ML12299A226
| ML12299A226 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/18/2012 |
| From: | Rudolph W FirstEnergy Nuclear Operating Co |
| To: | David Silk Operations Branch I |
| Jackson D | |
| Shared Package | |
| ML12136A033 | List: |
| References | |
| TAC U01850 | |
| Download: ML12299A226 (30) | |
Text
ES*401 PWR Examination Outline Form ES-401*2 Facility: BVPS UNIT 2 RO Date of Exam 9/24 thru 10/5 2012 Points Tier Group K K K A A A G 1 2 3 2 3 4
- 1 3 3 3 3 18 1.
Emergency 2
& 1 1 1 9 Abnormal Plant Tier Evolutions Totals 4 4 4 1
- 2. 3 2 3 3 2 3 2 2 Plant Systems 2 2 1 1 1 1 1 0 0 1 1 10 Tier Totals 5 3 4 4 3 3 4 3 2 3 4 38 1 2 3 4
- 3. Generic Knowledge and 10 Abilities Category 3 2 2 3 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).
- 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 KlAs 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) KlAs 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 KlAs.
- 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, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
NUREG-1021 , ReviSion 9 Supplement 1 RO Page 1 of 13 FENoe FaCSimile Rev. AG
ES-401 PWR Examination Outline Form ES-401*2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 1(RO)
~=======================F=F~=F=
E/APE # / Name 1 Safety Function KIA Topic(s} IR #
000008 Pressurizer Vapor Space Accident 1 AK2 Knowledge the interrelations between the 2.7 1 3 Pressurizer Vapor Space Accident and the following:
[Question 1]
AK2.02 Sensors and detectors (CFR 41.7/45.7) 000009 Small Break LOCA 13 EA2 Ability to determine or interpret the following as 4.2 1 they apply to a small break LOCA:
[Question 2]
EA2.37 Existence of adequate natural circulation (CFR 43.5 145.13) 000015/000017 Reactor Coolant Pump AK2 Knowledge of the interrelations between the 2.6 (RCP) Malfunctions 14 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:
[Question 3]
AK2.08 CCWS (CFR41.7/45.7) 000022 Loss of Reactor Coolant Makeup I 2.2.39 Knowledge of less than or equal to one hour 3.9 2 Technical Specification action statements for
[Question 4] systems.
(CFR: 41.7/41.10/43.2/45.13) 000025 Loss of RHR System 14 AA 1 Ability to operate and I or monitor the following 2.9 as they apply to the Loss of Residual Heat Removal
[Question 5] System:
AA1.11 Reactor building sump level indicators (CFR 41.7/45.5/45.6) 000027 Pressurizer Pressure Control AA 1 Ability to operate and lor monitor the following 4.0 System Malfunction 13 as they apply to the Pressurizer Pressure Control Malfunctions:
[Question 6]
AA1.01 PZR heaters, sprays, and PORVs (CFR 41.7 145.5/45.6) 000029 A TWS 11 EK2 Knowledge the 2.9* 1 and the following an ATWS:
[Question 7]
EK2.06 Breakers, relays, and disconnects (CFR 41.7 145.7) 000038 Steam Generator Tube Rupture I 3 EK3 Knowledge reasons for the following 3.9 responses as the apply to the SGTR:
[Question 8]
EK3.04 Automatic actions provided by each PRM (CFR 41.5/41.10 145.6 / 45.13) 000040 Steam Line Rupture - Excessive 4.2 1 Heat Transfer 14
[Question 9]
AK3.01 Operation of steam line isolation valves (CFR 41.5,41.10 145.6/45.13)
NUREG-1 021, Revision 9 Supplement 1 RO Page 2 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(RO) Continued
~======================9=9=~~
E/APE # 1 Name 1 Safety Function KIA Topic(s) IR #
000054 Loss of Main Feedwater I 4 AK1 Knowledge of the operational implications of 3.6 the following concepts as they apply to Loss of
[Question 10] Main Feedwater (MFW):
AK1.02 Effects offeedwater introduction on dry SIG (CFR 41.8/41.10 145.3) 000055 Station Blackout 16 EK1 the operationa 4.1 1 the following concepts as they apply to the Station
[Question 11] Blackout:
EK1.02 Natural circulation cooling (CFR 41.8/41.10 145.3) 000057 Loss of Vital AC Electrical 2.4.4 Ability to recognize abnormal indications for 4.5 Instrument Bus 16 system operating parameters that are entry-level conditions for emergency and abnormal operating
[Question 12] procedures.
(CFR: 41.10/43.2/45.6) 000058 Loss of DC Power I 6 AK owledge of the operational implications 2.8 the following concepts as they apply to Loss of DC
[Question 13] Power:
AK1.01 Battery charger equipment and instrumentation (CFR 41.8/41.10 145.3) 065 Loss of Instrument Air I 8 AK3 Knowledge the reasons the 3.7 responses as they apply to the Loss of Instrument
'estion 14] Air:
AK3.08 Actions contained in EOP for loss of instrument air (CFR 41.5,41.10 145.6/45.13) 000077 Generator Voltage and Electric Grid AA2 Ability to determine and interpret the following 3.5 Disturbances 16 as they apply to Generator Voltage and Electric Grid Disturbances:
[Question 151 AA2.03 Generator current outside the capability curve (CFR: 41.5 and 43.5145.5, 45.7, and 45.8)
W/E04 LOCA Outside Containment 13 2.1.23 Ability to perform specific system and 4.3 integrated plant procedures during all modes of
[Question 16] plant operation.
(CFR: 41.10/43.5 145.2 I 45.6)
W/E05 Loss of Secondary Heat Sink 14 EA 1 Ability to operate and I or monitor the following 3.7 as they apply to the (Loss of Secondary Heat Sink)
[Question 17]
EA 1.2 Operating behavior characteristics of the facility.
(CFR: 41.7 I 45.5 I 45.6)
NUREG-1021, Revision 9 Supplement 1 RO Page 3 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(RO) Continued
~=======================r=r=r=F=
E/APE # I Name I Safety Function KIA Topic(s) IR #
W/E 11 Loss of Emergency Coolant EA2 Ability to determine and interpret the following 3.4 Recirculation I 4 as they apply to the (Loss of Emergency Coolant Recirculation):
[Question 18]
EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facility's license and amendments.
(CFR: 43.5/45.13)
KIA Category Point Totals: 3 3 3 3 3 3 Group Point Total:
NUREG-1021. Revision 9 Supplement 1 RO Page 4 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier lIGroup 2{RO)
E/APE # I Name I Safety Function KKK KIA Topic(s) IR #
123 000036 Fuel Handling Incidents 18 AA2 Ability to determine and interpret the following 3.4 as they apply to the Fuel Handling Incidents:
[Question 19] AA2.02 Occurrence of a fuel handling incident (CFR: 43.5/45.13) 000061 ARM System Alarms 17 AA 1. Ability to operate and lor monitor the following 3.6 as they apply to the Area radiation Monitoring (ARM)
[Question 20] System Alarms:
AA 1.01 Automatic actuation (CFR 41.7 145.5/45.6)
, AK1 Knowledge of the operational implications of the 000067 Plant Fire On-site I 9 3.1 following concepts as they apply to Plant Fire on
[Question 21] Site:
AK1.02 Fire fighting (CFR 41.8 141.10 145.3) 000068 Control Room Evacuation I 8 AA 1 Ability to operate and I or monitor the following 3.2*
as they apply to the Control Room Evacuation:
[Question 22] AA 1.27 Local trip of main feed pumps and Condensate pumps (CFR 41.7 145.5/45.6) 000076 High Reactor Coolant Activity 19 2.1.31 Ability to locate control room switches, 4.6 controls, and indications, and to determine that they
[Question 23] correctly reflect the desired plant lineup.
(CFR:41.10/45.12)
Vv/E07 Saturated Core Cooling 14 EA 1 Ability to operate and I or monitor the following 3.5 as they apply to the (Saturated Core Cooling):
[Question 24] EA 1.3 Desired operating results during abnormal and emergency situations.
(CFR: 41.7/45.5/45.6)
W/E08 RCS Overcooling - PTS 14 EK3 Knowledge of the reasons for the following 3.4 responses as they apply to the (Pressurized Thermal
[Question 25] Shock):
EK3.1 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
(CFR: 41.5/41.10,45.6,45.13)
E09 Natural Circulation Operations 14 EA2 Ability to determine and interpret the following 3.1 as they apply to the (Natural Circulation Operations)
[Question 26] EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5/45.13)
NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401*2 Emergency and Abnormal Plant Evolutions* Tier 1/Group 2(RO) Continued 1F===========================T=~~=r~
E/APE # 1 Name I Safety Function K KIA Topic(s) IR #
1 W/E14 High Containment Pressure 15 EK2 Knowledge of the interrelations between the 3.4 (High Containment Pressure) and the following:
[Question 27]
EK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7/45.7)
KIA Category Point Totals: Group Point Total: 9 NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K K KIA Topic(s) IR #
1 2 003 Reactor Coolant Pump A 1 Ability to predict and/or monitor changes in 2.6 parameters (to prevent exceeding design
[Question 28] limits) associated with operating the RCPS controls including:
A 1.03 RCP motor stator winding temperatures (CFR: 41.5/45.5) 004 Chemical and Volume K2 Knowledge of bus power supplies to the 2.9 1 Control following:
K2.02 Makeup pumps
[Question 29]
(CFR: 41.7) 004 Chemical and Volume K4 Knowledge of CVCS design feature(s) 2.8*
Control and/or interlock(s) which provide for the following:
[Question 30] K4.14 Control interlocks on letdown system (letdown tank bypass valve)
(CFR: 41.7) 005 Residual Heat Removal 2.1.32 Ability to explain and apply system 3.8 limits and precautions.
[Question 31] (CFR: 41.10 /43.2/45.12) 005 Residual Heat Removal K1 Knowledge of the physical connections 3.3 and/or cause/effect relationships between the
[Question 32] RHRS and the following systems:
K1.13SIS (CFR: 41.2 to 41.9/45.7 to 45.8) 006 Emergency Core Cooling K1 Knowledge of the physical connections 2.9*
and/or cause/effect relationships between the
[Question 33] ECCS and the following systems:
K1.07 MFW System (CFR: 41.2 to 41.9/45.7 to 45.8) 007 Pressurizer Relief/Quench A3 Ability to monitor automatic operation of the 2.7*
Tank PRTS. including:
[Question 34] A3.01 Components which discharge to the PRT (CFR: 41.7 /45.5) 008 Component Cooling Water A1 Ability to monitor changes in 2.8 1 parameters (to prevent exceeding design
[Question 35] limits) associated with operating the CCWS controls including:
A1.01 CCW flow rate (CFR: 41.5/45.5) 010 Pressurizer Pressure K6 Knowledge of the effect of a loss or 3.2 Control malfunction of the following will have on the PZR PCS:
[Question 36] K6.03 PZR sprays and heaters (CFR: 41.7/45.7)
NUREG-1021. ReviSion 9 Supplement 1 RO Page 7 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued F=========~======9F9F9=9=~~~
System # I Name KJA Topic(s) IR 012 Reactor Protection 3.2*
[Question 37]
013 Engineered Safety Features nO~\Ile(:lae of the effect of a loss or 2.7*
Actuation malfunction on the following will have on the ESFAS:
[Question 38]
K6.01 Sensors and detectors (CFR: 41.7 145.5 to 45.8) 022 Containment Cooling K2 Knowledge of power supplies to the 3.0*
following:
[Question 39] K2.01 Containment cooling fans (CFR: 41.7) 026 Containment Spray K4 Knowledge of CSS design feature(s) and/or 3.7*
interlock(s) which provide for the following:
[Question 40] K4.09 Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover).
039 Main and Reheat Steam 2.7
,stion 41]
059 Main Feedwater K3 the effect that a loss or 3.6 malfunction of the MFW will have on the
[Question 42] following:
K3.02 AFW system (CFR: 41.7/45.6) 061 Auxiliary/Emergency K5 Knowledge of the operational implications 3.6 1 Feedwater of the following concepts as the apply to the AFW:
[Question 43]
K5.01 Relationship between AFW flow and ReS heat transfer (CFR: 41.5/45.7) 061 Auxiliary/Emergency A 1 Ability to predict and/or monitor changes in 3.9 1 Feedwater parameters (to prevent exceeding design limits) associated with operating the AFW
[Question 44] controls including:
A1.01 S/G level (CFR: 41.5/45.5)
NUREG-1021, Revision 9 Supplement 1 RO Page 8 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued System # 1 Name K KIA Topic(s) IR #
1 062 AC Electrical Distribution A4 Ability to manually operate and/or monitor 3.1" 1 in the control room:
[Question 45] A4.07 Synchronizing and paralleling of different ac supplies (CFR: 41.7/45.51 to 45.8) 062 AC Electrical Distribution K4 Knowledge of ac distribution system design 3.1 1 feature(s) and/or interlock(s) which provide for
[Question 46] the following:
K4.10 Uninterruptable ac power sources (CFR: 41.7) 063 DC Electrical Distribution 2.1.7 Ability to evaluate plant performance and 4.4 make operational judgments based on
[Question 47] operating characteristics, reactor behavior, and instrument interpretation.
063 DC Electrical Distribution to (a) predict the impacts 2.5 following malfunctions or operations on the DC
[Question 48] electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.01 Grounds (CFR: 41.5/43.5/45.3/45.13) 064 Emergency Diesel A2 Ability to (a) predict the impacts of the 2.6" Generator following malfunctions or operations on the ED/G system; and (b) based on those
[Question 49] predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.13 Consequences of opening auxiliary feeder bus (ED/G sub supply)
(CFR: 41.5/43.5 145.31 45.13) 064 Emergency Diesel A4 Ability to manually operate and/or monitor 3.2*
Generator in the control room:
A4.04 Remote operation of the air compressor
[Question 50] switch (different modes)
(CFR: 41.7/45.5 to 45.8) 073 Process Radiation K3 Knowledge of the effect that a loss or 3.6 1 Monitoring malfunction of the PRM system will have on the following:
[Question 51J K3.01 Radioactive effluent releases (CFR: 41.7/45.6) 076 Service Water A3 Ability to monitor automatic operation of the 3.7 SWS, including:
, [Question 52] A3.02 Emergency heat loads (CFR: 41.7/45.5)
NUREG-1021 , Revision 9 Supplement 1 RO Page 9 of 13 FENOC Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued System # 1 Name K KIA Topic(s) IR #
3 078 Instrument Air K1 Knowledge of the physical connections 3.3*
andlor cause-effect relationships between the
[Question 53] lAS and the following systems:
K1.03 Containment air (CFR: 41.2 to 41.9/45.7 to 45.8) 103 Containment A2 Ability to (a) predict the impacts of the 3.5*
following malfunctions or operations on the
[Question 54] containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations A2.03 Phase A and B isolation (CFR: 41.5/43.5 1 45.3 145.13) 103 Containment 2.4.6 Knowledge of EOP mitigation strategies. 3.7 (CFR: 41.10/43.5/45.13)
[Question 55]
KIA Category Point Totals: 3 2 3 28 NUREG-1 021, Revision 9 Supplement 1 RO Page 10 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2(RO)
System # / Name KKK KIA Topic(s)
IR #
123 001 Control Rod Drive System K2 Knowledge of bus power supplies to the 3.1*
following:
[Question 56] K2.05 M/G sets (CFR: 41.7) 015 Nuclear Instrumentation 2.2.37 Ability to determine operability and/or 3.6 availability of safety related equipment.
[Question 57] (CFR: 41.7/43.5/45.12) 016 Non-nuclear K5 Knowledge of the operational implication of 2.7*
Instrumentation the following concepts as they apply to the NNIS:
[Question 58]
K5.01 Separation of control and protection c:i rcu its (CFR: 41.5 /45.7) 017 In-Core Temperature A1 Ability to predict and/or monitor changes in 3.7 Monitor System (ITM) parameters (to prevent exceeding design limits) associated with operating the ITM system
[Question 59] controls including:
A1.01 Core exit temperature (CFR: 41.5 /45.7) 041 Steam Dump System (SDS) K1 Knowledge of the Physical connections 2.7 Turbine Bypass Control and/or cause-effect relationships between the SDS and the following systems:
lI:.JUestion 60] K1.02 S/G level (CFR: 41.2 to 41.9/45.7 to 45.8) 033 Spent Fuel Pool Cooling K4 Knowledge of design feature(s) and/or 3.1 interlock(s) which provide for the following:
[Question 61] K4.05 Adequate SDM (boron concentration)
(CFR: 41.7) 034 Fuel Handling Equipment K6 Knowledge of the effect of a loss or 2.6*
malfunction on the following will have on the
[Question 62] Fuel Handling System:
K6.02 Radiation monitoring systems (CFR: 41.7/45.7) 055 Condenser Air Removal K1 Knowledge of the physical connections 2.6 and/or cause/effect relationships between the
[Question 63] CARS and the following systems:
K1.06 PRM system (CFR: 41.2 to 41.9 /45.7 to 45.8) 071 Waste Gas Disposal A4 Ability to manually operate and/or monitor in 2.6*
the control room:
[Question 64] A4.05 Gas decay tanks, including valves, indicators, and sample line (CFR: 41.7/45.5 to 45.8)
NUREG-1 021, Revision 9 Supplement 1 RO Page 11 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Fonn ES-401-2 Plant Systems - Tier 2/Group 2(RO) Continued System # / Name K KIA Topic(s)
IR #
1 075 Circulating Water K3 Knowledge of the effect that a loss or 3.4*
malfunctions of the circulating water system
[Question 65] will have on the following:
K3.07 ESFAS (CFR: 41.7 145.6) 1 0 0 1 Group Point Total: 10 NUREG-1 021. Revision 9 Supplement 1 RO Page 12 of 13 FENoe Facsimile Rev. AG
01 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401*3
~ _,dhty: BVPS UNIT 2 RO Date of Exam 9/24 thru 10/5 2012 RO Category KlA# Topic IR #
- 1. 2.1.21 Ability to verify the controlled procedure copy. 3.5*
Conduct of Operations 1-----_~-:-[Q_:_u=e,_s_:_t-io-n-6_:6_:_]_(C,_F-R-:_41_,_10_':-4_5-;-.1-;-:0_:_'-45-.-,13-;}-;---:-----:-:-:------+---+--
2.1.8 Ability to coordinate personnel activities outside the control room. 3.4
[Question 67] (CFR: 41.10/45.5/45.12/45.13) 2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 response of another indication.
[Question 68] (CFR: 41.7 '43.5 145.4)
Subtotal
- 2. 2.2.23 Ability to track Technical Specification limiting conditions for operations.
Equipment Control [Question 69] (CFR: 41.10 143.2 145.13) 2.2.36 lity to maintenance as 3.1 power sources, on the status of limiting conditions for operations.
[Question 70] (CFR: 41.10 143.2 145.13)
Subtotal
- 3. 2.3.14 Knowledge of radiation or contamination hazards that may arise during Radiation normal, abnormal, or emergency conditions or activities.
Control
[Question 71] (CFR: 41.12 143.4 145.1 O) 2.3.4 Knowledge of radiation exposure limits under normal or emergency 3.2 1 conditions.
[Question 72] (CFR: 41.12 143.4/45.10)
Subtotal
- 4. 2.4.3 Ability to identify post-accident instrumentation.
Emergency Proceduresl [Question 73] (CFR: 41.6 145.4)
Plan 2.4.13 Knowledge of crew roles and responsibilities during EOP usage. 4.0 1
[Question 74] (CFR: 41.10 145.12) 2.4.34 Knowledge of RO tasks performed outside the main control room during 4.2 an emergency and the resultant operational effects.
[Question 75] (CFR: 41.10/43.5 145.13)
Subtotal Tier 3 Point Total NUREG-1021 , Revision 9 Supplement 1 RO Page 13 of 13 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401 ~2 Facil' SRO ONL Y Points Tier Group A2 G* TOTAL 1
3 3 6 1.
Emergency 2
& 3 1 4 Abnormal Plant Tier Totals 6 4 10 Evolutions 1
2.
3 2 5 Plant Systems 2 1 1 1 3 Tier Totals 5 3 8 1 2 3 4 7
- 3. Generic Knowledge and Abilities Category 2 1 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).
- 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES401 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 KlAs 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) KlAs 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 KlAs.
- 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, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
NUREG-1021 , Revision 9 Supplement 1 SRO Page 1 of 6 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(SRO)
E/APE # 1 Name 1 Safety Function K KIA Topic(s) IR #
1 000007 Reactor Trip -Stabilization 11 2.4.20 Knowledge of the operational implications of 4.3 EOP warnings, cautions, and notes.
[Question 76]
(CFR: 41.10/43.5/45.13) 000011 Large Break LOCA 13 2.4.44 Knowledge of emergency plan protective 4.4 action recommendations.
[Question 77]
(CFR: 41.10/41.12/43.5/45.11) 000026 Loss of Component Cooling Water 1 to interpret and execute re 4.6 8 steps.
[Question 78] (CFR: 41.10/43.5/45.12) 000056 Loss of Offsite Power 1 6 AA2. Ability to determine and interpret the following 3.9 as they apply to the Loss of Offsite Power:
[Question 79]
AA2.45 Indicators to assess status of ESF breakers (tripped/not-tripped) and validity of alarms (false/not false)
(CFR: 43.5/45.13) 000062 Loss of Nuclear Service Water 1 4 AA2. Ability to determine and interpret 3.5 as they apply to the Loss of Nuclear Service Water:
[Question 80]
AA2.01 Location of a leak in the SWS (CFR: 43.5/45.13)
W/E12 Steam Line Rupture - Excessive EA2. Ability to determine and interpret ng 4.0 Heat Transfer 14 as they apply to the (Uncontrolled Depressurization of all Steam Generators)
[Question 81]
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.51 45.13)
KIA Category Point Totals: 0 0 0 0 3 3 Group Point Total: 6 NUREG-1 021. Revision 9 Supplement 1 SRO Page 2 of 6 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(SRO) 1F=======================r=r=
E/APE # I Name 1 Safety Function K KIA Topic(s) IR #
1 000003 Dropped Control Rod 11 AA2. Ability to determine and interpret the following 3.8 as they apply to the Dropped Control Rod:
[Question 82]
AA2.03 Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature measurements (CFR: 43.5 145.13) 000074 Inadequate Core Cooling 14 2.1.19 Ability to use plant computers to evaluate 3.8 system or component status.
[Question 83] (CFR: 41.10/45.12)
WE02 SI Termination 13 and interpret the following 4.2 as they apply to the (SI Termination)
[Question 84]
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5/45.13)
Tube Leakl AA2. Ability to determine and interpret the 4.4 3 as they apply to the Steam Generator Tube Leak:
[Question 85] AA2.14 Actions to be taken if SIG goes solid and water enters steam lines (CFR: 43.5/45.13)
A Category Point Totals: Group Point Total: 4 NUREG-1021 , Revision 9 Supplement 1 SRO Page 3 of 6 FENOC Facsimile Rev. AG
ES401 PWR Examination Outline Form ES401-2 Plant Systems - Tier 21Group 1(SRO)
System # 1 Name K K KIA Topic(s) IR #
1 2 10 Pressure A2 Ability to (a) predict the impacts of the 4.2 Control System (PZR PCS) following malfunctions or operations on the
[Question 86] PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.03 PORV failures (CFR: 41.5/43.5 /45.3 / 45.13) 012 Reactor Protection System A2 Ability to 3.7 1 following malfunctions or operations on the
[Question 87] RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.07 Loss of de control power (CFR: 41.5/43.5/45.3/45.5) 013 Engineered Safety Features 2.2.37 Ability to determine operability and/or 4.6 1 Actuation System (ESFAS) availability of safety related equipment.
(CFR: 41.7/43.5/45.12)
[Question 88]
039 Main and Reheat Steam A2 Ability to (a) predict the impacts of the 3.6 System (MRSS) following malfunctions or operations on the
[Question 89] MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.05lncreasing steam demand, its relationship to increases in reactor power (CFR: 41.5/43.5 145.3/45.13) 061 Auxiliary 1 Emergency 2.1.2 Knowledge operator 4.4 Feedwater (AFW) System during all modes of plant operation.
(CFR: 41.10/45.13)
[Question 90]
NUREG-1021 , Revision 9 Supplement 1 SRO Page 4 of 6 FENoe Facsimile Rev. AG
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2(SRO)
~=================F=F=F=F~~=r=
System # 1 Name KKK K K KIA Topic(s) 1 234 5 IR 015 Nuclear Instrumentation A2 Ability to (a) predict the impacts of the 3.5*
System following malfunctions or operations on the NIS; and (b) based on those predictions, use
[Question 91] procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.02 Faulty or erratic operation of detectors or compensating components FR: 41.5/43.5/45.3/45 034 Fuel Handling Equipment K4 Knowledge of design feature(s) andlor 3.4 1 System (FHES) interlock(s) which provide for the following:
K4.01 Fuel protection from binding and
[Question 92] dropping (CFR: 41.7) 041 Dump System (SDS) 2.1.31 Ability to locate control room switches, 4.3 1 and Turbine Bypass Control controls, and indications, and to determine that
[Question 93] they correctly reflect the desired plant lineup.
(CFR: 41.10 145.12)
KIA Category Point Totals: Group Point Total: 3 NUREG*1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENoe Facsimile Rev. AG
ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: BVPS UNIT 2 SRO Date of Exam 9/24 thru 10/5 2012 Category KJA# Topic
- 1. 2.1.5 Ability to use procedures related to shift staffing, such as minimum Conduct crew complement, overtime limitations, etc.
of Operations
[Question 94] (CFR: 41.10 143.5/45.12) 2.1.32 Ability to explain and apply system limits and precautions.
[Question 95] (CFR: 41.10/43.2 145.12)
Subtotal
- 2. 2.2.20 Knowledge of the process for managing troubleshooting activities.
Equipment Control [Question 96] (CFR: 41.10 143.5/45.13)
Subtotal
- 3. 2.3.6 Ability to approve release permits.
Radiation Control [Question 97] (CFR: 41.13/43.4/45.10) 2.3.11 Ability to control radiation releases.
[Question 98] (CFR: 41.11 143.4 145.10)
Subtotal 2.4.20 Knowledge of the operational implications of EOP warnings, Emergency cautions, and notes.
Proceduresl Plan [Question 99] (CFR: 41.10/43.5/45.13) 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
[Question 100] (CFR: 41.10/43.5/45.3/45.12)
Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 FENoe Facsimile Rev. AG
ES-401 Record of Rejected KIAs Form ES-401-4 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/52012 Operating Test No.: 2LOT8 NRC
=
Tier I Randomly Reason for Rejection Group Selected KIA RO OUTLINE 1/1 000022 2.2.6 Question # 4; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.2.39 from same generic group.
1/1 000057 2.4.19 Question # 12; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.4.4 from same generic group.
1/2 000076 2.1.5 Question # 23; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.31 from same generic group.
2/1 025 K4.02 Question # 30; Beaver Valley Unit 2 does not have ice condensers. Randomly reselected 004 K4.14 as a replacement.
.,1 0052.1.5 Question # 31; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2 .
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.32 from same generic group.
2/1 025 A4.02 Question # 44; Beaver Valley Unit 2 does not have ice condensers. Randomly reselected 061 A 1.01 as a replacement.
2/1 0632.1.39 Question # 47; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.7 from same generic group.
2/2 0272.2.37 Question # 57; Beaver Valley Unit 2 has removed the CNMT Iodine Removal system and replaced it with a passive sodium tetra borate basket system.
Operations personnel do not have any tasks associated with this new system.
Randomly reselected the 015 system as a replacement.
2/2 028 K1.01 Question # 60; Beaver Valley Unit 2 has removed the Hydrogen Recombiner system. Hydrogen Recombiner functions are now directed by the TSC and the equipment that will be used is on skid that will be hooked-up and utilized as necessary. Operations personnel do not currently have any tasks associated with this system. The TSC will implement the use of the recombiners during SAMG implementation. Randomly reselected 041 K1.02 as a replacement.
NUREG-1 021, Revision 9 Supplement 1 Page 1 of3 FENOC Facsimile Rev. AG
ES-401 Record of Rejected KlAs Form ES-401-4 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/5 2012 Operating Test No.: 2LOT8 NRC Tier I Randomly Reason for Rejection Group Selected KIA 2/1 062 K4.05 Question # 46; KA is too similar to 062 A4.07 KA that was randomly selected for question # 45. Randomly reselected 062 K4.10 as a replacement.
1/1 WE042.1.27 Question # 16; Knowledge of system purpose/function does not apply to a LOCA outside containment. Randomly reselected 2.1.23 from same generic group 1/2 WE08 EK3.2 Question # 25; Unable to construct a discriminatory question about the reason for having procedures to address PTS. Randomly reselected EK3.1 for the same Emergency Plant evolution.
2/1 007 K5.02 Question # 34; The PRT is no longer used at Beaver Valley Unit 2 during PZR steam bubble formation. Randomly reselected A3.01 as a replacement 2/1 103 A2.04 Question 54; Beaver Valley Unit 2 does not have any operations procedures that address how to correct a containment evacuation that has failed. This would be dealt with through the work order process. Randomly reselected A2.03 as a replacement.
2/2 055A3.03 Question # 63; Beaver Valley Unit 2 does not have any automatic diversion of CARS exhaust. Re-alignment of CARS exhaust is done manually. Randomly reselected K1.06 as a replacement.
1/1 000008 AK2.03 Question # 1, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected AK2.02 as a replacement.
2/1 078 A3.01 Question # 53, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected K1.03 as a replacement.
3 2.1.39 Question # 67, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.1.8 from the same generic group.
3 2.2.41 Question # 70, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.2.36 from the same generic group.
3 2.3.15 Question # 72, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.3.4 from the same generic group.
NUREG-1021, Revision 9 Supplement 1 Page 2 of3 FENOC Facsimile Rev. AG
ES-401 Record of Rejected KIAs Form ES-401-4 Facility: BVPS UNIT 2 Date of Exam 9/24 thru 10/5 2012 Operating Test No.: 2LOT8 NRC
=
Tier I Randomly Reason for Rejection Group Selected KIA SRO OUTLINE 1/1 000007 2.4.26 Question # 76; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.4.20 from same generic group.
1/2 0000742.1.36 Question # 83; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.19 from same generic group.
2/1 0132.3.15 Question # 88; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.2.37 as a replacement.
2/1 041 2.3.11 Question # 93; ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2.
These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator. Randomly reselected 2.1.31 as a replacement.
1/1 056 AA2.58 Question # 79; Unable to construct a discriminatory question at the SRO level around the air compressor indicating light status during a Loss of Offsite Power.
Randomly reselected AA2.45 as a replacement.
2/2 015 A2.05 Question # 91, Unable to construct a discriminatory question at the SRO level around the impact of core voiding on the NIS and the procedural guidance to correct or mitigate. Randomly reselected A2.02 as a replacement.
1/1 000026 2.1.25 Question # 78, Unable to construct a discriminatory question at the SRO level around the use of graphs and charts during a loss of CCW. Randomly reselected 2.1.20 as a replacement.
2/1 061 2.1.7 Question # 90, Chief examiner requested this KIA be replaced due to over-sampling when compared to the last 2 exams. Randomly reselected 2.1.2 from the same generic group.
1/2 WE102.2.38 Question # 85 Unable to construct an SRO discriminatory question for conditions and limitations in the facility license while in ES-0.4, Natural Circulation Cooldown with Steam void in the vessel W/O RVLlS. Randomly re-selected 000037 AA2.14.
3 2.4.41 Question # 100 Chief examiner requested this KIA be replaced due to exam balance. EAL thresholds are already adequately covered on the exam. Randomly reselected 2.4.46 as a replacement.
NUREG-1021, Revision 9 Supplement 1 Page 3 of 3 FENoe Facsimile Rev. AG
ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 2 Date of Examination: 9/24 thru 10/42012
'amination Level RO [8] Operating Test Number 2LOT8 NRC Administrative Topic Type Describe activity to be performed Code*
(See Note)
Conduct of Operations M,R 2.1.23 (4.3)
Ability to perform specific system and integrated plant procedures (RO A.1.1) during all modes of plant operation.
(2AD-007) Perform an ECP Calculation Conduct of Operations M,R 2.1.37 (4.3)
Knowledge of procedures, guidelines, or limitations associated with (RO A.1.2) reactivity management.
(2CR-003) Perform a Quadrant Power Tilt Ratio Calculation Equipment Control D,P,R 2.2.13 (4.1)
""'OA.2) Knowledge of tagging and clearance procedures.
(2AD-031) Prepare a Clearance Tagout [2QSS-P21B] Quench Spray Pump 21B Radiation Control N,R 2.3.7 (3.5)
(RO A.3) Ability to comply with radiation work permit requirements during normal or abnormal conditions.
(2AD-044) Select RWP and Determine Maximum Allowable Stay Time Emergency NOT EVALUATED Procedures/Plan topics, when all 5 are required.
"Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (:: 3 for ROs; ::. 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (z: 1)
(P)revious 2 exams (:: 1; randomly selected)
NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. AG
ES-301 Administrative Topics Outline Form ES-301-1 Facility: BVPS Unit 2 Date of Examination: 9/24 thru 10/42012 II
'amination Level SRO IR1 Operating Test Number 2LOT8 NRC Administrative Topic Type Describe activity to be performed (See Note) Code*
Conduct of N, R 2.1.25 (4.2)
Operations Ability to interpret reference materials, such as graphs, curves, tables, (SRO A.1.1) etc.
(2AD-039) Review Completed SID Margin Calculation (At Power with One Inoperable rod).
Conduct of N,R 2.1.37 (4.6)
Operations Knowledge of procedures, guidelines, or limitations associated with (SRO A.1.2) reactivity management.
(2AD-045) Review completed Quadrant Power Tilt Ratio Calculation.
2.2.17 (3.8)
Equipment Control N,R (SRO A.2) Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
(2AD-041) Perform a Risk Assessment (2FWE*P23A maintenance)
Radiation Control N,R 2.3.11 (4.3)
(SRO A.3) Ability to control radiation releases.
(2AD-042) Determine Compensatory actions for 2GWS-RQ1 04 and 2GWS-OA 100A being OOS.
Emergency N,R 2.4.41 (4.1)
Procedures/Plan Knowledge of the emergency action level thresholds and classifications.
(SRO A.4)
(2AD-046) Classify an Emergency Event (Scenario Specific)
TE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
"Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank ~ 3 for ROs; ~ 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (~ 1; randomly selected)
~~==========================================================================~
NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev. AG
ES 301 Cont ro I RoomII n-PIant S,ystems o u trme Form ES 301 2 - -
Facility: BVPS UNIT 2 Date of Examination: 9/24 thru 10/4 2012 Exam Level: RO IRI Operating Test No.: 2LOT8 NRC Control Room Systems'<!! (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code* Safety Function S1 - Shift from Main FfIN Reg. Vlvs to Bypasses (2CR-072) S,D 4S 52 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622) S,D 7 53 - Raise Rx PWR to 10-8 AMPS (2CR-644) S,D,A,L 1 S4 - Isolate SI Accumulators During a LOCA (2CR-654) S,D,A,EN 3 55 - Perform Manual Makeup to the Charging Suction (2CR-581) S,D,A 2 S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597) S,N,A 6 S7 - Containment Spray Manual Actuation (2CR-656) S,M,A 5 S8 - Swap RHS Trains (2CR-636) S, M, A, EN, L 4P In-Plant 5ystems@ (3 for RO); (3 for 5RO-I); (3 or 2 for SRO-U)
P1 - Align Service Water Supply to AFW Pump Suction (2PL-167) N,R,E 4S P2 - Startup a Rod Drive MG Set (2PL-003) D 1 P3 - Place a RPS Channel in the Tripped Condition (2PL-009) D 7
@ All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-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 1 SRO-I 1 SRO-U (A)lternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ;::1/;::1/;::1 (EN)gineered safety feature - / - / ~ 1 (Control room system)
(L)ow-power I Shutdown ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1(A) ;::2/;::2/;::1 (P)revious 2 exams S3/S3/s2 (randomly selected)
(R)CA ;::1/;::1/;::1 (S)imulator NUREG-1021 , Revision 9 Supplement 1 FENOC Facsimile Rev. AG
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
~
BVPS UNIT 2 Date of Examination: 9/24 thru 10/4 2012
",,,,,,1: ~~O(I) [8] Operating Test No.: 2LOT8 NRC Control Room Systems\<Y (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code* Safety Function S1 - Shift from Main FIW Reg. Vlvs to Bypasses (2CR-072) S,D 4S S2 - Respond to Rad Monitor Alarm (leak Coli Vent) (2CR-622) S,D 7 S3 - Raise Rx PWR to 10-8 AMPS (2CR-644) S,D,A,L 1 II S4 - Isolate SI Accumulators During a LOCA (2CR-654) S,D,A,EN 3 S5 - Perform Manual Makeup to the Charging Suction (2CR-581) S,D,A 2 S6 - X-fer 4Kv AE Emerg Bus from Emerg to Norm (2CR-597) S,N,A 6 S7 - Containment Spray Manual Actuation (2CR-656) S,M,A 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
Pi - Align Service Water Supply to AFW Pump Suction (2PL-167) N, R, E 4S P2 - Startup a Rod Drive MG Set (2PL-003) D 1 P3 - Place a RPS Channel in the Tripped Condition (2PL-009) D 7
@ All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5SRO-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 1 SRO-II SRO-U (A)lternate Path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank ::;9/::;8/:>4 (E)mergency or abnormal in-plant 1ii:1/1ii:1/~1 (EN)gineered safety feature 1 ~ 1 (Control room system)
(L)ow-power / Shutdown 1ii:1/1ii:1/~1 (N)ew or (M)odified from bank including 1(A) 1ii:2/?!2/?!1 (P)revious 2 exams ::; 31::; 31 s 2 (randomly selected)
(R)CA ?!1/1ii:1/1ii:1 (S)imulator NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev. AG
Alppen d'IX D , 0 utrme S cenano Form ES D.1 ~
Facility: BVPS Unit 2 Scenario No.: 1 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 211(7): 25% power, BOL, Xe increasing, CB "D" @ 121 steps, RCS boron ~ 1935 ppm.
Conditions: Main feed regulating valves in service Turnover: Increase power to 100%. 2SAS-C21 BOOS Critical Tasks: 1. E-O.E Actuate 1 train of CNMT Spray
- 2. E-O.P Manually actuate SLI
- 3. E-2.A Isolate Faulted SIG Event Malf. No. Event Type Event Description No.
1 (R)ATC Raise power in accordance with reactivity plan.
(N) BOP, SRO 2 (TS) SRO 2FWE*P22 (turbine driven Aux Feedwater pump) trips 3 (I) ATC, SRO 2CHS-PT145, fails high, ATC required to manually control letdown pressure via 2CHS-PCV145.
4 (C) BOP, SRO Loss of2AE 4kv Emergency bus 12-1 Emergency Diesel fails (TS) SRO to auto start. BOP required to manually start EDG 2-1.
(C)ATC A TC manually aligns cooling water flow to EDG 2-1 5 (C) BOP, SRO 2CCS-P21A sheared shaft, auto start failure of2CCS-P21B, requires manually starting standby pump.
6 (M)ALL Feedline break inside CNMT.
7 (C) ATC, SRO CIB actuation failure 8 (C) BOP, SRO MSLI actuation failure with 2SDS* AOVl11's failing to auto close, requires BOP to manually actuate MSLI and close all 6 2SDS*AOVlll 's 9 (C) BOP, SRO "B" train CREV's fails to actuate, requires BOP to manually actuate.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. AG
Appendix 0 Scenario Outline Form ES-D-1 Facility: BVPS Unit 2 Scenario No.:2 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 219(17): 72% power, MOL, Eq Xe, CB "D"@180 steps, RCS boron - 1140 ppm.
Conditions:
Turnover: Maintain steady state power at 72%, 2FWE*P23A OOS, 2SAS-C21 BOOS Critical Tasks: 1. E-O.A Manually trip the Reactor
- 2. E-O.Q Manually trip the turbine
- 3. FR-H.1.A Establish feedwater flow before Feed and Bleed criteria Event Event Description No.
1 (C)ATC, SRO N44 fails high, rods automatically step in.
(TS) SRO 2 (R)ATC 2FWS-P21B trips! reduce power to 52%
(C) BOP, SRO 3 (TS) SRO Misaligned Rod 4 (M)ALL 2RCS*P21B locked rotor trip with Automatic Reactor trip failure and 400 gpm SBLOCA 5 (C) BOP, SRO Automatic turbine trip failure 6 (M) ALL Loss of all auxiliary feed water, entry into FR-H.l 7 (C) BOP, SRO Failure of2FWS-P24, 2FWS-P21A and P21B (requires secondary depressurization and use of condensate pump.
S (C) BOP, SRO 2HVS-FN204A and B trip, requires manual starting of at least 1 fan.
9 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG
A~ppen d'IX D . 0 utrme S cenana Farm ES D 1..
Facility: BVPS Unit 2 Scenario No.:4 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 214(18): 100% power, MOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1044 ppm.
Conditions:
Turnover: Maintain steady state power at 100%, 2FWE*P23A ~OS, 2SAS-e21 BOOS Critical Tasks: 1. E-O.O Close CNMT isolation valves
- 2. E-1.C Stop RCP's
- 3. FR-S.1.C Insert RCCA's Event Malf. No. Event Type Event Description No.
1 (I) ATC, SRO 2RCS*LT459 fails low.
(TS) SRO 2 (N) ATe, SRO Restore letdown to service 3 (R)ATe Valve position limiter failure causes load rejection with Auto (1) ATC, SRO rod malfunction, ATC required to insert negative reactivity.
4 (e) BOP, SRO During load rejection, "A" Main Feed Regulating Valve controller holds valve in position, BOP required to manually control "A" S/G level.
5 (e) ATC, SRO 2ReS*PT445 fails high, 2 PORV's open, 2ReS*peV456 fails (TS) SRO to 18% open with Block valve failed open, requiring crew to manually trip the reactor.
6 (M) ALL ATWS, crew enters FR-S.l.
I 7 (M) ALL 2000 gpm SBLOCA on return to E-O.
8 (e) BOP, SRO Train B CIA failure with 2eHS*MOV378 failing to auto close 9
(N)orrnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG
A~ppen d'IX D , 0 utrme s cenano Form ES D 1 ..
Facility: BVPS Unit 2 Scenario No.:5 Op Test No.: 2LOT8 NRC Examiners: Candidates: SRO ATC BOP Initial IC 217(10): 100% power, BOL, Eq Xe, CB "D" @ 225 steps, RCS boron 1458 ppm.
Conditions:
Turnover: Maintain steady state power at 100%, 2FWE*P23A OOS, 2SAS-C21 BOOS Critical Tasks: 1. E-O.D Crew manually actuates at least one train of SIS
- 2. E-O.F Crew establishes the minimum required AFW flow
- 4. E-O.I Establish flow from at least 1 High head ECCS pump Event Malf. No. Event Type Event Description No.
1 (I) ATe, SRO 2ReS*PT444 drifts low, requires ATC to manually control RCS pressure.
2 (TS) SRO 2FWS-LT485 fails high 3 (C) BOP, SRO Voltage regulator failure causes main generator over excitation, requires BOP to turn voltage regulator off and manually lower excitation.
4 (C) ATC, SRO 25 gpm ReS leak on HA" Loop.
(TS) SRO 5 (M)ALL 500 gpm RCS leak on "A" Loop.
6 (e) ATC, SRO 2RCS-peV455D fails open on Rx trip, requires ATC to close block valve.
7 (C) BOP, SRO AFW malfunctions, 2FWE*P23A OOS on turnover, 2FWE*P23B auto start failure, requires BOP to manually start.
2FWE*P22 running with reduced flow << 340 gpm) 8 (C) ATe, SRO Auto SIS inhibited, requires ATe to manually actuate SIS.
9 (e) ATC, SRO 2SIS*MOV867's fail to open on SIS actuation signal, ATe required to manually open valves to initiate Safety Injection flow.
(N)ormal, (R)eactivity, (I)nstrument, (e)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENoe Facsimile Rev. AG