ML033210402
| ML033210402 | |
| 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: ML033210402 (37) | |
Text
ES-401 BWR Examination Outline Form ES-401-1 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.
- 2.
- 3.
- 4.
- 5.
6.*
- 7.
- 8.
- 9.
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
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO)
~~
295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6
I!
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~
295006 SCRAM I 1 295016 Control Room Abandonment I 7 11 EIAPE # I Name I Safety Function 3.7 5
295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3 29501 8 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4
) I R I #
KIA Topic(s)
Ability to determine and/or 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 3.1 Emergency Procedures /Plan G2.4.1 Knowledge of EOP entry conditions and immediate action steps.
(CFR: 41. I O 143.5 145.13)
Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.7 / 45.6)
AA1.03 A.C. electrical distribution
~~
~
Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following:
(CFR: 41.7 145.8)
AK2.01 RPS 3.8 Knowledge of the operational implications of the following concepts as they apply to SCRAM :
(CFR: 41.8 to41.10)
AKI.01 Decay heat generation and removal
~~
~
Ability to determine andlor interpret the foliowing as they apply to CONTROL ROOM ABANDONMENT :
(CFR: 41. I O 143.5 145.13)
AA2.07 Suppression chamber pressure 3.2 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:
(CFR: 41.7 I 45.8)
AK2.01 System loads 3.3 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :
(CFR: 41.7 145.6)
AA1.04 Service air isolations valves: Plant-Specific 3.3 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 3.6
BWR Examination Outline Form ES-401-1 ES-401 Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO)
WAPE # I Name I Safety Function 295023 Refueling Acc Cooling Mode I 8 WA Topic(s)
Knowledge of the interrelations between REFUELING ACCIDENTS and the following:
(CFR: 41.7 I 45.8)
AK2.03 Radiation monitoring equipment 3.4 10 11 12 19 295024 High Drywell Pressure I5 3.5 3.4 2.5 Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
(CFR: 41.7 145.8)
EK2.12 Suppression pool cooling Conduct of Operations G2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41.10143.2145.12)
Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:
(CFR: 41.7 145.8)
EK2.04 SPDSIERISICRIDSIGDS: Plant-Specific 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 295028 High Drywell Temperature I 5 3.6 3.4 13 14 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE :
(CFR: 41.10143.5145.13)
EA2.05 Toruslsuppression chamber pressure:
Plant-Specific 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 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 Ability to determine andlor interpret the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41. I O 143.5 145.13)
EA2.02 Reactor power Ability to operate andlor monitor the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41.7 145.6)
EA1.I 1 Condensate 4.0 4.1 16 15 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 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 I 45.6)
EK3.04 Hot shutdown boron weight: Plant-Specific 3.2 17 295038 High Off-site Release Rate I 9 2.5 Equipment Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(CFR: 43.2)
ES-401 BWR Examination Outline EIAPE # I Name I Safety Function Emergency and Abnormal Plant Evolutions -Tier I/Group 1 (RO)
K 1
600000 Plant Fire On Site I
WA Category Totals:
1 2 4
KIA 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 20
BWR Examination Outline Form ES-401-1 11 ES-401 II Emergency and Abnormal Plant Evolutions -Tier IIGroup 2 (RO)
~.
EIAPE #I Name I Safety Function WA Topic@)
21 Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAN CONDENSER VACUUM :
(CFR: 41.8 to41.10)
AKI.04 Increased offgas flow 295002 Loss of Main Condenser Vac / 3 11 295007 High Reactor Pressure I 3
11 295008 High Reactor Water Level I 2 11 295009 Low Reactor Water Level I 2
22 Knowledge of the reasons for the following responses as they apply to HIGH DRMELL PRESSURE :
(CFR: 41.5 I 45.6)
AK3.02 Increased drywell cooling 3.4 295010 High Drywell Pressure I 5 11 295012 High Drywell Temperature I 5 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE :
(CFR: 41.5 I 45.6)
AK3.01 Suppression pool cooling operation 3.6 23 24 29501 3 High Suppression Pool Temp. I 5
295015 Incomplete SCRAM I 1 ll X
Equipment Control 3.4 G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 145.2) 295020 Inadvertent Cont. Isolation I 5 & 7 1
Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL :
(CFR: 41.8 to41.10)
EKI.01 Containment integrity 3.4 25 26 295029 High Suppression Pool Wtr Lvl I 5
295032 High Secondary Containment N Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 following as they apply to HIGH SECONDARY CONTAINMENT AREA RADtATfON LEVELS :
(CFR: 41.10 143.5 145.13)
EA2.01 Area radiation levels 27 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 3.9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High
I ES-401 WA Category Point Totals BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier I/Group 2 (RO) 2 -
2 1
1 1
GroupPointTotal:
7 ES-401-1 II
Form ES-401-1 BWR Examination Outline Plant Systems -Tier 2lGroup 1 (RO KIA Topic(s)
Wility to monitor automatic
,perations of the RHWLPCI:
NJECTION MODE (PLANT SPECIFIC) including:
ICFR: 41.7 145.7) 43.05 Reactor water level Sonduct of Operations 32.1.28 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 I 45.5)
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 I 45.4)
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 I 45.7 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 I 45.4)
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-Soecific I.4*
3.2
+.I*
2 3 3.8 2.7 4.3" 2.7
218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff BWR Examination Outline Plant ! stems -Tier 2/Group 1 (RO)
Form ES-401-1 WA Topic@)
(nowledge of the effect that a loss
)r malfunction of the NTERMEDIATE RANGE MONITOR IRM) SYSTEM will have on ollowing:
CFR: 41.7 I 45.4)
(3.04 Reactor power indication (nowledge of the effect that a loss
)r malfunction of the following will lave on the INTERMEDIATE RANGE YlONlTOR (IRM) SYSTEM :
CFR: 41.7 145.7)
<6.04 Detectors (nowledge of electrical power supplies to the following:
- CFR: 41.7)
(2.01 SRM channels/detectors Nbility to predict and/or monitor zhanges in parameters associated Nith operating the AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM controls including:
[CFR: 41.5 I 45.5) 41.02 RPS status Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) :
(CFR: 41.5 / 45.3)
K5.06 Turbine operation Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURlZATlON 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 3.6 3.0 2.6 3.9 2.7" 4.5*
2.9 16 37
$8 39 40 41
ll ES-401 System # I Name II Plant BWR Examination Outline stems - Tier 2/Gn Form ES-401-1 KIA Topic(s)
~
~
Knowledge of the physical connections andlor causeeffect relationships between RELlEFlSAFETY VALVES and the following:
(CFR: 41.2 to 41.9 145.7 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 GEMAClFoxborolBailey controller operation: Plant-Specific.
Knowledge of the physical connections andlor 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 AC. ELECTRICAL DISTRIBUTION design feature(s) and/or 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: 41.7 145.5 to 45.8)
A4.01 All breakers and disconnects (including available switch yard): Plant-Specific Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C.ID.C.) design feature@) andlor interlocks which provide for the following:
(CFR: 41.7)
K4.01 Transfer from preferred power to alternate power supplies 4.0 3.1 2.9 3.4 3.4 3.1 43 44 45 46 47 48
BWR Examination Outline Form ES-401-1 is-401 Plant Systems -Tier 2/Group 1 MA Topic(s)
System ## 1 Name K
K 1
2 X
3.3 2.8 49 50 263000 DC Electrical 3istribution Knowledge of the physical connections andlor causeeffect relationships between D.C.
ELECTRICAL DISTRIBUTION and the following:
(CFR: 41.2 to 41.9 1 45.7 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: 41.5 145.6)
A2.01 Grounds
~
Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :
(CFR: 41.7 145.7)
K6.09 D.C. power Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:
(CFR: 41.7 1 45.7)
A3.02 Air temperature 3.3 2.9 51 264000 EDGs 52 300000 Instrument Air 400000 Component Cooling uVater 3.0 53 Ability to monitor automatic operations of the CCWS including:
(CFR: 41.7 1 45.7)
A3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws Group Point Total:
WA Category Point Totals
Form ES-401-1 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO)
ES-401 201001 CRD Hvdraulic WA Topic@)
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 2.7 54 Mechanism 11 201006 RWM 3.4 55 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) 3.3 3.2 56 57 215002 RBM 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: 41.5 145.6)
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: 41.5 145.6)
A2.11 Heatup or cooldown of the reactor vessel 2.5' 219000 RHWLPCI: TorusIPool Cooling Mode Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 tValves
ES-401 System # I Name K
1 223001 Primary CTMT and Aux.
226001 RHWLPCI: CTMT Spray Mode 230000 RHWLPCI: TorusIPool Spray Mode 233000 Fuel Pool CoolingICleanup BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGroup 2 (RO) 239001 Main and Reheat Steam 11 241000 ReactorlTurbine Pressure 1 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 11 271000 Offgas I
)I 272000 Radiation Monitoring I
11 286000 Fire Protection I
288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC K
K 2
3 X
K K
4 5
X WA Topic(s) 4 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: PlantSoecific 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 Knowledge of the affect that a loss or malfunction of the MAIN AND REHEAT STEAM SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.06 Steam seallGland seal Ability to monitor automatic operations of the REACTORITURBINE PRESSURE REGULATING SYSTEM including:
(CFR: 41.7 145.7)
A3.12 Turbine trio testina x
Ability to manually operate andlor monitor in the control room:
(CFR: 41.7 I 45.5 to 45.8)
A4.07 Lights and alarms G2.1.30 Ability to locate and operate components I including 2.7 2.8 2.6 2.9 3.9
11 ES-401 System # I Name 290002 Reactor Vessel lntemals BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO)
K K
K 1
2 3
X Form ES-401-1 G
I 1
WA Topic@)
Knowledge of the physical connections and/or cause-effect relationships between REACTOR VESSEL INTERNALS and the following:
(CFR: 41.2 to 41.9 145.7 to 45.8)
K1.19 TIP WA Category Point Totals A
3 -
1 1
A 4 -
IR 2.5 :.
I 4 I 1 I 1 I 31 Group Point Total:
I 12
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ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
I IuA#
Category 2.1.18 2.1.20
- 1.
Conduct of Operations Date of Exam IR -
1 Subtotal I 2*2-23
- 2.
Equipment Control 2.2.1 1 2.2.1 k I 2.2.
oDerations.(CFR: 43.2 / 45.13)
I I
Knowledge of the process for controlling 2.5 69 temporary changes.
(CFR: 41.10/43.3/
45.13)
Ability to perform pre-startup procedures for 3.7 70 the facility / including operating those controls associated with plant equipment that could affect reactivity. (CFR: 45. I )
- 3.
Radiation Control 2.3.1 1 Ability to control radiation releases.
2.7 2.3.1 0 Ability to perform procedures to reduce 2.9 (CFR: 45.9 / 45.10) excessive levels of radiation and guard against personnel exposure.
(CFR: 43.4 / 45. IO) 1 2.3.
1 I
2.3.
2.3.
2.3.
71 72
- ES-40 1 Facility:
Date of Exam Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 during emergency operations.
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.I 2
262001 K1.O1 300000 A I 295031 295029 239001 Reason for Rejection KIA c 2.5 for RO (2.2)
KIA < 2.5 for RO ( I.6)
WA c 2.5 for RO (2.3)
Very similar to 21 1000 K1.02 No WA > 2.5 RNCl not at WN/Pilgrim RNCl not at WN/Pilgrim No WA WA < 2.5 Equipment not installed at VYN/Pilgrim Very similar to 21 1000 K1.02 Deselected to allow selection of 2"d K4 in Tier 2 No AI WA in this system; picked from remaining 10 chips EAI.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 G2.2.22 Removed, NRC lead examiner felt that WA was above RO knowledge level and the question developed was also. Directed de-selection and random selection of new WA (9/10/03)
EXAMINATION LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: RO NRC Exam 2003 Exam Activity Code:
Date Exam Prepared: 19 September 2003 Date Exam Taken: 3 October 2003 Source 295001/AA2.05 2 5614 3 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 b
15 c
16 a
17 b
18 d
19 a
20 a
21 d
22 a
23 a
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
5615 2 5616 3 5617 0 5618 2 5619 4 5620 0 5621 2 5622 1 5623 5 5624 1 5625 3 5626 3 5627 1 5628 3 5629 1 5630 0 5631 4 5632 0 5633 2 5634 4 5635 2 5636 1 5637 4 5638 1 5639 1 5640 2 5641 2 5642 1 5643 2 5644 0 5645 0 5646 2 5647 2 5648 1 5649 2 LOT-00-202 LOT-01-262 LOT-00-60 1 LOT-00-249 LOT 129 LOT-00-6 12 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-00-61 0 LOT-00-61 0 LOT-00-286 LOT-00-607 LOT-00-138 LOT-00-602 LOT-00-288 LOT-00-6 1 8 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 CRO2,3,4 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 CRO2,3,4,5 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-00-218 CRO 2 3
LOT-00-21 1 A 0 2g 3
LOT-00-626 CRO 4 3
LOT-00-212 CRO 2 3
LOT-02-215 CRO 2i 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 2950292.1.32 0
295028EA2.05 1 295030EA1.02 1 295031lEA1.11 0 29503 UEA2.02 2 295037/EK3.04 2 600000/AK3.04 1 295026EiK2.04 0 295038/2.2.25 0
295002/AK1.04 1 295010/AK3.02 1 295013/AK3.01 0 2950192.2.22 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 1000/K1.02 1
21 1000K3.01 0
212000/A1.09 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
38 d
39 c
40 c
41 a
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 b
56 c
57 a
58 c
59 a
60 b
61 c
62 a
63 a
64 c
65 a
66 b
67 a
68 b
69 a
70 b
71 b
72 d
73 c
74 b
75 a
5650 1 5651 0 5652 3 5653 2 5654 3 5655 3 5656 2 5657 1 5658 0 5659 6 5660 2 5661 1 5662 3 5663 2 5664 0 5665 1 5666 2 5667 3 5668 5 5669 4 5670 1 5671 2 5672 0 5673 1 5674 2 5675 2 5676 2 5677 1 5678 2 5679 1
5680 3 5681 2 5682 0 5683 1 5684 1 5685 4 5686 3 5687 1 5688 0 LOT-02-2 15 LOT-0 1-2 15 LOT-05-2 15 LOT-00-2 17 LOT-00-2 18 LOT-00-206 LOT-00-239 LOT-01-259 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-02-201 LOT-00-202 LOT-03-201 LOT-00-2 16 LOT-00-205 LOT-01 -229 LOT-00-234 LOT-00-302 LOT-00-249 LOT-00-256 LOT-01-288 LOT-04-2 1 5 LOT-00-302 LOT-03-400 LOT-01 -400 LOT-00-402 LOT-02-201 LOT-00-271 LOT-00-602 LOT-00-61 0 LOT-00-607 LOT-00-622 CRO 8 CRO 6 CRO 6 CRO 4b CRO 2 CRO 5 7, loa 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, cy e, 3 CRO 4,5 CRO 1f71j,2 CRO 4, lla, 14 CRO 2 CRO 5 A 0 2a, by c, 10a RO 13 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, by 7 CRO 5 CRO 3 CRO 3 CRO 2,3 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 CRO 4 3
225 215003K6.04 2 15004/K2.01 2 15005/A1.02 2 17000K5.06 218000K3.02 223 002/A2.02 239002K1.09 259002K5.01 26 1 OOOK1.03 262001K4.05 26200 UA4.0 1 262002K4.01 263000K1.01 263000/A2.0 1 264000K6.09 300000/A3.02 400000/A3.01 201 002/A2.0 1 202002/2.1.33 2 1 5002/A2.0 1 2 16000/A2.11 219000/K2.01 22300 1K5.13 234000/A2.03 239001K3.06 24 1 OOO/A3.12 256000/A4.07 290001/2.1.30 290002K1.19 0/2.1.18 012.1.20 012.2.23 0/2.2.11 0/2.2.0 1 012.3.11 0/2.3.10 Oj2.4.18 0/2.4.23 Oi2.4.19 2
0 1
0 0
2 1
1 2
1 1
0 0
1 0
0 0
0 0
1 2
0 0
2 1
1 2
1 0
0 0
0 0
0 0
1 0
1 0
New New New New New New New New New New New Bank Mo J Bank Mo New New New New New Bank Mo i New New New New New New New New New New New New New BankMo3 New New New New New New
Question Level Totals 0
Fundamental KnowledgeMemory 36 1
Comprehension 2
Analysis 27 12 Orkinator: Brown, Scott T.
Last Revised: 09/19/2003 7:32:38 PM by Brown, Scott T.
ES-401 BWR Examination Outline Form ES-401-1 Faci I ity :
Date of Exam:
RO WA Category Points SRO-Only Points 0
3 4
1 8
1 0
1 2
4 1
3 5
3 12
- 3. Generic Knowledge and Abilities Categories 2
3 2
3 2
1 2
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. 1.c for additional guidance regarding SRO sampling.
- 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 *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 categoryher.
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.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
ES-401 BWR Examination Outline F
O M
I ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 11GrouD 1 (SRO)
I KIA Topic(s)
IR -
3.2 EIAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 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)
AA2.02 Neutron monitoring
~~
~
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 3.4 77 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip 13 295006 SCRAM I 1 11 295016 Control Room Abandonment I7 2.9 78 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :
(CFR: 41.10 143.5 145.13)
AA2.04 System flow 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4 3.5 79 Ability to operate andlor monitor the following as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.7 I 45.6) 43(b)(2)
AA1.02 RHWshutdown cooling Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE:
(CFR: 41.lo 143.5 145.13)
EA2.02 Drywell temperature 11 295023 Refueling Acc Cooling Mode I 8 4.0 -
80 81 295024 High Drywell Pressure I 5 295025 High Reactor Pressure 1 3 Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE:
(CFR: 41.10143.5145.13)
EA2.02 Reactor power 4.2
~
Emergency Procedures /Plan G2.4.3 Ability to identify post-accident instrumentation.
(CFR: 41.6 I 45.4) 43(b)(5) 3.8 11 295026 Suppression Pool High Water II Temp./5 295028 High Drywell Temperature I 5 295030 Low SuDDression Pool Wtr Lvl I 5 11 295031 Reactor Low Water Level I2 295037 SCRAM Condition Present and Power Above APRM Downscale or
ES-401 BWR Examination Outline FOm ES-401-1 Emergency and Abnormal Plant Evolutions -Tier IIGroup 1 (SRO)
E/APE #I Name / Safety Function K
K K
1 2
3 295038 High Off-site Release Rate I 9 I
l l
600000 Plant Fire On Site I 8 WA Category Totals:
l o l o l o A
A G
WA Topic@)
IR 1
2 Ability to operate and I or monitor the following as they apply to PLANT FIRE ON I I I SITE:
AA1.05 Plant and control room ventilation systems 43(b)(2)
I I
3 1 4 I 1 1 GroupPointTotal:
1 8
ES-401 BWR Examination Outline F O I ~
ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1IGrouP 2 (SRO)
KIA Topic(s)
EIAPE # I Name I Safety Function 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I 3 Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 / 45.2)
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) 3.5 3.9 85 86 295008 High Reactor Water Level I 2
~~
~
Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE :
(CFR: 41.10 143.5 I45.13)
AA2.02 Drywell pressure 295010 High Drywell Pressure I 5 11 295012 High Drywell Temperature I 5 11 295017 High Off-site Release Rate I 9 11 295020 Inadvertent Cont. Isolation I 5 & 7 11 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 I 9 295035 Secondary Containment High Differential Pressure I5 295036 Secondary Containment High SumpIArea Water Level I5 500000 High CTMT Hydrogen Conc. I 5 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 I
WA Category Point Totals 0
0 0
4 Group Point Total:
ES-401 BWR Examination Outline Plant Systems -Tier 2/Group 1 (SRO)
F O ~ I ES-401-1 WA Topic@)
System # I Name 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 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 I 45.6) 43(b)(5)
A2.12 Inadequate system flow 206000 HPCl 209001 LPCS 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 21 1000 SLC 212000 RPS 215003 IRM 215004 Source Range Monitor 215005 APRM I LPRM 217000 RClC 218000 ADS 223002 PCISINuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Zontrol 261 000 SGTS G2.1.27 Knowledge of system purpose and or function.
262001 AC Electrical Xstribution 262002 UPS (ACIDC) 263000 DC Electrical listn bution
ES-401 System # f Name K
K 1
2 264000 EDGs 300000 Instrument Air 400000 Component Cooling WA Category Point Totals I 0 I 0 BWR Examination Outline Plant Systems -Tier ZGro I p 1 (SR( ;
Form ES-401-1 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 I45.7) 43(b)(2)
K6.01 Starting air IR 3.9
~ Group Point Total:
91
BWR Examination Outline Plant Systems -Tier ZGroup 2 (SRO)
IR 3.7 3.2 12 Form ES-401-1 92 93 ES-401 System # I Name WA Topic@)
11 201001 CRD Hydraulic Mechanism 201006 RWM 202001 Recirculation 11 202002 Recirculation Flow Control 11 204000 RWCU 11 214000 RPlS 11 21 5001 Traversing In-core Probe 11 215002 RBM 226001 RHWLPCI: CTMT Spray Mode 230000 RHWLPCI: TorudPool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 241000 Reactormurbine Pressure Regulator 245000 Main Turbine Gen. I Aux.
Equipment Control G2.2.25 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 / 45.6) 43(b)(2)
A2.07 High fuel pool temperature 256000 Reactor Condensate 11 259001 Reactor Feedwater 11 268000 Radwaste 11 271000 OffQas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 11 290003 Control Room HVAC 290002 Reactor Vessel lnternals WA Category Point Totals 0
0 0
0 1
0 Group Point Total:
11 ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Category
- 1.
Conduct of Operations
- 2.
Equipment Control
- 3.
Radiation Control Date of Exam monographs / and tables which contain performance data.
(CFR: 41.10 / 43.5 / 45.12)
F IR -
2.1.
I I
I 2.1.
I I
I 2.1.
I I
I 2.1.
I I
I 2.2.21 Knowledge of pre and post maintenance operability requirements.
(CFR: 43.2)
I 2.2.
2.2.
2.2.
2.2.
I 2.2.
2.3.9 2.3.1 0 2.3.
2.3.
2.3.
2.3.
Knowledge of the process for performing a containment purge.
CFR: 43.4 / 45.1 0)
Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
(CFR: 43.4 / 45. IO)
SRO-Only 3.5 I 96
+
3.4 97 3.3 98
+
ES-40 1 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Category
- 4.
Emergency Procedures i Plan Tier 3 Point Total WA #
2.4.40 2.4.43 2.4.
2.4.
2.4.
2.4.
Date of Exam Topic Knowledge of the SROs responsibilities in emergency plan implementation.
(CFR: 45.1 I ) 43(b)(l) & (5)
Knowledge of emergency communications systems and techniques.
(CFR: 45.1 3) 43(b)(5)
Subtotal t
I SRC IR 4.0 3.5 3nly 99 100
ES-401 Record of Reiected WAS (SROI Form ES-401-4 Tier I Group 1 / I 1 / I 1 / I Randomly Selected WA 6000000 AA1.02 6000000 AA1.03 6000000 AA1.07 Reason for Rejection WA < 2.5 WA < 2.5 WA < 2.5
EXAMINATION LICENSED OPERATOR INITIAL TRAINING PROGRAM Course: SRO NRC Exam 2003 Exam Activity Code:
Date Exam Prepared: 19 September 2003 Date Exam Taken: 3 October 2003 Exam Ouestions No. &s Q # Rev IG Objectives Time K&ARef Level Source 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 b
15 c
16 a
17 b
18 d
19 a
20 a
21 d
22 a
23 a
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 3 5615 2 5616 3 5617 0 5618 2 5619 4 5620 0 5621 2 5622 1 5623 5 5624 1 5625 3 5626 3 5627 1 5628 3 5629 1 5630 0 5631 4 5632 0 5633 2 5634 4 5635 2 5636 1 5637 4 5638 1 5639 1 5640 2 5641 2 5642 1 5643 2 5644 0 5645 0 5646 2 5647 2 5648 1 5649 2 LOT-00-202 CRO 3j LOT-01 -262 LOT-00-60 1 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-00-610 LOT-00-6 10 LOT-00-286 LOT-00-607 LOT 138 LOT-00-602 LOT-00-288 LOT-00-6 1 8 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 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-00-2 18 CRO 2 3
LOT-00-21 1 A 0 2g 3
LOT-00-626 CRO 4 3
LOT-00-2 12 CRO 2 3
LOT-02-21 5 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 295024EK2.12 1 29502Y2.1.32 0
295028EA2.05 1 29503OEA1.02 1 295031EAl.11 0 29503 1EA2.02 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
206000K2.03 0
206000/A1.08 0
209001/K3.02 0
21 1000K1.02 1
21 1000K3.01 0
2 12000/A1.09 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
38 d
39 c
40 c
41 a
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 b
56 c
57 a
58 c
59 a
60 b
61 c
62 a
63 a
64 c
65 a
66 b
67 a
68 b
69 a
70 b
71 b
72 d
73 c
74 b
75 a
76 c
77 c
78 c
79 d
80 c
81 c
5650 1 5651 0 5652 3 5653 2 5654 3 5655 3 5656 2 5657 1 5658 0 5659 6 5660 2 5661 1 5662 3 5663 2 5664 0 5665 1 5666 2 5667 3 5668 5 5669 4 5670 1 5671 2 5672 0 5673 1 5674 2 5675 2 5676 2 5677 1 5678 2 5679 1
5680 3 5681 2 5682 0 5683 1 5684 1 5685 4 5686 3 5687 1 5688 0 5689 2 5690 1 5691 2 5692 1 5693 3 5694 0 LOT-02-2 15 LOT-0 1 -2 15 LOT-05-2 15 LOT-00-2 17 LOT-00-2 18 LOT-00-206 LOT-00-239 LOT-0 1-25 9 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-00-302 LOT-00-249 LOT-00-256 LOT-01 -288 LOT-04-2 15 LOT-00-302 LOT-03-400 LOT-01-400 LOT-00-402 LOT-02-20 1 LOT-00-27 1 LOT-00-602 LOT-00-61 0 LOT-00-607 LOT-00-622 LOT-05-215 LOT-00-601 LOT-00-60 1 LOT-00-60 1 LOT-00-6 14 LOT-00-602 CRO 8 CRO 6 CRO 6 CRO 4b CRO 2 CRO 5,7,10a CRO 3 CRO 5e CRO 5 CRO 11 Id, 3 CRO 7 CRO 2,3,4 CRO 2 CRO 3 A 0 9d, 11; CRO Id CRO 7 CRO la, c, e, 3 CRO 4,5 CRO 1 f, lj,2 CRO 4, lla, 14 CRO 2 CRO 5 A 0 2a, b, c, 10a RO 13 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
21 5003K6.04 2 1 5 004K2.0 1 215005/A1.02 2 17000K5.06 21 8000K3.02 223 002/A2.02 239002K1.09 259002K5.01 261000K1.03 262001K4.05 26200 1 /A4.0 1 262002K4.0 1 263000K1.01 263000/A2.01 264000K6.09 300000/A3.02 2
0 1
0 0
2 1
1 2
1 1
0 0
1 0
0 400000/A3.01 0
201002/A2.01 0
202002/2.1.33 0
215002/A2.01 1
216000/A2.11 2
219000K2.01 0
223001K5.13 0
234000/A2.03 2
239001LK3.06 1
24 1 OOO/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 0
012.4.23 1
0/2.4.19 0
29500UAA2.02 2 295004/AA1.01 2 29501 8/AA2.04 0 295021/AA1.02 1 295024EA2.02 2 295025EA2.02 1 New New New New New New New New New New New Bank Mo Bank Mo A New New New New New Bank Mo New New New New New New New New New New New New New Bank Mo 1 New New New New New New New New New New New Bank MoII
82 c
83 c
84 a
85 d
86 a
87 d
88 d
89 b
90 a
91 c
92 a
93 a
94 b
95 d
96 a
97 c
98 b
99 a
100 a 5695 2 5696 1 5697 2 5698 4 5699 1 5700 1 5701 2 5702 2 5703 0 5704 4 5705 3 5706 3 5707 0 5708 2 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-00-61 5 SRO 1 LOT-00-261 SRO 1 LOT-00-205 LOT-00-614 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 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 4
4 LOT-00-900 SRO (CRS) 1,4 4 325 Question Level Totals Level Description Number of Questions 0
Fundamental KnowledgehAemory 45 1
Comprehension 35 2
Analysis 20 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 209001/A2.09 26 1000/2.1.27 264000/K6.01 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 NR 1 Bank Grand GI i B 1998 NR I New New New New New New New New New New Bank Palisade 2001 NR 1 New New Originator: Brown, Scott T.
Last Revised: 09/19/2003 7:36: 15 PM by Brown, Scott T.
Form ES-301-2 ES-301 Control Room/ln-Plant Systems
%&-Outline Type Code*
D, A, s Facility:
Vermont Yankee Exam Level (circle one): !Q / SRO(I) / SRO(U)
Safety Function 1
Date of Examination:
10/3/03 Operating Test No.:
1 System / JPM Title II
- a. Perform Weekly Operable Control Rod Check (Stuck Rod)
(201 07F)
- b. Parallel Main Generator to Grid (24507)
I
- 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)
I
- h.
3 7
E.2 F p
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
I II
- j. Respond to High Service Water Strainer D/P (27601)
- k. Startup RPS Motor Generator (21202F) 1
- 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
(1 999 NRC)Modified Scenario No.: I CRO CRS Objectives: Evaluate the crews ability to operate plant equipment to support a normal power ascension, respdddtoandfevaluate (Technical Specificatibn) 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 plant parameters for a major primary containment steam leak resulting in emergency depressurization as well as recognizing the inability to spray the drywell l
a 480 VAC ECCS bus on plant operation, and to implement the EOPs to monitor and control Initial Conditions: IC-67(Snapshot) 30% power, approaching conditions for second Feedwater Pump Start Turnover: See Attached Shift Turnover Sheet Malf.
No.
Key 1 RC04 Key 2 RRO7B RR08B Key 3 RRIO 3600 sec Key 4 EDOSC 100% @
Key 5
.4% @
300 sec MS06 Key 6 10% @
1000 sec RH03A RFHP05 Event Type*
CRS ACRO C
CRO CRS ACRO M
CRO CRS C
ACRO N/A Event Description Continue power ascension IAW OP 0105 Start the second Feedwater Pump Inadvertent RClC initiation (TS) 5 minutes after RFP start 6
Recirc Pump lower and upper seal failure A
Recirc Pump speed controller failure, pump speed increasing 480 VAC ECCS Bus 8 fails Steam line leak in the drywell - emergency depressurization Drywell Spray Valve does not open (6 valves have no power)
HPCl aux oil pump ACB open - out of service for governor oil leak repair (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor
ScenarioNo.:
2 ACRO CRO CRS o a loss of the startup I Specifi&tionfoTa loss of one and respond to anLPRM upscale failure. Recognize and respond to a loss of main condenser vacuum, ATWS, and SLC system failures.
Initial Conditions: IC-9, 100% power, preparing to chlorinate the Circ Water System I
Turnover: See Attached Shift Turnover Sheet Event Type*
Event Description Malf. No.
ACRO CRS Place CW in Closed Cycle for chlorination ACRO C
CRO CRS Key 1 ED-02A Preinsert ANN Failure FW-09A 9-5-E-2 Loss of Startup Transformers Power Reduction with stuck Feedwater regulating valve Soft panel FRV A lockup red light out R
CRO C
~~
~
~
Key 2 N M2-24-41 B NM5D 97%
ACRO I
CRO CRS LPRM upscale failure, APRMD upscale APRM D failure is Automatically deleted when LPRM 24-41 B is bypassed Key 3 MC-8 7%
ACRO c
CRO CRS Main Condenser air inleakage (minor)
ACRO M
CRO CRS Key 3 modify 50%
120 Sec MC-8 After control rod insertion for event 5 has started.
Main Condenser large air Leak Loss of Vacuum Turbine Trip / LNP ACRO M
CRO CRS Preinsert RD 12A 69%
RD 128 74%
Preinsert SLOI A SL02 B Hydraulic ATWS / Level Power Control CRO CRS SLC A Pump Failure I B Squib Failure Bypass APRM A Preinsert NM-OGA APRM A INOP, Bypass APRM A prior to insertion (I)nstrument, (C)omponent, (M)ajor (N)ormal, (R)eact ivity
Scenario No.: 3R 1 Objectives: Evaluate the crews response to a fault on 480 volt Bus 89B and to take the required
, Technical Specification actions for the bus loss. Recognize and take action for a trip of the running TBCCW pump with a failure of the automatic and manual start of the standby RBCCW pump. The I complete loss of TBCCW will cause condensate and feedwater pump bearing temperatures to rise to the alarm set points. They will attempt to transfer house loads to the startup transformers but the breakers will not close. They will scram the reactor due to degrading conditions in the feed and condensate pump bearings. The fast and residual bus transfer to the startup transformers will fail when the turbine trips after the scram causing an LNP. The crew will enter OT 3100 / EOP 1 (scram) and OT 3122 (LNP).
After the plant is stabilized a steam leak will occur in the drywell compounded by a loss of high pressure feed. EOP 3 will be entered to control primary containment parameters. After drywell sprays are initiated HPCl will trip. RPV level will lower due to the loss of high pressure feed sources and an RPV-ED will be preformed to allow low pressure injection sources to restore RPV level above TAF.
Multiple injection valve auto open failures will occur requiring operator actions to restore RPV level above TAF IC-9 100% power. RClC is out of service Initial Conditions:
See Attached "Shift Turnover" Sheet Event Description RClC isolation (RCIC 00s)
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I RF RCRO5 1 NIA 1 RClC 15 ACB opened after RClC 15 is closed (RCIC 00s)
CS03A preinsert 1
1 1
Core Spray A injection valve auto open failure
ally (Switch I/O) No 1
I EDl9B SW 14A 2
SWdiO6swl2b 3
I N/A RROIA 5% @ 800 4
sec ramp 5
I HPOl See above 6
preinserts 1
C Loss of Bus 89B C
the B TBCCW pump N
Failure of Bus 1 and 2 to auto transfer tothe startup transformers Trip of A TBCCW pump and failure of auto and manual starts of Power reduction due to increasing component temperatures M
Recirc loop rupture C
HPCl turbine trip, loss of all high pressure feed Failure of injection valves to auto open h
(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor