ML041750149
| ML041750149 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/19/2004 |
| From: | Hackenberg J AmerGen Energy Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| References | |
| 50-219/04-301 | |
| Download: ML041750149 (32) | |
Text
ES-401 Record of Rejected WAS Form ES-4014-M Oyster Creek Written Exam; SRO Portion I( Tier/
Grow I Randomly Selected WA Reason for Rejection 111 295006iAA2.06 Verifying rod position following a Scram is done during the operating test. This WA would be oversampling in the written exam.
2/2 286000/A2.0I No plant-specific logic failure identified as testable material.
314 2.4.41 Classification for EP done on Operating Test.
112 29501212.4.16 This WA is better tested on Operating Test and is expected to be Dart of one of the scenarios.
- 11 -
-12.1.5 I This KIA is better tested on a JPM.
311 2.1.25 This WA is better tested on a JPM.
211 259002lA2.03 This WA is better tested during the Operating Test. Licensee
- ~
agreed to have a level input event in one of the scenarios.
112 295015/AA2.02 Oversampling of ATWS between RO and SRO exams.
312 I 2-2.16 1
and is of low significance for SRO (2.6). In the SRO amlicants will take both exams.
313 2.3.7 This is not an SRO function. Even non-licensed personnel are aware of RWP DreDaration.
ES-401 Record of Rejected WAS Form ES-401444 Oyster Creek Written Exam; RO Portion
~ _ _ _ _ _ __ ~~
Tier / Randomly Reason for Rejection Group Selected WA ~ ~ ~ ~ ~ ~
1/2 295033/EK2.04 SGTS is oversampled considering Operating Test Scenarios and JPMs exercise SGTS . SGTS also examined in Questions# 23
~
and 70. ~ ~~
211 264000/K1.03 There is no fire protection associated with the emergency diesel
~
aenerators.
1/ I 295031/EA1.01 There is no LPCI at OC. The only low pressure ECCS is Core Spray. Discussed with Fred Guenther and he agreed it was armrowiate to use Core SDrav in dace of LPCI.
2/2 230000/K6.09 Torus sprays are not distinguished from Drywell Sprays in OC EOPs. The only modes of containment spray identified in EOPs are Drywell Spray and Torus Cooling. In addition this K/A was, essentially, a duplicate of 226001lK5.06.
3/1 2.1.10 The examiner reviewed the License Conditions and determined there were very few. None of these appeared to yield good testable material at the RO level. The licensee had requested this K/A be reiected based on a Dreviouslv amroved exam outline.
312 2.2.2 This K&A is more appropriately tested during the Operating Test.
211 259002/A2.03 This K&A is more appropriately tested during the Operating Test.
The Licensee agreed to include a Feedwater failure from level input in one of the scenarios.
211 205000/A1.05 This K&A is appropriate for a plant having Shutdown Cooling mode of RHR. Specifically where misoperation of RHR can effect RPV level (from opening the min flow valve, for example). No such relationship exists at OC which has a separate Shutdown Cooling svstem with no min flow valve discharaina to the torus. ~ _ _ ~
2/2 239001/AI .05 Main Steam Line Radiation no longer causes auto closure of MSIVs.
There is a question regarding manual response to increasing steam line radiation in Turbine Building.
wo ES-401 ES-401 BWR -Examination Outline Form ES-401-1 I.
Facilitv: Date of Exam:
I RO WA Cateaorv Points 1 4 2 3 2 2 2 1 3 1 4 2 2326 2.
Plant 2 1 0 2 2 2 1 1 1 2 0 0 4312 Systems 3 4 Tier 5 2 5 4 4 3 2 4 3 4 2 4838 Totals
- 3. GenericKnowledgeand at a# c8f Ga#
Abilities Categories I 2 3 4 3-210 3 3 7 7
ES-401 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. 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 finalRO exam must total 38875 points and the SRO-only exam must total 25 points.
- 3. Select topics from many systems and evolutions; avoid selecting more than two-er t h e WA topics from a given system or evolution unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* 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 I O CFR 55.43 or an SRO-level learning objective.
- 7. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for thefR8applicable license level, . and
. the point totals for each system and c a t e g o r y . - l W & e b w 2.5
. .. 5 Enter thegroup 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.
- h. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
I. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
3 of 34 NUREG-1021, Draft Revision 9
ES-401 I,
iination Outline FO~IES401-'
ES-401 Emergency -
utions Tier I/Group 1 (ROI SRO) -
7 11 UAPE # I Name I Safety Function WA Topic@)
IR 295001 Partial or Com lete Loss of Forced 2.1.33 Ability to recognize indicationsfor 3.4
?I core FIOW Circulation & 4 system operating pa.rameters which are entry-level conditions for technical s ecifications.
(8FR: 43.2 / 43.3 / 45.3) 295003 Partial or Complete Loss of AC I 6 AA1. Ability to operate and/or monitor the 4.4 following as the ap I to PARTIAL OR COMPLETE LOkS 8qA.C. POWER :
(CFR: 41.7 / 45.6)
AA1.03 S stems necessary to assure safe Y
plant shu down.......
295004 Partial or Total Loss of DC AA2. Ability to determine and/or interpret 3.5 Pwr/6 the followin as the ap I ?o PARTIAL OR COMPLETE LOgS d"FYD.C. POWER.
(CFR: 41.10 /43.5 / 45.13)
AA2.02 Extent of partial or complete loss of D.C. power.
295005 Main Turbine Generator AKI . Knowled e of the operational 4.0 Trip / 3 im lications o?the folkwin concepts as they apply to MAIN TURBI ii~
GENERATOR TRIP :
(CFR: 41.8 to41.10)
AKI . O l Pressureeffects on reactor Dower. -
295006 SCRAM / 1 AK2. Knowled e of the interrelations 3.7 between S C d M and the following:
(CFR: 41.7 / 45.8)
AK2.03 CRD hydraulic system...
295016 Control Room AK2. Knowled e of the interrelations 4.0 Abandonment I 7 between CONYROL ROOM ABANDONMENT and the following:
(CFR: 41.7 / 45.8)
AK2.02 Local control stations: Piant-Specific...
ES-401 AK1. Knowled e of the operational 3.5/
im lications o4he 3.4 fokwin conce ts as they a ply to PARTIAT EOMPLETE OR COMPONENT COOLING WATER :
L O ~ SOF (CFR: 41.8 to 41.10)
AKI .01 Effects on componentlsystem operations.6 AK2. Knowled e of the interrelations between PARTIIL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the followin *
(CFR: 41.7345.8)
AK2.02 Plant operations.
AK3. Knowledae of the reasons for the 3.5 following respcnses as they a ply to PARTIAL OR COMPLETE LOSS O F INSTRUMENTAIR :
(CFR: 41.5 / 45.6)
AK3.02 Standby air compressoroperation.
2.1.22 Ability to determine Mode of 2.8
? eration.
,63FR: 43.5 / 45.13) 295023 Refueling ACCCooling Mode / 8 295024 High Drywell Pressure / 5 3 2 . Ability to determine and/or interpret 3.9
- he followin as
- he$ a\p?y to HIGH DRYWELL
>R SSU E:
- CFR: 41. I O / 43.5 / 45.1 3) 32.04 Su pression chamber pressure:
F
'lant-Speci IC.
295025 High Reactor Pressure/ 3 fK3. Knowledge of the reasons for the 4.2*
ollowing responses 1s the apply to HIGH REACTOR
>RESS~;RE.
CFR: 41.5 I45.6) iK3.06 Alternate rod insertion: Plant-Specific..
5 of 34 NUREG-1021, Draft Revision 9
ES-401 EK3. Knowledae of the reasons for the 3.91 3.7 EK3.02 Suppression pool cooling..
2.4.21 Knowledge of the parameters and logic-used to assess the status of safety functions includin :
I.Reackity control
- 2. Core coolin and heat removal
- 3. Reactor coiant s stem integrity
- 4. Containpent conJtms
- 5. Radioactivi release control.
(CFR: 43.5 / 4 .12) 295027 High Containment TemDerature I5 EA1. Ability to operate and/or monitor the 3.9 following as they appl to HIGH DRYWELL TEMPERAT~RE.
(CFR: 41.7 45.6)
EA1.02 Drywell ventilation system..
EK2. Knowled e of the interrelations 3.5 between LOW?
SUPPRESSION POOL WATER LEVEL and the followin .
(CFR: 41.7 / 45%)
EK2.08 SRV discharge submergence..
EAI. Ability to operate and/or monitor the 4.4*
following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41.7 / 45.6)
EA1.03 Low pressure Core Spray System. -
295037 SCRAM Condition Present EK1. Knowled e of the operational 4.1*
and Power Above APRM implications oAhe Downscale or Unknown / 1 EK1.02 Reactor water level effects on reactor power.
EKI. Knowled e of the operational 2.5 im lications o?the folkwin conce ts as the apply to HIGH OFF-SI~ERELEASE RA+E :
(CFR: 41.8 to41.10)
EKI .Ol Biological effects of radioisotope ingestion.
ES-401 600000 Plant Fire On Site / 8 WA Category Totals:
~
7 of 34 NUREG-1021, Draft Revision 9
ES-401 ES-401 BWR S E x a m i n a t i o n Outline Form ES-401-'
Emeraencv and Abnormal Plant Evolutions - Tier l/Group 2 (RO / SRO) 1 UAPE # / Name I Safety Function WA Topic(s) 295002 Loss of Main Condenser 295007 Hiah Reactor PressureI 3 295008 High Reactor Water Level I2 295009 Low Reactor Water Level I2 295010 High Drywell Pressure 15 295011 High Containment Temp I 5
295012 High D AA2. Ability to determine andlor interpret 3.9 Temperature I Y the following as ap I t o HIGH DRYWELL
%dPEP,JJRE (CFR: 41.10 / 43.5 / 45.13)
AA2.02 Drywell pressure.
AK3. Knowledge of the reasons for the 3.6 following respo'nses as the a I to HIGH SUPPRESSION POOL TEJ~~RATURE (CFR: 41.5 145.6)
AK3.02 Limiting heat additions.
295014 Inadvertent Reactivity Addition / 1 1 295015 IncompleteSCRAM I 1 AK2. Knowled e of the interrelations 3.3 between HIG 80 FF-SITE RELEASE RATE and the following:
(CFR: 41.7 / 45.8)
AK2.03 Off-gas system.
295020 InadvertentCont.
Isolation/ 5 8 7
- 1) 295022 Loss of CRD Pumps / I I 295029 High Suppression Pool Wtr Lvl / 5
ES-401 295032 High Secondary EA1. Abilitv to oDerate and/or monitor the 3.7 ContainmentArea Temperature/
5 EA1.03 Secondanr containment ventilation..
295033 High Secondary EK3. Knowledge of the reasons for Containment Area Radiation Emergency Depressurizationas it applies Levels / 9 to (CFR: 41.7 1 45.8)
EK3.01 High Secondary Containment Radiation Levels.
295034 Secondary Containment EK1. Knowled e of the operational Ventilation High Radiation / 9 P implicationso the EKI.01 Personnel protection.
I I 295035 Seconda Containment EK3. Knowledae of the reasons for the High Differential gessure / 5 following respoYnses as they ly to SECONDARY CONTAINME???) HIGH DIFFERENTIAL PRESSURE *
(CFR: 41.5 / 45.6)
EK3.01 Blow-out panel operation: Plant-Specific..
295036 Seconda Containment High Sump/Area Xater Level / 5 500000 High CTMT Hydrogen u WA Category Point Totals: Group Point Total:
9of34 NUREG-1021, Draft Revision 9
ES-401 ES-401 ES-401 m fR8 3 ation Outline Form ES-401-1 ID 1 (RO / SROl System # / Name WA Topic(s) 203000 RHR/LPCI:
Injection Mode 205000 Shutdown K1. Knowledge of the physical 3.1/
Cooling connections andlor causeeffect 3.4 relationships between SHUTDOWN COOLING SYSTEM(RHR SHUTDOWN COOLING MODE1and the followin :
(CFR: 41.290 41.9 / 45.7 to 45.8)
K I.05 Component cooling water systems.
A2 Abili to redictthe impacton the SHUTD8d C O O L I N G SYSTEM RHR SHUTDOWN COOLING rSIODE) o eration from:
(8FR: 41.5 / 45.5)
A2.09 Low Reactor water level 206000 HPCl 207000 Isolation K1. Knowledge of the physical 3.8/
(Emergency) Condenser connectionsand/or causeeffect 3.5 relationshi s between ISOLATION (EMERGEkCY)CONDENSER and the followin :
(CFR: 41.290 41.9 / 45.7 to 45.8)
K1.01 Reactor vessel: BWR-2,3 .
K2. Knowledge of electrical power su lies to the following:
(CEk: 41.7)
K2.02 Initiation logic: BWR-2,3 11 of 34 NUREG-I021, Draft Revision 9
ES-401 K l . Knowledge of the physical 3.7/
connections and/or causeeffect 3.3 relationshi s between LOW PRESSURE~ORESPRAYSYSTEM and the followin -
(CFR: 41.2 to 47.b / 45.7 to 45.8)
K I.05 Automatic depressurization system. .
use pfocedures to correcf, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.05 Core spray line break.
I K2. Knowledge of electrical power 3.1/
su plies to the 2.6*
folkwing:
(CFR: 41.7)
K2.02 Explosive valves K3. Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on followin (CFR: 41.7 / 4 5 J j K3.03 Core plate differential pressure indication .
K3. Knowledge of the effect that a 3.7 loss or malfunctionof the REACTOR PROTECTION SYSTEM will have on following:
(CFR: 41.7 / 45.4)
K3.05 RPS logic channels 3.7 K4.01 Rod withdrawal blocks.
I K5. Knowledge of the operational 2.8 imolications of the followin conce ts as the ap I to SOUR& R A N ~ E SYSTEM :
MONIT~R (gib)
[CFR:41.5 / 45.3)
K5.03 Changing detector position
ES-401 K6. Knowledge of the effect that a 3.7 loss or malfunction of the following will have on the AVERAGE POWER RANGE MONITOIWLOCAL POWER RANGE MONITOR SYSTEM :
(CFR: 41.7 / 45.7)
K6.01 RPS A2. Abili to (a) predict the impacts 4.2 t h e 7
of the fol owing on A U T O M A T I C DEPRESSURIZATION SYSTEM :
and (b) based on those redictions, use proceduresto correc!
control, or mitigatethe consequences of those abnormal conditions or o erattons:
(8FR: 41.5 / 45.6)
A2.06 ADS initiation signals present A4. Ability to manually operate 3.6 and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.03 Reset system isolations K5. Knowledge of the operational 3.31 imriications of the 3.1 followin conce ts as they apply to RELIEIJSAFETV VALVES (CFR: 41.'5 / 45.3)
K5.04 Tail pipe temperature monitoring .
2.4.6 Knowledge symptom based EOP mitigation strate ies.
(CFR: 41.10 143.5 l4t.13)
A3. Ability to-monitor automatic 3.0 operations of the REACTOR WATER LEVEL CONTROL SYSTEM including:
(CFR: 41.5 / 45.6)
A3.06 Reactor Water level setpoint setdown following SCRAM .
13 of 34 NUREG-I021, Draft Revision 9
ES-401 261000 SGTS changes in arameters associatedwith o eratin L e STANDBY GAS TREATMEN?
SYSTEM controls including:
(CFR: 41.5 / 45.5)
I A4. Ability to manually operate and/or monitor in the II control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.03 Local operation of breakers I
262002 UPS (AC/DC) I 2.1.30 Ability to locate and operate components / including local controls.
(CFR: 41.7 145.7)
I 263000 DC Electrical A.4 Ability to manually operate Distribution and/or monitor in the control room:
(CFR 41.7/45.5)
I A4.03 Battery discharge rate: Plant-Specific I I K1. Knowledae of the Dhvsical I1 connections Znd/or caush effect relationshi s between EMERGENCY GENERAfORS (DIESEUJET) and the followin :
(CFR: 41.290 41.9 / 45.7 to 45:8)
I K1.03 Fire protection system .
K6. Knowledge of the effect that a loss or malfunction of the followin will have on the EMERGENCf GENERATORS DIESEUJET) :
(CFR: 41.7 / 45. )
I K6.01 Starting air f K4. Knowled e of (INSTRUMENT AIR SYSTEd design featuye(s 1' 2 and or interloc)ks which provide or the following:
(CFR: 41.7)
K4.02 Cross-over to other air systems
ES-401 400000 Component F K3. Knowledge of the effect that a 2.91 2 Cooling Water loss or malfunction of 2.5 the CCWS will have on the following:
(CFR: 41.7 145.6)
Ill K3.01 Loads cooled by CCWS 2.2.25 Knowled e of bases. in 9
technical s ecifica ions for limiting P
conditions or operations and safety limits.
(CFR: 43.2)
WA Category Point Group Point Total: 2 Totals: 6 I
4 15 of 34 NUREG-1021. Draft Revision 9
ES-401 ES-401 t Mine Form ES-401-F I (RO / SRO) 4 WA Topic@)
c K6. Knowled e of the effect that 3.0 9
a loss or mal unction of K6.02 Condensate storage tanks -
K4. Knowled e of REACTOR 3.3 MANUAL C O ~ T R O LSYSTEM design feature(s1 and/or interlocks which Drovide for the following:
(CFR: 41.7)
K4.05 "Notch override" rod withdrawal.
K4. Knowled e of ROD WORTH 3.2 MINIMIZER ~ Y S T E M(RWM)
LPLANT PECIFIC) design feature@)
and/or interlocks which provide for the following:
(CFR: 41.7)
K4.06 Correction of out of sequence rod positions: P-Spec K3. Knowledae of the effect that 3.9 a loss or malfunction of the RECIRCULATION SYSTEM will have on following:
(CFR: 41.7 / 45.4)
K3.03 Reactor power.
K3. Knowled e of the effect that 4.0 9
a loss or mal unction of the RECIRCULATION FLOW CONTROL SYSTEM will have on followin .
(CFR: 4 . 7 / 45.4)
K3.02 Reactor power.
K l . Knowledge of the physical 3.1 connections and/or causeeffect relationshi s betweenREACTOR WATERCkANUPSYSTEMand the followin :
(CFR: 41.290 41.9 / 45.7 to 45.8)
K1.01 Reactor vessel .
ES-401 17 of 34 NUREG-1021, Draft Revision 9
ES-401 268000 Radwaste -
271000 Offgas A3. Ability to monitor automatic 2.8 o erations of the OFFGAS S k T E M including:
(CFR: 41.7 145.7)
A3.03 System temperatures 272000 Radiation A2.Ability to (d redict the Monitoring 2P impacts of the o lowin on the RADIATION MOkfITORING 2.6 SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or o erations:
(CFR: 41.5 14p.6)
A2.07 H dro en injection 8 %
operation: lant- pecific .
286000 Fire Protection 288000 Plant Ventilation (I 290001 Secondary CTMT 1 290003 Control Room HVAC I lnternalsReactor Vessel 290002 1 KIA Category Point Totals: Group Point Total:
ES-401 ES-40I Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-53 Facility: Date of Exam:
Category WA # Topic -I 3nly IR #
2.1.2 knowledge of operator responsibilitiesduring all 3.0 modes of operation.
- 1. (CFR: 41.10 / 45.13)
Conduct of Operations 2.1.12 Ability to apply TS for a system. 2.9 (CFR: 43.1 145.13) 2.1.23 Ability to perform specific system and integrated 3.9 plant procedures during different modes of operation.
(CFR: 41.10 / 43.5 145.12)
Subtotal 3.7 controls associated with plant equipment that could
- 2. affect reactivity.
Equipment (CFR:45.1)
Control 2.2.11 Knowledge of the process for controlling temporary 2.5 changes.
(CFR: 41. I O / 43.3 / 45.13) 2.2.26 Knowledge of refueling administration requirements 2.5 (43.5145.131 I
Subtotal 2.3.2 Knowledge of facility ALARA program. 2.5 (CFR: 41.12 143.4 145.9 145.10) 3.
2.3.9 Knowledge of the process for performing a 2.5 Radiation containment purge.
Control (CFR: 43.4 / 45.10)
I 9 of 34 NUREG-I021, Draft Revision 9
ES-401 t-I t Subtotal i-2.4.29 Knowledge of the emergency plan. 2.6 1 (CFR: 43.5 / 45.1 1) 4.
Emergency 2.4.50 Ability to verify system alarm setpoints and operate 3.3 Procedures/
controls identified in the Plan alarm response manual.
(CFR: 45.3)
I Subtotal Tier 3 Point Total
ES-401 ES-401 BWR ffte-Examination Outline Form ES-401-1 I Facility: Date of Exam: 1.
L
~ ~~ ~~ ~
RO WA Category Points SRO-Only Points Tier 0 0 4 4 8 Emergency 0 0 2 2 4 Abnormal Plant 0 0 6 6 12 Evolutions 0 0 1 3 4 0 0 1 I 2 0 0 2 4 6
ES-401 h
ES-401 BWR i &Examination Outline Form ES-401-Emergency ant Evolutions -Tier l/Group 1(RO I SRO)
E/APE # / Name / Safety Function 9l"l I I WA Topic(s)
S AA2. Ability to determine and/or interpret the following as they a ly to PARTIAL OR COMPLETE LOSS 6% FORCED CORE FLOW CIRCULATION :
(CFR 41.10/43.5145.13)
AA2.01 Powerlflow map8 1 295003 Partial or Complete Loss ofAC16 295004 Partial or Total Loss of DC 2.1.33 Ability to recognize indications of DC Pwr 16 System o erating parameters which are entry level for .Fs.
(CFR 43.2I 43.5/ 45.3) 1 295005 Main Turbine Generator Trip I 3 I I 295006 SCRAM / 1 S AA2. Ability to determine and/or interpret the following as the ap 1ytoSCRAM-(CJR tl.10 / 43.5 / 45.13)
AA2.02 Control rod position.
(I Abandonment 295016 Control Room I 7 295018 Partial or Total Loss of CCWl8 295019 Partial or Total Loss of 2.2.27 Knowled e of the refueling process. 3.5 Inst. Air I 8 (CFR 43.6/ 45.f3) 295021 Loss of Shutdown Cooling 295023 Refueling Acc Cooling Mode 1 8 295024 High Drywell Pressure I 5 EA2. Ability to determine and/or interpret the followin as the ap Ky to HIGH DRYWELL PRESSURE:
(CJR fl.10 / 43.5/ 45.13)
I/ 295025 High Reactor Pressure 13 295026 Suppression Pool High I I EA2.02 Drywell temperature.
Water Temp. I 5 I 295027 High Containment Temperature / 5 3 of 34 NUREG-I021, Draft Revision 9
ES-401 I I 295028 High Drywell Temperature S 2.4.20 Knowledge of operational I5 implications of EOP warnings / cautions / and notes.
(CFR 41.10 /45.13) 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2
m S EM. Ability to determine and/or interpret the followlng as the apply to REACTOR LOW WATER LEVE~.
(CFR:4i.10/43.5/45.13)
II EA2.02 Reactor power.
295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I I 295038 High Off-site Release Rate I9 600000 Plant Fire On Site I 8 S 2.4.27 Knowledge of fire in the plant rocedure.
PCFR 41.10/43.5/45.13)
KIA Category Totals: Group Point Total:
ES-401 1
ES-401 BWF jR4Examination Outline Form ES-401-1 Emergency ana -
Plant Evolutions Tier l/Group 2 (RO / SRO)
II E/APE # / Name / Safety Function 41AIGI 1 2 WA Topic(s)
I IR S 2.4.31Knowledge of annunciators alarms and 3.4 indications / and use of the response instructions.
(CFR41.10/45.3)
I 295007 High Reactor Pressure / 3 295008 High Reactor Water Level S AA2. Ability to determine and/or interpret the followin as they a p p t to LOW REACTOR WATERLEVEL I I I (CFR41.10/43.5/45.13) I AA2.03 Reactor water cleanup blowdown rate._....,............
2.9 2.9 11 295010 Hiah D w e l l Pressure / 5 29501 1 High Containment Temp /
5 295012 High D well S 2.4.44Ability to recognize abnormal 4.O Temperature / ?! r indications for s stem operating arameters F
which are entry eve1 conditions or Emergenc Operating Procedures [related to High Drywelr tern erature]
(CFk: 41.10 143.5 /45.13) 295013 High Suppression Pool 1
Temp. I5 I l l I AA2.03 Ability to determine andor interpret 4.3 the cause of reactivity addition as it applies to inadvertent reactivity addition Ill (CFR: 41.10 /43.5 /45.13)
I 295015 IncompleteSCRAM / 1 29501 7 High Off-site Release Rate / 9 I 295020 Inadvertent Cont.
Isolation / 5 & 7 1 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 5 of 34 NUREG-1021, Draft Revision 9
ES-401 295032 High Secondary Containment Area Temperature /
5 295033 High Secondary ContainmentArea Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure / 5 295036 Seconda Containment High Sump/Area Rater Level / 5 500000 High CTMT Hydrogen Conc. 15 KIA Category Point Totals: Group Point Total: 7 2 3%
W
ES-401 BWR WG-Exarr ation Outline Form ES-401-1 Plar S ;terns - Tier 21 row 1 (RO / SROI WA Topic(s)
A2. Ability to (a) predict the impacts of 3.8 the followln on the INTEkMEDIATE RANGE MONITOR (IRM) 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 / 45.6)
A2.04 Up scale or down scale trips E I 7 of 34 NUREG-1021, Draft Revision 9
- 2. I.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation.
(CFR 43.5 145.12/ 45.13) 2.2.25 Knowledge of bases in TS for limiting.conditions of operations and safe limits [Related to AC Electrical Distri ution I 262002 UPS (ACIDC) 263000 DC Electrical Distribution 2.4.48 Ability to interpret control room indications to veri@ the status and operation of system I and understand how operator action s and directives affect lant and system conditions. Related to EDGs]
(CFR 43.5 145.12f 11 300000 InstrumentAir
+ I 400000 Component Coolina Water KIA Category Point Group Point Total:
Totals:
E-l
ES-401 9 of 34 NUREG-1021, Draft Revision 9
ES-401 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection A2. Abili to a) redict the 3.0 t;y 6 P impactso the olowin on the FIRE FROTECTIO% SYSTEM
- and (b) based on those predictions, useprocedures to correct, control, or mitigate the consequences of those abnormal conditions or operations
(CFR 4 1.5 / 45.6)
A2.03 A.C. distribution failure:
Plant-Specific 290001 Secondarv CTMT 1 2HgvOAOC03 Control Room 290002 Reactor Vessel 2.2.32 Knowledge of the effects 3.3 lnternals of alterations on core configuration.
(CFR: 43.6)
I l l I I/
WA Category Point Totals: Group Point Total:
~
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5:
1 Facilitv: Date of Exam:
+
Category WA# Topic F -SRC 3nIy IR IR - #
1.
Conduct of 2.1.33 Ability to recognize indications for system Operations operating parameters which are entry conditions for TS (CFR 43.2/43.3/45.3) 2.1.14 Knowledge of system status criteria which requires notification of plant personnel
+
(CFR 43.5/45.12) 2.1.
2.1. ~ I Subtotal I
2.2.21 Knowledge of pre and post maintenance 1
- 2. operability requirements.
Equipment (CFR: 43.2)
Control -
2.2.26 I Knowledge of refueling administrative 1 requirements (CFR 45.3145.13) 2.2.
2.2. I Subtotal 2.3.9 I Knowledge of the process for performing a 1 containment purge 3.
(CFR 43.4/45.10)
Radiation Control 2.3.
2.3.
2.3.
2.3.
13 of 34 NUREG-1021, Draft Revision 9
ES-401 2.4.36 Knowledge of chemistry / health physics tasks 1 during emergency operations.
(CFR 43.5)
Emergency Procedures I Plan 2.4.41 Knowledge of the emergency action level thresholds and classifications.
(CFR: 43.5 / 45.1 1)