ML061950362
| ML061950362 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/02/2005 |
| From: | Gody A Operations Branch IV |
| To: | Forbes J Entergy Operations |
| References | |
| 50-313/06-301, ES-401, ES-401-2 50-313/06-301 | |
| Download: ML061950362 (10) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Note:
- 1.
Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and the SRO only outlines (Le. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
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 f l from that specified in the table based on NRC revisions. The final RO exam must total 75 point:
and the SRO -only exam must total 25 points.
Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
Select topics from many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
Absent a plant specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
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.
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; if fuel handling equipment is sampled in other than Category A2 or G" on the SRO-Only exam, enter it on the left side of Column A2 for Tier 2, Group 2. Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA number, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43
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7.*
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NUREG-I 021, Revision 9 1 of10
ES-401 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 I G r o u D I a R O )
K K
K 1
2 3
EIAPE # I Name I Safety Function 00007 (BWIE02 & E10; CEIE02) Reactor Trip
- Stabilization -Recovery I 1 00008 Pressurizer Vapor Space Accident I 3 X
000009 Small Break LOCA I 3 00001 1 Large Break LOCA I 3 X
00001 5/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup I 2 X
000025 Loss of RHR System I 4 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 X
X 000038 Steam Gen. Tube Rupture I 3 000040 (BWIEOS; CEIEO5; WIE12)
Steam Line Rupture - Excessive Heat Transfer I 4 000054 (CEIEO6) Loss of Main Feedwater I 4 I l l I l l 000055 Station Blackout I 6 I I I x 000056 Loss of Off-site Power I 6 I 3 5 2 4 3 -Ability to identify post-accident instrumentation 2.7*
EKI 01 - Knowledae of the ooerational imdications of the 1 4 1 following concepts& they apply to the Large Break LOCA:
Natural circulation and cooling, including reflux boiling.
Not selected AK3 01 - Knowledge of the reasons for the following responses as they apply to Loss of Rx Coolant Makeup Adjustment of RCP seal backpressure regulator valve to obtain normal flow AK3 02 - Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System Isolation of RHR low pressure piping prior to pressure increase above specified level AA2 01 -Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water Location of a leak in the CCWS 2.7 -
3.3 2.9 interrelations between the 01 Malfunctions and the following
'My to operate and monitor the following as they ation Blackout. Battery, when approaching fully ffsite Power. Order a 4.3 -
3.3 -
3.5 -
3 4 -
5 6
NUREG-1021, Revision 9 2of 10
ES-401 Form ES-401-2 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 I
/ I
/ I 000065 Loss of Instrument Air / 8 I
W/E04 LOCA Outside Containment I 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BWIE04; W/E05 Inadequate Heat Transfer
- Loss of Secondary Heat Sink I 4 X
C I
I I
I I 3 1 WA Category Totals:
AA2.05 - Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: S/G pressure and 1
I Not applicable to this unit.
Not applicable to this unit.
3 3 3
Group PointTotal:
14 -
15 -
16 17 18 NUREG-1021, Revision 9 30f10
ES-401 Form ES-401-2 ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier1 I G r o u p 2 a R O )
Form ES-401-2 1 EIAPE # / Name I Safety Function 000003 Dropped Control Rod I 1 000005 InoperableIStuck Control Rod I 1 000024 Emergency Boration I 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Range NI I 7 000033 Loss of Intermediate Range NI I 7 000036 (BWIA08) Fuel Handling Accident I 8 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid RadWaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms I 7 000067 Plant Fire On-site / 8 000068 (BWIAO6) Control Room Evac. I 8 000069 (WIE14) Loss of CTMT Integrity I 5 x
I 000074 (W/E06&E07) Inad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9 W/E15 Containment Flooding I 5 I
WIE16 High Containment Radiation I 9 BWIAOI Plant Runback I 1 AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation: Guidance contained in Different inputs that will cause a reactor building evacuation Replaced during development with 033 AK3.02.
ne and interpret the following as enerator Tube Leak When to I Not applicable to this Unit IR 3 3 19 3.6 20 3.8 21 2.6 22 3.4 23 2.6 24 4.0 25 3.7 26 NUREG-I 021, Revision 9 4 of 10
Form ES-401-2 ES-QOI BWlA02&A03 LOSS of NNI-X/Y 17 BWlA04 Turbine Trip I 4 BWIAOS Emergency Diesel Actuation I 6 BWlA07 Flooding I 8 BWlEO3 Inadequate Subcooling Margin I 4 BWIEO8; WlE03 LOCA Cooldown - Depress. 14 BWIEOS; CEIAI 3; W/EOS&El 0 Natural Circ. 1 4 BWlE13&E14 EOP Rules and Enclosures CEIAI 1; WIE08 RCS Overcooling - PTS I 4 CEIA16 Excess RCS Leakage 12 CEIEOS Functional Recovery KIA Category Point Totals:
NUREG-I 021, Revision 9 5of10
NUREG-I 021, Revision 9 6of 10
ES-401 Form ES-401-2 059 Main Feedwater
~
I 059 Main Feedwater 061 AuxiliarylEmergency Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 062 AC Electrical Distribution 063 DC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment WA Category Point Totals:
perations: Effect on plant of de-NUREG-l 021, Revision 9 7of 10
ES-401 Form ES-401-2 ES-401 DI I
System # I Name K
K K
K K
1 2
3 4
5 X
001 Control Rod Drive X
002 Reactor Coolant 01 1 Pressurizer Level Control X
014 Rod Position Indication 015 Nuclear Instrumentation 01 6 Non-nuclear Instrumentation 017 In-core Temperature Monitor X
027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling NUREG-1021. Revision 9 PWR Examination Outline -
Form ES-401-2 ed during exam development with 072 8of 10 56 57 58 -
59 60 61 62 63 64 65 -
ES-401 Form ES-401-2 NUREG-1021, Revision 9 9of 10
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-2 Facility: Arkansas Nuclear One Unit 2 RO Written Outline Date of Exam: 12/9/2005 Category KIA #
Topic RO ___
IR 2.1 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2.1.8 - Ability to coordinate personnel activities outside the control room.
2.1.29 - Knowledge of how to conduct and verify valve lineups.
3.7 66
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Conduct of Operations 2.1 3.8 2.8 -
67 68 -
2.1 2.1 2.1 3
Subtotal 2.2 69 2.2.12 - Knowledge of surveillance procedures.
2.2.30 - Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.
3.0 2.2 3.5 70
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fquipment
>ontrol 2.2 2.2 2
Subtotal 2.3 71 2.3.1 - Knowledge of 10CFR20 and related facility radiation control requirements.
2.3.4 - Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.3.10 - Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
2.6 2.3 2.5 2.9 72 -
73
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iadiation Control 2.3 2.3 2.3 Subtotal 2.4 2.4 2.4.10 Knowledge of annunciator response procedures.
2.4.25 Knowledge of fire protection procedures.
3 74 75 -
3.0 3.3 -
2.4 2.4 Subtotal
- mergency
'roceduresl Plan 2
10 -
'ier 3 Point Total NUREG-1021, Revision 9 10 of 10