Recovery 3.7 3.4 T/G controls
/1 008AK2.01 Pressurizer Vapor Space Accident! 3 2.7 2.7 Valves 009EK2.03 Small Break LOCA /3 3
3.3 S/Gs 011 EKI.01 Large Break LOCA / 3 4.1 4.4 Natural circulation and cooling, including reflux boiling.
015AK2.l0 RCP Malfunctions!4 2.8 2.8 RCP indicators and controls 022AA1.07 Loss of Rx Coolant Makeup! 2 2.8 2.7 Excess letdown containment isolation valve switches and indicators 025AA2.0l Loss of RHR System / 4 2.7 2.9 Ej Proper amperage of running LPI/decay heat removal/RHR pump(s) 027AG2.l.31 Pressurizer Pressure Control System 4.6 4.3 Ability to locate control room switches, controls and Malfunction / 3 indications and to determine that they are correctly reflecting the desired plant lineup.
029E02.2.25 ATWS / 1 3.2 4.2 j j Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
038EA1.l1 Steam Gen. Tube Rupture / 3 3.8 3.9 El El El El El El El S!G level indicators 040AK3.01 4.2 4.5 El El j El El El El El El El El Operation of steam line isolation valves Page 1 of 12/6/2010 8:09 PM
ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 Inadequate Heat Transfer Loss of Secondary Heat Sink /4 Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink).
KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 054AA2.08 Loss of Main Feedwater /4 2.9 3.3 3
Steam flow-feed trend recorder 055EK1.02 Station Blackout/6 4.1 4.4 Natural circulation cooling 056AG2.2.40 Loss of Off-site Power / 6 3.4 4.7 El j
Ability to apply technical specifications for a system.
057AK3.01 Loss of Vital AC Inst. Bus / 6 4.1 4.4 Actions contained in EOP for loss of vital ac electrical instrument bus 062AA2.0l Loss of Nuclear Svc Water / 4 2.9 3.5 El El LI El El LI El El El El Location of a leak in the SWS 065AK3.08 Loss of Instrument Air / 8 3.7 3.9 El El El El El El El El El El Actions contained in EOP for loss of instrument air WEO5EK1.3 3.9 4.1 ElElElElElElElElElEl Page 2 of 2 12/6/2010 8:09PM
Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.
Knowledge of surveillance procedures.
ES-401, REV 9 TIG2 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 003AA2.03 Dropped Control Rod I 1 3.6 3.8 Li Dropped rod, using in-core/ex-core instrumentation in-core or ioop temperature measurements 024AK2.01 Emergency Boration / 1 2.7 2.7 Valves 059AA2.02 Accidental Liquid RadWaste Rel. / 9 2.9 3.9 The permit for liquid radioactive-waste release 061AK3.02 ARM System Alarms / 7 3.4 3.6 Guidance contained in alarm response for ARM system 074EK2.01 Inad. Core Cooling /4 3.6 3.8 RCP WE01EA1.l Rediagnosis / 3 3.7 3.7 J j Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WE13EK1.3 Steam Generator Over-pressure 14 3.0 3.2 Li Annunciators and conditions indicating signals, and remedial actions associated with the (Steam Generator Overpressure).
WE14EK3.3 Loss of CTMT Integrity / 5 3.5 3.5 LI El El El El LI El El El El wel6EG2.2.12 High Containment Radiation / 9 3.7 Page 1 of 1 12/6/2010 8:10PM
ES-401, REV 9 T2GI 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 003A1.03 Reactor Coolant Pump 2.6 2.6 RCP motor stator winding temperatures 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004A2.28 Chemical and Volume Control 3.7 4.3 j H Depressurizing of RCS while it is hot 005G2.4.31 Residual Heat Removal 4.2 4.1 j
Knowledge of annunciators alarms, indications or response procedures 005K6.03 Residual Heat Removal 2.5 2.6 RHR heat exchanger 006A3.03 Emergency Core Cooling 4.1 4.1 ESFAS-operated valves 006K5.02 Emergency Core Cooling 2.8 2.9 Relationship between accumulator volume and pressure 007G2.4.31 Pressurizer Relief/Quench Tank 4.2 4.1 j
Knowledge of annunciators alarms, indications or response procedures 010K6.0l Pressurizer Pressure Control 2.7 3.1 Pressure detection systems 012A2.02 Reactor Protection 3.6 3.9 Loss of instrument power 012K2.01 Reactor Protection 3.3 3.7 LI I LI LI LI LI LI LI LI LI LI RPS channels, components and interconnections Page 1 of 3 12/6/2010 8:11 PM
ES-401, REV9 T2GI 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:
ESFAS/safeguards equipment control Safety system logic and reliability Automatic containment isolation Containment temperature Increasing steam demand, its relationship to increases in reactor power Automatic isolation of steam line Feedwater isolation AFW diesel driven pump Local operation of breakers DC system ED/G
01 3K2.01 Engineered Safety Features Actuation 3.6 3.8 LI El El El El 013K5.02 Engineered Safety Features Actuation 2.9 3.3 LI LI El LI [I LI LI LI LI LI LI 022K4.03 Containment Cooling 3.6 4.0 El El LI LI El El El El El El 026A1.02 Containment Spray 3.6 3.9 El El LI El LI LI El El El El 039A2.05 Main and Reheat Steam 3.3 3.6 El El El El El El El El LI El 039K4.05 Main and Reheat Steam 3.7 3.7 El El LI LI LI LI El El El El 059A3.06 Main Feedwater 3.2 3.3 El El LI LI LI LI LI LI LI LI 061 K2.03 Auxiliary/Emergency Feedwater 4.0 3.8 El l] El LI LI LI El LI LI LI LI 062A4.04 AC Electrical Distribution 2.6 2.7 LI El LI LI LI LI LI El LI LI 062K3.03 AC Electrical Distribution 3.7 3.9 El LI LI LI LI LI LI LI LI LI 063K3.01 DC Electrical Distribution 3.7 4.1 LI LI ll El El El El El El El El Page 2 of 3 12/6/2010 8:11 PM
ES-401, REV 9 T2GI 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:
RD SRO 064A1.04 Emergency Diesel Generator 2.8 2.9 Crankcase temperature and pressure 064K1.02 Emergency Diesel Generator 3.1 3.6 D/G cooling water system 073K1.01 Process Radiation Monitoring 3.6 3.9 J
Those systems served by PRM5 076A4.04 Service Water 3.5 3.5 Emergency heat loads 103A3.0l Containment 3.9 4.2 Containment isolation 103G2.4.6 Containment 3.7 4.7 Knowledge symptom based EOP mitigation strategies.
Page 3 of 3 12/6/2010 8:11 PM
ES-401, REV 9 SRO 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 034A1.02 Fuel Handling Equipment 2.9 3.7 LI LI LI LI LI LI LI LI LI LI Water level in the refueling canal 072G2.4.31 Area Radiation Monitoring 4.2 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of annunciators alarms, indications or response procedures 086A2.0l Fire Protection 2.9 3.1 LI LI LI LI LI LI LI LI LI LI Manual shutdown of the FPS Page 1 of 1 12/6/2010 8:14 PM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:
Ability to make accurate, clear and concise verbal reports.
ri El El El Knowledge of primary and secondary chemistry limits El El El El [j Knowledge of procedures, guidelines or limitations associated with reactivity management El El El El []
Knowledge of the process for controlling equipment configuration or status El El El El []
(multi-unit license) Knowledge of the design, procedural and operational differences between units.
El El El El []
Ability to use radiation monitoring systems Fl [1 El El Ability to comply with radiation work permit requirements during normal or abnormal conditions El El El El ]
Knowledge of EOP entry conditions and immediate action steps.
El El El El []
Knowledge of operator response to loss of all annunciators.
El El El El Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
G2.1.17 Conduct of operations 3.9 El El El El El El G2.l.34 Conduct of operations 2.7 3.5 El El El El El El G2.l.37 Conduct of operations 4.3 4.6 El El El El El El G2.2.14 Equipment Control 3.9 4.3 ElEl El El El El G2.2.3 Equipment Control 3.8 3.9 El El El El El El G2.3.5 Radiation Control 2.9 2.9 El El El El El El G2.3.7 Radiation Control 3.5 3.6 El El El El El El G2.4.l Emergency Procedures/Plans 4.6 4.8 El El El El El El G2.4.32 Emergency Procedures/Plans 3.6 4.0 El El El El El El G2.4.4 Emergency Procedures/Plans 4.5 4.7 El El El El El El Page 1 of 1 12/6/2010 8:12PM
ES-401, REV9 KA NAME I SAFETY FUNCTION:
007EA2.04 Reactor Trip
- Stabilization
- Recovery
/1 TOPIC:
If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP Containment temperature, pressure, and humidity 009EA2.1 1 Small Break LOCA I 3 3.8 4.1 FORM ES-401-2 O11EG2.4.31 Large Break LOCA/3 4.2 4.1 056AA2.72 Loss of Off-site Power / 6 4.1 4.3 SRO TIGI PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 0 RO SRO 4.6 4.4 DDE L1DD DDDDDL1DL1D DDE DEED DDE DLDD DDE DEED DEE ED 057AG2.1.28 Loss of Vital AC Inst. Bus / 6 4.1 4.1 ED ED ED ED 062AG2.1.20 Loss of Nuclear Svc Water /4 4.6 4.6 Knowledge of annunciators alarms, indications or response procedures Auxiliary feed flow D
j Knowledge of the purpose and function of major system components and controls.
Ability to execute procedure steps.
Page 1 of 1 12/6/2010 8:12PM
ES-401, REV 9 SRO TIG2 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 003AA2.04 Dropped Control Rod I 1 3.4 3.6 Rod motion stops due to dropped rod 036AG2.2.12 Fuel Handling Accident /8 3.7 4.1 Knowledge of surveillance procedures.
037AA2.13 Steam Generator Tube Leak/3 4.1 4.3 which SG is Leaking.
067AG2.2.25 Plant Fire On-site / 8 3.2 4.2 fl Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Page 1 of 1 12/6/2010 8:13 PM
ES-401, REV 9 SRO T2GI 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:
RD SRO 006G2.4.20 Emergency Core Cooling 3.8 4.3 3 j j Knowledge of operational implications of EOP warnings, cautions and notes.
022G2.4.41 Containment Cooling 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
059A2.12 Main Feedwater 3.1 3.4 Failure of feedwater regulating valves 064A2.05 Emergency Diesel Generator 3.1 3.2 Loading the ED/G 073A2.02 Process Radiation Monitoring 2.7 3.2 Detector failure Page 1 of 1 12/6)2010 8:13 PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.14 Conduct of operations 3.1 3.1 f
j Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
G2.1.35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance
activities during shutdown operations.
G2.2.19 Equipment Control 2.3 3.4 Knowledge of maintenance work order requirements.
G2.3.5 Radiation Control 2.9 2.9 j
Ability to use radiation monitoring systems G2.4.11 Emergency Procedures/Plans 4.0 4.2 Knowledge of abnormal condition procedures.
G2.4.23 Emergency Procedures/Plans 3.4 4.4 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
Page 1 of 1 12/6/2010 8:14PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 KS Al A2 A3 A4 G TOPIC:
RD SRO 002K1.17 Reactor Coolant 3.5 3.8 LI MT/G 011K2.02 Pressurizer Level Control 3.1 3.2 PZR heaters 014K3.02 Rod Position Indication 2.5 2.8 Plant computer 016A2.0l Non-nuclear Instrumentation 3.0 3.1 Detector failure 029A3.0l Containment Purge 3.8 4.0 CPS isolation 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems 034G2.4.45 Fuel Handling Equipment 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.
035K6.01 Steam Generator 3.2 3.6 LI LI LI LI LI LI LI LI LI LI MSIV5 071K5.04 Waste Gas Disposal 2.5 3.1 LI LI LI LI LI LI LI LI LI LI Relationship of hydrogen/oxygen concentrations to flammability 079A4.01 Station Air 2.7 2.7 LI LI LI LI LI LI LI LI LI LI Cross-tie valves with lAS Page 1 of 1 12/6/2010 8:11 PM
ES-301 Administrative Topics Outline Form ES-301-i DRAFT (Rev_041311L_
Facility:
McGuire Date of Examination:
6/27/1 1 Examination Level:
RO Operating Test Number:
Nil-i Administrative Topic Type Code*
Describe activity to be performed (see Note) 2.1.20 (4.6)
Ability to interpret and execute procedure Conduct of Operations steps M,R JPM:
Perform a Manual Shutdown Margin Calculation 2.1.25 (3.9)
Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.
M,R JPM:
Calculate Dilution Needed for a Specified Rod Change 2.2.3 (3.8)
Knowledge of the design, procedural, and Equipment Control D R operational differences between units.
JPM:
Use Main Generator Capability Curve 2.4.34 (4.2)
Knowledge of RO responsibilities Emergency performed outside the main control room Procedures/Plan during an emergency and the resultant N, R operational effects.
JPM:
Independently Verify Spent Fuel Pool Level Adjustment 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) (0)
NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-l DRAFT (Rev_041311)
RO Admin JPM Summary Ala This is a modified version bank JPM ADM-NRC-A1-011.
The operator will be told that Unit 1 was shutdown to Mode 3, 15 minutes ago, that they are the
- OATC, that the reactivity computer (REACT) is out of service, and that preparations are being made to commence a plant cooldown.
The operator will be directed to perform a Shutdown Margin Calculation per 0P101A161001006.5 (Shutdown Margin
- Unit Shutdown, Modes 5, 4, or 3 Without Xenon Credit), and identify whether or not the cooldown can be initiated under the present conditions.
The operator by completing Enclosure 4.5 of OP/1/A/6100/006 (Reactivity Balance Calculation) will determine the Effective Boron Concentration to assure SDM to be 1382 ppm, and identify that the NC System must be borated to this value before the cooldown can be initiated.
Aib This is a modified JPM using Bank JPM OP-MC-JPM-ADM-214 as its basis. The operator will be given a set of initial conditions and told that it is desired to insert the Bank D Control Rods about 35 steps.
The Operator will be given the Core Data Book and asked to manuaUy determine the amount of Reactor Makeup Water that will be necessary to add, to complete the rod height adjustment.
A2 This is Bank JPM-ADM-NRC-A2-003. The operator will told that Unit I is at 74%
reactor power, given a set of Main Generator conditions, and that a power increase to 100% is imminent.
The operator will be directed to determine the maximum permissible generator load, the maximum reactive load the desired voltage per the Generator Voltage Operating Schedule assuming a power factor of 0.85 is maintained constant during the power increase.
The operator will select the correct Generator Capability Curve and use it to determine the maximum permissible generator load and reactive load; and then determine the desired voltage per the Generator Voltage Operating Schedule.
A4 The operator will be told that the Emergency Plan has been implemented due to an attack on the facility, that the hostile threat has been eliminated and the plant is now recovering, however heavy damage has been sustained.
The operator will also be told that AP/1/A15500/24 (Loss of Plant Control Due to Fire or Sabotage) has been implemented on Unit 1, that the Standby Makeup Pump is operating to provide inventory to the NC System, and that the crew is attempting to maintain Spent Fuel Pool Level greater than minus 2 feet in accordance with.4 (Spent Fuel Pool Level Control) of OP/1/A16200/005 (Spent Fuel Cooling System). The operator will be provided with paperwork associated with the control of the SFP level and other pertinent data, and then directed perform an independent verification (IV) ensuring that the total desired SFP Level change is within the guidance of the Enclosure 4.4 of OP/1/A16200/005; and then to identify any corrections or changes that are needed.
The operator will be expected to review Table 4.4-1 of Enclosure 4.4 of OP/1/A16200/005 and identify three errors, and make the required corrections.
NUREG-l 021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-l DRAFT (Rev_041311)
Facility:
McGu ire Date of Examination:
6/27/11 Examination Level:
SRO Operating Test Number:
Nil-i Administrative Topic Type Code*
Describe activity to be performed (see Note) 2.1.7 (4.7)
Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M, R and instrument interpretation.
JPM:
Calculate QPTR 2.1.25 (4.2)
Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.
M,R JPM:
Calculate Reactor Vessel Head Venting Time 2.2.18 (3.9)
Knowledge of the process for managing Equipment Control maintenance activities during shutdown operations, such as risk assessments, work M, R prioritization, etc.
JPM:
Perform a Thermal Margin Determination 2.3.4 (3.7)
Knowledge of radiation exposure under Radiation Control normal or emergency conditions.
D, R JPM:
Take On-Site Protective Actions During a General Emergency 2.4.41 (4.6)
Knowledge of emergency action level Emergency thresholds and classifications.
Procedures/Plan M, R JPM:
Classify an Emergency Event NOTE:
All items (5 total) are required for SROs. RD 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 & RD retakes) (1)
(N)ew or (M)odified from bank (> 1) (4)
(P)revious 2 exams ( 1; randomly selected) (0)
NUREG-102i, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_041 311)
SRO Admin JPM Summary Ala This is a modified JPM using bank JPM ADM-NRC-Al -004 as its basis. With the plant at 99% power, the operator wiH be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/i/A14600/021A (Loss of Operator Aid Computer while in Mode 1).
The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PTI1IAI4600I21A.
The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4 (Quadrant Power Tilt Ratio) has been exceeded, and identify any required Technical Specification ACTION.
Alb This is a modified JPM using Bank JPM-ADM-NRC-Al-018 as its basis.
The operator will be told that McGuire Unit 1 is in a Post-Accident situation, that they are available for assignment within the Operational Support Center (OSC), and given a set of NC System and Containment conditions, along with a copy of EP/1/A/5000/FR-l.1 (Response to Voids in Reactor Vessel). The operator will be directed to calculate maximum head venting time in accordance with Enclosure I of FR-i.3, and be required to calculate this time within an allowable band.
A2 This is a modified JPM using Bank JPMs ADM-NRC-A2-06 as its basis.
The operator will be told that Unit 1 was shutdown 24 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 145 F and A Train ND in service; and that preparations are being made to lower NC system level to 9 inches above Hot Leg Centerline per Enclosure 4.1 (Draining the NC System) of OPI1IAI6100ISD-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 9
inches above Hot Leg Centerline and make the appropriate notifications.
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 Attachment 12.7 (Shutdown Assessment Status) and on MC-6, as well as make the required notifications to the CCC and STA.
A3 This is a Bank JPM.
The operator will be told that a General Emergency has been declared and that, as the OSM, they have initiated and completed the immediate actions of Enclosure 4.1 of RP/0/A15700/004 (General Emergency).
Additionally, the operator will be told that On-Site Protective Actions are being considered in accordance with RP/0/A15700/004, and that there are reports of an injured non-ambulatory person on-site.
The operator will be required to select two rescuers, from among seven potential rescuers, and dispatch them to the injured individual by completing Enclosure 4.4, (Request for Emergency Exposure),of RP/0/A15700/004.
A4 This is a modified form of a Bank JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where NUREG-1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1 DRAFT (Rev_041311) each of two procedures identifies a
need to address RPIOIAI5700I000, Classification of Emergency. The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, and that a Site Area Emergency exists upon entry into the EOP network.
NUREG-1 021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV_041311)
Facility:
McGuire Date of Examination:
6/27/il Exam Level (circle one):
Operating Test No.:
Ni i-i Control Room Systems@ (8 for RO; 7 for SRO-l; 2 or 3 for SRO-U, including 1 ESF)
Type Code*
Safety System / JPM Title Function A.
010 Pressurizer Pressure Control System S,D,P,L 3
Place LTOP in Service B.
028 Hydrogen Recombiner and Purge Control System S,D,P,EN 5
Manually Align Phase B HVAC Equipment C.
004 Chemical and Volume Control System S,N,A I
Emergency Borate the RCS D.
EPE 074 Inadequate Core Cooling S,M,EN,A 4P Establish NC System Feed and Bleed E.
045 Main Turbine Generator System S,D,A 4S Perform the Main Turbine Overspeed Trip Test F.
APE 067 Plant Fire On Site S,N,A 8
Restore from a Fire in the Unit 1 Cable Spreading Room G.
006 Emergency Core Cooling System S,D,EN 2
Increase Pressure in Cold Leg Accumulator 1A H.
062 AC Electrical Distribution S,N 6
Restore Power to 6900 V Buses In-Plant Systems© (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)
I.
061 AuxiliarylEmergency Feedwater System M,R 4S Start and Stop # I Turbine Driven CA Pump J.
086 Fire Protection System D
8 Manually Initiate Diesel Generator Halon K.
EPE 055 Station Blackout D,E 6
Establish NC Pump Seal Injection from the SSF NUREG-1 021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV O4111)
All RD 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 / SRO-l / SRO-U (A)lternate path 4-6 (4) /4-6 (4) / 2-3 (2)
(C)ontrol room (D)irect from bank
<9 (6) I 8 (6) /
4 (2)
(E)mergency or abnormal in-plant
- 1 (1) I 1 (1) /
1 (1)
(EN)gineered Safety Feature
/
I 1 (1) (Control Room System)
(L)ow-Power/Shutdown 1 (1) L 1 (1) I 1 (1)
(N)ew or (M)odified from bank including 1 (A) 2 (5) / < 2 (5) I 1 (3)
(P)revious 2 exams 3 (2) /
3 (2)1 2 (1) (Randomly Selected)
(R)CA
.1(1)I1(1)I1(1)
(S)imulator JPM Summary JPM A This is a bank JPM.
The Operator will be placed in a situation in which Unit 1 is in a cooldown and depressurization in accordance with OPI1IAI6100ISD-4, (Cooldown to 240 Degrees F). The operator will be told that the 1A and lB NCPs are operating, that NC System pressure is 347 psig and NC System temperature is 310-320°F.
The operator will be asked to place the LTOP System in operation in accordance with.1 of OP/1/A/6100/SO-10, (Controlling Procedure for LTOP Operation), and monitor for proper operation.
JPM B This is a bank JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, (Phase B HVAC Equipment), of EP/1/A15000/E-0, (Reactor Trip or Safety Injection).
During the performance of, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems.
The operator will be told that with the plant at power, a Reactor Makeup System failure has resulted automatic Control Rod insertion, that MCB Annunciator 1AD-2, A9, CONTROL ROD BANK LO
- LIMIT, has
- alarmed, that AP/1/A15500/38 (Emergency Boration) has been entered, and that the 1 B BA Transfer Pump is OOS.
The operator will be directed to initiate Emergency Boration by performing Step 12 of AP/1/A15500/38 (Emergency Boration).
When the operator attempts to start the 1A BA Transfer Pump the Boric Acid Filter will become plugged (Alternate Path). The operator will be expected to establish Emergency Boration from the FWST.
JPM D This is a modified JPM that uses Bank JPM PS-NC-46 as its basis. The operator will be told that a Reactor Trip on Lo-Lo SIG Level has occurred due to the loss of both Main Feedwater Pumps, that the CA System will not start, that EP/1/A15000/FR-H.1 (Loss of Secondary Heat Sink) has been implemented, and that Feed and Bleed initiation criteria has been met. The operator will be directed to initiate an NC System Feed and Bleed by performing Steps 22
- 28 of EP/1/A15000/FR-H.1 (Loss of Secondary Heat Sink). When NUREG-1 021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV_041 311) the operator attempts to verify that a high pressure injection flowpath exists, it will be observed that 1NI-9A and lOB (Cold Leg Injection Isolation Valves) have failed to open automatically (Alternate Path). The operator will be expected to establish an RCS feed and bleed flowpath such that all NCPs off, flow is High Pressure Injection flow is established through NI-9/10, at least two Pzr PORVs are open, and both NV Pump Recirculation Valves are closed within 5 minutes of the first Pzr PORV being opened.
The closure of the NV Pump Recirculation Valves is a Time Critical Task (5 minutes) as identified in PT/01A14600/113, (Operator Time Critical Task Verification), Enclosure 13.10, (Initiate Feed and Bleed Once Criteria Met).
JPM E This is Bank JPM OP-MC-GEN-EHC-154A.
The operator will be told that Unit 1 is starting up after a refueling outage, that the Turbine/Generator is off line and rolling at 1800 RPM in preparation for performing PT/1/A/4250/004C (Turbine OPC and Mechanical Overspeed Trip Test), that all prerequisite conditions have been met, that two operators have been stationed at the Turbine as required, and that communications have been established with all involved.
The operator will be directed to complete the Turbine OPC and Mechanical Overspeed Trip Test per PT/1/A14250/004C (Turbine OPC and Mechanical Overspeed Trip Test), starting with Step 12.7.
The operator will raise Turbine speed to OPC setpoint, and then raise speed until the Turbine Overspeed trip should be actuated (Alternate Path). The operator is expected to recognize the turbine has failed to trip at the expected setpoint and then manually trip the Turbine.
JPM F This is a new JPM. The operator will be told that Unit 1 is at 100% power and that a fire has been reported in the Unit 1 Cable Spreading Room.
The operator will be told that the crew has implemented AP/1/A15500/45 (Plant Fire) and is presently in Enclosure 17 (AB 750 Unit 1 Cable Spreading Room Fire Unit 1 and Unit 2 Actions. The operator will also be told that several control room switch manipulations have been made, that the Fire Brigade has reported that the fire is no longer active, and that Station Management has indicated that the crew may return Control Room controls to normal as identified within Enclosure 17. The operator will be directed to restore the Control Room controls to normal by performing Step 21.a through e of Enclosure 17 (AB 750 Unit 1 Cable Spreading Room Fire Unit 1 and Unit 2 Actions) of AP/1/A15500/45 (Plant Fire).
The operator will be expected to determine that one Pzr PORV has inadvertently opened, and take action to isolate it by ensuring that its isolation valves is closed, and by directing that its motor breaker be opened (Alternate Path). The operator will then open the remaining Pzr PORV isolation valves, direct that the motor breaker for 1 CA-7AB be closed, and open the manual loaders for the main Steam Line PORVs while the valves remain closed.
JPM G This is Bank JPM ECC-CLA-69. The operator will be told that the plant is at 100% power, that the 1A Cold Leg Accumulator Abnormal Press Alarm is received, and that the 1A Cold Leg Accumulator pressure is approximately 590 psig and holding. The operator will be directed to increase the 1A Cold Leg Accumulator pressure to approximately 620 psig per OP/i /A/6200/009 (Accumulator Operation) Enclosure 4.3 (Adjusting Accumulators Pressure).
The operator will be expected to align N2 to CLA IA and raise pressure to greater than 620 psig and less than 639 psig.
The operator will be told that a total loss of Offsite Power has occurred at both Units, that Unit 1 has tripped from 100% power, that AP/1/A/5500/07 (Loss of Electrical Power), Case I (Loss of Normal Power to I ETA and 1 ETB) has been implemented and that the crew is preparing to restore power to the 6900VAC Buses.
NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT (REV 041311)
The operator will be directed to restore power to the 6900V buses by performing Steps 43.n-q of AP/1/A15500/07 (Loss of Electrical Power), Case I (Loss of Normal Power to 1 ETA and 1 ETB).
The operator will be expected to re-energizes all four 6900V Buses per APIIIAI5500IO7.
JPM I
This is a modified JPM that uses Bank JPM CF-CA-256. The Operator will be told that Unit I is at 100% power when the OAC alarm M1A1 276 (UI CA Temp at Chk Vlv ICA
- 37) is received, that the temperature in the TD CA Pump discharge to the 1D S/G is 223°F, and that the CRS has determined the #1 Turbine Driven CA Pump should be started to cool the piping to the ID S/G. The operator will be directed to locally start the Unit I Turbine Driven CA Pump per OP/1/A/6250/002 (Auxiliary Feedwater System),.4 (Manual Operation of #1 TD CA Pump). The operator will be expected to locally start the #1 TD CA Pump and align the CA System valves to provide the required cooling.
JPM J This is Bank JPM SS-RFY-019. The operator will be told that the control power for the 1A DIG Halon Fire Protection System has been tagged out for Electrical Maintenance, that the Halon Bank transfer switch is selected to the MAIN position, that they have been assigned as the Fire Watch, and that a Fuel Oil fire starts in the IA D/G Room.
The operator will be directed to initiate a MANUAL PNEUMATIC actuation of the Halon Fire Suppression System to the 1A D/G Room, per OP/0/A16400/002B (Halon Fire Protection System) Enclosure 4.3 (Local Manual Actuation of D/G Halon). The operator will be expected to manually align Halon to the 1A DIG Room and manually-pneumatically discharge the system into the room.
JPM K This is Bank JPM-CP-AD-061T.
The Operator will be placed in a situation in which a Loss of All AC has occurred on Unit 1. The operator will be told that EP/1/A15000/ECA-0.0, Loss of All AC Power has been implemented, and that one operator has been dispatched to I ETA to swap 1 EMXA4.
The operator will be asked to obtain the Brown Folder at SSF and complete Enclosure 1, (Unit I SSF-ECA-0.0 Actions), which will require the re-establishment of NCP Seal Water flow. The re-establishment of NCP Seal Water flow is a Time Critical Task (8 minutes) as identified in PT/0/A/4600/113, (Operator Time Critical Task Verification), Enclosure 13.11, (Initiate SSF NCP Seal Injection and Swap to the SSF).
NUREG-1021, Revision 9