ML033090621
| ML033090621 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/03/2003 |
| From: | Gosekamp M Entergy Nuclear Vermont Yankee |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-271/03-301 | |
| Download: ML033090621 (38) | |
Text
ES-401 BWR Examination Outline Form ES-401-I Facility:
Vermont Yankee Date of Exam:
10/3/03 RO KIA Category Points Note:
- 1.
- 2.
- 3.
- 4.
- 5.
6.*
- 7.
- 8.
- 9.
SRO-Only Points BE Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the Tier Totals in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.
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 _+I 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.
Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category/tier.
The generic (G) WAS 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inarmorxiate WA statements.
ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO)
Form ES-401-1 EIAPE # I Name f Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC f 6 295004 Partial or Total Loss of DC Pwr 16 295005 Main Turbine Generator Trip f 3 295006 SCRAM I 1
295016 Control Room Abandonment f 7 29501 8 Partial or Total Loss of CCW I 8
295019 Partial or Total Loss of Inst. Air 18 295021 Loss of Shutdown Cooling f 4 WA Topic(s)
Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :
(CFR: 41.10143.5145.13)
AA2.05 Jet pump operability: Not-BWR-1&2 Emergency Procedures Plan G2.4.1 Knowledge of EOP entry conditions and immediate action steps.
(CFR: 41.10/43.5f45.13)
Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.7 145.6)
AA1.03 A.C. electrical distribution Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following:
(CFR: 41.7 f 45.8)
AK2.01 RPS Knowledge of the operational implications of the following concepts as they apply to SCRAM :
(CFR: 41.8 to 41.10)
AKI.01 Decay heat generation and removal
~
Ability to determine andlor interpret the following as they apply to CONTROL ROOM ABANDONMENT :
(CFR: 41.10143.5145.13)
AA2.07 Suppression chamber pressure Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:
(CFR: 41.7 f 45.8)
AK2.01 System loads Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :
(CFR: 41.7 f 45.6)
AA1.04 Service air isolations valves: Plant-Specific Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.8 to41.10)
AKI.04 Natural circulation
K K
1 2
X X
X F
o
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ES-401-1 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier IIGroup 1 (RO)
WA Topic(s)
EIAPE # I Name I Safety Function 3.4 3.5 3.4 2.5 Knowledge of the interrelations between REFUELING ACCIDENTS and the following:
(CFR: 41.7 145.8)
AK2.03 Radiation monitoring equipment Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
(CFR: 41.7 I 45.8)
EK2.12 Suppression pool cooling 295023 Refueling Acc Cooling Mode I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 1
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Conduct of Operations G2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10143.2 145.12)
Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:
(CFR: 41.7 145.8)
EK2.04 SPDSIERISICRIDSIGDS: Plant-Specific 295026 Suppression Pool High Water Temp. I 5 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE :
(CFR: 41.10143.5145.13)
EA2.05 Toruskuppression chamber pressure:
Plant-Specific 3.6 3.4 13 14 16 15 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5
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Ability to operate andlor monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:
(CFR: 41.7 I 45.6)
EA1.02 RCIC: Plant-Specific Ability to determine andlor interpret the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41.10143.5145.13)
EA2.02 Reactor power Ability to operate andlor monitor the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41.7 I 45.6)
EA1.I 1 Condensate 4.0 4.1 295037 SCRAM Condition Present and II Power Above APRM Downscale or Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :
(CFR: 41.5 145.6)
EK3.04 Hot shutdown boron weight: Plant-Specific 3.2 2.5 17 20 Unknown I 1 295038 High Off-site Release Rate I 9 Equipment Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for 0Deration.s and safety limits.
(CFR: 43.2)
ES-401 BWR Examination Outline FOITI ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1IGroup 1 (RO)
WA Category Totals:
2 5
I!:
1,"
EIAPE # I Name I Safety Function 600000 Plant Fire On Site I 8 Q
14 1 413 WA Topic(s)
Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE:
AK3.04 Actions contained in the abnormal procedure for plant fire on site Group Point Total:
IR 2.8 18
ll ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1IGroup 2 (RO)
Form ES-401-1 11 EIAPE #I Name I Safety Function 295002 Loss of Main Condenser Vac I 3
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295007 High Reactor Pressure I 3 295008 High Reactor Water Level I 2 11 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I 5
295012 High Drywell Temperature I 5 295013 High Suppression Pool Temp. I 5 295015 Incomplete SCRAM I 1
]I 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation I5 & 7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Wtr Lvl I 5 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation / 9
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295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High WA Topic(s)
Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM :
(CFR: 41.8 to 41.10)
AKI.04 Increased offgas flow Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE :
(CFR: 41.5 145.6)
AK3.02 Increased drywell cooling Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE :
(CFR: 41.5 145.6)
AK3.01 Suppression pool cooling operation Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 145.2)
Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL :
(CFR: 41.8 to 41.10)
EK1.O1 Containment integrity Ability to determine andlor interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :
(CFR: 41.10143.5145.13)
EA2.01 Area radiation levels Ability to operate andlor monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :
(CFR: 41.7 I 45.6)
EA1.02 Process radiation monitoring system
II ES-401 WA Category Point Totals BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier l/Group 2 (RO) 2 2
1 1
1 GroupPointTotal:
7 F
o
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BWR Examination Outline Plant Systems -Tier 2/Group 1 F
o
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ES-401-1 WA Topic@)
Ability to monitor automatic operations of the RHWLPCI:
INJECTION MODE (PLANT SPECIFIC) including:
(CFR: 41.7 145.7)
A3.05 Reactor water level Conduct of Operations 62.1.28 Knowledge of the purpose and function of major system components and controls.
(CFR: 41 -7)
Ability to predict andlor monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:
(CFR: 41.5 145.5)
A I.08 System lineup: BWR-2,3,4 Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.03 Initiation logic: BWR-2,3,4 Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.02 ADS logic Knowledge of the physical connections andlor causeeffect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:
(CFR: 41.2 to 41.9 145.7 to 45.8)
K1.02 Core plate differential pressure indication Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.01 tAbility to shutdown the reactor in certain conditions Ability to predict andlor monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including:
(CFR: 41.5 145.5)
A I.09 Individual relay status: Plant-Specific 4.4*
3.2 4.1*
2.8*
3.8 2.7 4.3' 2.7 28
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29 31 30 32 33 34
Plant BWR Examination Outline stems -Tier ZGroup 1 (RO)
F o
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ES-401-1 WA Topic@)
Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.04 Reactor power indication Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :
(CFR: 41.7 145.7)
K6.04 Detectors Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 SRM channelsldetectors Ability to predict andlor monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM controls including:
(CFR: 41.5 I 45.5)
AI.02 RPS status Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) :
(CFR: 41.5 I 45.3)
K5.06 Turbine operation Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.02 Ability to rapidly depressurize the reactor Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.02 D.C. electrical distribution failures IR -
3.6 3.0 2.6 3.9 2.7*
4.5' 2.9 36 37 38
ES-401 System # I Name 239002 SRVs 259002 Reactor Water Level BWR Examination Outline Plant ! stems -Tier 2/Group 1 (RO)
WA Topic@)
F o
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ES-401-1 Knowledge of the physical connections and/or causeeffect relationships between RELlEFlSAFETY VALVES and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.09 Drywell pressure (for safety valves which discharge to the drywell airspace): Plant-Specific Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM :
(CFR: 41.5 I 45.3)
K5.01 GEMACIFoxborolBailey controller operation: Plant-Specific.
Knowledge of the physical connections and/or causeeffect relationships between STANDBY GAS TREATMENT SYSTEM and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.03 Suppression pool Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) andlor interlocks which provide for the following:
(CFR: 41.7)
K4.05 Paralleling of A.C. sources (synchroscope)
Ability to manually operate andlor monitor in the control room:
(CFR: 41.7 I 45.5 to 45.8)
A4.01 All breakers and disconnects (including available switch yard): Plant-Specific Knowledge of UNINTERRUPTABLE POWER SUPPLY (AC./D.C.) design feature(s) andlor interlocks which provide for the following:
(CFR: 41.7)
K4.01 Transfer from preferred power to alternate power supplies 2.9 3.4 3.4 3.1 43 44 45 46 47
ES-401 System # I Name 263000 DC Electrical Distribution Plant BWR Examination Outline Form ES-401-1 rstems - Tier ZGroup 1 WA Topi@)
Knowledge of the physical connections andlor causeeffect relationships between D.C.
ELECTRICAL DISTRIBUTION and the following:
(CFR:
41.2 to 41.9 145.7 to 45.8)
K1.01 A.C.
electrical distribution Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR:
41.5 I 45.6)
A2.01 Grounds
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Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :
(CFR:
41.7 I 45.7)
K6.09 D.C.
power Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:
(CFR:
41.7 145.7)
A3.02 Air tern peratu re Ability to monitor automatic operations of the CCWS including:
(CFR:
41.7 145.7)
A3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws Group Point Total:
3.3 2.8 3.3 2.9 3.0 49 50 51 52 53
BWR Examination Outline Plant Systems -Tier 2Group 2 (RO)
Form ES-401-1 ES-401 IR WA Topic(s)
System # I Name 201001 CRD Hydraulic 2.7 54 201002 RMCS Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.01 Rod movement sequence timer malfunctions 201003 Control Rod and Drive Mechanism 201006 RWM 3.4 202001 Recirculation 202002 Recirculation Flow Control Conduct of Operations G2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
(CFR: 43.2 143.3 145.3) 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM 3.3 3.2 56 57 Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 I 45.6)
A2.01 Withdrawal of control rod in high power region of core: BWR-3,4,5 Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 I 45.6)
A2.11 Heatup or cooldown of the reactor vessel 216000 Nuclear Boiler Inst.
Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 tValves 2.5*
21 9000 RHWLPCI: ToruslPool Cooling Mode
ES-401 System ##I Name 223001 Primary CTMT and Aux.
226001 RHWLPCI: CTMT Spray 11 Mode 230000 RHR/LPCI: ToruslPool Spray Mode 11 233000 Fuel Pool CoolingICleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 11 241000 Reactornurbine Pressure Regulator 245000 Main Turbine Gen. I Aux.
256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 11 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 11 290003 Control Room HVAC BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO)
Form ES-401-1 WA Topic(s)
Knowledge of the operational implications of the following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :
(CFR: 41.5 I 45.3)
K5.13 Oxygen concentration measurement: Plant-Specific Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.03 tLoss of electrical power Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 145.2)
Ability to monitor automatic operations of the REACTORlTURBINE PRESSURE REGULATING SYSTEM including:
(CFR: 41.7 I 45.7)
A3.12 Turbine trip testing Ability to manually operate andlor monitor in the control room:
(CFR: 41.7 145.5 to 45.8)
A4.07 Lights and alarms Conduct of Operations G2.1.30 Ability to locate and operate components I including local controls.
(CFR: 41.7 145.7)
ES-401 System # / Name G
WA Topic(s)
Knowledge of the physical connections andlor causeeffect relationships between REACTOR VESSEL INTERNALS and the following:
(CFR: 41.2 to 41.9 145.7 to 45.8)
K1.19TIP 290002 Reactor Vessel lnternals WA Category Point Totals IR 2.5 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 2 (RO) 3 I Group Point Total:
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Date of Exam WA #
Topic L
66 -
3nJ F
SRC IR -
IR P
2.9 4.3 67 2.1.1 2.1.
I 2.1.
2.1.
Subtotal 2.6 2.2.23 --Ability to track limiting conditions for 2.2.1 1 operations.(CFR: 43.2 / 45.13)
Knowledge of the process for controlling temporary changes.
(CFR: 41.10 / 43.3 /
45.13)
Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity. (CFR: 45.1) 2.2.1 2.2.
Subtotal 68 2.5 69 70 3.7 2.7 71 2.3.1 1 2.3.1 0 Ability to control radiation releases.
(CFR: 45.9 / 45.1 0)
Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
(CFR: 43.4 / 45. IO) 2.3.
72 2.9 2. 3. 1 2.3.
I 2.3.
Subtotal
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility :
Category
- 4.
Emergency Procedures I
Plan WA #
2.4.1 8 2.4.23 2.4.19 2.4.
2.4.
Date of Exam Topic Knowledge of the specific bases for EOPs.
(CFR: 41.10 / 45.13)
Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
(CFR: 41.10/45.13)
Knowledge of EOP layout I symbols I and icons. (CFR: 41.10 145.13)
Subtotal Tier 3 Point Total F
IR 2.7 -
2.8 2.7
ES-401 Record of Rejected WAS (RO)
Form ES-401-4 Randomly Selected WA 2.2.31 2.2.5 2.4.41 21 1000 K3.03 223002 K2 259002 K5.09 259002 K5.08 400000 A I 202002 K2.01 202002 K2.02 290002 K1.12 262001 K1.O1 300000 A I 295031 295029 Reason for Rejection WA < 2.5 for RO (2.2)
WA < 2.5 for RO (1.6)
WA < 2.5 for RO (2.3)
Very similar to 21 1000 K1.02 No WA > 2.5 FWCl not at VYN/Pilgrim FWCl not at VYN/Pilgrim No WA WA < 2.5 Equipment not installed at WNlPilgrim Very similar to 21 I000 K I.02 Deselected to allow selection of 2nd K4 in Tier 2 No A I WA in this system; picked from remaining 10 chips EA1.05 removed: 4 questions on RCIC EA1.04 removed: 4 questions on RCIC:
295031 EA1.05,295029 EA1.04 removed 295030 EA2.02,217000 K5.06 kept Replacements poker chipped in
EXAMINATION LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: Draft RO NRC Exam 2003 Exam Activity Code:
Date Exam Prepared: 9 July 2003 Date Exam Taken: 3 October 2003 1
c 5614 2 LOT-00-202 CRO3j 3
295001/AA2.05 2 New 2
c 5615 1 3
b 5616 3 4
b 5617 0 5
d 5618 2 6
c 5619 2 7
d 5620 0 8
a 5621 1 9
d 5622 1 10 d
5623 3 11 a
5624 0 12 c
5625 2 13 c
5626 2 14 a
5627 0 15 c
5628 2 16 a
5629 1 17 b
5630 0 18 d
5631 3 19 a
5632 0 20 a
5633 2 21 d
5634 4 22 a
5635 1 23 b
5636 0 24 b
5637 2 25 a
5638 1 26 c
5639 0 27 b
5640 1 28 b
5641 2 29 a
5642 0 30 c
5643 2 31 c
5644 0 32 d
5645 0 33 d
5646 2 34 c
5647 1 35 a
5648 0 36 d
5649 1 37 a
5650 1 38 d
5651 0 39 c
5652 2 LOT-0 1-262 LOT-00-601 LOT-00-249 LOT 129 LOT-00-612 LOT-00-603 LOT-00-279 LOT-00-601 LOT-00-620 LOT-00-205 LOT-00-302 LOT-00-607 LOT-00-2 17 LOT-00-256 LOT-00-6 10 LOT-00-6 10 LOT-00-286 LOT-00-607 LOT 1 3 8 LOT-00-602 LOT-00-288 LOT-00-61 8 LOT-00-308 LOT-00-607 LOT-00-61 1 LOT-01-223 LOT-00-205 LOT-00-205 LOT-00-206 LOT-00-206 LOT-00-2 18 LOT-00-2 1 1 LOT-00-626 LOT-00-2 12 LOT-02-2 15 LOT-02-2 1 5 LOT-01 -2 15 LOT-05-2 15 CRO 6 3
CRO 2,3,4 3
CRO 8 3
31 3
A2, A4 3
CRO 3g 3
CRO le, 5 3
CRO 3,4 3
3 3
CRO 2 3
CRO 3 3
CRO 2 3
CRO 5b 3
CRO 2 3
CRO 2 3
CRO 2 3
CRO 4a 3
CRO 1 3
17,19 3
CRO 3 3
CRO 5 3
1, 13, 15 3
CRO2,3,4,5 3
CRO 2,3 3
CRO 3,5 3
CRO 4,5 3
CRO 2,4 3
CRO 2 3
1 oc 3
CRO 3,5b, 6b, 7 3 CRO 2 3
A 0 2g 3
CRO 4 3
CRO 2 3
CRO 2i 3
CRO 8 3
CRO 6 3
CRO 6 3
295003/2.4.01 2
295004/AA1.03 1 295005/AK2.01 1 295006/AK1.01 0 295016/AA2.07 2 295018/AK2.01 1 295019/AA1.04 1 295021/AK1.04 1 295023/AK2.03 0 295024EK2.12 1 295025/2.1.32 0
295028EA2.05 1 295030EA1.02 1 295031EA1.11 0 295031EA2.02 2 295037EK3.04 2 600000/AK3.04 1 295026EK2.04 0 295038/2.2.25 0
295002/AK1.04 1 295010/AK3.02 1 295013/AK3.01 0 29501Y2.2.22 0
295029EK1.01 1 295033EA2.01 0 295034EA1.02 1 203000/A3.05 2
205000/2.1.28 0
206000/K2.03 0
206000/A1.08 0
209001K3.02 0
21 1000K1.02 1
21 1000K3.01 0
212000/A1.09 1
2 15003K3.04 0
2 15003K6.04 2
215004/K2.01 0
215005/A1.02 1
New New New New New New New New New New New New New New New New New New New New New New New Bank New New New New New New New New Bank New New New New New
40 c
41 c
42 d
43 d
44 b
45 c
46 c
47 a
48 c
49 a
50 a
51 c
52 c
53 b
54 a
55 c
56 d
57 a
58 c
59 a
60 b
61 b
62 c
63 a
64 c
65 a
66 b
67 a
68 b
69 a
70 b
71 b
72 d
73 b
74 b
75 a
5653 1 5654 2 5655 1 5656 1 5657 0 5658 0 5659 5 5660 1 5661 1 5662 1 5663 2 5664 0 5665 0 5666 0 5667 2 5668 3 5669 2 5670 0 5671 1 5672 0 5673 1 5674 1 5675 1 5676 1 5677 0 5678 1 5679 0 5680 1 5681 1 5682 0 5683 1 5684 1 5685 3 5686 2 5687 1 5688 0 LOT-00-21 7 LOT-00-608 LOT-00-206 LOT-00-239 LOT-01-259 LOT-00-26 1 LOT-00-264 LOT-00-262 LOT-03-262 LOT-00-601 LOT-00-263 LOT-00-603 LOT-00-279 LOT-00-208 LOT-02-201 LOT-00-202 LOT-03-20 1 LOT-00-2 16 LOT-00-205 LOT-0 1-229 LOT-00-234 LOT-00-2 12 LOT-00-249 LOT-00-256 LOT-0 1-288 LOT-04-2 15 LOT-00-302 LOT-03-400 LOT-01 -400 LOT-00-402 LOT-02-201 LOT-00-27 1 LOT-00-602 LOT-00-61 0 LOT-00-607 LOT-00-622 CRO 4b CRO 1,2 CRO 5,7,10a CRO 3 CRO 5e CRO 5 CRO 11 Id, 3 CRO 7 CRO2,3,4 CRO 2 CRO 3 A 0 9d, 11; CRO Id CRO 7 CRO la, c, e, 3 CRO 4,5 CRO 4 CRO 4, lla, 14 CRO 2 CRO 5 A 0 2a, b, c, 10a CRO 3 CRO 5,7,9 A 0 3, CRO 3,5 CRO 1, FND 3 CRO 2 CRO 1 CRO 3 CRO 2,3 CRO la, b, 7 CRO 5 CRO 3 CRO 3 CRO 2,3 CRO 4 U, 2 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 225 Ouestion Level Totals Level Description Number of Questions 0
Fundamental Knowledge/Memory 34 1
Comprehension 2
Analysis 29 12 217000K5.06 2 1 8000/K3.02 223002/A2.02 239002K1.09 259002K5.0 1 261000K1.03 262001K4.05 26200VA4.0 1 262002K4.0 1 263000K1.01 263000/A2.01 264000K6.09 300000/A3.02 400000/A3.O 1 201002/A2.01 202002/2.1.33 2 1 5002/A2.0 1 2 16000/A2.11 2 1900O/K2.01 223001K5.13 23 4000/A2.03 23900U2.2.22 24 1 OOO/A3.12 256000/A4.07 290001/2.1.30 290002K1.19 0/2.1.18 0/2.1.20 0/2.2.23 0/2.2.11 0/2.2.0 1 0/2.3.11 0/2.3.10 0/2.4.18 0/2.4.23 0/2.4.19 0
0 2
1 1
2 1
1 0
0 1
0 1
0 0
0 1
1 0
0 2
2 1
2 1
0 0
0 0
0 0
0 1
1 1
0 New New New New New New New New Bank Mod Bank Mod New New New New New Bank Mod New New New New New New New New New New New New New Bank Mod New New New New New New Originator: Brown, Scott T.
Last Revised: 08/20/2003 9:05:36 AM by Hallonquist, Nora E.
ES-401 BWR Examination Outline Form ES-401-1 Faci I ity :
Date of Exam:
RO KIA Category Points 0
3 4
1 1
0 1
2 1
3 5
3 1
2 Note:
- 1.
Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two)..Refer to Section D.l.c for additional guidance regarding SRO sampling.
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 *I 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.
Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category/tier.
The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
- 2.
- 3.
- 4.
- 5.
6.*
- 7.
- 8.
- 9.
8 4
11 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (SRO)
Form ES-401-1 WA Topic@)
EIAPE #I Name I Safety Function Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :
(CFR: 41.10 143.5 I 45.13)
AA2.02 Neutron monitoring 3.2 76 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 3.4 -
77 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.7 145.6) 43(b)(5)
AA1.01 D.C. electrical distribution systems 295004 Partial or Total Loss of DC Pwr I 6 11 295005 Main Turbine Generator Trip I 3 295006 SCRAM I 1 295016 Control Room Abandonment I 7
~~~
~~~
Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :
(CFR: 41.10143.5145.13)
AA2.04 System flow 2.9 -
78 295018 Partial or Total Loss of CCW I 8 11 295019 Partial or Total Loss of Inst. Air I 8 Ability to operate andlor monitor the following as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.7 I45.6) 43(b)(2)
AA1.02 RHRlshutdown cooling 3.5 79 80 295021 Loss of Shutdown Cooling I 4 11 295023 Refueling Am Cooling Mode 18 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE:
(CFR: 41. I O 143.5 145.13)
EA2.02 Drywell temperature 4.0 295024 High Drywell Pressure I 5 4.2 3.8 81 82 Ability to determine andlor interpret the following as they apply to HIGH REACTOR PRESSURE:
(CFR: 41. I O 143.5 145.13)
EA2.02 Reactor power Emergency Procedures /Plan G2.4.3 Ability to identify post-accident instrumentation.
ICFR: 41.6 145.4) 43(b)(5) 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 11 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I5 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1
ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1IGroup 1 (SRO)
E/APE #I Name I Safety Function 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 KIA Category Totals:
K K
1 2
K A
3 1
X Form ES-401-1 KIA Topic@)
- l G l 2
I IR I
I Abilitv to oDerate and I or monitor the I 3.1 follovkg as they apply to PLANT FIRE ON I I SITE:
I AA1.05 Plant and control room ventilation systems 43(b)(2) 4 I Group Point Total:
83 8
ES-401 BWR Examination Outline F
o
~
ES-401-1 Emernencv and Abnormal Plant Evolutions -Tier 1lGroup 2 (SRO)
KIA Topic(s)
IR 295002 Loss of Main Condenser Vac I 3
4.1 3.5 84 85 295007 High Reactor Pressure I 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level I 2
Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 145.2)
Equipment Control G2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
(CFR: 45.2) 43(b)(5)
Ability to determine andlor interpret the following as they apply to HIGH DRWELL PRESSURE :
(CFR: 41.10 143.5 145.13)
AA2.02 Drywell pressure 3.9 86 295010 High Drywell Pressure I 5 11 295015 Incomplete SCRAM I 1
11 295017 High Off-site Release Rate I 9 295022 Loss of CRD Pumps / 1 295032 High Secondary Containment II Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9
295034 Secondary Containment Ventilation High Radiation I 9 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :
[CFR: 41.5 I 45.6) 43(b)(2)
EK3.02 Starting SBGTIFRVS: Plant-Specific 4.1 87 295035 Secondary Containment High II Differential Pressure I 5 295036 Secondary Containment High N SumplArea Water Level 15 11 500000 High CTMT Hydrogen Conc. I 5
4 Sroup Point Total:
BWR Examination Outline F
O I
T T
I ES-401-1 ES-401 System # I Name 203000 RHWLPCI: Injection sterns -Tier 2/Grc Plant I WA Topic@) t Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6) 43(b)(5)
A2.12 Inadequate system flow (1 206000 HPCl 89 Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6) 43(b)(5)
A2.09 Low suppression pool level 3.3 11 212000 RPS 21 5004 Source Range Monitor 11 21 5005 APRM I LPRM 11 217000 RClC 11 218000ADS 223002 PClSlNuclear Steam Supply Shutoff 11 239002 SRVs 259002 Reactor Water Level I( Control 90 Conduct of Operations G2.1.27 Knowledge of system purpose and or function.
261000 SGTS 262001 AC Electrical Distribution 11 262002 UPS (ACIDC) 263000 DC Electrical
11 ES-401 System # I Name K
K 1
2 264000 EDGs WA Category Point Totals 0
0 BWR Examination Outline Plant Systems -Tier ZGroup 1 (SRO)
Form ES-401-1 ll WA Topic(s)
Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :
(CFR: 41.7 / 45.7) 43(b)(2)
K6.01 Starting air Group Point Total:
BWR Examination Outline Plant Systems -Tier 2/Group 2 (SRO)
FOm ES-401-1 ES-401 201001 CRD Hydraulic WA Topic@)
IR 11 201002 RMCS 201003 Control Rod and Drive Mechanism 11 201006 RWM 11 202001 Recirculation 11 202002 Recirculation Flow Control 204000 RWCU 215001 Traversing In-core Probe 11 215002 RBM 11 216000 Nuclear Boiler Inst.
219000 RHWLPCI: ToruslPool Cooling Mode 11 223001 Primary CTMT and Aux.
226001 RHWLPCI: CTMT Spray (1 Mode 92 230000 RHWLPCI: TONS~POOI Spray Mode 233000 Fuel Pool CoolinglCleanup Equipment Control 62.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(CFR: 43.2)
Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 I 45.6) 43(b)(2)
A2.07 High fuel pool temperature 3.2 93 11 234000 Fuel Handling Equipment 11 239001 Main and Reheat Steam 241000 Reactornurbine Press=
I Regulator 11 245000 Main Turbine Gen. I Aux.
256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste Ij 271 000 Offgas 11 272000 Radiation Monitoring 11 286000 Fire Protection 11 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel lnternals WA Category Point Totals 0
3 3
Group Point Total:
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Date of Exam Category
- 1.
Conduct of Operations
- 2.
Equipment Control
- 3.
Radiation Control WA #
2.1.22 2.1.25 2.1.
2.1.
2.1.
2.1.
Topic reference materials such as graphs I monographs / and tables which contain performance data.
(CFR: 41.10 / 43.5 / 45.12) operability requirements.
(CFR-43 7) 2.2.
2.2.
I I
I 2.2.
2.2.
2.2.
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Date of Exam Category 2.4.40
--i-2.4.43
- 4.
Emergency Procedures I Plan 3nly 99 -
100
Record of Reiected WAS (SRO)
Form ES-401-4 ES-40 1 Tier J Group 1 / I 1 / I 1 / I Randomly Selected WA 6000000 AA1.02 6000000 AA1.03 6000000 AA1.07 Reason for Rejection WAc2.5 WA 2.5 WA 2.5
EXAMINATION LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: Draft SRO NRC Exam 2003 Exam Activity Code:
Date Exam Prepared: 9 July 2003 Date Exam Taken: 3 October 2003 Exam Questions 1
c 2
c 3
b 4
b 5
d 6
c 7
d 8
a 9
d 10 d
11 a
12 c
13 c
14 a
15 c
16 a
17 b
18 d
19 a
20 a
21 d
22 a
23 b
24 b
25 a
26 c
27 b
28 b
29 a
30 c
31 c
32 d
33 d
34 c
35 a
36 d
5614 2 5615 1 5616 3 5617 0 5618 2 5619 2 5620 0 5621 1 5622 1 5623 3 5624 0 5625 2 5626 2 5627 0 5628 2 5629 1 5630 0 5631 3 5632 0 5633 2 5634 4 5635 1 5636 0 5637 2 5638 1 5639 0 5640 1 5641 2 5642 0 5643 2 5644 0 5645 0 5646 2 5647 1 5648 0 5649 1 LOT-00-202 LOT-01 -262 LOT-00-60 1 LOT-00-249 LOT 129 LOT-00-61 2 LOT-00-603 LOT-00-279 LOT-00-601 LOT-00-620 LOT-00-205 LOT-00-302 LOT-00-607 LOT-00-217 LOT-00-256 LOT-00-61 0 LOT-00-6 10 LOT-00-286 LOT-00-607 LOT 138 LOT-00-602 LOT-00-288 LOT-00-6 18 LOT-00-308 LOT-00-607 LOT-00-6 1 1 LOT-0 1-223 LOT-00-205 LOT-00-205 LOT-00-206 CRO 3j CRO 6 CRO 2,3,4 CRO 8 31 A2, A4 CRO 3g CRO le, 5 CRO 3,4 3
CRO 2 CRO 3 CRO 2 CRO 5b CRO 2 CRO 2 CRO 2 CRO 4a CRO 1 17,19 CRO 3 CRO 5 1, 13, 15 CRO 2,3,4,5 CRO 2,3 CRO 3,5 CRO 4,5 CRO 2,4 CRO 2 1 oc 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 LOT-00-206 CRO 3,5b, 6b, 7 3 LOT-00-21 8 CRO 2 3
LOT-00-21 1 A 0 2g 3
LOT-00-626 CRO 4 3
LOT-00-212 CRO 2 3
LOT-02-2 15 CRO 2i 3
295001/AA2.05 2 295003/2.4.01 2
295004/AA1.03 1 295005/AK2.01 1 295006/AK1.01 0 295016/AA2.07 2 295018/AK2.01 1 295019/AA1.04 1 295021/AK1.04 1 295023/AK2.03 0 295024/EK2.12 1 295025/2.1.32 0
295028/EA2.05 1 295030/EA1.02 1 29503 VEA1.11 0 29503 VEA2.02 2 295037/EK3.04 2 600000/AK3.04 1 295026/EK2.04 0 295038/2.2.25 0
295002/AK1.04 1 295010/AK3.02 1 295013/AK3.01 0 295015/2.2.22 0
295029/EKl.O1 1 295033/EA2.01 0 295034/EA1.02 1 203000/A3.05 2
205000/2.1.28 0
206000/K2.03 0
206000/A1.08 0
20900 1K3.02 0
211000K1.02 1
21 1000K3.01 0
2120001A1.09 1
215003K3.04 0
New New New New New New New New New New New New New New New New New New New New New New New New Bank New New New New New New New New Bank New New
37 a
5650 1 38 d
5651 0 39 c
5652 2 40 c
5653 1 41 c
5654 2 42 d
5655 1 43 d
5656 1 44 b
5657 0 45 c
5658 0 46 c
5659 5 47 a
5660 1 48 c
5661 1 49 a
5662 1 50 a
5663 2 51 c
5664 0 52 c
5665 0 53 b
5666 0 54 a
5667 2 55 c
5668 3 56 d
5669 2 57 a
5670 0 58 c
5671 1 59 a
5672 0 60 b
5673 1 61 b
5674 1 62 c
5675 1 63 a
5676 1 64 c
5677 0 65 a
5678 1 66 b
5679 0 67 a
5680 1 68 b
5681 1 69 a
5682 0 70 b
5683 1 71 b
5684 1 72 d
5685 3 73 b
5686 2 74 b
5687 1 75 a
5688 0 76 c
5689 2 77 c
5690 0 78 c
5691 1 79 d
5692 1 80 c
5693 3 81 c
5694 0 LOT-02-2 15 LOT-01 -2 15 LOT-05-2 15 LOT-00-2 17 LOT-00-608 LOT-00-206 LOT-00-239 LOT-0 1-259 LOT-00-26 1 LOT-00-264 LOT-00-262 LOT-03-262 LOT-00-60 1 LOT-00-263 LOT-00-603 LOT-00-279 LOT-00-208 LOT-02-20 1 LOT-00-202 LOT-03-20 1 LOT-00-2 16 LOT-00-205 LOT-01 -229 LOT-00-234 LOT-00-2 12 LOT-00-249 LOT-00-256 LOT-01-288 LOT-04-2 15 LOT-00-302 LOT-03-400 LOT-0 1-400 LOT-00-402 LOT-02-201 LOT-00-271 LOT-00-602 LOT-00-6 10 LOT-00-607 LOT-00-622 LOT-05-2 15 LOT-00-601 LOT-00-601 LOT-00-601 LOT-00-6 14 LOT-00-602 CRO 8 CRO 6 CRO 6 CRO 4b CRO 1,2 CRO 5,7,10a CRO 3 CRO 5e CRO 5 CRO 11 Id, 3 CRO 7 CRO2,3,4 CRO 2 CRO 3 A 0 9d, 11; CRO Id CRO 7 CRO la, c, e, 3 CRO 4,5 CRO 4 CRO 4, lla, 14 CRO 2 CRO 5 A 0 2a, b, c, 10a CRO 3 CRO 5,7,9 A 0 3, CRO 3,5 CRO 1, FND 3 CRO 2 CRO 1 CRO 3 CRO 2,3 CRO la, b, 7 CRO 5 CRO 3 CRO 3 CRO 2,3 CRO 4 SRO 1 SRO 8 SRO 8 SCRO (CRS) 5,7 SRO 1 SRO 6 lj, 2 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
3 3
4 4
4 4
4 4
215003K6.04 215004/K2.01 215005/A1.02 217000K5.06 2 18000K3.02 223 002/A2.02 239002K1.09 259002K5.01 261 OOOK1.03 26200 1 K4.05 262001/A4.01 262002K4.01 263000K1.01 263000/A2.0 1 264000K6.09 300000/A3.02 2
0 1
0 0
2 1
1 2
1 1
0 0
1 0
1 400000/A3.01 0
201002/A2.01 0
202002/2.1.33 0
215002/A2.01 1
2 16000/A2.11 1
219000K2.01 0
223001K5.13 0
234000/A2.03 2
23900U2.2.22 2
241000/A3.12 1
256000/A4.07 2
290001/2.1.30 1
290002K1.19 0
0/2.1.18 0
0/2.1.20 0
0/2.2.23 0
0/2.2.11 0
0/2.2.0 1 0
0/2.3.11 0
0/2.3.10 1
0/2.4.18 1
0/2.4.23 1
0/2.4.19 0
295001/AA2.02 2 295004/AA1.01 2 295018/AA2.04 2 295021/AA1.02 1 295024EA2.02 2 295025EA2.02 1 New New New New New New New New New New New Bank Mod Bank Mod New New New New New Bank Mod New New New New New New New New New New New New New Bank Mod New New New New New New Bank Mod New New New New New
82 c
83 c
84 a
85 d
86 a
87 d
88 d
89 b
90 a
91 a
92 a
93 a
94 b
95 d
96 a
97 c
98 b
99 a
100 a 5695 1 5696 1 5697 2 5698 3 5699 0 5700 1 5701 1 5702 1 5703 0 5704 3 5705 2 5706 2 5707 0 5708 1 5709 0 5710 1 5711 2 5712 2 5713 1 LOT-00-614 SRO 1 LOT-00-603 SRO 4 LOT-00-308 SCRO 1 LOT-00-610 SRO 3,4 LOT-00-615 SRO 1 LOT-00-261 SRO 1 LOT-00-205 LOT-00-6 14 LOT-00-223 LOT-00-264 LOT-00-205 LOT-00-233 LOT-00-308 LOT 138 LOT-00-400 LOT-00-223 LOT-00-404 SCRO 1 SRO 1,2 SRO 3 SCRO la SCRO 1 SRO 1 SCRO (CRS) 1 22,24 SCRO 3 SRO 3 SRO 1 LOT-00-900 SRO 1,4 LOT-00-900 SRO (CRS) 1,4 325 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
uestion Level Totals 0
Fundamental KnowledgeMemory 42 1
Comprehension 37 2
Analysis 21 295026/2.4.03 1
600000/AA1.05 1 295007/2.2.22 0
295008/2.2.02 1
295010/AA2.02 1 295034EK3.02 0 205000/A2.12 20900 UA2.09 261000/2.1.27 264000K6.01 230000/2.2.25 233 OOO/A2.07 0/2.1.22 0/2.1.25 0/2.2.2 1 0/2.3.09 0/2.3.10 2
2 1
2 1
0 0
2 0
0 2
0/2.4.40 0
0/2.4.43 0
New New New New Bank Clinton 2000 NRC Bank Grand Gulf 1998 NRC New New New New New New New New New New Bank Palisade 2001 NRC New New Originator:
Brown, Scott T.
Last Revised: 08/20/2003 9:45:25 AM by Hallonquist, Nora E.
Administrative Topics Outline Form ES-301-1 ES-301 Facility:
Vermont Yankee Date of Examination:
10/3/03 Examination Level (circle one): RO / SRO Operating Test Number:
1 Administrative Topic (see Note)
Conduct of Operations pt;2 Equipment Control fu Radiation Control Describe activity to be performed 1 r l
- 2. T P
Take actions for inadequate shift staffing (new)
Generic 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities.
(CFR: 41.10 / 43.5 I45.12)
IMPORTANCE SRO 3.4 Isolate leaking RHR piping leak and determine Technical Specification impact (new)
Generic 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
(CFR: 45.12 / 45.1 3)
IMPORTANCE SRO 3.1 Determine if equipment can be removed from service for minor unscheduled maintenance (new)
Generic 2.2.17 Knowledge of the process for managing maintenance activities during power operations.
(CFR: 43.5 / 45.1 3)
IMPORTANCE SRO 3.5 Determine emergency plan allowed radiation exposure (new)
Generic 2.3.4 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.
(CFR: 43.4 / 45.10)
IMPORTANCE SRO 3.1
_ _ _ _ _ _ _ ~
Determine protective action recommendation (bank)
Generic 2.4.29 Knowledge of the emergency plan.
(CFR: 43.5 / 45.1 I)
IMPORTANCE SRO 4.0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
Form ES-301-2 ES-301 Control Room/ln-Plant Systems W O u t li ne D, s D, c Facility:
Vermont Yankee Date of Examination:
10/3/03 Exam Level (circle one): RO / SRO(I)/ SRO(U)
Operating Test No.:
1 4
5
((W Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
- a. Perform Weekly Operable Control Rod Check (Stuck Rod)
(201 07F)
- c. Bypass Reactor Building HVAC Trips (20041)
- d. Transfer MCC 89A from the Maintenance Tie to RUPS (26209)
- e. Core Spray Pump Surveillance (20901 F)
- f. Initiate Manual Scram (OE 3107 Appendix F) (20023F)
- g. Parallel Main Generator to Grid (24503) 1 1/ h. none In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 7 3
I
/Ij. Respond to High Service Water Strainer D/P (27601)
D 8
- k. Startup RPS Motor Generator (21 202F)
/I 7
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
ES-30 I Administrative Topics Outline Form ES-301-1 Facility:
Vermont Yankee Date of Examination:
1013103 Examination Level (circle one):
/ SRO Operating Test Number:
1 Administrative Topic l%sw@m-(see Note) w Conduct of Operations M
Describe activity to be performed 4 n Isolate leaking RHR piping weld leak (new)
Generic 2.1 2 4 Ability to obtain and interpret station electrical and mechanical drawings.
(CFR: 45.12 / 45.13)
IMPORTANCE RO 2.8 Perform emergency in functional test (new)
Generic 2.2.1 Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity.
(CFR: 45.1)
IMPORTANCE RO 3.7 Prepare Control Room Shift Turnover Checklist (new)Alternate path Generic 2.1.3 Knowledge of shift turnover practices.
(CFR: 41.10 / 45.13)
IMPORTANCE RO 3.O Generic 2.1.3 1 Ability to locate control room switches / controls and indications and to determine that they are correctly reflecting the desired plant lineup.
(CFR: 45.12)
IMPORTANCE RO 4.2 Conduct of Operations Control room Emergency Communication check (new)
Generic 2.4.43 Knowledge of emergency communications systems and techniques CFR: 45.13)
IMPORTANCE RO 2.8
Form ES-301-2 ES-301 Control Room/ln-Plant Systems Tes&O ut1 i ne Facility: Vermont Yankee Date of Examination:
10/3/03 Exam Level (circle one):
Operating Test No.:
1 W Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System / JPM Title
- a. Perform Weekly Operable Control Rod Check (Stuck Rod)
(201 07F)
- b. Parallel Main Generator to Grid (24507)
- d. Bypass Reactor Building HVAC Trips (20041)
- e. Transfer MCC 89A from the Maintenance Tie to RUPS (26209)
- f. Core Spray Pump Surveillance (20901 F)
- g. Initiate Manual Scram (OE 3107 Appendix F) (20023F)
- h. Swap SJAE Suction Valves (516) (27106) 1 3
6 2
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- j. Respond to High Service Water Strainer D/P (27601)
- k. Startup RPS Motor Generator (21 202F)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
Appendix D Scenario Outline Form ES-D-1 Vermont Yankee I
Facility:
(I 999 NRC)Modified Scenario No.:
1 Op-Test No.:
Examiners :
Operators:
ACRC CRO CRS Objectives: Evaluate the crews ability to operate plant equipment to support a normal power ascension, respond to and evaluate (Technical Specification) a level instrument failure and the resultant reactivity addition transient. Recognize and take action for a Recirc Pump failure, recognize and limit the positive reactivity from a Recirc Pump speed transient. Determine the affect of a loss of a 480 VAC ECCS bus on plant operation, and to implement the EOPs to monitor and control plant parameters for a major primary containment steam leak resulting in emergency depressurization as well as recognizing the inability to spray the drywell Initial Conditions: IC-67(Snapshot) 30% power, approaching conditions for second Feedwater Pump Start Turnover: See Attached Shift Turnover Sheet Malf.
No.
Event Type*
Event Description Continue power ascension IAW OP 01 05 CRO CRS CRO CRS Start the second Feedwater Pump ECCS level instrument failure, Inadvertent RClC initiation (TS) 5 minutes after RFP start B Recirc Pump lower and upper seal failure Key 1 RR18A RC04 ACRO I
CRO CRS Key 2 RR07B RR08B CRO CRS Key 3 RR10 100% @
3600 sec
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A Recirc Pump speed controller failure, pump speed increasing CRO I
CRS Key 4 ED05C ACRO c
CRO CRS 480 VAC ECCS Bus 8 fails Key 5
.4% @
300 sec MS06 Key 6 1000 sec 10% @
Steam line leak in the drywell - emergency depressurization ACRO M
CRO CRS RHOBA C
ACRO Drywell Spray Valve does not open (B valves have no power)
RFHP05 N/A HPCl aux oil pump ACB open - out of service for governor oil leak reDair (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
Amendix D Scenario Outline Form ES-D-1 ACRO CRO CRS Objectives: Evaluate the crews ability to operate plant equipment in response to a loss of the startup transformers during closed cycle operation. Evaluate the Technical Specification for a loss of one off-site power source, and commence a plant shutdown to ensure NPDES compliance.
Recognize a stuck FWRV and take actions to avert a high reactor water level scram. Recognize and respond to an LPRM upscale failure. Recognize and respond to a loss af main condenser vacuum, ATWS, and SLC system failures.
Initial Conditions: IC-9, 100% power, preparing to chlorinate the Circ Water System Turnover: See Attached Shift Turnover Sheet Event Type*
Event Description Malf. No.
ACRO CRS Place CW in Closed Cycle for chlorination Key 1 ED-02A ACRO c
CRO CRS Loss of Startup Transformers Preinsert ANN Failure FW-O9A 9-5-E-2 R
CRO C
CRS Power Reduction with stuck Feedwater regulating valve Soft panel FRV A lockup red light out Key 2 N M2-24-41 B NM5D 97%
Key 3 MC-8 7%
LPRM upscale failure, APRM D upscale APRM D failure is Automatically deleted when LPRM 24-41 B is bypassed Main Condenser air inleakage (minor)
ACRO I
CRO CRS ACRO C
CRO CRS ACRO M
CRO CRS After control rod insertion for event 5 has started.
Main Condenser large air Leak Loss of Vacuum Turbine Trip / LNP Key 3 modify 50%
120 Sec Preinsert MC-8 RD 12A 87%
RD 128 92%
ACRO M
CRO CRS Hydraulic A W S / Level Power Control Preinsert SLOI A SL02 B CRO CRS SLC A Pump Failure / B Squib Failure Bypass APRM A Preinsert NM-O6A APRM A INOP, Bypass APRM A prior to insertion (I)nstrument, (C)omponent, (M)ajor (N)ormal, (R)eactivity
Scenario Outline Form ES-D-1 Appendix D Facility :
Vermont Yankee (new)
Scenario No.:
3 (spare) Op-Test No.:
Examiners:
Operators:
ACRO CRO CRS Objectives: Evaluate the crews ability to operate the service water system, respond to a condensate pump trip and maneuver the plant. Evaluate crew response to a loss of stator cooling, control reactor level when a FWRV controller fails. Evaluate crew response to a failure of transient level instrument and implement Technical Specifications. Evaluate crew response to a loss of off-site power, reactor scram, loss of high pressure feed.
Initial Conditions: IC-9, 100% power, preparing to swap service water pumps for maintenance See Attached Shift Turnover Sheet Turnover:
Event NO.
Malf.
NO.
Event Type*
Event Description 1
ACRO CRS Swap operating service water pumps KEY 1 CDOIA 2
C CRO CRS Trip of the A Condensate Pump Power Reduction due to Condensate Pump Trip 3
CRO CRS KEY 2 EG05A Preinsert EG12B c
ACRO CRS Trip of running stator cooling water pump with stby pump auto start failure 4
KEY 3 W l O A Ramp 200 sec CRO I
CRS A FWRV Controller Failure to 0 5
ACRO I
CRO CRS KEY 4 RR-18N KEY 5 ED17 6
B Transient level downscale failure
~
ACRO M
CRO CRS 7
LNP Load Reject Scram KEY 6 RROIA 5% 1200 sec ramp ACRO M
CRO CRS 8
Recirc Loop leak in drywell ACRO CRS 9
HPCl flow controller failure (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor