ML19098B273
| ML19098B273 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/09/2019 |
| From: | David Silk Operations Branch I |
| To: | Swiger K Exelon Generation Co |
| Shared Package | |
| ML18296A408 | List: |
| References | |
| EPID L-2019-OLL-0036 | |
| Download: ML19098B273 (14) | |
Text
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 3/25/2019 Exam Level: SRO-U Operating Test#: 2019 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Reactivation of SRO License Conduct of Operations R,N G2. l.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. (SR0-3.8)
Respond to a Condenser Tube Leak Conduct of Operations R,D G2. l.34 Knowledge of primary and secondary plant chemistry (SRO-3.5)
Monitor Azimuthal Power Tilt (Tq) using Excore Nuclear Equipment Control R,D instrumentation G2.2.40 Ability to apply Technical Specifications for a system (SRO-4.7)
Authorize Emergency Exposures Radiation Control R,N G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions. (SR0-3.7)
Emergency Plan R,N Recommend Protective Action Guidelines to public officials G2.4.44 Knowledge of emergency plan protective actions. (SR0-4.4)
NOTE:
All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes) [2]
(N)ew or (M)odified from bank (2': 1) [3]
(P)revious 2 exams (:S 1; randomly selected) [O]
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 3/25/2019 Exam Level: SRO-U Operating Test#: 2019 Control Room Systems:
Safety Function
- a.
SIM-I Respond to a Fuel Handling incident in the Containment 103 Containment System A, E,EN, L, N 5
A3.0l Containment Isolation (SR0-4.2)
- b.
SIM-2 Respond to a Pressurizer Spray Valve Failure 010 Pressurizer Pressure Control System A,E,M 3
A2.02 Sorav Valve Failures (SR0-3.9)
C.
SIM-3 Respond to a condensate or feedwater rupture at power 059 Main Feed water System A,E,N 4S A2.05 Rupture in MFW suction or discharge line (SR0-3.4)
- d.
- e.
- f.
- g.
- h.
In-Plant Systems
- 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U I.
PL T-1 Starting/Securing Containment Purge System 029 Containment Purge System D,R 8
A2.03 Startup operations and the associated required valve lineups (SR0-3.1)
J.
PLT-2 Tie 120 VAC instrument buses 2Yl0 and 2Y09 062 AC Electrical Distribution System N,E 6
A2.05 Methods for energizing a dead bus (SR0-3.3)
- k.
- 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 I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 [3]
(C)ontrol room (D)irect from bank
- S9/:S8/:S4 [l]
(E)mergency or abnormal in-plant 2: I /2: 1/2: 1 [l]
(EN)gineered safety feature 2: 1 / 2: I / 2: 1 ( control room system) [I]
(L)ow-Power I Shutdown 2: I /2: I /2:1 [l]
(N)ew or (M)odified from bank including l(A) 2: 2 / 2: 2 / 2: 1 [ 4 including 3(A)]
(P)revious 2 exams
- S 3 I :S 3 I :S 2 (randomly selected) [OJ (R)CA 2: I /2: I /2:1 [I]
(S)imulator
AppendixD Scenario Outline Form ES-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 L 1 S/G as the ruptured SG and isolates 11 S/G.
- 3. Trip llA & 12B RCPs or llB & 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
<2D°F.
Event#
Malfunction #
Event Type*
Event Description 1
NIA N-RO/SRO Recirculate 11 BAST ni008_04 I-BOP/SRO 2
NIB Upper Detector Fails Low T-SRO C-BOP/SRO 3
srw003_01 11 SRW Pump Breaker Trip/AOP-7B T-SRO msOOl_Ol C-BOP/SRO 4
R-ATC 11 S/G Tube Leak (100 gpm)/AOP-2A Down power 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
Scenario Overview Initial Conditions:
Unit-I at 100% power, MOC, Unit-2 at 100% power Equipment OOS: 12 EHC Pump. 11 CAC.
Abnormal Conditions: None Instructions for shift: 11 BAST was not sampled this week yet due to maintenance on 11 BA Pump. 11 BA Pump has been returned to service. Chemistry requests 11 BAST in Direct Recirc to get a sample.
Event 1 - The crew will place 11 BAST in direct recirculation per 0I-2C section 6.3 for Chemistry request.
Event 2 - A LRNI upper detector failure for Channel B occurs. Alarm Response Manual (ARM 1C05) actions will have crew investigate failure at IC15 and when failure is recognized the crew should reference OP-CA-103-102-0200 and bypass T/U's 1,2,7,8, & 10 and enter TS 3.3.1.A &
D.
Event 3 - Once the trip units are bypassed, 11 SRW Pump Breaker will trip. The crew will implement AOP-7B, Loss of Service Water, which will direct their actions in protecting plant equipment and aligning and starting 13 SRW Pp. Determines T.S. LCO 3.7.6.B is applicable.
Event 4 - 11 S/G will begin to experience tube leakage ramping in from O GPM to 100 GPM over a one (1) minute period. The crew will respond using AOP-2A, Excessive Reactor Coolant Leakage, and will reduce power to reduce TAVE to less than 537°F at which point the reactor will be tripped. EOP-0, Post-Trip Immediate Actions will be implemented. Determines T.S. LCOs 3.4.13.A and 3.4.13.B are applicable.
Event 5 - During EOP-0, the SIG tube leak will increase to a rupture of 1 S/G tube. The crew is expected to implement EOP-6. The crew will commence a cooldown, not to exceed I00°F/hr, to prepare to isolate 11 S/G. Once Th <515°F, the crew will isolate 11 S/G. If plant conditions degrade or the crew is unsure of the diagnosis it is acceptable for them to enter EOP-8 directly from EOP-0. If EOP-8 is entered all critical tasks still apply unless individual tasks are invalidated by the exam team.
Event 6 - After 11 S/G has been isolated a 5000gpm RCS leak to containment will occur. The crew should identify degrading Containment pressures and temperatures. The crew is expected to implement EOP-8 based on the combined SGTR and LOCA in progress. The crew should trip all 4 RCPs after CIS initiates. The crew should identify the success paths in EOP-8 (RC-I Met, V A-1 Met, PIC-4 Met, HR-2 Met, CE-3 Met, RLEC-2 Met) and priority (PIC-4, CE-3, RLEC-2, RC-I, VA-I, HR-2). Crew will commence PIC-4 and CE-3. As part of PIC-4, the crew should try and identify location of leak. As part of CE-3, the crew will establish containment environment. The scenario will end once containment environment has been established.
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 A2 G*
1 2
3 4
5 6
1 2
3 4
Total Total 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 Kl As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and 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 Kl As.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (I Rs) 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 Kl As that are linked to 10 CFR 55.43.
G*
Generic Kl As
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 I Safety Function K
K K
A KIA Topic(s)
IR 2
3 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
Knowledge of the reasons for the following responses as they apply to the Pressurizer 4.2 4
Vapor Space Accident: RCP tripping requirements 00009 Small Break LOCA / 3 0
Knowledge of the operational implications of the following concepts as they apply to 4.2 the small break LOCA: Natural circulation and cooling, including reflux boiling 00011 Large Break LOCA I 3 0
Knowledge of the interrelations between the and the following Large Break LOCA:
2.6 2
Pumps 00015 RCP Malfunctions/ 4 0
Knowledge of the operational implications of the following concepts as they apply to 00017 RCP Malfunctions (Loss of RC Flow)/ 4 3
Reactor Coolant Pump Malfunctions (Loss of RC Flow): The basis for operating at a 3.0 reduced ower level when one RCP is out of service 00022 Loss of Rx Coolant Makeup / 2 Ability to verify that the alarms are consistent with the plant conditions.
4.2 00025 Loss of RHR System / 4 Ability to operate and I or monitor the following as they apply to the Loss of Residual 3.6 2
, < Heat Removal System: RCS temperature indicators 00026 Loss of Component Cooling Water/ 8 0
Ability to operate and I or monitor the following as they apply to the Loss of 3.2 2
Component Cooling Water: Loads on the CCWS in the control room 00027 Pressurizer Pressure Control System 0
Knowledge of the reasons for the following responses as they apply to the Pressurizer 3.5 alfunction / 3 Pressure Control Malfunctions: Isolation of PZR spray following loss of PZR heaters 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 Ability to determine and interpret the following as they apply to the (Excess Steam E/E05 Excessive Steam Demand / 4 Demand): Adherence to appropriate procedures and operation within the limitations in 3.4 the Facilit 's license and amendments.
00054 Loss of Main Feedwater / 4 Knowledge of the interrelations between the (Loss of Feedwater) and the following:
E/E06 Loss of Feedwater / 4 0
Facility's heat removal systems, including primary coolant, emergency coolant, the 3.5 2
decay heat removal systems, and relations between the proper operation of these s stems to the o eration of the facilit.
00055 Station Blackout / 6 0
Ability to operate and monitor the following as they apply to a Station Blackout:
3.3 5
Battery, when approaching fully discharged 00056 Loss of Off-site Power I 6 Knowledge of how abnormal operating procedures are used in conjunction with 3.8 EOPs.
00057 Loss of Vital AC Inst. Bus/ 6 0
00058 Loss of DC Power I 6 Ability to determine and interpret the following as they apply to the Loss of DC Power:
3.5 DC loads lost; 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
Knowledge of the reasons for the following responses as they apply to Generator rid Disturbances / 6 2
Voltage and Electric Grid Disturbances: Actions contained in abnormal operating 3.6 rocedure for volta e and rid disturbances KIA Category Totals:
3 3
3 3
Group Point Total:
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 2
3 00001 Continuous Rod Withdrawal/ 1 16 Knowledge of the operational implications of the following concepts as they apply to 3.0 Continuous Rod Withdrawal: Definition and application of power defect 00003 Dropped Control Rod I 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 / 1 0
00024 Emergency B0rat1on / 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 / 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 000059 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/ 5 0
Ability to determine or interpret the following as they apply to a Inadequate Core 00074 lnad. Core Cooling/ 4 Cooling: Trends in water levels of PZR and makeup storage tank caused by various 3.4 sized leaks in the RCS 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. I 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 limitations and reasons tor these operating characteristics.
Knowledge of the interrelations between the (RCS Overcooling) and the following:
E/ A 11 RCS Overcooling / 4 01 Components, and functions of control and safety systems, including instrumentation, 3.2 signals, interlocks, failure modes, and automatic and manual features.
E/ A 16 Excess RCS Leakage / 2 0
Knowledge of the reasons for the following responses as they apply to the (Functional E/E09 Functional Recovery 02 Recovery): Normal, abnormal and emergency operating procedures associated with 3.0 (Functional Recovery).
0 0
0 0
0 0
0 0
0 KIA Category Totals:
3 2
2 0
Group Point Total:
9 t:::i-4U I, 4U OT :JU
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # I Name K K K K K K A A A KIA Topic(s)
IR 1 2 3
4 5
6 1
3 4
0 I-0
- si
< Knowledge of RCPS design feature(s) and/or inter1ock(s) which provide for 2.5; 003 Reactor Coolant Pump 2
6 the following: Prevention of cold water accidents or transients; Ability to 2.9 2
manually operate and/or monitor in the control room: RCP parameters 004 Chemical and Volume Control 0
Knowledge of the effect that a loss or malfunction of the eves wm have on 3.8 1
7 the following: PZR level and pressure I-005 Residual Heat Removal 0
Ability to manually operate and/or monitor in the control room: AHR 2.8 1
3 f
temperature, PZR heaters and flow, and nitrogen 0
Ability to predict and/or monitor changes in parameters (to prevent exceeding 006 Emergency Core Cooling 7 '
design limits) associated with operating the ECCS controls including:
3.3 1
.,_ Pressure hinh and low
~,
Ability to predict and/or monitor changes in parameters (to prevent exceeding 007 Pressurizer Relief/Quench Tank design limits) associated with operating the PATS controls including:
2.6; 2
Monitoring quench tank temperature; Knowledge of the design, procedural, 3.8 and ooerational differences between units.
008 Component Cooling Water 0
i, Knowledge of bus power supplies to the following: CCW pump, including 3.0 1
2 emergency backup 010 Pressurizer Pressure Control 0 ti Knowledge of the effect of a loss or malfunction of the following will have on 3.2 1
2
- the PZR PCS
- PZR 012 Reactor Protection 0
I
!I Knowledge of the operational implications of the following concepts as the 3.3 1
1 apply to the RPS: ONB r;w,g ri l Ability to (a) predict the impacts of the following malfunctions or operations on 013 Engineered Safety Features the ESFAS; and (b) based Ability on those predictions, use procedures to 4.4 1
Actuation u
1 ff correct, control, or mitigate the consequences of those malfunctions or ooerations; Rapid deoressurization 0
Knowledge of power supplies to the following: Containment cooling fans; 022 Containment Cooling 1
~\\ Knowledge of system set points, interlocks and automatic actions associated 3; 4.5 2
}l i( ~i with EOP entry conditions.
025 Ice Condenser l,~
'1ffi' 0
1\\J;,;
- ~~ Knowledge of the effect that a loss or malfunction of the CSS will have on the 026 Containment Spray 0
0 l,(;
following: Recirculation spray system; Ability to predict and/or monitor 4.2; 2
2 2
,::*,;i changes in parameters (to prevent exceeding design limits) associated with 3.6 operating the CSS controls including: Containment temperature iii t~
Ability to (a) predict the impacts of the following malfunctions or operations on 039 Main and Reheat Steam the MASS; and (b) based on predictions, use procedures to correct, control, 3.4 1
,; 1 or mitigate the consequences of those malfunctions or operations:
Malfunctionina steam dump
!I
- , Knowledge of the physical connections and/or cause-effect relationships
~j ~ between the MFW and the following systems S/Gs; Ability to (a) predict the 059 Main Feedwater 0
impacts of the following malfunctions or operations on the MFW; and (b) 3.1; 3 2
3 h~
based on those predictions, use procedures to correct, control, or mitigate the
'"' consequences of those malfunctions or operations: Tripping of MFW pump
.,,,.-: turbine 061 Auxiliary/Emergency Feedwater 0
H~
' ~ Knowledge of the operational implications of the following concepts as the 2.7 1
5 L\\t,,
'*; apply to the AFW: Feed line voiding and water hammer
,.f~
ri I Knowledge of ac distribution system design feature(s) and/or interlock(s) 0 0
which provide for the following: Interlocks between automatic bus transfer and 2.8; 062 AC Electrical Distribution 3
l,i 2
Ii breakers; Ability to manually operate and/or monitor in the control room:
2.5 2
Remote rackina in and out of breakers 0
RI I
Knowledge of the physical connections and/or cause-effect relationships 063 DC Electrical Distribution 2
between the DC electrical system and the following systems: AC electrical 2.7 1
svstem 0
_/,,.
0 y; Knowledge of the effect of a loss or malfunction of the following will have on 064 Emergency Diesel Generator 7
g~
1 t~
the ED/G system: Air receivers; Ability to manually operate and/or monitor in 2.7; 4 2
the control room: Local and remote operation of the ED/G 073 Process Radiation Monitoring 0
f~;
- ~~ Knowledge of PAM system design feature(s) and/or interlock(s) which provide 3.3 1
2 for the following: Letdown isolation on high-RCS activity 076 Service Water
,, Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 1
078 Instrument Air tl~
Ability to monitor automatic operation of the IAS, including: Air pressure 3.1 1
103 Containment I~
Ability to monitor automatic operation of the containment system, including:
3.9 1
Containment isolation 0
KIA Category Totals:
2 2
2 3
2 2
3 3
2 4
3 Group Point Total:
28 ES-401 41 of 50
ES-401 ES-401 System # I Name P01 Control Rod Drive P02 Reactor Coolant P11 Pressurizer Level Control 014 Rod Position Indication Kl15 Nuclear Instrumentation P16 Non-nuclear Instrumentation P17 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal P72 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection KIA Category Totals:
K 1
K 2
0 2
K 3
0 1
K 4
K 5
5 Form ES-401-2 PWR Examination Outline Plant Systems - Tier 2/Group 2 (RO)
Form ES-401-2 K
6 1
0 A fl] A 1 lll 3 A
4 "
KIA Topic(s)
I Ability to (a) predict the impacts of the following malfunctions or operations on l
'f the RCS; and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of forced circulation Knowledge of bus power supplies to the following: PZR heaters I>. 1 1
0 3
Knowledge of the physical connections and/or cause-effect relationships between the RPIS and the following systems: CRDS Ability to manually operate and/or monitor in the control room: Trip bypasses
~
Knowledge of annunciator alarms. indications. or response procedures.
, :'°':.' Knowledge of design feature(s) and/or interlock(s) which provide for the following: Automatic purge isolation
- .
- _* Ability to predict and/or monitor changes in parameters (to prevent exceeding
- ,;, design limits) associated with Spent Fuel Pool Cooling System operating the l ;i;'. controls includina
- Spent fuel oool water level i, "'*
Ability to monitor automatic operation of the MT/G system, including: Generator trip Knowledge of the effect that a loss or malfunction of the CARS will have on the
, " following: Main condenser
, Knowledge of the effect of a loss or malfunction on the following will have on the
,~-/- Liquid Radwaste System: Radiation monitors IR 0
4.1 3.1 3.2 3.8 4.2 0
0 0
3.2 2.7 0
0 0
2.6 2.5 0
2.5 0
0 0
0 0
1 1
1 1
O 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)
E/APE #/Name/Safety Function K
K K
A KIA Topic(s)
IR 1
2 3
1 000007 Reactor Trip/ 1 0
CE/E02 Reactor Trip Recovery/ 1 000008 Pressurizer Vapor Space Accident/ 3 0
000009 Small Break LOCA / 3 Ability to recognize abnormal indications for system operating parameters that are 4.7 1
entry-level conditions for emergency and abnormal operating procedures.
000011 Large Break LOCA / 3 0
000015 RCP Malfunctions/ 4 0
000017 RCP Malfunctions (Loss of RC Flow)/ 4 000022 Loss of Rx Coolant Makeup / 2 0
000025 Loss of AHR System / 4 1.,,,... *~~,"*.oo,~..... **-* ~ **, *""* **,_,. "~""*
3.4 1
Heat Removal System: Existence of proper AHR overpressure protection 000026 Loss of Component Cooling Water/ 8 i
0 000027 Pressurizer Pressure Control System
.s ;.;; i\\"I I';iii:'.1 0
Malfunction / 3
- 1 l
000029 ATWS / 1 1#1 0
- ~
b00038 Steam Gen. Tube Rupture/ 3 Knowledge of low power/shutdown implications in accident (e.g., loss of coolant 4.2 1
'.I accident or loss of residual heat removal) mitigation strategies.
b00040 Steam Line Rupture/ 4 J:,
- (i 0
~E/E05 Excessive Steam Demand / 4
- ~
- i; P00054 Loss of Main Feedwater / 4
-;, '*cl;
<r' 0
~E/E06 Loss of Feedwater / 4
,~~,,;,
b00055 Station Blackout / 6 i
Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
4.5 1
000056 Loss of Off-site Power I 6 0
000057 Loss of Vital AC Inst Bus/ 6 0
000058 Loss of DC Power / 6 0
000062 Loss of Nuclear Svc Water / 4 0
000065 Loss of Instrument Air/ 8 Ability to determine and interpret the following as they apply to the Loss of Instrument 4.1 1
Air: When to commence plant shutdown if instrument air pressure is decreasing 000077 Generator Voltage and Electric Ability to determine and interpret the following as they apply to Generator Voltage and 3.6 1
~rid Disturbances/ 6 Electric Grid Oisturbances: Voltage outside the generator capability curve KIA Category Totals:
0 0
0 0
3 3 IGroup Point Total:
6 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 (SRO)
E/APE #/Name/Safety Function K
K K
A KIA Topic(s)
IR 1
2 3
1 b00001 Continuous Rod Withdrawal/ 1 0
b00003 Dropped Control Rod / 1 0
b00005 Inoperable/Stuck Control Rod/ 1 0
000024 Emergency Boration / 1 0
000028 Pressurizer Level Malfunction / 2 0
000032 Loss of Source Range NI / 7 0
000033 Loss of Intermediate Range NI / 7 0
,,.a-.,
p00036 Fuel Handling Accident/ 8 0
000037 Steam Generator Tube Leak/ 3 0
000051 Loss of Condenser Vacuum/ 4 0
000059 Accidental Liquid RadWaste Rel. / 9 li;,;!;:;::
0 000060 Accidental Gaseous Radwaste Rel. / 9
- t;'.ft'il; ;';
0 000061 ARM System Alarms I 7
.,,w,:._:;:"'
0 000067 Plant Fire On-site/ 9 8 Ability to locate control room switches, controls, and indications, and to determine that 4.3 1
they correctly reflect the desired plant lineup.
000068 Control Room Evac. / 8
. jf Ability to determine and interpret the following as they apply to the Control Room 4.3 1
Evacuation: Availabilitv of heat sink 000069 Loss of CTMT Integrity/ 5 0
000074 lnad. Core Cooling/ 4 0
000076 High Reactor Coolant Activity/ 9 I:, ;i.~*
Ability to determine and interpret the following as they apply to the High Reactor 2.5 1
Coolant Activity: Response of PZR LCS to changes in the letdown flow rate CE/A13 Natural Gire. I 4 0
CE/ A 11 RCS Overcooling I 4 0
~E/A16 Excess RCS Leakage/ 2
-~*~*-**** *-* = roM,S~*~*** "' ro-s.
4.2 1
K:;E/E09 Functional Recovery 0
't 0
0 0
11 *;;
0 0
0 0
0 0
KIA Category Totals:
0 0
0 0
2 2
Group Point Total:
4 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 (SRO)
System # I Name K K K K K K A \\ A A ti KIA Topic(s)
IR 1 2 3
4 5
6 1
~* 3 4.
I003 Reactor Coolant Pump fil tfi{1 0
I004 Chemical and Volume Control
- ~
ti 0
I005 Residual Heat Removal l~
[II 0
tl ell Ability to (a) predict the impacts of the following malfunctions or operations on 006 Emergency Core Cooling t the ECCS; and (b) based on those predictions, use procedures to correct, 3.2 1
\\ ~] control, or mitigate the consequences of those malfunctions or operations:
- 11 Radioactive release from venting RWST to atmosphere 007 Pressurizer Relief/Quench Tank
~~
l1 :;
/;;
0 ll~
008 Component Cooling Water IA:~
0 t:,
1;:
Ability to (a) predict the impacts of the following malfunctions or operations on 01 O Pressurizer Pressure Control tl the PZR PCS; and (b) based on those predictions, use procedures to correct, 3.6 1
I*.'
fl~;
control, or mitigate the consequences of those malfunctions or operations:
Heater failures I012 Reactor Protection
[)i 0
013 Engineered Safety Features
- j Actuation
- ,1
'.t*
0 022 Containment Cooling I I it;:1 0
025 Ice Condenser 0
026 Containment Spray l:~{,
0 039 Main and Reheat Steam r~:,
0 059 Main Feedwater tj/
it; 0
c',
- it..
061 Auxiliary/Emergency Feedwater 30 Ab1l1ty to locate and operate components, 1nclud1ng local controls.
4.0 1
~;sf//
I062 AC Electrical Distribution L1.:
- (
0 I063 DC Electrical Distribution 1,:1
- w;.1:
0 I064 Emergency Diesel Generator 0
I073 Process Radiation Monitoring h~
Knowledge of EOP entry conditions and immediate action steps.
4.8 1
I076 Service Water
- ~
0 i'
~ t Ability to (a) predict the impacts of the following malfunctions or operations on I078 Instrument Air
!.).
the IAS; and (b) based on those predictions, use procedures to correct, 2.9 1
- ~;.; control, or mitigate the consequences of those malfunctions or operations
- Air 103 Containment mdrver and filter malfunctions 0
II 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 # I Name K
K K
K K
K A.*} A A KIA Topic(s)
IA 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 4.0 1
alarm response manual.
,F'*
002 Reactor Coolant 0
011 Pressurizer Level Control 5:;:
- )
0
<lie 014 Rod Position Indication t{~
J 0
015 Nuclear Instrumentation iJJ 0
P16 Non-nuclear Instrumentation 0
P17 In-core Temperature Monitor 0
b27 Containment Iodine Removal l'l'4 0
()28 Hydrogen Recombiner and Purge
~
M 0
Control 029 Containment Purge
,;~
l,i4t 0
!4~
033 Spent Fuel Pool Cooling
- ~4 0
034 Fuel Handling Equipment 11 l*;;.;; *;..,
0
,,., 'J'-'
?'J:
035 Steam Generator
- j 0
i~~ Ability to (a) predict the impacts of the following malfunctions or operations on 041 Steam Dump/Turbine Bypass Control
- ,'.t
,<, the SOS; and (b) based on predictions, use procedures to correct, control, or 3.1 1
- ,u Ii mitigate the consequences of those malfunctions or operations: Loss of IAS P45 Main Turbine Generator
- r11,
)'
0 055 Condenser Air Removal
- J 0
056 Condensate
~\\
0
,\\i,,
068 Liquid Radwaste 14i 0
~ ~ Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those predictions, use 071 Waste Gas Disposal IJ procedures to correct, control, or mitigate the consequences of those 2.8 1
- (j, malfunctions or operations: Use of WGDS to prevent entry of oxygen into holdup
':*" tanks durina liauid transfers 072 Area Radiation Monitoring ll J4 0
075 Circulating Water
[,it f
0 079 Station Air
~~
0 P86 Fire Protection
- ~
0 K,'A 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)
!Facility Name:CCNPP Date of Exam:3/25/2019 Category K/ A #
Topic
- 1.
Conduct of Operations
- 2.
2.1. 01 Knowledge of conduct of operations requirements.
2.1. 25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
2.1. 36 Knowledge of procedures and limitations involved in core alterations.
2.1. 29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
2.1.
2.1.
Subtotal 2.2. 20 Knowledge of the process for managing troubleshooting activities.
2.2. 43 Knowledge of the process used to track inoperable alarms.
15 Ability to determine the expected plant configuration using design and configuration control 2.2.
documentation, such as drawings, line-ups, tag-outs, etc.
Equipment 2.2. 21 Knowledge of pre-and post-maintenance operability requirements.
Control
- 3.
Radiation Control 2.2.
2.2.
Subtotal 2.3. 11 Ability to control radiation releases.
14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 2.3.
or emergency conditions or activities.
05 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.
portable survey instruments, personnel monitoring equipment, etc.
2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions.
07 Ability to comply with radiation work permit requirements during normal or abnormal 2.3.
conditions.
2.3.
Subtotal 23 Knowledge of the bases for prioritizing emergency procedure implementation during 2.4.
emergency operations.
2.4. 43 Knowledge of emergency communications systems and techniques.
- 4.
2 4 34 Knowledge of RO tasks pertormed outside the main control room during an emergency Form ES-401-3 IR IR 3.8 1
4.2 3.9 1
4.2 3.0 1
4.1 4.1 4.0 1
2.6 3.8 3.0 3.3 3.9 4.3 2.9 4.1 2
3.8 4.3 3.4 1
3.8 2.9 1
2.9 3.2 3.7 1
3.5 3.6 1
2 3.4 1
4.4 3.2 3.8 4.2 4.1 1
and the resultant operational effects.
Emergency i-----i---------------------------1----1---
Procedures
/ Plan 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions.
2.4.
2.4.
Subtotal Tier 3 Point Total ES-401, Page 43 of 50 4.2 4.2 1
2 7