ML103490486
| ML103490486 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/19/2010 |
| From: | David Silk Operations Branch I |
| To: | Momm E NextEra Energy Seabrook |
| Hansell S | |
| Shared Package | |
| ML101870654 | List: |
| References | |
| TAC U01694 | |
| Download: ML103490486 (40) | |
Text
RANDOMSAMPLING PROCESS
. 2010 SEABROOKLOITNRC WRITTENEXAM As required by NUREG 1021, Rev 9, Supplement 1, (ES-401 D.1.b), the licensee shall submit along with the NRC examination outline, a description of the systematic and random selection process used to develop the examination outline.
The manual random sampling process describt:d in Attachment 1 of ES-401 was used to generate the NRC Examination RO and SRO outlines.
- During the exam outline generation the following KIA statements were eliminated as not applicable to Seabrook design.
o All KlAs associated with Ice Condenser (025) - This system is N/A to Seabrook.
o All KIAs associated with Containment Iodine Removal (27) - This system is included as part of the Containment Building Spray System at Seabrook.
o Generic KIA statements 2.2.3 and 2.2.4 (multi-unit) were not sampled
- Seabrook is a single unit facility.
- During the examination development, any KIA statements eliminated and resampled were documented on ES-401-4, Record of Rejected KlAs as required by ES-401, Attachment 2.
The facility lead exam developer is overseeing the audit exam development to ensure no specific subject matter overlap occurs between the exams.
Page 1 of 1
ES-401 PWR Examination Outline Form ES-401-2 n
Date of Exam: December 2010 RO KIA CateQory Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A2 G*
Total AI?I 1
2 3
4 5
6 1
2 3
4 Total 1,
1 18 3
3 6
Emergency &
Abnormal N/A N/A 2
9 3
I 4
Plant Tier Totals 27 6
4 10 Evolutions 1
28 3
2 5
2, Plant 2
10 I 2 1
3 Systems Tier Totals 38 5
3 8
3, Generic Knowledge and Abilities 1
2 3
4 10 1 I 2 3
4 7
Categories 2
I 2
21 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 (Le" 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.
B.
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 paint totals (#) on Form ES401-3, Limit SRO selections to KlAs that are linked to 10 CFR 55,43,
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 I Emergenc and Abnormal Plant Evolutions - Tier llGroup 1 (RO 1SRO)
E/APE # 1 Name 1Safety Function 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery 11 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA 13 000011 Large Break LOCA I 3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water 18 000027 Pressurizer Pressure Control System Malfunction I 3 000029 A TWS I 1 000038 Steam Gen, Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12)
Steam Line Rupture Excessive Heat Transfer 14 000054 (CE/E06) Loss of Main Feedwater I 4 000055 Station Blackout I 6 000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst Bus 16 000058 Loss of DC Power I 6 K
1 K
2 K
3 A
1 A
2 G
X KIA Topic(s) 2.4,18 Knowledge of the specific bases for EOP's CFR 41,10143,1/45,13 IR 4,0 76 i
X 2,1.20 Ability to interpret and execute procedure
- steps, CFR 41,10/43.5/45,12 4,6 77 X
AA2 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System:
AA2,04 Location and isolability of leaks, CFR 43,5/45.13 3.6 78 X
2.4.6 Knowledge of EOP mitigation strategies.
CFR 41.10/43,5/45,13 4,7 79 I
X EA2 Ability to determine or interpret the following as they apply to a Station Blackout:
EA2.02 RCS cooling through natural circulation cooling to SIG cooling, CFR 43,5/45,13 4.6 80 I
I I
000062 Loss of Nuclear Svc Water I 4
==;;:1 PWR Examination Outline Form ES-401-2 nd Abnormal Plant Evoluti E/APE # I Name I Safety Function KJA Topic(s)
IR K K KW G 1
2 3
Loss of Instrument Air I 8 W/E04 LOCA Outside Containment I 3 W/E11 Loss of Emergency Coolant Recirc./4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 X
EA2 Ability to operate andlor monitor the following as they apply to the Loss of Secondary Heat Sink:
4.3 81 EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
CFR 43.5/45.13 000077 Generator Voltage and Electric Grid Disturbances 16 KJA Category Totals:
!:l 3
Group Point Total:
1
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 EI E/APE # / Name / Safety Function K
K K
A A
G KiA Topic(s)
IR I
2 3
1 2
000001 Continuous Rod Withdrawal/1 000003 Dropped Control Rod /1 000005 Inoperable/Stuck Control Rod 11 000024 Emergency Boration / 1 X
AA2 Ability to determine and interpret 4.4 83 the following as they apply to the I
Emergency Soration:
AA2.02 When use of manual boration valve is needed.
CFR 43.5/45.13 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range Nil 7 000033 Loss of Intermediate Range Nil 7 000036 (BW/A08) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 X
2.4.11 Knowledge of abnormal condition 4.2 82 procedures CFR 41.10/43.5145.13 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid RadWaste ReI. 19 000060 Accidental Gaseous Radwaste ReI. / 9 I
000061 ARM System Alarms 17 000067 Plant Fire On-site / 8 000068 (SW/A06) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT Integrity 15 000074 (W/E06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity I 9 X
AA2 Ability to determine and interpret 3.4 84 the following as they apply to the High Reactor Coolant Activity:
AA2.02 Corrective actions required for high fission product activity in the RCS.
CFR43.5/45.13 W/E01 & E02 Rediagnosis & SI Termination 13 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding /5 II
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO 1SRO)
E/APE # I Name 1Safety Function K
I K
2 K
3 A
I A
2 G
KIA Topic(s)
IR W/E16 High Containment Radiation 19 BW/A01 Plant Runback 1 1 BW/A02&A03 Loss of NNI-XIY I 7 BW/A04 Turbine Trip 14 BW/A05 Emergency Diesel Actuation 1 6 BW/A07 Flooding 18 BW/E03 Inadequate Subeooling Margin 14 BW/E08; W/E03 LOCA Cooldown - Depress, 14 BW/E09; CE/A13; W/E09&E10 Natural Cire, 14 X
(E09) EA2 Ability to determine and interpret the following as they apply to the Natural Circulation Operations:
3,8 85 EA2,1 Facility conditions and selection of appropriate procedures during abnormal and emergency conditions.
CFR 43.5/45,13 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling - PTS I 4 CE/A16 Excess RCS Leaka1}e 12 CE/E09 Functional Recovery KIA Category Point Totals:
3 1
Group Point Total:
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PI'~ 1,RO 18RO)
T System # 1 Name K
K K
K G
KIA Topic(s)
IR I
2 3
4 3
4 I 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal X
A2 Ability to (a) predict the impacts of 3.1 86 the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.03 RHR Pump/Motor Malfunction.
CFR 41.5/43.5145.5/45.13 006 Emergency Core Cooling X
2.1.7 Ability to evaluate plant 4.7 87 performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
CFR 41.5/43.5145.12/45.13 007 Pressurizer Relief/Quench Tank 008 Component Coolina Water 010 Pressurizer Pressure Control 012 Reactor Protection X
A2 Ability to (a) predict the impacts of 3.2 88 the following malfunctions or operations on the RPS, and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.05 Faulty or erratic operation of detectors and function generators.
CFR 41.5/43.5/45.3145.5 013 Engineered Safety Features X
A2 Ability to a)predict the impacts of 4.0 89 Actuation the following malfunctions or operations on the ESFAS; and b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
A2.06 Inadvertent ESFAS actuation.
CFR 41.5/43.5/45.3/45.13 022 Containment Cooling 025 Ice Condenser
026 Containment Spray 039 Main and Reheat Steam I
ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 1 (RO 1SRO)
I System # 1Name K
I K
2 K
3 K
4 K
5 K
6 A
I A
2 A
3 A
4 G
KIA Topic(s)
IR 059 Main Feedwater 061 Auxiliary/Emergency Feedwater X
2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.7 90 CFR 41.5/43.2/45.2 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment KIA Category Point Totals:
3 2
Group Point Total:
28/
5
II ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 2 RO 1SRO)
System # 1Name KKK! KKK A A A
A G
KIA Topic(s)
IR :11 123145612 3
4 001 Control Rod Drive 002 Reactor Coolant X
2.1.32 Ability to explain and apply system 4.0 91 limits and precautions.
CFR 41.10/432/45.12 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation x
A2 Ability to (a) predict the impacts of the 3.1 93 following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.01 Detector failure CFR 41.5/435/453/45.5 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling x
A2 Ability to (a) predict the impacts of the 3.0 92 following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.02 Loss of SFPCS CFR 41.5/43.5/45.3/45.13 034 Fuel Handling Equipment 035 Steam Generator 041 Steam DumplTurbine Bypass Control
ES-401 System # I Name K
I K
2 PWR Examination Outline Plant Systems - Tier 2/Group 2 RO I SRO)
I AlA K
K K K A A G 3
4 5
6 I
2 3
4 KIA Topic(s)
Form ES-401-2 IR 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate I
068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection KIA Category Point Totals:
2 1
Group Point Total:
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 SEABROOK Category KIA #
2.1.23
- 1.
Conduct of Operations 2.1.36 2.1.
2.1.
2.1.
2.1.
Subtotal 2.2.21
- 2.
Equipment 2.2.40 Control 2.2.
2.2.
2.2.
2.2.
Subtotal 2.3.4
- 3.
Radiation i 2.3.
Control 2.3.
2.3.
2.3.
2.3.
Subtotal Date of Exam:
December 2010 Topic Ability to perform specific system and integrated plant procedures during all modes of plant operation.
CFR 41.10/43.5/45.2/45.6 Knowledge of procedures and limitations involved in core alterations.
CFR 41.10/43.6145.7 IR RO SRO-Only IR 4.4 94 4.1 95 Knowledge of pre and post maintenance operability requirements.
CFR 41.10/43.2 Ability to apply Technical Specifications for a system.
CFR 41.10/43.2/43.5/45.3 4.1 4.7 2
96 97 Knowledge of radiation exposure limits under normal or emergency conditions.
CFR 41.12/43.4/45.10 3.7 2
98 I
Facility: SEABROOK Category KJA#
2.4.5
- 4.
Emergency Procedures I Plan 2.4.27 2.4.
2.4.
2.4.
2.4.
Subtotal Tier 3 Point Total Date of Exam:
December 2010 Topic RO SRO-Only IR IR Knowledge of the organization of the operating 4.3 99 I
procedures network for normal, abnormal, and emergency evolutions.
CFR 41.10/43.5/45.13 Knowledge of "fire in the plant" procedures.
3.9 100 CFR 41.10/43.5/45.13 2
10 7
ES-401 PWR Examination Outline Form ES-401-2 Facility:
SEABROOK RO Section Date of Exam: December 2010 Tier Group K
K K
RO KIA Category Points K
K K
A A
G A2 SRO-Only Points G*
Total 1
2 3
4 5' 6 1
~ I ~ 4 Total
- 1.
1 2
2 5
4 2
3 18 6
Emergency &
Abnormal N/A N/A 2
I I
3 I
2 I
9 4
Plant Tier Totals 3
3 8
5 4
4 27 10 Evolutions 1
5 2
2 6
1 2
I 2
4 2
I 28 5
2, 2
I 0
I 1
I 0
2 2
I 0
I 10 3
Plant Systems Tier Totals 6
2 3
7 2
2 3
4 5
2 2
38 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 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 (Le" 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 paint totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-2 PWR Examination Outline Form ES-401*2 Emergencv and Abnormal Plant Evolutions* Tier 1/Group 1 (RO 1SRO)
E/APE # I Name 1Safety Function K
K K A A
G KIA Topic(s)
IR 1
2 3
1 2
000007 (BW/E02&E10; CE/E02) Reactor X
EK2 Knowledge of the interrelationship between the 2.6 I
Trip - Stabilization* Recovery 1 1 reactor trip and the following:
EK2.02 Breakers, relays and disconnects.
CFR 41.7/45.7 i
000008 Pressurizer Vapor Space Accident/3 000009 Small Break LOCA 13 X
EA2 Ability to determine or interpret the following as 4.2 2
they apply to a small break LOCA:
EA2.37 Existence of adequate natural circulation.
CFR 43.5/45.13 000011 Large Break LOCA I 3 X
EK3 Knowledge of the reasons for the following 4.1 3
responses as they apply to the large break LOCA:
EK3.14 RCP tripping requirement.
41.5/41.10/45.6/45.13 000015/17 RCP Malfunctions 1 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling X
AK3 Knowledge of the reasons for the following 3.6 4
Water 18 responses as they apply to the Loss of Component Cooling Water:
AK3.02 The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS.
CFR 41.7/45.7 000027 Pressurizer Pressure Control X
2.1.7 Ability to evaluate plant performance and 4.4 5
System Malfunction 13 make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
CFR 41.5/43.5/45.12/45.13 000029 A TWS 11 X
EA 1 Ability to operate and monitor the following as 4.2 6
they apply to an ATWS:
EA 1.14 Driving of Control Rods into the core.
CFR 41.7/45.5145.6 000038 Steam Gen. Tube Rupture 13 000040 (BW/E05; CE/E05; W/E12)
X AAl Ability to operate andlor monitor the following 4.1 7
Steam Line Rupture* Excessive Heat as they apply to Steam Line Rupture:
Transfer 14 AA1.20 Containment pressure and temperature trends.
CFR 41.7/45.5/45.6
ES*401 PWR Examination Outline Form ES*401*2 Emer E/APE # / Name I Safety Function K K K A A
G KIA Topic(s)
IR I #
1 213 1 1 2
000054 (CE/E06) Loss of Main X
4.0 8
2.4.21 Knowledge of the parameters and logic used Feedwater / 4 to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, reactivity release control, etc.
CFR 41.7/43.5/45.12 000055 Station Blackout / 6 X
EK3 Knowledge of the reasons for the following 4.3 9
responses as they apply to the Station Blackout:
EK3.02 Actions contained in EOP for loss of offsite and onsite power.
41.5/41.10/45.6/45.13 000056 Loss of Off*site Power / 6 X
AA 1 Ability to operate andlor monitor the following 3.3 10 as they apply to the Loss of Offsite Power:
AA1.21 Reset of ESF load sequencers.
CFR 41.7/45.5/45.6 000057 Loss of Vital AC Inst. Bus /6 X
AA2 Ability to determine and interpret the following 3.8 11 as they apply to the Loss of Vital AC Instrument Bus:
AA2.15 That a loss of ac has occurred.
CFR 43.5/45.13 000058 Loss of DC Power / 6 X
AK3 Knowledge of the reasons for the following 4.0 12 responses as they apply to the Loss of DC Power:
AK3.02 Actions contained in EOP for loss of dc power.
CFR 41.5/41.10/45.6/45.1 000062 Loss of Nuclear Svc Water 1 4 X
3.2 13 AA1 Ability to operate andlor monitor the following as they apply to the Loss of Nuclear Service Water:
AA 1.02 Loads on the SWS in the control room.
CFR 41.7/45.5145.6 000065 Loss of Instrument Air 1 8 X
2.1.32 Ability to explain and apply system limits and 3.8 14 precautions.
CFR 41.10/43.2/45.12 W/E04 LOCA Outside Containment / 3 X
EK 1 Knowledge of the operational implications of 3.5 15 the following concepts as they apply to the LOCA Outside Containment:
EK1.3 Annunciators and conditions indicating signals, and remedial actions associated with the LOCA Outside Containment CFR 41.8/41.10/45.3 I
ES-401 PWR Examination Outline EmerQencv C'r))
E/APE # 1Name 1Safety Function K
K A A
G KIA Topic(s)
IR I #
1 2
3 1
2 W/E11 Loss of Emergency Coolant X
EK3 Knowledge of the reasons for the following 3.6 16 Recirc./4 responses as they apply to the Loss of Emergency Coolant Recirculation:
EK3.4 RO and SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
CFR 415/41.10/45.6/45.13 BW/E04; W/E05 Inadequate Heat X
EK2 Knowledge of the interrelations between the 3.9 17 Transfer - Loss of Secondary Heat Sink 14 Loss of Secondary Heat Sink and the following:
EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operations of these systems to the operation of the facility.
CFR41.7/45.7 000077 Generator Voltage and Electric X
AK1 Knowledge ofthe operational implications of 18 33 Grid Disturbances 1 6 the following concepts as they apply to Generator Voltage and Electrical Grid Disturbances:
AK1.03 Under-excitation.
CFR 41.4/41.5/41.7/41.10/45.8 I
KIA Category Totals:
'" Total:
181 2 21St 2 ~
6
I ES-401 3
Form ES-401*2 ES-401 PWR Examination Outline Form E5-401-2 Emergency and Abnormal Plant Evolutions - Tier 1tGroup 2 (RO t SRO)
EtAPE # t Name / Safety Function K
K K
A A
G KIA Topic(s)
IR I
2 3
I 2
000001 Continuous Rod Withdrawalt1 000003 Dropped Control Rod 1 1 000005 Inoperable/Stuck Control Rod / 1 X
AK1 Knowledge of the operational 3.1 19 implications of the following concepts as they apply to Inoperable/Stuck Control Rod:
AK1.02 Flux tilt CFR 41.8/41.10/45.3 000024 Emergency Boration 1 1 000028 Pressurizer Level Malfunction 12 X
AA 1 Ability to operate and/or monitor the 3.3 20 following as they apply to the Pressurizer Level Control Malfunctions:
AA1.07 Charging pump maintenance of PZR level (including manual backup).
I CFR 41,7/45,5/45.6 000032 Loss of Source Range NI/ 7 X
AA2 Ability to detenmine and interpret 3.1 21 the following as they apply to Loss of Source Range Nuclear Instrumentation:
AA2.04 Satisfactory source-range/intermediate-range overlap.
CFR 43.5/45,13 000033 Loss of Intenmediate Range Nil 7 000036 (BW/A08) Fuel Handling Accident 18 000037 Steam Generator Tube Leak 13 X
AK3 Knowledge of the reasons for the 3.7 t;;
following responses as they apply to the Steam Generator Tube Leak:
AK3.05 Actions contained in procedures for radiation monitoring, RCS water level inventory balance, S/G tube failure, and plant shutdown.
I CFR 41,5/41.10/45,6/45,13 000051 Loss of Condenser Vacuum 1 4 X
2.4.11 Knowledge of abnonmal condition 4.0 23 procedures.
CFR 41,10/43.5/45.13 000059 Accidental Liquid RadWaste ReI. 1 9 000060 Accidental Gaseous Radwaste ReI. 19 I
000061 ARM System Alarms 17 000067 Plant Fire On-site I 8 000068 (BW/A06) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT Integrity 15
ES-401 PWR Examination Outline Form ES-40 Emergency and Abnormal Plant Evolutions - Tier 1fGroup 2 (RO f SRO)
E/APE # I Name I Safety Function A
G KJA Topic(s)
IR 1
2 K ltt 000074 (W/E06&E07) Inad. Core Cooling f 4 X
(E06) EA2 Ability to determine and 3.4 24 interpret the following as they apply to the Degraded Core Cooling:
EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency conditions.
CFR 43.5/45.13 i 000076 High Reactor Coolant Activity 19 W/E01 & E02 Rediagnosis & SI Termination 13 X
(E02) EK2 Knowledge of the 3.5 25 interrelations between the SI Termination and the following:
EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
CFR 41.7/45.7 W/E13 Steam Generator Over-pressure 14 EK3 Knowledge of the reasons for the 3.2 26 X
following responses as they apply to the Steam Generator Overpressure:
EK3.3 Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.
CFR 41.5/41.10/45.6/45.13 i
W/E15 Containment Flooding 15 I
W/E16 High Containment Radiation 19 BW/A01 Plant Runback 11 i
BW/A02&A03 Loss of NNI-X/Y I 7 BW/A04 Turbine Trip I 4 BW/A05 Emergency Diesel Actuation 16 BW/A07 Flooding 18 BW/E03 Inadequate Subcooling Margin I 4 BW/E08; W/E03 LOCA Cooldown - Depress. 1 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. 14 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling PTS 14 X
EK3 Knowledge of the reasons for the 3.6 27 following responses as they apply to the Pressurized Thermal Shock:
EK3.2 Normal, abnormal and emergency operating procedures associated with Pressurized Thermal Shock.
CFR 41.5/41.10/45.6/45.13
Emer E/APE # I Name f Safety Function e/2 enc PWR Examination Outline and Abnormal Plant Evolutions Tier 1/Grou KKKAA G I
2 3
I 2
KIA Topic(s)
IR 3
2 Grou Point Total:
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Plant S stems - Tier 2IGroup 1 (RO 1SRO)
I System # 1Name K
I K
2 K
3 K
4 K
5 K
6 A
I A
2 A
3 A
4 G
KIA Topic(s) lR 003 Reactor Coolant Pump X
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RCP's and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
2.5 28 A2.05 Effects ofVCT pressure on RCP seal leakoff flows.
CFR 41.5/43.5/45.3/45.13 004 Chemical and Volume Control X
X K1 Knowledge of the physical connections and/or cause effect relationships between the CVCS and the following systems:
2.7 29 K1.26 Flow path from CVCS to reactor coolant drain tank and holdup tank.
CFR 41.2 to 41.9/45.7 to 45.8 K4 Knowledge of the CVCS design feature(s) and/or interlock(s) which provide for the following:
3.0 30 K407 Water supplies CFR 41.7 005 Residual Heat Removal X
X A 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including:
3.3 31 A1.02 RHR flow rate CFR 41.5/45.5 2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.0 32 CFR 41.5/43.2145.2 006 Emergency Core Cooling X
A4 Ability to manually operate and/or monitor in the control room:
4.4 33 A4.07 ECCS pumps and valves.
CFR 41.7/45.5 to 45.8 007 Pressurizer Relief/Quench Tank X
A3 Ability to monitor automatic operation of the PRTS, including:
2.7 34 A3.01 Components which discharge to the PRT.
CFR41.7/45.5
ES-401 PWR Examination Outline Form ES-401-2
)
System # / Name K
K K
K K
K A
A A
A G
KJA Topic(s)
IR I
2 3
4 5
6 I
2 3
4 008 Component Cooling Water X
K2 Knowledge of the bus power 3.0 35 supplies to the following:
K2.02 CCW pump, including emergency backup.
CFR41.7 010 Pressurizer Pressure Control X
X K3 Knowledge of the effect that a loss 3.8 36 or malfunction of the PZR PCS will have on the following:
K301 RCS CFR41.7/45.6 3.6 37 A4 Ability to manually operate and/or monitor in the control room:
A4.02 PZR heaters.
CFR 41.7/45.5 to 45.8 012 Reactor Protection X
X K4 Knowledge of the RPS design 3.2 38 feature(s) and/or interlocks(S) which provide for the following:
K4.06 Automatic or manual enable/disable of reactor trips.
CFR 41.7 K6 Knowledge of the effect that a loss 3.3 39 or malfunction of the following will have on the RPS:
K6.10 Permissive Circuits i
CFR41.7/45.7 013 Engineered Safety Features X
X K5 Knowledge of the operational 2.9 40 Actuation implications of the following concepts as they apply to the ESFAS:
K5.02 Safety system logic and reliability.
CFR 41.5/45.7 K6 Knowledge of the effect that a loss 2.7 41 or malfunction of the following will have on the ESFAS:
K6.01 Sensors and detectors.
CFR 41.7/45.5 to 45.8 022 Containment Cooling X
K4 Knowledge of the CCS design 2.8 42 features(s) and/or interlock(s) which provide for the following:
K4.04 Cooling of control rod drive motors.
CFR 41.7 025 Ice Condenser
System # I Name K
I K
2 K
3 K
4 K
5 K
6 A
I A
2 A
3 A
4 G
KIA Topic(s)
IR 026 Containment Spray X
A3 Ability to monitor automatic operation of the CCS, including:
4.3 43 A3.01 Pump starts and correct MOV positioning.
CFR 41.7/45.5 039 Main and Reheat Steam X
K4 Knowledge of the MRSS design features andlor interlocks which provide for the following:
3.7 44 K4.05 Automatic isolation of steam line.
CFR 41.7 059 Main Feedwater X
K1 Knowledge of the physical connections and/or cause effect relationships between the MFW and the following systems:
3.4 45 K1.04 S/Gs water level control system.
CFR 41.2 to 41.9/45.7 to 45.8 061 Auxiliary/Emergency Feedwater X
X K2 Knowledge of the bus power supplies to the following:
3.2 46 K2.01 AFW system MOV's.
CFR41.7 A3 Ability to monitor automatic operation of the AFW, including:
4.0 47 A3.02 RCS cooldown during AFW operations.
CFR 41.7/45.5 062 AC Electrical Distribution X
K 1 Knowledge of the physical connections and/or cause-effect relationships between the ac distribution system and the following systems:
4.1 48 K1.02 ED/G CFR 41.2 to 41.9 063 DC Electrical Distribution X
K4 Knowledge of DC electrical system design feature(s) andlor interlock(s) which provide for the following:
2.9 49 K4.02 Breaker interlocks, permissives, bypasses and cross-ties.
CFR41.7
I ES-401 PWR Examination Outline Form ES-401-2 System # / Name K
I K
2 Plant Systems - Tier 2/Group 1 (RO / SRO)
K K ill A
A Lili G
3 4
I 2
KIA Topic(s)
IR 064 Emergency Diesel Generator X
X K1 Knowledge of the physical connections and/or cause effect relationships between the EDG system and the following systems:
3,1 50 K1,02 D/G cooling water system, CFR 41,2 to 41,9/45,7 to 45.8 A3 Ability to monitor automatic operation of the EDG system, including:
3.6 51 A3,07 Load sequencing, CFR41,7/45,5 073 Process Radiation Monitoring X
K3 Knowledge of the effect that a loss or malfunction of the PRM system will have on the following:
3.6 52 K3.01 Radioactive effluent releases, CFR 41.7/45.6 076 Service Water X
K4 Knowledge of the SWS design feature(s) and/or interlock(s) which provide for the following:
2,5 53 K4,01 Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return
- valves, CFR 41.7 078 Instrument Air X
K1 Knowledge of the physical connections and/or cause-effect relationships between the lAS and the following systems:
2,7 54 K1,02 Service air CFR 1,2 to 41,9/45,7 to 45,8 103 Containment X
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
3.5 55 A2,03 Phase A and B isolation, CFR 41,5/43.5/45.3/45,13 KIA Category Point Totals:
- )
L L
6 1 2 I 2 4
L I
281 5
ES-401 5
Form ES-401-2 ES-401 System # I Name K
I K
2 K
3 PWR Examination Outline Plant Systems - Tier 21Group 2 RO 1SRO)
K K
K A A AI ;1 G 4
5 6
I 2
3 4
KIA Topic(s)
Form ES-401-2 IR 001 Control Rod Drive X
K3 Knowledge of the effect that a loss or malfunction of the CRDS will have on the following:
3,4 56 K3.02 RCS CFR41.7/45.6 002 Reactor Coolant 011 Pressurizer Level Control X
A3 Ability to monitor automatic operation of the PZR LCS, including:
3.2 57 A3.03 Charging and Letdown CFR41.7/45.5 014 Rod Position Indication X
A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:
3.2 58 A 1.02 Control rod position indication on control room panels.
CFR41.5/45.5 015 Nuclear Instrumentation X
2,4,4 Ability to recognize abnormal indications from system operating parameters that are entry level conditions for emergency and abnormal operating procedures.
4.5 59 016 Non-nuclear Instrumentation I I CFR 41.10/43.2/45.6 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge X
A 1 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the Containment Purge System controls including:
3.0 60 A1.03 Containment pressure, temperature, and humidity.
033 Spent Fuel Pool Cooling IT CFR 415/45.5 034 Fuel Handling Equipment 035 Steam Generator
ES-401 PWR Examination Outline F
ffi P'"I S,slems - TO, 21G","' 'An SRO)
System # 1Name K
I KKKAA AAG 4561234 KIA Topic(s) 041 Steam DumplTurbine Bypass Control X
K4 Knowledge of the SDS design feature(s) andlor interlock(s) which provide for the following:
K4.09 Relationship of lowllow Tavg setpoint in SDS to primary cooldown.
CFR41.7 045 Main Turbine Generator X
K5 Knowledge of the operational implications of the following concepts as they apply to the MT/G System:
K5.17 Relationship between MTC and boron concentration in RCS as turbine load increases.
CFR 41.5/45.7 055 Condenser Air Removal X
K1 Knowledge of the physical connections andlor cause effect relationship between the CARS and the following:
K1.06 PRM system 056 Condensate X
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the condensate system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.04 Loss of condensate pumps.
CFR 41.5/43.5/45.3/45.13 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water X
A2 Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations:
A2.02 Loss of circulating water pumps.
CFR 41.5/43.5/45.3/45.13 079 Station Air 086 Fire Protection I I Is:
1 0 1 1 I 0 2 2 I 0 1 Group Point Total:
1::" '"
IR 3.0 61 2.5 62 2.6 63 2.6 64 2.5 65 I
t:J
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 II SEABROOK Date of Exam:
December 2010 Category KJA#
Topic RO SRO-Only IR IR 2.1.1 Knowledge of conduct of operations requirements.
3.8 1
66
- 1.
CFR 41.10/45.13 i
Conduct of Operations 2.1.28 Knowledge of the purpose and function of major system components and controls.
4,1 1
67 CFR41.7 2.1,37 Knowledge of procedures, guidelines, or limitations 4.3 1
68 associated with reactivity management CFR 41,1/43.6/45.7 2.1.
2.1.
2.1.
Subtotal 3
2.2.12 Knowledge of surveillance procedures.
3.7 1
69 CFR 41.10/45.13
- 2.
Equipment Control 2.2.43 Knowledge of the process used to track inoperable alarms.
3,0 1
70 CFR 41.10/43.5/45.13 2.2.
2.2.
2.2.
2.2.
Subtotal 2
2,3.11 Ability to control radiation releases.
3.8 1
71 CFR 41.11/43.4/45,10
- 3.
Radiation Control 2.3.13 Knowledge of the radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment 3.4 1
72 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc, CFR 41,12/43.3/45.9/45.10 2.3.
! 2.3, 2.3.
2.3. Facility
SEABROOK Category KJA#
Subtotal 2.4.9
- 4.
Emergency Procedures I Plan 2.4.11 2.4.20 2.4.
2.4.
2.4.
Subtotal Tier 3 Point Total Date of Exam:
December 2010 Topic RO SRO-Only IR IR 2
Knowledge of low power/shutdown implications in 3.8 1
73 accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
CFR 41.10/43.5/45.13 Knowledge of abnormal condition procedures.
4.0 1
74 CFR 41.10143.5/45.13 Knowledge of the operational implications of EOP 3.8 I
75 warnings, cautions, and notes.
CFR 41.10/43.5/45.13 3
10 7
Seabrook Station 2010 NRC Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Group Tier 21 Group 1 ROand SRO section Tier 21 Group 2 ROand SRO section Generic KIA Generic KIA Tier 11 Group J RO Randomly Selected KIA 025 Ice Condenser 027 Containment Iodine Removal 2.2.3 (Multi-Unit License)
Knowledge of the
- design, procedural, and operational differences between units.
2.2.4 (Multi-Unit License) Ability to explain the variations in control board/control room layouts,
- systems, instrumentation, and procedural actions between units at a facility.
040 Steam Line Rupture Reason for Rejection During exam outline generation the KIA's associated with Ice Condenser (025) were suppressed.
This system is NIA to Seabrook.
During exam outline generation the KIA's associated with Containment Iodine Removal (027) were suppressed.
This system is included as part ofthe Containment Building Spray System at Seabrook During exam outline generation this KIA was suppressed.
Seabrook is not a multi-unit facility.
During exam outline generation this KIA was suppressed.
Seabrook is not a multi-unit facility.
Originally selected KA AAl.22, Ability to operate and/or monitor the following as they apply to the Steam Line Rupture: Load Sequencer Status Light. Rejected this KA as it was difficult finding an operationally valid question topic relating the Emergency Diesel Generator load sequencer to a Steam Line Rupture.
Selected new KA AA1.20: Containment pressure and temperature trends.
Page I of3
Seabrook Station 2010 NRC Written Exam ES-401 Tier I Group Tier I/Group I RO Tier II Group 1 RO Tier 21 Group I RO Tier 21 Group 2 RO Tier 2/Group 2 SRO Randomly Selected KJA 056 Loss of Offsite Power 062 Loss of Nuclear Service Water 012 Reactor Protection System 014 Rod Position Indicating System 075 Circulating Water Record of Rejected KlAs Form ES-401-4 Reason for Rejection Originally selected KA AA1.15, Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power: Service water booster pumps. Rejected KA as Seabrook Station does not have Service Water Booster Pumps.
Selected new KA AA1.21: Reset of ESF load sequencers.
Originally selected KA AA1.03, Ability to operate and/or monitor the following as they apply to the Loss ofNuclear Service Water: SWS as a backup to CCWS. Rejected KA as Seabrook Stations CCWS is not configured such that the SWS functions as a backup.
Selected new KA AA1.02: Loads on the SWS in the control room.
Originally selected KA K6.09, Knowledge of the effect ofa loss or malfunction of the following will have on the RPS:
CEAC. Rejected the KA as Seabrook Station does not have a Control Element Assembly System. Per NUREG-1122 Prior to randomly selecting an Al KA identified KA Al.01 associated with "metroscope reed switch display" as not being applicable to Seabrook Station. KA Al.OI was suppressed from the random sampling.
Originally selected category 075 Circulating Water, A2 Ability to (a) predict the impacts of the following malfunctions or operations on the Circulating Water System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences ofthose malfunctions or operations: A2.0 I Loss of intake structure.
During exam validation the specific open reference question selected for KA was found to overlap questions and provide answers to two questions on RO section ofexam. Per discussion with NRC lead examiner new Tier 2/Group2 category 016, Non nuclear Instrumentation, A2 Ability to (a) predict the impacts ofthe following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences ofthose malfunctions or operations: A2.01 Detector failure, was selected.
Page 2 of3
Seabrook Station 2010 NRC Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KiA Page 3 of3
ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2010 NRC Exam JPM - RO Facility:
Seabrook Date of Examination: December 2010 Examination Level: RO [8J SRO D Operating Test Number:
I Administrative Topic Type Describe activity to be performed (see Note)
Code*
Manual QPTR Calculation Conduct of Operations R,M,P KA: 2.1.7 Ability to evaluate plant performance and make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.
Shutdown Margin Calculation (Mode 1)
Conduct of Operations R,M KA: 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
Calculate Boron Change R,D KA: 2.2.12 Knowledge of Surveillance Procedures Equipment Control Establish COP Exhaust RM Setpoints Prior to Gaseous Effluent Release R,D Radiation Control KA 2,3.11 Ability to control radiation releases.
Emergency Procedures/Plan I NOTE: 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 (S 3 for ROs; S 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (<?: 1)
(P)revious 2 exams (S 1; randomly selected)
Page 1 of 1
Administrative Topics Outline Seabrook Station 2010 NRC Exam JPM - SRO -I Facility:
Seabrook Date of Examination: December 2010 Examination Level: RO 0 SRO ~
Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note)
Code*
Verify Manual QPTR Calculation Conduct of Operations R,N KA: 2,1.7 Ability to evaluate plant performance and make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation, Verify Shutdown Margin Calculation(Mode 1)
Conduct of Operations R,N KA: 2.1,37 Knowledge of procedures, guidelines, or limitations associated with reactivity management Technical Specification Determination and Required Off-site Notifications, R,M Equipment Control 2.2.40 Ability to apply Tech. Specs for a System Authorize an Emergency Dose Limit Extension R,D,P KA: 2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions.
Post Scenario EAL Determination and Event Classification S,D Emergency Procedures/Plan KA: 2,4,29 Knowledge of the Emergency Plan NOTE: 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 (S 3 for ROs; S 4 for SROs &RO retakes)
(N)ew or (M)odified from bank (<!: 1)
(P)revious 2 exams (::; 1, randomly selected)
Page 1 of 1
i ES-301 Administrative Topics Outline Form ES-301-1 Seabrook Station 2010 NRC Exam "IPM - SRO-U Facility:
Seabrook Examination Level: RO D Administrative Topic (see Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Date of Examination: December 2010 SRO [ZJ Operating Test Number:
Type Describe activity to be performed Code*
Verify Manual QPTR Calculation R,N KA: 2.1.7 Ability to evaluate plant performance and make operational judgments based on the operating characteristics, reactor behavior, and instrument interpretation.
Verify Shutdown Margin Calculation(Mode 1)
R,N KA: 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.
- CFR: 41.10/43.5/45.12 Technical Specification Determination and Required Off-site Notifications.
R,M 2.2.40 Ability to apply Tech. Specs for a System Authorize an Emergency Dose Limit Extension R,D,P KA: 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
Post Scenario EAL Determination and Event Classification S,D 2.4.29 Knowledge of the Emergency Plan NOTE: 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 (:5 3 for ROs; :5 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2: 1)
(P)revious 2 exams (S 1; randomly selected)
Page 1 of 1
i i
-ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2010 NRC Exam JPM - RO Facility:
Seabrook Date of Examination:
December 2010 Exam Level: RO 181 SRO-ID SRO-U 0 Operating Test No.:
System I JPM Title
- a. FR H.1 Bleed and Feed
- b. Recover from a CRFM Actuation
- c. Loss of Containment Instrument Air
- d. Transfer SW from the Cooling Tower to the Ocean
- e. Lower Accumulator Level
- f. Emergency Trip of EDG B
- g. Recover a Dropped Rod
- h. Start H2 Recombiners In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- a. Local Reactor Trip
- b. Hydrogen Analyzer Local Operation
- c. Perform Local Ops to Swap CC Pumps Type Code*
Safety Function A,L,M,S 4 (Primary)
D,S,EN 2
A,N,S 8
A,D,S 4 (Secondary)
N,S 3
A,P,S 6
D,S 1
D,P,S 5
D,E,A 7
D,E 5
D,E,R 8
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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA i (S)imulator Criteria for RO I SRO-II SRO-U 4-6/4-6 12-3
- 59/:58/:54
<:11<:1/~1
- I -
I <:1 (control room system) 1/~1/<:1 2n:2/~1 31 :5 31:5 2 (randomly selected) 1/~1/<:1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Seabrook Station 2010 NRC Exam JPM - SRO-I Facility:
Date of Examination:
December 2010 Exam Level: RO 0 SRO-I [;?J SRO-U 0 Operating Test No.:
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Ii System I JPM Title Type Code' Safety Function I
- a. FR H.1 Bleed and Feed A,L,M,S 4 (Primary)
- 1 2
- b. Recover from a CRFM Actuation
! D,S,EN i
- c. Loss of Containment Instrument Air A,N,S 8
I
- d. Transfer SW from the Cooling Tower to the Ocean A,D,S 4 (Secondary)
- e. Lower Accumulator Level N,S 3
I f. Emergency Trip of EDG B A,P,S 6
- g. Recover a Dropped Rod D,S 1
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 7
- a. Local Reactor Trip D£A 5
- b. Hydrogen Analyzer Local Operation D.E 8
- c. Perform Local Ops to Swap CC Pumps D,E,R All RO and SRO-I control room (and in-plant) systems must be different and selVe different safety functions; all 5 SRO-U systems must selVe different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO 1SRO-II SRO-U (A)lternate path 4-6 1 4-61 2-3 (C)ontrol room (D)irect from bank
- 91s8/s4 (E)mergency or abnormal in-plant
~11~1/;::1 (EN)gineered safety feature 1 ~1 (control room system)
(L)ow-Power 1Shutdown
- 11<
- :1/<::1 (N)ew or (M)odified from bank including 1(A)
<::21<::2/;::1 (P)revious 2 exams S 31 S 3 1 S 2 (randomly selected)
(R}CA
<::1/<::1/<::1 (S)imulator
-ES-301 Control Room/In-Plant Systems Outline Form ES-301*2 Seabrook Station 2010 NRC Exam ~IPM - SRO-U Facility:
Seabrook Exam Level: RO 0 SRO-I 0 SRO-U Date of Examination:
('gI December 2010 Operating Test No.:
I 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
- a. FR H.1 Bleed and Feed A,L,M,S 4 (Primary)
I
- b. Recover from a CRFM Actuation D,EN,S 2
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- a. Local Reactor Trip D,E,A 7
- b. Hydrogen Analyzer Local Operation D,E 5
- c. Perform Local Ops to Swap CC Pumps D,E,R 8
~
." Dr.
I 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 I SRO-I 1SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank
$9/$8/$4 (E)mergency or abnormal in-plant
~1/~1/~1 (EN)gineered safety feature I -
I
~1 (control room system)
(L)ow-Power I Shutdown 1/~1/~1 (N)ew or (M)odified from bank including l(A) 2/~21?:1 (P)revious 2 exams 31$ 3 I $ 2 (randomly selected)
(R)CA 1/~1/?:1 (S)imulator
Appendix 0 Scenario Outline Form ES-D-1 Seabrook StatIon 2016 NRC Exam-SImulator Scenanos Facility: Seabrook Scenario No.: 1 Op-Test No.:
Examiners:
D.Sllk Operators:
Initial Conditions: MOL 50% power. Both Main feed Pumps and one Heater Drain pump are in service.
Turnover:
- Plant is at 50-55% power.
- Procedure OS1000.05, Power Increase is being performed and is completed to step 4.3.10.
Maintain AFD on target.
- Increase power to 75% at 5%/hour.
SW-P-41 C tagged out for motor replacement.
Event Malf. No.
No.
1 ptFWPT505 2
RCLT459 3
4 mfRC049C mfHF001 5
mfHF002 svo7186HF rvMSAVR36 6
rvMSAVR50 avMSVSV2 7
avMSVCV2 mfRPS019 mfRPS020 mfSI003 8
mfSI004 Event Type*
PSOR BOPN USN PSOI US I, TS BOPI PSOI USI, TS psoe USe,TS Bope usc PSOM USM BOPM Bope psoc Event Description Crew begins the power increase Turbine Impulse Pressure PT -505 Fails Low causing automatic rod insertion RC-U-459 PZR Level, Channel 1 Fails High, requiring manual control of charging and letdown.
Crew responds to a 20 GPM RCS Leak. Supports E Plan Classification (End of scenario)
Crew responds to sequential loss of EHC pumps with complete loss producing an automatic Turbine/Reactor trip signal.
A turbine trip - Reactor trip will occur when EHC pressure decays below '1100 psig or when MANUALL Y tripped by the crew. When the MSIVs are shut, two SG safeties will fail open causing the need for a SI.
One Turbine Stop and Control valve sticks Open requiring a Manual MSI.
SI pumps A & B will fail to auto-start on the SI signal and require manual actions to start (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Note: Anticipated AOP/EOP flow-path: OS1235.05, OS1201.07, OS1201.02, E-O, E-2, ES 1.1 1
I
Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2010 NRC Exam-SImulator Scenanos Facility: Seabrook Scenario No.: 2 Op-Test No.:
Examiners:
D. Silk Operators:
Initial Conditions: MOL 100% Power Turnover:
- No other outstanding testing or maintenance in progress.
- SW-P-41 C tagged out for motor replacement.
Event Malf. No.
No.
1 2
mfCS016 3
mfRM002 4
ptMSPT507 r---s-1 avMSVCV1 6
mfED037 bkCPRTA bkCPRTB mfRPS001 mfRPS002 7
mfCC015 mfCC009 8
100ZMDRC S456B1 Event Type*
PSOR USN BOPN psoe USe,TS USTS BOP I USI Bope usc BOPM USM PSOM psoc usc psoc Event Description Crew commences 25 minute power reduction for grid stability control.
The operating Charging Pump 2A Trips requiring manual actions to isolate letdown and eventual restoration of charging and letdown.
The Containment Particulate, Iodine, and Gas (PIG) radiation monitor will fail (Alarms in Control Room) requiring entry into the RCS Leak Detection Tech. Spec.
Main Steam Header Press Instrument PT-507 Fails Low. The speed of the main feed pumps will decrease. SG levels will decrease requiring manual operator actions.
- 1 turbine control valve fails closed causing a decrease in turbine load and automatic rod insertion.
The turbine generator breaker will trip producing a large load rejection. Automatic reactor trip is disabled requiring manual trip that fails, producing an A TWS.
When the reactor is tripped locally, CC-P-11 B will trip, with P 1'1 D failing to auto-start requiring manual actions to restore.
When the Gen BKR trips, the "A" PORV fails open, requiring manual isolation.
(N)ormal, (R)eactivity, (I)nstrument, (C)omponsnt, (M)ajor Note: Anticipated AOP/EOP flow-path: OS1231.04,. OS1202.02, OS1230.01, OS1231.03, E-O, FR-S.1, E-O, ES-0.1 or ES-1.1.
1
'Appendix D Scenario Outline Form ES-D-1 Seabrook Station 2010 NRC Exam-Simulator Scenarios Facility: §eabrook Scenario No.: Q Op-Test No.:
Examiners: Dave Silk Operators:
Initial Conditions: MOL, 100% Power.
Turnover:
- The plant is at 100% power.
- Decrease plant power at 10%/hr.
- Main Steam Atmospheric Steam Dump ("A"ASDV) valve, MS-PV-3001 is Danger Tagged due to excessive seat leakage. MS-V-5 is closed and tagged. Plant Engineering has recommended a plant shutdown to work on the valve safely. Tech. Spec. 3.7.1.6 and 3.6.3 were entered 4 days ago.
- SW-P-41 C tagged out for motor replacement.
Event Malf. No.
Event Event No.
Type*
Description 1
ttRCTT411 PSOI RCS Loop 1 T cold will fail high causing inward control rod motion.
USI,TS 2
PSOR Decrease plant power @ 10%/hr.
BOPN us N 3
mfCS012 PSOC Initiation of a letdown line leak.
USC, TS 4
ptMSPK3004 BOPC liD" ASDV controlling pressure channel will fail high causing liD" ASDV to open.
USTS 5
mfED038 PSOM Loss of Offsite Power, complicated by "A" EDG failure to start, BOPM "B" EDG starts then trips on low oil pressure and Steam mfED031 Driven EFW pump trip on overspeed.
USM mfED034 avMSVSV2 6
mfSW013 BOPC On Bus 6 power restoration from SEPs no Service water pump will start.
mfSW015 The Motor Driven EFW Pump Trips on Overcurrent.
mfSW017 mfFW055 7
rmvMSV129 BOPC Crew directs reset and restart of FW-P37A (terry turbine) to establish EFW flow to the Steam Generators.
USC (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Note: As discussed with the 2010 Chief Examiner, This scenano IS a modified version of the approved "Spare" scenario from the 2009 NRC exam reviewed by P. Presby Note: Anticipated AOP/EOP flow-path: OS1201.08, OS1201.02, E-O, ECA-O.O,E-O, ES-0.1 1
Appendix 0 Scenario Outline Form ES-O-1 Seabrook StatlOn 2010 NRC Exam-SImulator Scenanos Facility: Seabrook Scenario No.:
4 Op-Test No.:
Examiners:
D.Silk Operators:
Initial Conditions: MOL 78% power Turnover:
- ISO directed power reduction to < 80% due to grid loading limitations. Achieved - 78% power 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 45 minutes ago. Maintaining power at -78% per OS1000.06.
- Xenon is still building in slowly at - (-)0.3 pcm I minute or (-) 0.15°F every 10 minutes
- SW-P-41 C is tagged out for motor replacement.
- No TSAS, No releases in progress.
Event Malf. No.
Event Event No.
Type*
Description PSOR 1
Crew begins power increase.
BOPN USN PSOI 2
mfNI002 NI 42 Fails High causing automatic rod insertion.
USI,TS Bope 3
mfSW001 Service Water Pump 41A Overcurrent Trip. With Pump 41 C US e, TS tagged out and automatic actuation disabled, manual cooling cSWV22 tower alignment is required.
100ZMDISW CS61481 cSWP41C PSOI 4
mfED026 Loss of Vital Instrument Panel 1 B causing multiple instruments BOPI to fail, requirin~J manual actions by the PSO and BOP to USI, TS stabilize.
psoe 5
mfSG001B "B SG tube leak develops at 50 gpm tube leak requiring manual US e, TS control of Charging and Letdown. Crew commences a rapid power decrease that is required due to the steam generator tube leak.
PSOM 6
mfSG001B uB" SG tube Ruptures at 500 gpm, requiring manual start of the BOPM second charging pump and safety injection.
USM psoe 7
mfRPS011 PSO (C) PSO recognizes automatic T signal failure on Train A and aligns in accordance with E-O Attachment "A" (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Note: Anticipated AOP/EOP flow-path: OS1211.04, OS1216.01, OS1247.01, OS1227.02, OS1231.04, E-O, E-3 1