ML19098B557
| ML19098B557 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/15/2019 |
| From: | David Silk NRC Region 1 |
| To: | Swiger K Exelon Generation Co |
| Shared Package | |
| ML18296A408 | List: |
| References | |
| EPID L-2019-OLL-0036 | |
| Download: ML19098B557 (12) | |
Text
AppendixD Scenario Outline FormES-D-1 Calvert Cliffs Nuclear Power Plant Scenario #1 OP-Test # 2019 Examiners:
Operators:
Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.
Turnover: 12 EHC Pump is OOS, 11 CAC is OOS.
Instructions to the crew: Prepare to place 11 BAST in direct recirculation to obtain a sample for analyzing per OI-2C, Concentrated Boric Acid System Operations.
Critical Tasks
- 1. Identifies 11 S/G as the ruptured SG and isolates 11 S/G within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the reactor trip.
- 3. Trip 1 lA & 12B RCPs or 1 lB & 12A RCPs when RCS pressure decreases to <1725 PSIA prior to RCS pressure reaching 1300 PSIA.
- 4. Trips all RCPs within 15 minutes after receiving CIS or within 4 minutes of subcooling
<20°F.
Event#
Malfunction #
Event Type*
Event Description 1
NIA N-RO/SRO Recirculate 11 BAST 2
ni008 04 I-BOP/SRO NI B Upper Detector Fails Low T-SRO 3
srw003 01 C-BOP/SRO 11 SRW Pump Breaker Trip/AOP-7B T-SRO msOOl 01 C-BOP/SRO 4
R-ATC 11 S/G Tube Leak (100 gpm)/AOP-2A Downpower T-SRO ms002 01 EOP-0 5
M-ALL SGTR (1 tube) in 11 SG/EOP-6 6
rcs002 M-ALL LOCA (5000gpm)/EOP-8 (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (T)ech Spec
ES-401 PWR Examination Outline FORM ES-401-2 Facility Name:CCNPP Date of Exam:3/25/2019 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A
A A G Total A2 G*
Total 1
2 3
4 5
6 1
2 3
4
- 1. Emergency 1
3 3
3 3
3 3
18 3
3 6
Abnormal 2
3 2
2 N/A 0
1 N/A 1
9 2
2 4
Plant Evolutions Tier Totals 6 5
5 3
4 4
27 5
5 10 1
2 2
2 3
2 2
3 3
2 4
3 28 3
2 5
- 2.
2 1
1 1
1 0
1 1
1 1
1 1
10 0
2 1
3 Plant Systems Tier Totals 3 3
3 4
2 3
4 4
3 5
4 38 5
3 8
1 2
3 4
1 2
3 4
- 3. Generic Knowledge and Abilities 10 7
Categories 3
2 3
2 1
2 2
2 Note: 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).
- 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 KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) Kl As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
G*
Generic KIAs
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE #/Name/Safety Function K
K K
A KIA Topic(s)
IR 2
3 1
00007 Reactor Trip/ 1 0
Knowledge of the interrelations between a reactor trip and the following: Breakers, 2.6 2
relays and disconnects E/E02 Reactor Trip Recovery/ 1 00008 Pressurizer Vapor Space Accident / 3 0
Knowiedge of the reasons for the following responses as they apply to the Pressurizer 4
Vapor Space Accident: RCP tripping requirements 4.2 00009 Small Break LOCA / 3 0
Knowledge of the operational implications of the following concepts as they apply to 3.5 2
the small break LOCA: Use of steam tables 00011 Large Break LOCA / 3 0
Knowledge of the interrelations between the and the following Large Break LOCA:
2.6 2
Pumps 00015 RCP Malfunctions/ 4 0
3.0 00017 RCP Malfunctions (Loss of RC Flow)/ 4 3
00022 Loss of Rx Coolant Makeup / 2 4.2 00025 Loss of RHR System I 4 1
Ability to operate and / or monitor the following as they apply to the Loss of Residual 2
Heat Removal System: RCS temperature indicators 3.6 00026 Loss of Component Coc;,ling Water I 8 0
Ability to operate and / or monitor the following as they apply to the Loss of 2
Component Cooling Water. Loads on the CCWS in the control room 3.2 00027 Pressurizer Pressure Control System 0
Knowledge of the reasons for the following responses as they apply to the Pressurizer Malfunction / 3 Pressure Control Ma~unctions: Isolation of PZR spray following loss of PZR heaters 3.5 00029 ATWS / 1 Ability to determine or interpret the following as they apply to a ATWS: Reactor 4.4 nuclear instrumentation 00038 Steam Gen. Tube Rupture/ 3 0
Knowledge of the operational implications of the following concepts as they apply to 3.9 3
the SGTR: Natural circulation 00040 Steam Line Rupture / 4 E/E05 Excessive Steam Demand I 4 3.4 00054 Loss of Main Feedwater / 4 E/E06 Loss of Feedwater / 4 0
2 3.5 00055 Station Blackout/ 6 0
Ability to operate and monitor the following as they apply to a Station Blackout:
5 Battery, when approaching fully discharged 3.3 00056 Loss of Off-site Power/ 6 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
3.8 00057 Loss of Vital AC Inst. Bus / 6 0
00058 Loss of DC Power/ 6 Ability to determine and interpret the following as they apply to the Loss of DC Power:
3.5 DC loads los~ impact on to operate and monitor plant systems 00062 Loss of Nuclear Svc Water/ 4 Ability to recognize system parameters that are entry-level conditions for Technical 3.9 Specifications.
00065 Loss of Instrument Air/ 8 0
00077 Generator Voltage and Electric 0
Know!
ge of the reasons for t e fo lowing responses as t ey app y to enerator rid Disturbances / 6 2
Voltage and Electric Grid Disturbances: Actions contained in abnormal operating 3.6 KIA Category Totals:
3 3
3 3
18 ES-401, 39 of 50
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
E/APE #/Name/Safety Function K
K K
A KIA Topic(s)
IR 1
2 3
1 00001 Continuous Rod Withdrawal/ 1 16 Knowledge of the operational implications of the following concepts as they apply to 3.0 Continuous Rod Wlthdrawal: Definition and application of power defect 00003 Dropped Control Rod / 1 16 Knowledge of the operational implications of the following concepts as they apply to 2.9 Dropped Control Rod: MTC 00005 Inoperable/Stuck Control Rod I 1 0
00024 Emergency Boration / 1 0
00028 Pressurizer Level Malfunction / 2 0
00032 Loss of Source Range NI / 7 01 Knowledge of the interrelations between the Loss of Source Range Nuclear 2.7 Instrumentation and the following: Power supplies, including proper switch positions 00033 Loss of Intermediate Range NI / 7 0
00036 Fuel Handling Accident I 8 0
00037 Steam Generator Tube Leak/ 3 0
00051 Loss of Condenser Vacuum/ 4 Knowledge of the purpose and function of major system components and controls.
4.1 00059 Accidental Liquid RadWaste Rel. / 9 0
00060 Accidental Gaseous Radwaste Rel. / 9 0
00061 ARM System Alarms/ 7 01 Knowledge of the operational implications of the following concepts as they apply to 2.5 Area Radiation Monitoring (ARM) System Alarms: Detector limitations 00067 Plant Fire On-site / 9 8 0
00068 Control Room Evac. / 8 0
00069 Loss of CTMT Integrity I 5 0
00074 lnad. Core Cooling/ 4 3.4 00076 High Reactor Coolant Activity / 9 0
Knowledge of the reasons for the following responses as they apply to the (Natural E/A 13 Natural Circ. / 4 01 Circulation Operations): Facility operating characteristics during transient conditions, 3.4 including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating !imitations and reasons for these operating characteristics.
Knowledge of the interrelations between the (RCS Overcooling) and the following:
E/A11 RCS Overcooling / 4 01 Components, and functions of control and safety systems, including instrumentation, 3.2 signals, inte~ocks, failure modes, and automatic and manual features.
E/A16 Excess RCS Leakage/ 2 0
E/E09 Functional Recovery 02 3.0 0
0 0
0 0
0 0
0 0
Category Totals:
3 2
2 0
Group Point Total:
9 ES-401, 40 of 50
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
- s:y:st:e:m:#::, N:a:m:e::::::::::::::::K:1 ::~::~::K:4::~::~::A~
1
-r.1~11,; ----~~:-T":":""'1
-:r--------K/-A_T_o_p-ic-(s-)--------r-1-R--,,-#-;
1 l
~----------------+-1-+-lf-~O+--,l-+--,IH""
06 Knowledge of RCPS design feature(s) and/or intertock(s) which provide for the 003 Reactor Coolant Pump following: Prevention of cold water accidents or transients; Ability to manually 2.5; 2.9 operate and/or monitor in the control room: RCP parameters 004 Chemical and Volume Control O
Knowledge of the effect that a loss or maffunction of the eves will have on the 7
following: PZR level and pressure 3.8 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater I061 Auxiliary/Emergency Feedwater
!062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monit6ring 076 Service Water 078 Instrument Air 103 Containment KIA Category Totals:
0 3
0 2
0 2
0 1
0 2
0 3
0 1
0 1
0 5
0 2
0 7
0 3
,* it 0
2 0
2 0
1 Ability to manually operate and/or monitor in the control room: RHR temperature, PZR heaters and flow, and nitrogen Ability to predict and/or monitor Changes 1n parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Pressure.
ioh and low Ability to predict and/or monitor Changes in parameters (to prevent exceeding design limlts) associated with operating the PRTS controls including: Monitoring quench tank temperature; Knowledge of surveillance procedures.
r; Knowledge of bus power supplies to the following: CCW pump, including
[! emergency backup Knowledge of the effect of a loss or malfunction of the following will have on the
- PZR PCS: PZR Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB
,111ty to \\8) prea1ct me impacts v, u,e rouowing ma1runct1ons or operauons on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those maffunctions or o... n.ill'4...,___
- --~*
- Knowledge of power supplies to the following
- Containment cooling fans; 2.8 3.3 2.6; 3.7 3.0 3.2 3.3 4.4
- . Knowledge of system set points, intertocks and automatic actions associated 3; 4.5
- , with EOP entry conditions.
I 1<.nvw,..uge OT me enect mat a 1oss or marrunction OT me ""' wm nave on me owing: Recirculation spray system; Ability to predict and/or monitor changes parameters (to prevent exceeding design limits) associated with operating f'C:C: rnnt~I* inrl,oninn* -
,,my 10 \\SJ prea,ct me impacts OT me rouow,ng marrunct1ons or operauons on e MRSS; and (b) based on predictions, use procedures to correct, control, or ligate the consequences of those maffunctions or operations: Maffunctioning r,1 IURIVUl::f'w 0T Ult, p1 IJ.:Ol'**C:11 vUI., *--**-*,,,., GIi IUfVI
, -*---*,_;Ill-'.:,
between the MFW and the following systems S/Gs; Ability to (a) predict the impacts of the following maffunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those maffunctions or operations: Tripping of MFW pump
-~*-
Knowledge of the operational implications of the following concepts as the apply to the AFW: Feed line voiding and water hammer novv,11:JUge OT ac a1Su1uudon system aes1gn rea1ure{S) ana,or 1menOCK{SJ wrncn
,,, provide for the following: lntertocks between automatic bus transfer and
breakers; Ability to manually operate and/or monitor in the control room:
. --11:-... in.........1 n,,t nf 1..--*1 -*-
,~ "now1eage OT me pnys1ca1 conneet1ons anCJor cause-tmect re1at1onsnips
'ii ~; be~een the DC electrical system and the following systems: AC electrical "now1eage oT me enect OT a 1oss or ma1runct1on OT me To11owing WIii nave on me
- . ED/G system
- Air receivers; Ability to manually operate and/or monitor in the
!,~.
-~-- rnnm*
,..,..,.1.,.,..n r.o.mnto nri.""'r"'tinn nf fhA Cr\\l~
'3* Knowledge of PRM system design feature(s) and/or interlock(s) which provide
- t: L for the following: Release termination when radiation exceeds setpoint
' ii Ability to interpret reference materials, such as graphs, curves, tables, etc.
- i'
~i(.; Ability to monitor automatic operation of the IAS, including: Air pressure ii:, Ability to monitor automatic operation of the containment system, including:
l::'t Containment isolation 4.2; 3.6 3.4 3.1; 3 2.7 2.8; 2.5 2.7 2.7; 4 4.0 3.9 3.1 3.9 2
2 2
3 2
2 3
3 2
4 3 Group Poin!Total:
ES-401, 41 of 50 2
2 2
0 2
2 2
2 0
28
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # I Name K
K K
K K
K AIA A iii~
KIA Topic(s)
IR 1
2 3
4 5
6 1
3 4
'1 I001 Control Rod Drive 0
Ability to (a) predict the impacts of the following malfunctions or operations on the I002 Reactor Coolant RCS; and (b) based on those predictions, use procedures to correct, control, or 4.1 1
mitigate the consequences of those ma~unctions or operations: Loss of forced circulation 011 Pressurizer Level Control 0
~Knowledge of bus power supplies to the following: PZR heaters 3.1 1
2 014 Rod Position Indication 0
l"""""""~"'""'ro _____....,,,..._ 3.2 1
1 the RPIS and the following systems: CRDS lcf
~
Ability to manually operate and/or monitor in the control room: Trip bypasses 015 Nuclear Instrumentation
~.
3.8 1
016 Non-nuclear Instrumentation
~
Ii!" Knowledge of annunciator alarms, indications, or response procedures.
4.2 1
017 In-core Temperature Monitor cl 0
Kl27 Containment Iodine Removal 0
028 Hydrogen Recombiner and Purge
'i K:;ontrol t
0 029 Containment Purge 0
Knowledge of design feature(s) and/or interlock(s) which provide for the following:
3.2 1
3 Automatic purge isolation 0
Ability to predict and/or monitor changes in parameters (to prevent exceeding 033 Spent Fuel Pool Cooling 111'.design limits) associated with Spent Fuel Pool Cooling System operating the 2.7 1
1................... ;...... 1,,..i;...,.,. ~
034 Fuel Handling Equipment I i I 0
035 Steam Generator
~
0
!041 Steam Dump/Turbine Bypass Control J
0
',i 1
.. Ability to monitor automatic operation of the MT/G system, including: Generator 045 Main Turbine Generator 1
trio 2.6 1
055 Condenser Air Removal 0
Knowledge of the effect that a loss or malfunction of the CARS will have on the 2.5 1
1 i
followina: Main condenser 056 Condensate rt
,i 0
068 Liquid Radwaste 1
e' Knowledge of the effect of a loss or malfunction on the following will have on the 2.5 1
0 Liauid Radwaste Svstem: Radiation monrtors
}'
071 Waste Gas Disposal
/
0
.,F i072 Area Radiation Monitoring 0
i075 Circulating Water
.'.j:,
~;
0 079 Station Air
\\
0 086 Fire Protection 1?
1::,,
0 KIA Category Totals:
1 1
1 1
0 1
1 1
1 1
1 Group Point Total:
10 ES-401, 42 of 50
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO) lt-----------------,-K--,-K--,-K--.-A-,,..,.,..,,-----------------------,,----.----ti E/APE #/Name I Safety Function 1
2 3
1 KIA Topic(s)
IR 00007 Reactor Trip/ 1 E/E02 Reactor Trip Recovery/ 1 00008 Pressurizer Vapor Space Accident/ 3 00009 Small Break LOCA I 3 00011 Large Break LOCA / 3 00015 RCP Malfunctions / 4 00017 RCP MaWunctions (Loss of RC Flow)/ 4 00022 Loss of Rx Coolant Makeup / 2 00025 Loss of RHR System/ 4 00026 Loss of Component Cooling Water I B 00027 Pressurizer Pressure Control System MaWunction / 3 00029 ATWS / 1 00038 Steam Gen. Tube Rupture/ 3 00040 Steam Line Rupture / 4 E/E05 Excessive Steam Demand / 4 00054 Loss of Main Feedwater I 4 E/E06 Loss of Feedwater I 4 00055 Station Blackout / 6 00056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst. Bus I 6 00058 Loss of DC Power I 6 000062 Loss of Nuclear Svc Water/ 4 00065 Loss of Instrument Air I B Ability to recognize abnormal indications for system operating parameters that are
- entry-level conditions for emergency and abnormal operating procedures.
Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System: Existence of proper RHR overpressure protection Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
4.7 3.4 4.2 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 Ability to determine and interpret the following as they apply to the Loss of Instrument Air. When to commence plant shutdown ff instrument air pressure is decreasing Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage outside the generator capability curve O
O O o 3
3 Group Point Total:
ES-401, 39 of 50 4.1 3.6 0
0 0
0 0
0 0
0 0
0 0
0 0
0 6
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO) 11----------------"T""--r--...---ir---
,------------------------r---r----11 E/APE #/Name I Safety Function K
K K
A 2
3 00001 Continuous Rod Withdrawal/ 1 00003 Dropped Control Rod / 1 00005 Inoperable/Stuck Control Rod / 1 00024 Emergency Boration / 1 00028 Pressurizer Level Malfunction/ 2 00032 Loss of Source Range NI / 7 00033 Loss of Intermediate Range NI/ 7 00036 Fuel Handling Accident/ 8 00037 Steam Generator Tube Leak/ 3 00051 Loss of Condenser Vacuum I 4 00059 Accidental Liquid RadWaste Rel. / 9 00060 Accidental Gaseous Radwaste Rel. / 9 00061 ARM System Alarms/ 7 00067 Plant Fire On-site I 9 8 00068 Control Room Evac. / 8 00069 Loss of CTMT Integrity I 5 00074 lnad. Core Cooling/ 4 00076 High Reactor Coolant Activity / 9 E/A13 Natural Circ. / 4 E/A11 RCS Overcooling / 4 E/A16 Excess RCS Leakage/ 2 E/E09 Functional Recovery KIA Category Totals:
0 0
0 0
2 KIA Topic(s)
Ability to locate control room switches, controls, and indications, and to detennine that they correctly reflect the desired plant lineup.
Ability to detennine and interpret the following as they apply to the Control Room Evacuation: vailabili of heat sink Ability to detennine and interpret the following as they apply to the High Reactor Coolant Activity: Response of PZR LCS to changes in the letdown flow rate Ability to verify that the alanns are consistent with the plant conditions.
2 Group Point Total:
ES-401, 40 of 50 IR 4.3 4.3 2.5 4.2 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
4
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
K K K K K K A '
A ~1 System # I Name 1 2 3
4 5
6 1
.. 3 KIA Topic(s)
IR 003 Reactor Coolant Pump lj~
rr ;t.
0 004 Chemical and Volume Control I~
}"
0 i'
r~
~~
0 Ability to (a) predict the impacts of the following malfunctions or operations on 006 Emergency Core Cooling
- < the ECCS: and (b) based on those predictions, use procedures to correct, 3.2 1
control, or mitigate the consequences of those ma~unctions or operations:
W,i,1.3
- Radioactive release from venting RWST to atmosphere 007 Pressurizer Relief/Quench Tank
,1'
'ii':
0 008 Component Cooling Water 0
ll MulmY to \\0) prea1ct me impacts u, " e 10now,ng ma11unct1ons or operanons on 01 O Pressurizer Pressure Control the PZR PCS: and (b) based on those predictions, use procedures to correct, 3.6 1
control, or mitigate the consequences of those mafunctions or operations:
- t*
.J...... 1..... fi:::aih**-
012 Reactor Protection 1
0 013 Engineered Safety Features
- {*
0 Actuation Ii t
022 Containment Cooling i:
0 025 Ice Condenser 0
,*~
0 039 Main and Reheat Steam 1.~~;,
0 059 Main Feedwater 0
061 Auxiliary/Emergency Feedwater
)l i.
Ability to locate and operate components, including local controls.
4.0 1
062 AC Electrical Distribution
- t 0
063 DC Electrical Distribution 0
064 Emergency Diesel Generator t,1,;
)?
0 073 Process Radiation Monitoring
~.
- r,i\\) Knowiedge of EOP entry conditions and immediate action steps.
4.8 1
076 Service Water i?
~;~
0
,-"'~';;,ul 11y,o 1*1 preu1c, tne impacts 01 tne 1011owmg ma..., ~.ons or operauons on 078 Instrument Air ll~ the IAS: and (b) based on those predictions, use procedures to correct, control, 2.9 1
".'1<
or mitigate the consequences of those mafunctions or operations: Air dryer
'~.
I""" """*
.u. *- -*'
it{:
103 Containment 0
l*i iilJ}
0 KIA Category Totals:
0 0
0 0
0 0 0 3 0 0 2 Group Point Total:
5 ES-401, 41 of 50
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # / Name K
K K
K K
K A
A A
KIA Topic(s)
IR 1
2 3
4 5
6 1
3 4
001 Control Rod Drive
. ; Ability to verify system alarm setpoints and operate controls identified in the alarm
~ *'t response manual.
4.0 1
1Do2 Reactor Coolant 0
p11 Pressurizer Level Control J
0 P14 Rod Position Indication 0
015 Nuclear Instrumentation 0
- ,;:.~
016 Non-nuclear Instrumentation 0
t 017 In-core Temperature Monitor
'P,"1; 0
I
~
027 Containment Iodine Removal 0
028 Hydrogen Recombiner and Purge r
l:&'it'J 0
K:;ontrol P29 Containment Purge I\\
0 033 Spent Fuel Pool Cooling
~
0 034 Fuel Handling Equipment 0
1.::!l'.
035 Steam Generator 0
l'miAbility to (a) predict the impacts of the following malfunctions or operations on the 041 Steam Dump/Turbine Bypass Control
- \\
SDS; and (b) based on predictions. use procedures to correct. control, or mitigate 3.1 1
the consequences of those malfunctions or operations: Loss of IAS 045 Main Turbine Generator 0
055 Condenser Air Removal 0
loss Condensate
"'i
'f:'
t 0
P68 Liquid Radwaste 0
1,'~
(f,~u, ny,o \\8/ prea,c, me,mpac,s or me ro11ow1ng manuncuons or operanons on me lo71 Waste Gas Disposal 1,,J,
., Waste Gas Disposal System ; and (b) based on those predictions. use 2.8 1:';
t\\~ procedures to correct. control, or mitigate the consequences of those 1
malfunctions or operations: Use of WGDS to prevent entry of oxygen into holdup i
I*--*,-.-4,...:-- lin,,irl *----ll---
P72 Area Radiation Monitoring
~ ~*,
0 lo75 Circulating Water
\\r i{
0 079 Station Air t
0
',:i' 086 Fire Protection
- r i
0 KIA Category Totals:
0 0
0 0
0 0
0 2
0 0
1 Group Point Total:
3 ES-401, 42 of 50
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3
!Facility Name:CCNPP Date of Exam:3/25/2019 I
Category KIA#
Topic KU
~KU-Only IR IR 2.1. 01 Knowledge of conduct of operations requirements.
3.8 1
4.2 2.1. 25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 1
4.2
- 1.
2.1. 36 Knowledge of procedures and limitations involved in core alterations.
3.0 1
4.1 Conduct of 2.1. 29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
4.1 4.0 1
Operations 2.1.
2.1.
Subtotal 3
1 2.2. 20 Knowledge of the process for managing troubleshooting activities.
2.6 1
3.8 2.2. 43 Knowledge of the process used to track inoperable alarms.
3.0 1
3.3
- 2.
2.2. 15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc.
3.9 4.3 1
Equipment 2.2. 21 Knowledge of pre-and post-maintenance operability requirements.
2.9 4.1 1
Control 2.2.
2.2.
Subtotal 2
2 2.3. 11 Ability to control radiation releases.
3.8 1
4.3 2.3. 14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 3.4 1
3.8 or emergency conditions or activities.
- 3.
2.3. 05 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 1
2.9 Radiation 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 3.7 1
Control 2.3. 07 Ability to comply with radiation work permit requirements during normal or abnormal 3.5 3.6 1
conditions.
2.3.
Subtotal 3
2 2.4. 23 Knowledge of the bases for prioritizing emergency procedure implementation during 3.4 1
4.4 emergency operations.
2.4. 43 Knowledge of emergency communications systems and techniques.
3.2 1
3.8
- 4.
2.4. 34 Knowledge of RO tasks performed outside the main control room during an emergency 4.2 4.1 1
Emergency and the resultant operational effects.
Procedures 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 4.2 1
/ Plan 2.4.
2.4.
Subtotal 2
2 Tier 3 Point Total 10 7
ES-401, Page 43 of 50
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Group Randomly Selected Reason for Rejection KIA Spent several unsuccessful hours attempting to develop RO 009 Small Break a discriminating question for this combination of system LOCA and Kl A. Kept system and replaced Kl A with one that 1/1 Kl.01 had not been sampled. Kl.02 was randomly selected using a random number generator.
RO 007 Pressurizer This system and Kl A combination is not applicable to Relief/Quench Tank the plant. Kept system and replaced Kl A with one that 2/1 G2.2.03 had not been sampled. G.2.2.12 was randomly selected using a random number generator.
073 Process This Kl A is not applicable to the plant. Kept system RO Radiation and replaced Kl A with one that had not been sampled.
2/1 Monitoring K4.01 was randomly selected using a random number K4.02 generator.