ML041750149

Final Outlines (Change Summaries - Optional)

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 111 2/2 314 1 12 Oyster Creek Written Exam; SRO Portion 295006iAA2.06 286000/A2.0 I 2.4.41 29501 212.4.16 Verifying rod position following a Scram is done during the operating test. This WA would be oversampling in the written exam.

No plant-specific logic failure identified as testable material.

Classification for EP done on Operating Test.

This WA is better tested on Operating Test and is expected to be Dart of one of the scenarios.

I( Tier/ I Randomly Grow Selected WA 311 2.1.25 Reason for Rejection This WA is better tested on a JPM.

21 1 11; 259002lA2.03 This WA is better tested during the Operating Test. Licensee agreed to have a level input event in one of the scenarios.

-12.1.5 112 I This KIA is better tested on a JPM.

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295015/AA2.02 Oversampling of ATWS between RO and SRO exams.

312 I 2-2.16 and is of low significance for SRO (2.6). In the SRO amlicants will take both exams.

313 2.3.7 1

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 /

Group 1 /2 211 1 / I 2/2 3/1 312 211 211 2/2 Randomly Selected WA 295033/EK2.04

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264000/K1.03

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295031/EA1.01 230000/K6.09 2.1.10 2.2.2 259002/A2.03 205000/A1.05 239001/AI.05

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Reason for Rejection

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SGTS is oversampled considering Operating Test Scenarios and JPMs exercise SGTS. SGTS also examined in Questions# 23 and 70.

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There is no fire protection associated with the emergency diesel aenerators.

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.

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.

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.

This K&A is more appropriately tested during the Operating Test.

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.

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.

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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 Facilitv:

Date of Exam:

I RO WA Cateaorv Points 1

4 2

3 2

2 2

1 3

1 4

2 2326 2

1 0

2 2

2 1

1 1

2 0

0 4312

2.

Plant 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 3-21 0 3

3 7

7 I.

ES-401 Note: 1.

2.

3.

4.

5.

6.*

7.

h.

I.

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 finalRO exam must total 38875 points and the SRO-only exam must total 25 points.

Select topics from many systems and evolutions; avoid selecting more than two-er the 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 I O 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 thefR8applicable license level, and the point totals for each system and category.-lW&ebw 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.

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 of 34 NUREG-1021, Draft Revision 9

ES-401 I,

ES-401 Emergency 11 UAPE # I Name I Safety Function 295001 Partial or Com lete Loss of Forced core FIOW Circulation ?I & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr/6 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 295016 Control Room Abandonment I 7 iination Outline FO~I ES401-'

utions - Tier I/Group 1 (RO I SRO)

WA Topic@)

2.1.33 Ability to recognize indications for system operating pa.rameters which are entry-level conditions for technical s ecifications.

(8FR: 43.2 / 43.3 / 45.3)

AA1. Ability to operate and/or monitor the 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 plant shu Y down.......

AA2. Ability to determine and/or interpret 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.

AKI. Knowled e of the operational im lications o?the folkwin concepts as they apply to MAIN GENERATOR TRIP :

(CFR: 41.8 to41.10)

AKI.Ol Pressure effects on reactor Dower.

TU RBI ii~

AK2. Knowled e of the interrelations between S C d M and the following:

(CFR: 41.7 / 45.8)

AK2.03 CRD hydraulic system...

AK2. Knowled e of the interrelations between CONYROL ROOM ABANDONMENT and the following:

(CFR: 41.7 / 45.8)

AK2.02 Local control stations: Piant-Specific...

7 IR -

3.4 4.4 3.5 4.0 3.7 4.0

295023 Refueling ACC Cooling Mode / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 ES-401 AK1. Knowled e of the operational im lications o4he fokwin PARTIAT OR EOMPLETE L O ~ S OF COMPONENT COOLING WATER :

(CFR: 41.8 to 41.10)

AKI.01 Effects on componentlsystem operations.6 conce ts as they a ply to 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 following respcnses as they a ply to PARTIAL OR COMPLETE INSTRUMENT AIR :

(CFR: 41.5 / 45.6)

LOSS OF AK3.02 Standby air compressor operation.

2.1.22 Ability to determine Mode of

? eration.

,63FR: 43.5 / 45.13) 3 2. Ability to determine and/or interpret

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:

'lant-Speci F IC.

fK3. Knowledge of the reasons for the ollowing responses 1s the apply to HIGH REACTOR

>RESS~;RE.

CFR: 41.5 I45.6) iK3.06 Alternate rod insertion: Plant-Specific..

3.5/

3.4 3.5 2.8 3.9 4.2*

5 of 34 NUREG-1021, Draft Revision 9

295027 High Containment TemDerature I5 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 EK3. Knowledae of the reasons for the 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)

EA1. Ability to operate and/or monitor the 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 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 following as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.7 / 45.6)

EAI. Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.7 / 45.6)

EA1.03 Low pressure Core Spray System.

EK1. Knowled e of the operational implications oAhe EK1.02 Reactor water level effects on reactor power.

EKI. Knowled e of the operational im lications o?the folkwin conce ts as the apply to HIGH (CFR: 41.8 to41.10)

EKI.Ol Biological effects of radioisotope ingestion.

OFF-SI~E RELEASE RA+E :

ES-401 3.91 3.7 3.9 3.5 4.4*

4.1*

2.5

ES-401 600000 Plant Fire On Site / 8 WA Category Totals:

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7 of 34 NUREG-1021, Draft Revision 9

ES-401 ES-401 BWR SExamination Outline Form ES-401-'

Emeraencv and Abnormal Plant Evolutions - Tier l/Group 2 (RO / SRO) 11 UAPE # / Name I Safety Function 295002 Loss of Main Condenser 295007 Hiah Reactor Pressure I 3 295008 High Reactor Water Level I 2 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure 15 29501 1 High Containment Temp I 5

295012 High D Temperature I Y

295014 Inadvertent Reactivity Addition / 1 11 29501 5 Incomplete SCRAM I 1 295020 Inadvertent Cont.

Isolation / 5 8 7

1) 295022 Loss of CRD Pumps / I 295029 High Suppression Pool II Wtr Lvl / 5 WA Topic(s)

AA2. Ability to determine andlor interpret the following as (CFR: 41.10 / 43.5 / 45.13) ap I to HIGH DRYWELL

%dPEP,JJRE AA2.02 Drywell pressure.

AK3. Knowledge of the reasons for the following respo'nses as the a I to HIGH SUPPRESSION (CFR: 41.5 145.6)

POOL TEJ~~RATURE AK3.02 Limiting heat additions.

AK2. Knowled e of the interrelations between HI G 80 FF-SITE RELEASE RATE and the following:

(CFR: 41.7 / 45.8)

AK2.03 Off-gas system.

3.9 3.6 3.3

295032 High Secondary Containment Area Temperature /

5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 I

I 295035 Seconda Containment High Differential gessure / 5 295036 Seconda Containment High Sump/Area Xater Level / 5 500000 High CTMT Hydrogen WA Category Point Totals: u ES-401 EA1. Abilitv to oDerate and/or monitor the EA1.03 Secondanr containment ventilation..

EK3. Knowledge of the reasons for Emergency Depressurization as it applies to (CFR: 41.7 1 45.8)

EK3.01 High Secondary Containment Radiation Levels.

EK1. Knowled e of the operational implications o P the EKI.01 Personnel protection.

EK3. Knowledae of the reasons for the following respoYnses as they ly to SECONDARY CONTAINME???) HIGH DIFFERENTIAL PRESSURE *

(CFR: 41.5 / 45.6)

EK3.01 Blow-out panel operation: Plant-Specific..

Group Point Total:

3.7 9 o f 3 4 NUREG-1021, Draft Revision 9

ES-401

ES-401 ES-401 System # / Name 203000 RHR/LPCI:

Injection Mode 205000 Shutdown Cooling 206000 HPCl 207000 Isolation (Emergency) Condenser 3m fR8 ation Outline ID 1 (RO / SROl 11 of 34 Form ES-401-1 WA Topic(s)

K1. Knowledge of the physical connections andlor causeeffect relationships between SHUTDOWN C O O L I N G S Y S T E M ( R H R SHUTDOWN COOLING MODE1 and the followin :

(CFR: 41.290 41.9 / 45.7 to 45.8)

K I.05 Component cooling water systems.

A2 Abili to redict the impact on the S H U T D 8 d COOLING SYSTEM RHR SHUTDOWN COOLING rSIODE) o eration from:

(8FR: 41.5 / 45.5)

A2.09 Low Reactor water level K1. Knowledge of the physical connections and/or causeeffect 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 3.1/

3.4 3.8/

3.5 NUREG-I 021, Draft Revision 9

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K l. Knowledge of the physical connections and/or causeeffect relationshi s between LOW PRESSURE~ORESPRAY SYSTEM and the followin -

(CFR: 41.2 to 47.b / 45.7 to 45.8)

KI.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.

K2. Knowledge of electrical power su plies to the 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 / 45Jj K3.03 Core plate differential pressure indication.

K3. Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.05 RPS logic channels K4.01 Rod withdrawal blocks.

K5. Knowledge of the operational imolications of the followin conce ts as the ap I to SYSTEM :

SOUR& R A N ~ E MONIT~R (gib)

[CFR:41.5 / 45.3)

K5.03 Changing detector position ES-401 3.7/

3.3 3.1/

2.6*

3.7 3.7 2.8

13 of 34 K6. Knowledge of the effect that a 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 t h e A U T O M A T I C DEPRESSURIZATION SYSTEM :

of the fol 7 owing on and (b) based on those redictions, use procedures to correc!

control, or mitigate the consequences of those abnormal conditions or o erattons:

(8FR: 41.5 / 45.6)

A2.06 ADS initiation signals present A4. Ability to manually operate 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 imriications of the followin conce ts as they apply to VALVES (CFR: 41.'5 / 45.3)

RELIEIJSAFETV 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 operations of the REACTOR WATER LEVEL CONTROL SYSTEM including:

(CFR: 41.5 / 45.6)

A3.06 Reactor Water level setpoint setdown following SCRAM.

ES-401 3.7 4.2 3.6 3.31 3.1 3.0 NUREG-I 021, Draft Revision 9

261000 SGTS changes in SYSTEM controls including:

(CFR: 41.5 / 45.5) arameters associated with o eratin L e STANDBY GAS TREATMEN?

I K4. Knowled e of (INSTRUMENT AIR SYSTEd design featuye(s (CFR: 41.7)

K4.02 Cross-over to other air systems 1 and or interloc )k s which provide 2 or the

' following:

262002 UPS (AC/DC) I 263000 DC Electrical Distribution f

I A4. Ability to manually operate I and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

I I A4.03 Local operation of breakers I 2.1.30 Ability to locate and operate components / including local controls.

(CFR: 41.7 145.7)

A.4 Ability to manually operate and/or monitor in the control room:

(CFR 41.7/45.5)

A4.03 Battery discharge rate: Plant-Specific I

I K1. Knowledae of the Dhvsical connections Znd/or caush effect relationshi s between EMERGENCY I GENERAfORS (DIESEUJET) and the followin :

1 (CFR: 41.290 41.9 / 45.7 to 45:8)

K1.03 Fire protection system.

I 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 ES-401

400000 Component F

Cooling Water WA Category Point Totals:

2.91 2.5 K3. Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:

(CFR: 41.7 145.6) 2 2

6 I 4

K3.01 Loads cooled by CCWS I l l 2.2.25 Knowled e of bases. in limits.

(CFR: 43.2) technical s ecifica 9 ions for limiting conditions P or operations and safety Group Point Total:

ES-401 15 of 34 NUREG-1021. Draft Revision 9

ES-401 F

4 c

t I ES-401 Form ES-401-Mine (RO / SRO)

WA Topic@)

K6. Knowled e of the effect that a loss or mal 9 unction of K6.02 Condensate storage tanks K4. Knowled e of REACTOR MANUAL CO~TROL SYSTEM 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 PLANT L 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 MINIMIZER ~YSTEM (RWM)

K3. Knowledae of the effect that 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 the RECIRCULATION FLOW CONTROL SYSTEM will have on followin.

(CFR: 4. 7 / 45.4)

K3.02 Reactor power.

a loss or mal 9 unction of K l. Knowledge of the physical connections and/or causeeffect relationshi s between REACTOR WATERCkANUPSYSTEMand the followin :

(CFR: 41.290 41.9 / 45.7 to 45.8)

K1.01 Reactor vessel.

3.0 3.3 3.2 3.9 4.0 3.1

ES-401 17 of 34 NUREG-1021, Draft Revision 9

ES-401 268000 Radwaste 271 000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation (I 290001 Secondary CTMT 290003 Control Room 11 HVAC 290002 Reactor Vessel II lnternals 11 KIA Category Point Totals:

A3. Ability to monitor automatic o erations of the OFFGAS SkTEM including:

(CFR: 41.7 145.7)

A3.03 System temperatures A2. Ability to (d the RADIATION MOkfITORING 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) redict the impacts of the 2 P o lowin on A2.07 H dro en injection operation: 8 lant-pecific.

Group Point Total:

2.8 2.6

ES-401 ES-40 I Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-53 Date of Exam:

Topic Facility:

Category I -

IR 3nly WA #

2.1.2 knowledge of operator responsibilities during all modes of operation.

(CFR: 41.10 / 45.13) 3.0 2.9

1.

Conduct of Operations 2.1.12 Ability to apply TS for a system.

(CFR: 43.1 145.13) 2.1.23 Ability to perform specific system and integrated plant procedures during different modes of operation.

(CFR: 41.10 / 43.5 145.12) 3.9 Subtotal controls associated with plant equipment that could affect reactivity.

(CFR:

45.1) 3.7

2.

Equipment Control 2.2.1 1 Knowledge of the process for controlling temporary changes.

(CFR: 41. I O / 43.3 / 45.13)

Knowledge of refueling administration requirements (43.5145.131 2.2.26 2.5 2.5 I

Subtotal 2.3.2 Knowledge of facility ALARA program.

(CFR: 41.12 143.4 145.9 145.10) 2.5

3.

Radiation Control 2.5 2.3.9 Knowledge of the process for performing a containment purge.

(CFR: 43.4 / 45.10)

I 9 of 34 NUREG-I 021, Draft Revision 9

4.

Emergency Procedures /

Plan Tier 3 Point Total I

t Subtotal 2.4.29 2.4.50 Knowledge of the emergency plan.

(CFR: 43.5 / 45.1 1)

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

(CFR: 45.3)

Subtotal 2.6 3.3 ES-401 t-i-

1 I

ES-401 0

0 4

4 0

0 2

2 0

0 6

6 0

0 1

3 0

0 1

0 0

2 4

ES-401 BWR ffte-Examination Outline Form ES-401-1 8

4 12 4

I 2

6 I Facility:

Tier L Emergency Abnormal Plant Evolutions Date of Exam:

RO WA Category Points

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SRO-Only Points

ES-401 h

ES-401 Emergency E/APE # / Name / Safety Function 295003 Partial or Complete Loss 11 ofAC16 295004 Partial or Total Loss of DC Pwr 16 295005 Main Turbine Generator 11 Trip I 3 295006 SCRAM / 1 295016 Control Room (I Abandonment I 7 29501 8 Partial or Total Loss of CCWl8 29501 9 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling 295023 Refueling Acc Cooling Mode 18 295024 High Drywell Pressure I 5 I/ 295025 High Reactor Pressure 13 295026 Suppression Pool High Water Temp. I 5 295027 High Containment II Temperature / 5 BWR i

&Examination Outline Form ES-401-ant Evolutions -Tier l/Group 1 (RO I SRO)

I I

9l"l 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 41.10/43.5 145.13)

AA2.01 Powerlflow map8 2.1.33 Ability to recognize indications of DC System o erating parameters which are entry level for.Fs.

(CFR 43.2 I 43.5 / 45.3)

I I

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.

2.2.27 Knowled e of the refueling process.

(CFR 43.6 / 45. f3)

EA2. Ability to determine and/or interpret the followin as (CJR fl.10 / 43.5 / 45.13) the ap Ky to HIGH DRYWELL PRESSURE:

I I EA2.02 Drywell temperature.

3.5 3 of 34 NUREG-I 021, Draft Revision 9

295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2

295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I I 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 KIA Category Totals:

I I

S 2.4.20 Knowledge of operational implications of EOP warnings / cautions / and notes.

(CFR 41.10 /45.13) m S

EM. Ability to determine and/or interpret the as the apply to REACTOR LOW WATER (CFR:4i.10/43.5/45.13) followlng L E V E ~.

I I EA2.02 Reactor power.

S 2.4.27 Knowledge of fire in the plant rocedure.

P CFR 41.10/43.5/45.13)

Group Point Total:

ES-401

ES-401 1

ES-401 E/APE # / Name / Safety Function Emergency ana II 295007 High Reactor Pressure / 3 295008 High Reactor Water Level I 11 295010 Hiah D w e l l Pressure / 5 29501 1 High Containment Temp /

5 295012 High D well Temperature / !!?

295013 High Suppression Pool Temp. I5 1

I 29501 5 Incomplete SCRAM / 1 29501 7 High Off-site Release Rate / 9 295020 Inadvertent Cont.

II Isolation / 5 & 7 11 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 BWF jR4Examination Outline Form ES-401-1 Plant Evolutions - Tier l/Group 2 (RO / SRO) 1 2 41AIGI WA Topic(s)

I IR S 2.4.31 Knowledge of annunciators alarms and indications / and use of the response instructions.

(CFR41.10/45.3) 3.4 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 S 2.4.44 Ability to recognize abnormal 4.O indications for s stem operating arameters Operating Procedures [related to High Drywelr tern erature]

(CFk: 41.10 143.5 /45.13) which are entry r eve1 conditions F or Emergenc I l l I

AA2.03 Ability to determine andor interpret the cause of reactivity addition as it applies to inadvertent reactivity addition (CFR: 41.10 /43.5 /45.13)

I l l 4.3 5 of 34 NUREG-1021, Draft Revision 9

ES-401 295032 High Secondary Containment Area Temperature /

5 295033 High Secondary Containment Area 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 2 3%

KIA Category Point Totals:

Group Point Total:

7 W

ES-401 Plar BWR WG-Exarr S ;terns - Tier 21 E

7 of 34 ation Outline row 1 (RO / SROI Form ES-401-1 WA Topic(s) >

A2. Ability to (a) predict the impacts of 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) 3.8 A2.04 Up scale or down scale trips I

NUREG-1021, Draft Revision 9

I 262002 UPS (ACIDC) 263000 DC Electrical Distribution 11 300000 Instrument Air I+

400000 Component Coolina Water KIA Category Point Totals:

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 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 Group Point Total:

ES-40 I 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 290001 Secondarv CTMT 11 2HgvOAOC03 Control Room 290002 Reactor Vessel lnternals WA Category Point Totals:

I/

A2. Abili to a) redict the

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) impactso t;y the 6 P olowin on the FIRE FROTECTIO% SYSTEM A2.03 A.C. distribution failure:

Plant-Speci fic 3.0 2.2.32 Knowledge of the effects of alterations on core configuration.

(CFR: 43.6) 3.3 I

l l

I Group Point Total:

ES-401

~

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-5:

Facilitv:

Date of Exam:

Category WA# 1 Topic SRC -

IR 3nIy F

IR +

1.

Conduct of Operations 2.1.33 Ability to recognize indications for system 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

1 1

2.2.21 Knowledge of pre and post maintenance operability requirements.

(CFR: 43.2)

2.

Equipment Control 2.2.26 I Knowledge of refueling administrative 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 (CFR 43.4/45.10) 2.3.

2.3.

2.3.

2.3.

3.

Radiation Control 13 of 34 NUREG-1021, Draft Revision 9

ES-401 Emergency Procedures I Plan 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations.

(CFR 43.5) 2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR: 43.5 / 45.1 1) 1