ML051400345

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Draft Outlines (Folder 2)
ML051400345
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 01/25/2005
From: Berry P
FitzPatrick
To: Conte R
Operations Branch I
Conte R
References
50-333/05-301 50-333/05-301
Download: ML051400345 (36)
v • d • e


Text

ES-401 1

F o

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ES-401-1 Facility:

I J.A. FitzPatrick Date of Exam:

May 16 - 20,2005

3. Generic Knowledge and Notes:
1.
2.
3.
4.
5.
6.

7.*

8.
9.

Ensure that at least two topics from every WA category are sampled within each tier of the RO and 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 i1 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.

Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted or justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES401,, for guidance regarding the elimination of inappropriate WA statements.

Select topics from as 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 K/A 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. Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

i E M 0 1 2

Form ES-401-I ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier l/Group 1 (RO I SRO)

Form ES-401-1 IR WAPE # I Name I Safety Function KIA Toplc(8)

AA1.07 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

+ Nudear Boiler Instrumentation System 62.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4

3. I 8 295003 Partial or Complete Loss of AC / 6 3.7 14 3.6 47 G2.1.8 (ldc/R 55.43.5 - SRO Only)

AbiMy to wodihati? pemnnel artivitie outsiide the mnttvl mom.

AK2.03 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C.

POWER and the following:

+ D.C. bus loads 295004 Partial or Total Loss of DC Pwr I 6 11 3.3 3.9 AA202 (1OCICR 55.43.2 - SRO Only)

Ability to determine anuor inti?pn?t the following as they apply to PARTZAL OR COMPLETE LOSS OF D.C. POWER:

+

AK1.03 Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP:

Extent of pattial or mmplete loss of 0.

C power

+ Pressure effects on reactor level 33 295005 Main Turbine Generator Trip / 3 3.5 45 4.1 -

31 -

G2.2.22 (10CFR 55.43.2 - SRO Only)

Knowldw of limiting mnaitims for opxations and saMy fimits.

1/25/2005 - 8:44:58 AM SRO only K/AS shown in its//cr Page 2

I 2

I ES-401 2

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ES-dl-1 1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO I SRO)

Form ES401-1 I

ElAPE C I Name I Safety Function 295021 Loss of Shutdown Cooling / 4 I

KIA Topic(8)

AK2.01 Knowledge of the interrelations between SCRAM and the following:

+

RPS 62.4.29 (IOCFR 55.43.5 - SRO on/yl Knowledge of tiie emergency plan.

62.1.30 Ability to locate and operate components / includiw local controls.

AK2.01 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

+ System loads AA2.05 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

+ System pressure AA1.04 Abilw to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:

+ Service air isolation valves: Plant-Specific AA1.06 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING:

+ Containment / drywell temperature

~~

SRO only K/As shown in itaiics 4-3 I 38,,

1/25/2005 - 8:27:31 AM Page 3

(

i I

ES401 2

Form ES-41-1 BWR Examination Outline Form ES-401-I Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO I SRO)

ES-401

&APE # / Name / Safety Function 295023 Refueling Acc Cooling Mode / 8 KIA Topic@)

IR K

A 3

1 1

1 AK3.02 Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS:

+ Interlocks associated with fuel handlinq eauiment 3.4 12 295024 High Drywell Pressure I 5 EK3.05 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE:

+

RWflooding 3.5 4.0 15 40 46 62-4-44 (1KFR 55.43.2 - SUO Ontj+)

Knowledge of emergency plan protective action nxornmendations.

295025 High Reactor Pressure / 3 62.2.12 Knowledge of surveillance procedures.

1 3.0 295026 Suppression Pool High Water Temp. I 5 G2.1.18 AbiJity to make accurate / clear and concise logs / records / status boards / and reports.

2.9 76 EA2.01 (1XFR 55.43.2/5 - SUO Ody)

Ability to determihe and/or interpret the following as they apply to SUPPRESSION POOL HIGH WA 7ER TEMPERA NRE:

+ Supprssim pool water temperatun?

4.2 98 N/A for 3AF - KJA for Mark I11 Containments ONLY----------------------

SRO only K/As shown In /ta/icr 1/25/2005 - 8:27:31 AM Page 4

(

1 ES401 2

Form ES-dl-1 E S 4 1 ElAPE # I Name I Safety Function 295028 High Drywell Temperature 15 295030 Low Suppression Pod Wtr Lvl I 5 295031 Reactor Low Water Level 12 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 295038 High off-site Release Rate I 9 K

K 1

2 1

BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 11Group 1 (RO I SRO)

KIA Toplc(s)

EK3.04 Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE:

+ Increased drywell coding EAl.06 Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

+ Condensate storage and transfer (make-up to the suppression pool):

Plant-Specific EA2.02 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:

+

Reactor power EK3.01 Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

+ Recirculation pump trip/runback: Plant-Specific EK2.03 Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:

+ Plant ventilation systems Form ES-401-1 IR 3.6 3.4 4.0 4.1 3.6 -

93 79 74 02 94 1/25/2005 - 8:44:41 AM SRO only K/As shown in italics Page 5

[

f E M 0 1 2

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E S 1 I ES401 1

EIAPE I I Name I Safety Function WA Category Totals: (RO) 1/25/2005 - 8:27:31 AM K

K 2

3 4

4 WNR Examination Outline Emergency and Abnormal Plant Evolutions -Tier I/Group 1 (RO I SRO)

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ES-401-1 KIA Topic(.)

62.1.22 Ability to determine Mode of Operation.

2.8 57 Group Point Total: (RO)

Gmup Point Total: (SRO) 7 SRO only K/As shown in /ts//cr Page 6

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I ES-401 3

Form ES-WJI-I R

BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier f/Group 2 (RO I SRO)

Form ES-401-1 IR 1

UAPE I I Name I Safety Function KIA Topic($)

~

295007 High Reactor Pressure I 3 84 2.9 AA1.02 **Plant OE**

Ability to operate and/or monitor the following as they apply to HIGH DRYWELL PRESSURE:

4 D w e l l floor and equipment drain sumps N/A for JAF - K/A for Marlc III Containments ONLY

---7-.

AK2.02 Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the foltowing:

4 Drywell cooling 295012 High Drywell Temperature I 5 3.6 91 G2.1.20 (IOCIR 55.43.5 - SUO Only)

Ability to eyecute p&u~

skps.

4.2 53 SRO only K/As shown in &tics 1/25/2005 - 8:27:31 AM Page 7

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i E M 0 1 3

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ES-4-1 ES401 WAPE # I Name I Safety Function 295015 Incomplete SCRAM / 1 295029 High Suppression Pool wtr Lvl I5 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment Hgh Differential Pressure I 5 BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier lIGroup 2 (RO I SRO)

Form ES401-1

  • I O 1 2

KIA Toplc(s)

I 1 162.4.20 Knowledge of operational implications of EOP warnings / cautions / and notes.

- - NOTRANDOMLY SELECTED------

-u--

f EA1.01 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

+

HPCI: Plant-Specific 62'4.8 (IOCFR 55A3.5 - SRO OnW)

Knowledge of how the event-based emegerq/abnorma/ operating p/clrcedures an? used in conjundbn with the symptom-&&

EO&.

- - NOT RANDOMLY SELECTED------------

I -I EK2.01 Knowledge of the interrelations between SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following:

+

Process radiation monitoring system 1 62.1.21 Ability to obtain and verify controlled procedure copy.

IR 1

I 3.3 I 92 3-4 I 73 t

3.7 I 59 SRO only K/AS shown in italics 1/25/2005 - 8:27:31 AM Page 8

2 i

ES-401 3

Form ESudl-1 ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1IGroup 2 (RO I SRO)

FOIT~

ES-401-1 K

K WAPE t I Name I Safety Function 500000 High CTMT Hydrogen Conc. I 5 WA Category Totals: (RO)

A A

G 1 1 2 1 I KIA Topic@)

7 EA2.02 (10 CFR 55.43.2 - SRO AbiHy tv determihe and/w interptet the MJowing as they appfy to HIGH PWMRY CON7-AINMENTHYDROGEN CONENJ7U77ONS:

+

Oxygen mnRorthg system svaihbiJ#y I

l l

1R I 3.5 57 I

+

~

~~~~

~

Group Point Total: (RO) 1 7 Group Point Total: (SRO) 1 3 1/25/2005 - 8:27:31 AM SRO only K/AS shown in italics

2 I

1 ES-401 4

Form ES+d-l BWR Examination Outline Plant Systems -Tier ZGroup I (RO I SRO)

FOITII ES-401 26 1

48 43 29 KIA Toplc(s)

= I IR A

A 1

2 1

I System # / Name 1 62.3.4 Knowledge of radiation exposure limits and contamination control /

including permissible levels in excess of those authorized.

2.5 K2.02 Knowledge of electrical power supplies to the following:

+ Motor operated valves 2.5 K5.05 Knowledge of the operational implications of the following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSlEM:

+ Turbine speed control: BWR-2,3,4 A1.07 Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYmM controls including:

+ System discharge pressure: BWR-2,3,4 3.3 3.7 K6.03 Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSlEM:

Torus/suDpression pool water level 3.3 SRO only K/& shown in &lks 1/25/2005 - 8:27:31 AM Page 10

I

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E M 0 1 4

Form ESsd-1 BWR Examination Outline Plant Systems -Tier 2/GrouD 1 (RO I SRO)

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ES-401-1 KIA Topic($)

A3.07 Ability to monitor automatic operations of the STANDBY LIQUID CONTROL SYSTEM including:

6 Lights and alarms: Plant-Specific K3.12 Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION SYSTEM will have on the following:

6 Secondary containment integrity K5.01 Knowledge of the operational implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:

6 Detector operation K6.05 Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM:

6 Trip units IR 3.7 3.2 2.6 3.1 24 32 44 25 -

1/25/2005 - 8:27:31 AM SRO only K/As shown in italics Page 11

ES-401 4

Form ES-WJI-1 K

K 2

3 BWR Examination Outline Plant Systems -Tier ZGroup 1 (RO I SRO)

Form ES-401-1 KIA TopIc(s)

K4.04 Knowledge of SOURCE RANGE MONITOR (SRM) S Y m M design featwe(s) and/or interlocks which provide for the following:

+ Changing detector position A4.05 Ability to manually operate and/or monitor in the control room:

+

SRM back panel switches, meters, and indicating lights A3.05 Ability to monitor automatic operations of the AVERAGE POWER RANGE MOMITOR/LOCAL POWER RANGE MONITOR SYSIEM including :

Flow cortverter/comparator alarms

-0 only K/AS shown in &#cx IR 1

I 1

1/25/2005 - 8~27~31 AM Page 12

f i

ES-401 4

Form ES-WJI-~

P K

K 5

6 I

c P

A 1 -

BWR Examination Outline Plant Systems -Tier ZGroup 1 (RO I SRO)

A A

3 4

1 KIA Toplc(s)

K6.04 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR CORE ISOLATION COOLING SYSEM (RCIC):

+ Condensate storage and transfer system A2.01 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING S Y m M (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

+ System initiation signal 624.16 (IOCFR 55.43.5 - StO Onw)

Kmwkdge of EOP impkmeniatkm hierarchy and modination wth other supprt p&un?s.

A4.02 Ability to manually operate and/or monitor in the control room:

+ ADS logic initiation Form ES-401-1 IR 3.5 3.8 4.0 4.2 -

41 58 64 97 I_

1/25/2005 - 8:27:31 AM

-0 only K/As shown in /talks Page 13

03 03

1 I

ES401 4

Form ES-WJI-I 262001 AC Electrical BWR Examination Outline Plant Systems -Tier ZGroup 1 (RO I SRO)

KIA Topic(8)

A1.O1 Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT S Y m M controls including:

62.4.27 Knowledge of fire in the plant procedure.

+ systemflow A 2 0 1 ( I K F R 55.43.5 - 5RO Onlyl Ability to (a) p m f.. the imp& of the tblowing on the A. C ELECTRIC;IIL OISiT.lBU77ON; and (b) k e d on those p&idionnS, use pmcedures to cv&/

cvntrvb or mitiipte the cvnsquences of thse abnomat cvndtions or operahons:

+

Tuhihe/genemtor ttip A4.01 Ability to manually operate and/or monitor in the control room:

+ Transfer from alternative source to preferred source Form ES-401-1 IR 2.9 3.0 3.6 2.0 56 77 60 87 -

SRO only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 15

2 I

I ES-401 4

FOIITI ES-d-1 ES-401 BWR Examination Outline Plant Systems - Tier 2lGroup 1 (RO I SRO)

F O ~ I ES-401-1 IR -

I 63 System # I Name 263000 DC Electrical Distribution KIA Toplc(s)

K1.04 Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECIRICAL DISTRIBUTION and the following:

+ Grounddetection A3.01 Ability to monitor automatic operations of the D.C. ELECTRICAL DI!3RIBUTION including:

+ Meters, dials, recorders, alarms, and indicating lights 3.2 89 A 2 0 2 (IOCFR 55.43.5 - -0 Om)

AbiMy to (a) p d i d the imp& of the following on the D.C.

ELEMG4L DISlRiBUl7Oh$- and (6) based on r/7ose pw"ions, use prvceduns to cvm wntrvb or mitrigate the wnsquences of those abnormal cvndmns or optations:

+

Loss of ventilabbn dwng charging 62 2.9 264000 EDGs K3.03 Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEUJET') will have on the following:

+ Major loads powered from electrical buses fed by the emergency generator(s)

K2.01 Knowledge of electrical power supplies to the following:

+ Instrument air compressor 4.1 65 90 -

300000 Instrument Air 2.8 SRO only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 16

2 I

i ES-401 4

Form ESvrll-1 b

II ES-401 BWR Examination Outline Plant Systems -Tier 2/GrouD 1 (RO / SROl F

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ES-401-1 K

K 1

2 System # I Name 400000 Component Cooling Water I 1 1 2 1 2 1 KM&atego'y Point Totals:

Knowledge of CCWS design feature(s) and/or interlocks which provide for the following:

+ Automatic start of the standby pump I

I I

I 4131 Group Point Total: (RO) 1 I 26 1/25/2005 - 8:27:31 AM SRO only K/AS shown in its/ics Page 17

i I

ES-401 5

Form ESUdl-1 11 ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO I SRO)

FOITI ES-401-1 I

System1YIName I:

KIA Topic($)

IR A1.01 Ability to predict and/or monitor changes in parameters associated with operating the REACTOR MANUAL CONTROL SYSTEM controls including:

+ CRD drive water flow 2.8 42 K6.02 Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD AND DRIVE MECHANISM:

+ Reactor pressure 201003 Control Rod and Wive Mechanism 3.0 9

I-I -

K5.02 Knowledge of the operational implications of the following concepts as they apply to RECIRCULATION FLOW CONTROL SY!3EM:

+

Feedback signals 202002 Recirculation Flow Control 2.6 17 62.214 (10CFR 55.43.3 - SRO Only]

Knowledge of the prvces for making mnfiguration changes.

3.0 30

_I_

StO only K/As shown in italics 1/25/2005 - 8:27:31 AM Page 18

Sldtl OOOPCZ C-Cf-S3 U O j E

COPS3 I

i

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Form ESUd1-1 2

ES-401 5

BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO I SRO)

Form ES-401-1 I

IR I

System # / Name

= I K/A Topic(8)

_I- -

- NOT RANDOMLY SELE(=TED-------------------

K1.03 Knowledge of the physical connections and/or cause-effect relationships between RADWA5l-E and the following:

+ Reactor building equipment drains: Plant-Specific A2.10 Ability to (a) predict the impacts of the following on the OFFGAS SYSIEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.16 Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

+

Offgas system high flow

+ Instrument malfunctions 268000 Radwaste 2.6 2

271000 Offgas

3. I 19 272000 Radiation Monitoring 2.7 66 SRO only K/AS shown in ita/ics 1/25/2005 - 8:27:31 AM Page 20

I I

I 5

Form ES-dl-1 A:

ES-401 ll ES401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO I SRO)

I1 Form ES401-1

/

I R

/

K/A Topic(8)

K4.01 Knowledge of FIRE PROTECTION S Y m M design feature(s) and/or interlocks which provide for the following:

+ Adequate supply of water for the fire protection system 3.4 20 NOTRANDOMLY w---

1-1 A2.01 Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

+ Personnel airlock failure A2.03 Abillty to (a) predict the impacb of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

+ Initiation/reconfiguratin failure K4.02 Knowledge of REACTOR VESSEL INTERNALS design feature(s) and/or interlocks which provide for the following:

Separation of fluid flow paths within the vessel

+

SRO only K/AS shown in its/lb Group Point Total: (RO) 3.3 85 3.4 71 Group Point Total: (SRO) 1 3 1/25/2005 - 8:27:31 AM Page 21

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

FOIWI ES-401-3 lay 16 - 20,2 A

RO 35 SRO-Only KIA#

Topic I

IR IR 4.3 2.8 3

4 G 2.1.20 Ability to execute procedure steps.

2.1.

G2.1.9 (1OcFR 5543.5 - s;RO mw)

Abillly to d i m pefionnel activities inside the 4.0 -

4.2 23 -

52 3 1 I 62.1.27 Knowledge of system purpose and/or function.

-. I.

I 62.1.20 (locF# 55,43.2/6 -mO on/LI Ability to ewxute procedure steps.

?A NOT RANDOMLY SELECTED-----------

?&

NOT RANDOMLY SELECTED----------

I NOT RANDOMLY SELECT-

?&

1 NOT RANDOMLY SELECT-m 2.6 Subtotal 2

80 -

55 2.2.

62.2.24 **Plant OE**

Abilrty to analyze the affect of maintenance activities on LCO status.

62.2.13 (lOcn0 55.43.5 - -0 on/LI

    • p/ant O**

KmwMge of tagging and dearam G2.2.1 Ability to perform pre-startup procedures for the facility / including operating those controls associated with plant equipment that could affect reactivity.

pmedures.

2.2.

3.7 62.2.29 (1oIcFR 55.43.2/6 - -0 on/y)

Knowledge of SRO fuel bandlihg respnsibiliti&s.

2.2.

62.2.30 3.5 35 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 supportinq instrumentation.

NOT RANDOMLY SELECTE-NOT RANDOMLY SELECTE-NOT RANDOMLY SELECTE-Subtotal SRO only K/As shown in italics 1/25/2005 - 8~32~28 AM Page 22

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

Form ES-401-3 Facility:

J.A. FitzPat -

ck Date of Exam:

May 16 - 20,2 1

RO 05 SRO-Only i 2.9 69 Category KIA #

Topic 18 2.3 62.3.4 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.

2.5 62.3.2 (ZOICFR 55.4.3.24 -mO on/j.)

Knowme of hdt& AMRA pmqram.

62.3.9 Knowledge of the process for performing a containment purge.

KmwMge of the process for preparing a radiation work permit.

2.7 62.3.11 Ability to control radiation releases.

NOT RANDOMLY SELECTED----------

NOT RANDOMLY SELECTE-NOT RANDOMLY SELECTE-

_I 2.5 62.3.7 (10CfR 55.4.3.4 - m0 T

3.3 70 2.3 16 2.3 3 T

Subtota 2.4.

62.4.2 I 3.9 Knowledge of system setpoints / interlocks and automatic actions associated with EOP entry conditions.

62.4.49 (JOCFR 55.43.5 - m0 onlj.)

Abilty to pedorm without reference to procedures those actions that q u i r e immeaiate operation of systm mpunents and 4.0 22 cvntmls.

62.4.26 I

I 2.4.

2.9 72 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usaqe.

NOT RANDOMLY SELECTE-z?

P c

Q)

E w

NOT RANDOMLY SELECTE-NOT RAN WMLY SELECTED----------

--I-NOT RANDOMLY SELECTED----------

- I - -

I -- E rier 3 Point Total SRO only K/AS shown in italics 1/25/2005 - 8:32:28 AM Page 23

ES-401 Record of Rejected WAS Form ES-4014 Tier I Group Randomly Selected WA Reason for Rejection 111 295016 G2.1.5 RO WA 2.5 (2.3), No Plant-Specific Priority 111 295023 AK3.05 Plant-Specific BWR-1 Only 111 295023 AK3.04 No Plant Procedures for Non-Coincident Scram No reasonable link between High Drywell Pressure Emergency Procedures and the facility ALARA Program that is testable at the SRO level 111 295024 G2.3.2 111 295025 G2.2.5 RO KIA 2.5 (1.6), No Plant-Specific Priority 111 295026 G2.1.4 RO WA < 2.5 (2.3), No PlantSpecific Priority 111 295038 EK2.12 Plant-Specific BWR-6 Only 1 I 1 600000 AA2.01 SRO WA < 2.5 (2.3), No Plant-Specific Priority 112 29501 5 G2.4.44 RO KIA < 2.5 (2.1), No Plant-Specific Priority 1 / 2 295035 G2.1.34 RO WA < 2.5 (2.3), No Plant-Specific Priority 112 295035 G2.1.5 RO WA < 2.5 (2.3), No Plant-Specific Priority 211 203000 G2.3.7

~

RO WA < 2.5 (2.0), No Plant-Specific Priority 211

~

RO WA 2.5 (2.2), No Plant-Specific Priority 215003 K5.02 211 21 5004 K4.03 RO KIA < 2.5 (2.4), No Plant-Specific Priority 2 / 1 RO KIA < 2.5 (2.3), No Plant-Specific Priority 223002 G2.3.5 No WAS > 2.5, No Plant-Specific Priority, Randomly Selected Another Category 262002 A1 211 211 No WAS In This Category, Randomly Selected Another Category 300000 A I 211 300000 K5.03 RO WA < 2.5 (2.1), No Plant-Specific Priority 212 20 1 004

~

N/A JAF - All WAS for BWRs-486 Only No Reasonable Link Between RPlS And Radioactive Control Generic WAS 212 214000 G3 2 / 2 226001 K5.01 RO WA < 2.5 (2.2), No Plant-Specific Priority 1/25/2005 - 8106148 AM Page 1

ES401 Record of Reiected WAS Form ES401-4 Tier I Group 212 212 Randomly Selected WA 268000 K1.15 290001 K2 3

G2.1.34 3

G2.2.10 3

G2.2.16 3

G2.2.3 3

G2.2.6 3

G2.2.14 3

G2.2.3 1 111 295024 G.2.3.4 1 I 2 500000 G.2.3.6 Reason for Rejection RO WA < 2.5 (2.3), No Plant-Specific Priority No WAS In This Category, Randomly Selected Another Category RO WA 2.5 (2.3), No Plant-Specific Priority RO WA < 2.5 (1.9), No Plant-Specific Priority RO WA 2.5 (1.9), No Plant-Specific Priority JAF Single Unit - WA for Multi-Unit RO KIA 2.5 (2.3), No Plant-Specific Priority RO WA < 2.5 (2.1), No Plant-Specific Priority RO WA < 2.5 (2.2), No Plant-Specific Priority Rejected On Overlap With Questions 18 And 26. Randomly Selected Another Category WA.

Rejected On No Reasonable Linkage Between High Containment H2 And Knowledge Of Requirements To Review And Approve Release Permits.

1/25/2005 - 8106148 AM Page 2

ES-301 Administratlve ToPics Outline F

o

~

ES-301-1 Facility:

J.A. FitzPatrick Date of Examination: May 16 - 20, 2005 Examination Level (circle one): R8 Operating Test Number:

LOI-05-01 Administrative Topic Type Code (see Note)

Conduct of Operations Conduct 3 of Operations I

Equipment Control N

Radiation Control N

Emergency Plan N, s Describe activity to be performed G2.1.7 (SRO VR: 4.4) AbUw to Wuate phnt perfonncmce 1Md make op.rrdonul/udgmeurlrbared~tin~charscteritics/mcfw b a h s v i o r / a n d i n ~ ~ ~ t a i o n.

Perform Core Thermal Heat Balance Verification (RAP-7.3.03, Section 9.2, Attachment 2)

~~

02.1.25 (SRO m:

3.1) ~billly to oGin 8nd interpret strrdion

~ ~ m ~ t s ~ 1 1 o o r q p h d / m o ~ ~ / a n d t s b (

contain perfonnance dutr.

Determine HPCl High RPV Water Level Trip Setpoint (OP-I 5, Attachment 3) 62.222 (SRO UR: 4.1) Knowledge of llmiting conditions fbr Given a Chemistry Report, Evaluate Technical Specification Compliance (TS 3.4.6, TRM 3.4.8 and Table 3.4.8-1) m o t 3 8 8nd ha.

62.3.4 (SRO UR: 3.1) Kmwb@m of rsdladon expasum limb and contaminatbn contrd/MWngpemisdbie ieveh in excess of thme 8uthorized.

Determine Visitor RCA Access Requirements (AP-07.05, Section 8.1 and Attachments 3 & 5) 62.4.41 (SRO UR: 4.1) Knowledg. of the e m w y action level thmshokib and chss&at&rs.

Classify the Event Following NRC Exam Scenarios l(2)

(IAP-2)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Ir Type Codes & Criteria:

(C)ontrol Room (D)irect from bank (I 3 for ROs; 5 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (r 1)

(P)revious 2 exams (S)imulator 1; randomly selected)

ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 Facility:

J.A. FitzPatrick Date of Examination:

May 16 - 20, 2005 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Safety Function System I JPM Title Type Code*

a.

Verify HPCl Isolation SI A, N 4

b.

Reset PClS Group I Isolation s, D, L, p 5

c.

Re-open MSlVs s, D, L, p 3

d.

Respond to CRD Pump Trip s, A, N 1

e.

Swap FWLC, Single to 3-Element s, N 2

f.

Swap Electrical Bus, Reserve to Normal Service s, M, A 6

3.

Perform APRM Gain Adjustments s, A, p 7

h.

NIA SRO-In-Plant Systemse (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

I.

Remove a HCU from Service 1

All control room (and inplant) systems must be different and serve different safety functions; inplant systems and functions may overlap those tested in the control room.

8 Type Codes (A)lternate (C)ontrol room (D)ired from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank induding l(A)

(P)revious 2 exams (S)imulator

( W A Criteria for RO I SRO-I I SROY 46 I 46 I 2-3

Appendix D Scenario Outline F

o

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ES-D-1 Facility :

J. A. FitzPatrick Scenario No.:

1-1 Op-Test No.:

LOI-05-01 I

I I

I I

I I

I CRS:

SROI-1 1 Examiners:

SROI-2 I

RO:

SURROGATE Initial Conditions: Operating normally at 100% O P Turnover:

Operating normally at 100% CTP; RHR Loop "Alpha" in Torus Cooling Mode; HPCI Surveillance Testing recently completed successfully; Torus Cooling needs to be secured; Then, reduce power to 95% per Reactor Engineer's guidance and perform ST-208.

Event Event No.

Malf. No.

Type*

(Credited Position) / Event Description 1

N (SNO) Shut down Torus Cooling 2

SW04:A TS (CRS) Running RHR/SW Pump Trip (Before S/D) 3 R

(SNO) Power Reduction to 95%

4 I

NMl4(X) 1 I

1 (RO) APRM Fails to Respond to Power Reduction

~-

I ------ [ APRM Bypassed 5

j I

TS I (CRS) APRM Declared Inoperable 6

I I

C I (SNO) NPO Reports EHC Leak; Swap EHC Pumps 7

I RH1O:A I

C 1 (SNO) Torus Rupture in RHR Suction; Level Drops; EOP-5/4 (ALL) Manual Scram; ATWS; SDN Blockage; EOP-3; Level/Power Control 8

1 RD22(A/B) 1 M

1 9

SLOl:A/B C

(RO) SLC Pump Start Failure (NOTE 1) 10 TC02:B C

(SNO) EHC Pump Trip; Turbine Trip; Bypass Valve Failure 11 M

(ALL) Level / Power Control NOTE 1 - SLC initiation is related to the JAF IPE ATWS Dominant Accident Sequence (N)omal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 2.2.2 - SITE AREA

Appendix D Scenario Outline FOITII ES-D-1 Facility:

J. A. FitzPatrick Scenario No.:

1-2 t----i Examiners:

Op-Test No.:

LOI-05-01 CRS:

SROI-3 Operators:

SNO:

SROI-4 RO:

SURROGATE Facility:

3. A. FitzPatrick Scenario No.:

1-3 Op-Test No.:

LOI-05-01 Examiners:

I t------l Facility:

3. A. FibPatrick Scenario No.:

1-4 Op-Test No.:

LOI-05-01 m

F Examiners:

CRS:

SROI-7 SNO:

SURROGATE.

SURROGATE I

ANTICIPATED EAL: 2.2.2 - SITE AREA

LOI-05-01 NRC EXAM SCENARIO 1 NARRATIVE 1

The scenario will begin with the plant operating normally at 100% Core mermal Power. HPCI surveillance testing has just been completed and the Torus Cooling Mode of RHR is to be secured. During the shutdown of the Torus Cooling Mode, the " A RHR/SW pump will trip. Dispatch of the NPO will produce a local report of "A" RHR/SW pump breaker charring. The CRS will declare the RHR/SW Subsystem inoperable. Per Reactor Engineer's guidance, a power reduction to 95% will then be commenced for performance of ST-20B. During the power reduction, "C" APRM will not respond as expected. The APRM will be declared inoperable and bypassed. An NPO performing rounds will report a sizable EHC leak in the running 'A" EHC pump discharge filter. The crew will swap the running EHC pumps isolating the leak. A rupture in the Torus shell will then start a slow reduction in Torus Water Level. AOP-9 may be entered momentarily resulting in immediate direction to enter EOP-4/EOP-5. EOP4 will be entered on low Torus water level and EOP-5 will be entered on High Sump/Floor Water Level in the Crescent Area. Local investigation will reveal that the leak is isolable and isolation actions will commence. Before Torus Water Level reaches 10.75 feet, HPCI will be tripped and a manual scram inserted. Shortly after the manual scram occurs, the leak will be reported isolated. The manual scram will result in a power reduction to 20-30% due to a blockage in the SDN(s). EOP-2 will be entered then exited to EOP-3 resulting in a start of either SLC pump. SLC injection will fail resulting in a manual start of the other SLC pump. The Level/Power Control contingency will be exercised by first terminating and preventing injection sources followed by re-injection at a reduced R W water level. A loss of the remaining EHC pump will result in a turbine trip and a loss of the bypass valves shortly thereafter. This will force transitioning pressure control to the SRV's and trending the approach to the Boron Injection Initiation Temperature (BITT). If BIIT is reached, another Terminate and Prevent will result in RPV water level control at an even lower level. Timely action to complete rod insertion may avoid exceeding BIIT. The control rod insertion success path will require resetting the scram signal, draining the SDN(s) and re-inserting a manual scram. Upon inserting the second manual scram, all control rods will be reported full-in and the scenario will be terminated.

I

ADDendix D Scenario Outline F

o

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ES-D-1 5

6 7

Facility:

J. A. FitzPatrick Scenario No.:

2-1 Op-Test No.:

LOI-05-01 TS (CRS) SRV Inoperable Degraded Containment Cooling on Operating Side EDl8(X)

C (SNO) 10500 / 10600 Bus Loss AD08(X)

C (SNO) Same (Leaking) SRV Opens Mechanically c

Examiners:

9 10 11 CRS:

SROI-2 loperston:

SNO:

SROI-1

~

~

~

MS16(X)

C (SNO) SRV Tailpipe Failure in Torus; EOP-4 RHOl(X) c (SNO) RHR Pump Trip During Torus Spray M

(ALL) RPV Emergency Depressurization I

I RO:

SURROGATE I

initial Conditions: 3% - 5% CTP, Reactor Startup In-Progress Turnover:

Reactor Startup In-Progress at 3 - 5% CTP; Currently at OP-65, Step D.19; Reactor Mode Switch in "Startup"; Continue Power Ascent to 25% CTP Using Control Rods; Reactor Engineer is present in Control Room; "Alpha" Circulating Water Pump Has Just Been Repaired; Start Up "Alpha" CW Pump and Secure "Bravo" CW Pump for Inspection.

Event Event No.

Malf. No.

TY Pe*

(Credited Position) / Event Description 1

N (SNO) Swap Circulating Water Pumps 2

RR19(X)

I (SNO) Selected Level Transmitter Fails Downscale 3

TS (CRS) Level Transmitter Inoperable 4

AD0600 I

(SNO) Inadvertent Safety Relief Valve (SRV) Opening

I AD05(X)

I I SRV Experiences Leakage 8

I I

M I (ALL) Manual Scram; EOP-2 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 3.1.I - ALERT

~~

Atmendix D Scenario Outline Form ES-0-1 Facility:

J. A. FitzPatrick Scenario No.:

2-2 Op-Test No.:

LOI-05-01 Examiners:

SURROGATE I

I Facility:

J. A. FitzPatrick Scenario No.:

2-3 Op-Test No.:

LOI-05-01 Exam hers :

SURROGATE Facility:

J. A. FitrPatrick Scenario No.:

2-4 Op-Test No. :

LOI-05-01 SURROGATE Examiners:

SURROGATE ANTICIPATED EAL: 3.1.1 - ALERT

LOI-05-01 NRC EXAM SCENARIO 2 NARRATIVE The scenario will begin with a reactor startup in progress at 3-5% Core Thermal Power. Turnover information will indicate that repairs to the 'A' Circulating Water Pump have just been completed. Crew will be directed to place the 'A' CW pump in service and secure 'B'.

The "selected" Reactor Water Level Transmitter will fail downscale resulting in a slow rise in RPV Water Level. The crew will take manual control of RPV water level, swap level columns and return to automatic level control. The CRS will declare the failed transmitter inoperable. An inadvertent ADS SRV opening will result in actions to place Toms cooling in service and remove the SRV fuses. Fuse removal will close the SRV; yet it will continue to have pilot valve leakage that slowly worsens. The CRS will declare the SRV inoperable. A 4160 VAC bus loss will remove / degrade the containment cooling functions of the loop in Torus Cooling. Continued SRV leakage will result in mechanical opening of the SRV (industry OE) requiring the crew to manually scram the reactor. The crew will enter and perform EOP-2. The leaking SRV tailpipe will start leaking into the Torus air space resulting in EOP-4 entry. Torus spray will have to occur on the opposite RHR loop; and shortly after initiation, the only RHR pump in that loop will trip unexpectedly. This will force the crew to conclude that an Emergency Depressurization (contingency) is or will soon be required. The scenario will terminate upon the opening of 7 ADS valves.

ADnendix D Scenario Outline Form ES-D-1 m

l Facility :

3. A. FitzPatrick Scenario No.:

3-1 CRS:

Op-Test No.:

LOI-05-01 Examiners:

    • MODIFIED CONTINGENCY SCENARIO FROM LOI-03-01 EXAMINATION**

I I

I I I Operators: 1 SNO:

1 2

RFI EP09 RFI HP15 C

Seismic Event (Cry Wolf RFP Turbine Vibration Alarm)

(SNO) HPCI Power Supply Loss (Aux Oil Pump, MOV)

TS (CRS) HPCI Inoperable l

l I

RO:

5 6

Initial Conditions: 75% CTP RP13 (Pre)

RD 13(X)

(ALL) Main Steam Line Break in Turbine Building (w/ Failure to (RO) One (1) Control Rod Fails to Scram MSO5 Auto-Isolate, Manual Scram); EOP-2 C

Turnover:

Alpha Circulating Water Pump Just Repaired and Returned to Service; Return Power to 92% Using Recirculation Flow; Hold at 92% for Reactor Engineers Ramp Guidance.

Event No.

1 Malf. No. I Fz 1 (Credited Position) I Event Description

-~

3 I

MCOl 1

C I ( S N 0 ) <ow Loss of Condenser Vacuum 4

I I

R I (SNO) AOP-Required Power Reduction 7

I I ------ I RCIC for Level Control; SRVs for Pressure Control (Note 1/2) 8 1

AD07(X) 1 I/C I (SNO/RO) Several SRVs Fail to Open NOTE 1 - RCIC is an IPE Risk-Reduction System NOTE 2 - Use of RCIC for level Control Upon HPCI Failure is an IPE Key Operator Action (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ANTICIPATED EAL: 8.4.4 - ALERT

ADDendix D Scenario Outline F

o

~

ES-D-1 Facility:

J. A. FitzPatrick Scenario No.:

3-2 Op-Test No.:

LOI-05-01 Examiners:

Faciltty:

3. A. FitzPatrick Scenario No.:

3-3 Op-Test No.:

LOI-05-01 Examiners:

LOX-05-01 NRC EXAM SCENARIO 3 NARRATIVE The scenario will begin with the reactor at 75% Core Thermal Power. A seismic event will result in several failures starting with a 'crywolf' RFP Turbine alarm on high vibration. Vibration will be slightly elevated and monitored by the crew.

The following event will be a HPCI power supply loss that will disable HPCI. The CRS will declare HPCI inoperable. The crew will then notice a slow loss of condenser vacuum and perform the AOP actions including a power reduction using recirculation flow. The major event will be a Main Steam tine Break in the Turbine Building that will fail to automatically isolate. A manual scram will be inserted followed by manually isolating the steam lines. During the scram, one control rod will fail to scram but will be inserted using RMCS. RCIC will be operated for Level Control and the SRVs will be operated in Pressure Control.

Several SRVs will fail to open forcing alternative SRV selection. The scenario will terminate upon stabilization of Pressure and Level Control.

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