ML070820358

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Final - Outlines (Folder 3)
ML070820358
Person / Time
Site: Pilgrim
Issue date: 02/20/2007
From:
NRC Region 1
To:
Entergy Nuclear Operations
Sykes, Marvin D.
Shared Package
ML060800104 List:
References
Download: ML070820358 (20)
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Text

ES-401 BWR Examination Outline Form ES-401-1 RO WA Category Points Group K1 K2 K3 K4 I K5 I K6 A I A2 A3 I A4 G* Total Tier

1.

1 4

3 4

5 2

1 I 9 2

1 2

2 1

8 1

1 NIA Emergency Abnormal Evolutions Totals N/A Plant Tier 5

5 6

6 3

2 27

2.

1 5

4 2

(

3 3

1 0

4 1

2 1

~

26 Plant 2

1 0

0

/

1 1

2 2

0 2

2 1

(

12 T

i e

r 5

4 2

4 4

3 2

4 3

4 2

3 8

Systems Totals Abilities Categories

~

10

3. Generic Knowledge and 1

2 3

4 4

2 2

2 SRO-Only Points A2 G*

Total 3

5 8

2 2

4 5

7 12 2

2 4

0 1 0 2

2 2

4 6

1 2

3 4

1 2

2 2

Note:

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 outline (i.e., the Tier Totals in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.

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 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

Select topics from many systems and evolutions; avoid selecting more than two KIA topics from a given system or evolution unless they relate to plant-specific Driorities.

Systems/evolutions within each group are identified on the associated outline.

~

~~

The shaded areas are not applicable to the categoryltier.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A.

Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the KIA 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.

NU REG-I 021 1

ES-401 Pilgrim 2007 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier I Group 1 Form ES-401-1 I

4.2 I 76 Conduct of Operations: Ability to execute procedure 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC I 6 X

4.0 77 -

78 Conduct of Operations: Ability to apply technical Conduct of Operations: Ability to perform specific modes of plant operation.

1 x 1 I I

295006 SCRAM / 1 4.0 Emergency Procedures I Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295021 Loss of Shutdown Cooling I 4 l x I I I

2.4.4 79 -

80 4.3 4.4 I

I I

I

~

~-

Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

Drywell pressure 295024 High Drywell Pressure I 5 I

I I

I EA2.01 Ability to determine andlor interpret the following as they apply to SCRAM Condition Present and Power Above APRM Downscale or Unknown: Containment conditions/isolations 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295028 High Drywell Temperature I 5 X

295030 Low Suppression Pool Water Level / 5 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 EA2.07 4.2 81 Conduct of Operations: Ability to execute procedure I 4.2 I 82 Ability to determine and/or interpret the following as LEVEL : Reactor pressure EA2.03 they apply to LOW SUPPRESSION POOL WATER 3.9 83 3.1 -

4.4 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Jet pump operability: Not-BWR-1&2 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER : Systems necessary to assure safe plant shutdown 39 -

40 AA2.05 AA1.03 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 X

295005 Main Turbine Generator Trip I 3 X

41 -

42 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the following: D.C. bus loads Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP : Pressure effects on reactor level AK2.03 AKI.03 NUREG-1021 2

ES-401 Form ES-401-1 Pilgrim 2007 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 43 X

AK2.05 Knowledge of the interrelations between SCRAM and the following: CRD mechanism Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT : Disabling control room controls 3.1 3.5 3.2 3.5 3.9 3.4 295006 SCRAM I 1 295016 Control Room Abandonment I 7 44 AK3.03 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER : Placing standby heat exchanger in service AK3.05 45 295018 Partial or Total Loss of CCW I 8 Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

Standby air compressor operation Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING : Adequate core cooling 46 AK3.02 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4 T-48 -

49 X -

AKI.03 X

EK2.01 Knowledge of the interrelations between HI SECONDARY CONTAINMENT AREA TEMP and the following: Arealroom coolers Ability to operate andlor monitor the following as they apply to HIGH DRYWELL PRESSURE:

Suppression pool spray: Mark-l&ll I

295032 HI Secondary Containment Area Temps I 8

~

295024 High Drywell Pressure I 5 I

295025 High Reactor Pressure I 3 3.8 50 -

51 EA1.12 X

Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE : Pressure effects on reactor power 3.9 EKI.01

~

~

Ability to operate andlor monitor the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Sumression Pool cooIin(l 52 -

53 EA1.01 4.1 3.7 295026 Suppression Pool High Water Temp. I 5 295028 High Drywell Temperature I 5 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

Reactor water level Knowledge of the reasons for the following responses as they apply to LOW SUPPRESSION POOL WATER LEVEL: Emergency depressurization Knowledge of the operational implications of the following concepts as they apply to REACTOR LOW WATER LEVEL: Adequate core Cooling X -

EA2.03 295030 Low Suppression Pool Water Level I 5 EK3.01 54 3.8 4.6 55 -

X -

EKI.01 295031 Reactor Low Water Level I 2 3

NUREG-IO21

ES-401 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 Emergency Procedures / Plan Knowledge symptom 3,,

2'4'6 1 based EOP mitigation strategies.

Pilgrim 2007 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 56 Form ES-401-1 295038 High Off-site Release Rate I 9 (1

E/APE#/ Name Safety Function I G 1 K I 1 K2 1 K3 I A I 1 A2 1 Number 1 KIA Topic(s)

I Imp. I Q# I1 Ability to operate andlor monitor the following as monitoring system.

X EA1.01 they apply to high off-site release rate: Stack gas 3.9 57 1 600000 Plant Fire On-site I 8 1

3.0 1 58 I Ability to operate and / or monitor the following as I

I I

I 1 x 1 I A A 1

  • O 6 I they apply to PLANT FIRE ON SITE: Fire alarm

~~

~

I K/A Category Point Totals:

I 2/5 I 4 -1 3

T 4 I 5 I 2/3 I GrGPoint Total: I NUREG-I 021 4

ES-401 Pilgrim 2007 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-401-1 E/APE # / Name Safety Function I G I K1 I K2 I K3 I A I I A2 I Number I WA Topic(s)

I Imp. I Q# 11 Emergency Procedures I Plan Knowledge of which events related to system operationskitatus should be reported to outside agencies.

2.4.30 3.6 84 295010 High Drywell Pressure I 5 X

Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

Dtywell temperature Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

85 295012 High Drywell Temperature I 5 295029 High Suppression Pool Water Level I 5 3.9 3.7 AA2.01 2.2.25 86 Ability to determine and I or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Combustible limits for drywell 500000 High CTMT Hydrogen Conc. I 5 EA2.03 3.8 87 Emergency Procedures/Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following:

Recirculation system 2.4.49 47 4.0 3.1 295007 High Reactor Pressure I 3 295009 Low Reactor Water Level I 2 AK2.03 59 Ability to operate andlor monitor the following as they apply to HIGH SUPPRESSION POOL TEMPERATURE : Suppression pool cooling Knowledge of the interrelations between INADVERTENT REACTIVITY ADDITION and the following: RPS 3.9 60 295013 High Suppression Pool Temperature I 5 295014 Inadvertent Reactivity Addition I 1 AA1.01 AK2.01 3.9 61 I

l l

Ability to determine andlor interpret the following as they apply to INCOMPLETE SCRAM : Control rod position Knowledge of the reasons for the following responses as they apply to INADVERTENT CONTAINMENT ISOLATION: Drywelllcontainment temaerature resaonse 295015 Incomplete SCRAM I 1 AA2.02 4.1 62 295020 Inadvertent Cont. Isolation I 5 & 7 I I I I Y AK3.03 63 -

64 3.2 3.7 Knowledge of the reasons for the following responses as they apply to LOSS OF CRD PUMPS:

Reactor SCRAM Knowledge of the operational implications of the following concepts as they apply to HIGH SUPPRESSION POOL WATER LEVEL :

Containment integrity AK3.01 295022 Loss of CRD Pumps I 1 X

295029 High Suppression Pool Water Level I 5 I

I x I I EKI.01 65 -

3.4 5

NUREG-I 021

Y I

Y 0

t ci, W

E L

0 LL nl Q

3 6

ES-401 215003 IRM 215004 Source Range Monitor Pilgrim 2007 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 x

Form ES-401-1 262001 AC Electrical Distribution 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCl I System #/Name I G I K1 I K2 I K3 I K4 I K5 1 K6 I A I I A2 I A3 I A4 I Number I KIA Topics I

Imp. I Q# )I x

X 206000 HPCl 209001 LPCS 21 1000 SLC 21 1000 SLC X

X X

Ability to (a) predict the impacts of the following on the INTERMEDIATE 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: Faulty range switch 3.2 88 Equipment Control Knowledge of bases in technical specifications for limiting conditions for ooerations and safetv limits.

2.2.25 3.7 89 -

90 91 261 000 SGTS I Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High train temperature Conduct of Operations: Ability to apply technical specifications for a system.

A2,03 2.1.12 3.2 4.0 Knowledge of electrical power supplies to the K2.03 following: Initiation logic 2.7 1

Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor temperatures (moderator, vessel, flange)

K3.03 3.8 2

X Ability to manually operate andlor monitor in the control room: Turbine speed controls A4.01 1

3.8 3 -

4 -

5 -

6 3.2 Knowledge of electrical power supplies to the following: System valves: BWR-2,3,4 Knowledge of the physical connections andlor cause-effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following: A.C. electrical power K2.01 K1.08 3.2 Knowledge of the physical connections and/or cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:

RWCU K1.05 3.4 X

Ability to manually operate and/or monitor in the A4.01 1 control room: Tank level 3.9 7 -

NUREG-I021

F I 7 0

B co W

E b LL In 7

R l a c9 N

x In 9

E X

x x

--I-

+

x X

X x

0 (0 9 o

oc 0

0 0

0 0

0 N

N z

5 B 4.

Form ES-401-1 Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design feature(s) andlor interlocks which provide for the following:

Manual and automatic control of the system Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations
High Fuel Pool ventilation radiation:

Plant-Specific Knowledge of the physical connections andlor cause-effect relationships between A.C.

ELECTRICAL DISTRIBUTION and the followina: Off-site Dower sources ES-401 3,5 3.2 3.4 Pilgrim 2007 NRC Written Examination Outline Plant Systems - Tier 2 Group I K4.12 A2.12 K1.03 A2.01 K2.01 K3.03 K5.01 A2.03 K1.02 System #/Name I G I K1 1 K2 I K3 I K4 I K5 1 K6 1 A I 1 A2 I A3 I A4 I Number I WA Topics I Imp. I Q# I

~~~~

Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEUJET) will have on following: Major loads powered from electrical buses fed by the emergency generator@)

Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air ComDressors 4.1 2.5 259002 Reactor Water Level Control 18 19 X

261000 SGTS 20 -

21 262001 AC Electrical Distribution Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Under voltage Knowledge of electrical power supplies to the following: Major D.C. loads 2.6 262002 UPS (ACIDC)

X 3.1 22 263000 DC Electrical Distribution 23 264000 EDGs

~~

300000 Instrument Air 24 -

25 26 Ability to (a) predict the impacts of the following on the CCWS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Highllow CCW temoerature 400000 Component Cooling Water 2.9 X

400000 Component Cooling Water Knowledge of the physical connections and l or cause-effect relationships between CCWS and the following: Loads cooled by CCWS 3.2 2614 WA Category Point Totals:

3 3

412 NUREG-1021 9

ES-401 3.3 4.0 3.2 2.8 3.2 2.7 3.0 3.1 3.4 2.8 3.3 Form ES-401-1 92 93 27 28 29 30 31 32 33 34 35 Pilgrim 2007 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 1 G 1 K I 1 K2 1 K3 1 K4 I K5 I K6 I A I 1 A2 1 A3 I A4 1 Number 1 System #/Name WA Topics 1

Imp. 1 Q# 1 K1.I 1

A3*09 1 x 1 204000 RWCU Knowledge of the physical connections andlor cause-effect relationships between RHWLPCI:

CONTAINMENT SPRAY SYSTEM MODE and the following: Component cooling water systems Ability to monitor automatic operations of the REACTOFirrURBlNE PRESSURE REGULATING SYSTEM including:

ControVaovernor valve operation 286000 Fire Protection 201002 RMCS 239001 Main and Reheat Steam 201006 RWM 204000 RWCU I

I 215001 Traversing In-core Probe I

/

215002 RBM

tt I

I 216000 Nuclear Boiler Inst.

I I x 226001 RHWLPCI: CTMT Spray Mode 241000 Reactornurbine Pressure Regulator I

I

~

Knowledge of procedures relating to emergency response to sabotage 24.28 I 2.1.23 2.1.28 Ability to perform specific and integrated plant procedures during all modes of plant operation Conduct of Operations: Knowledge of purpose and function of major system components and controls K5.05 A1.O1 Knowledge of the operational implications of the following concepts as they apply to Main and Reheat Steam system: Flow Indication Ability to predict andlor monitor changes in parameters associated with operating the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) controls including: Rod position: P-SpedNot-BWRG)

K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER CLEANUP SYSTEM : CRD hydraulics: Plant-Specific Ability to manually operate andlor monitor in the Ability to monitor automatic operations of the Four rod display: BWR-3,4,5 K4.03 Knowledge of the Nuclear Boiler Instrumentation design features andlor interlocks which provide for the following:

Redundancy of sensors.

NUREG-I021 10

ES-401 System #/Name G

K1 K2 K3 K4 K5 K6 A I A2 A3 A4 Number KIA Topics 256000 Reactor Condensate X

Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CONDENSATE SYSTEM controls including: Hotwell level Knowledge of the effect that a loss or malfunction of the following will have on the RADIATION MONITORING SYSTEM : AC power Ability to operate andlor monitor in the control room: Start and Stop fans

.04 K6.03 272000 Radiation Monitoring X

A4.0, 228000 Plant Ventilation Form ES-401-1 Imp.

Q#

2.9 36 2.8 37 3.1 38 K/A Category Point Totals:

I 1/2, 1, 0, 0, 1, 1, 2, 2, 010, 2, 2, Group Point Total: I NU REG-I 02 1

, 1212,

11

KIA #

RO SRO-Only IR I Q#

IR I Q#

Topic Knowledge of less than one hour technical specification action statements for systems.

Ability to make accurate, clear and concise loas. records. status boards. and reoorts.

2.1 2'1'18 3.8 94 2.9 66 2'1'8 2'1.25 3.8 67 Ability to coordinate personnel activities outside the control room.

Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain 2.8 68 Facility:

Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures I Plan Tier 3 Point Total 2.1'2 performance data.

Knowledge of operator responsibilities during all modes of plant operation.

3.0 69 NUREG-I 021 12 Subtotal 2.2.25 Knowledge of bases in technical operations and safety limits.

Knowledge of the effects of alterations on Knowledge of the refueling process.

Knowledge of the process for determining the internal and external effects on core reactivitv.

specifications for limiting conditions for 2.2.32 core configuration.

2.2.27 2.2.34 4

1 3.7 95 3.3 96 2.6 70 2.8 71 2.4'1 2.4.5 2.4.2 coolant system integrity 4. Containment conditions 5. Radioactivity release control.

Knowledge of annunciator response procedures.

Knowledge of the organization of the operating procedures network for normal, 2.9 74 abnormal, and emergency evolutions.

Knowledge of system set points, interlocks and automatic actions associated with EOP 3.9 75 entry conditions.

3.1 100 Subtotal 2

2 10 7

201 Oo5 K5.02 295028 Tier /

Randomly Reason for Rejection Group Selected WA System does not exist at facility. Randomly reselected 239001 K5.05 Impossible to meet KA Topic requirement at SRO level. Randomly 212 111 211 212 211 211 211 211 Ill Ill 212 1 / 1 1 / I 1 / I 212 1 / I 1 / I 1 / I 1 / I 111 211 211 212 G2.1.27 262001 reselected G2.1.20 for APE.

Impossible to meet KA Topic requirement at SRO level. Randomly G2.1.30 272000 K6.01 206000 A4.11 212000 K5.01 reselected G2.1.12 for system.

No effect between systems, either directly or indirectly. Randomly reselected K6.03 for system Component does not exist at facility. Randomly reselected A4.03 for system. Subsequently randomly selected A4.01 for same reason.

Concept does not apply to facility. Randomly reselected K5.02 for system 217000 A2.17 261000 A2.14 295005 AKI.02 295024 EA2.03 286000 Action does not exist at facility. Randomly reselected A2.09 for topic No action for condition at facility. Randomly reselected A2.12 for topic Not applicable to facility. Randomly reselected AKI.03 for topic Impossible to meet topic requirement at SRO Level. Randomly reselected EA2.01 for topic Impossible to develop question applicable to facility. Randomly G2.2.26

    • 295019 reselected G2.1.23 for topic Topic area not directly or indirectly pertinent to system. Randomly reselected 2.1.I4 295001 295007 2.4.49 4.0 IQ. #47) This moved a TI G7 topic fo a TI 6 2 topic Impossible to meet KA Topic requirement at SRO level. Randomly reselected G2.1.28 295005 G2.1.20 (4.2) for APE. (Q. #76)

Impossible to meet KA requirement at SRO level. Randomly reselected NUREG-I 021 13 AA.2.04 201002 G2.1.14 295025 EA. 2.04

    • 295038 295003 G2.1.12 (4.0) for'system. (Q. #77)

Topic area not directly or indirectly pertinent to system. Randomly reselected G2.1.28 (3.2) for system. (Q. #27)

Double jeopardy with question #83. Randomly reselected 295037 EA2.07 (4.2) for system. (Q. #81)

No operational valid question could be written for the topic. Randomly EKI.01 295023 AK2.03 295026 EA1 -03

    • 204000 A2.11 21 1000 reselected EA 1.01 for topic (Q. #57) This moved a T I K7 to a T I A7 fopic Double jeopardy with Q. #19. Randomly reselected 295032 EK2.01 (3.5) for Q.#49 No operational valid question could be written for the topic. Randomly reselected EA 1.01 for topic (Q. #52)

Operational valid SRO level question could not be written for topic. Randomly reselected G2.4.28 (3.3) (Q. #92) This moved a T2 A2 to a T2 G topic Operationally valid question could not be written for topic. Randomly K1.02 239002 reselected K1.05 (Q:# 6)

Operational Valid question at RO level could not be written for topic.

2.2.25 216000 2.2.25 Randomly reselected K1.05. (Q.#16)

Operational Valid question at RO level could not be written for topic.

Randomly reselected K4.03. (Q.#33)

295031 2.2.22 I /I Operational Valid question at RO level could not be written for topic.

Randomly reselected EKI.01. (Q.#55)

NUREG-I021 14

ES-30 I Administrative Topics Outline Form ES-301-1 Examination Level (circle one):

RO / SRO Operating Test Number:

Conduct of Operations Conduct of Operations

~

Describe activity to be performed JPM - Perform a Short Form Heat Balance Comparison WA:

2.1.7 (4.4)

Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

JPM - Verify AOG Recombiner OperationlDirect Field Monitoring WA:

2.1.25 (3.1)

Ability to obtain and interpret station reference materials such as graphs / monographs / and tables which contain performance data.

Equipment Control Radiation Control N

JPM:

WA:

2.2.13 (3.8)

Knowledge of tagging and clearance procedures Review a danger tagoutrremporarily lift tags JPM:

Re4 Er-Lk-hynNC N

Red-*

' MCTE R-4 L r t L q WA:

2.3.10 (3.3)

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

I I WA:

2.4.44 (4.0)

I JPM:

Perform Dose Assessment Using DAPAR Software rgency plan protective action ire only 4 items unless they are

  • Type Codes & Criteria:

(C)ontrol room (D)irect from bank (s 3 for ROs; I for SROs & RO retakes)

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

(P)revious 2 exams (s 1; randomly selected)

(S)imulator NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Examination Level (circle one):

RO / SRO Operating Test Number:

N N

N Describe activity to be performed

~

JPM - Perform a Short Form Heat Balance WA: 2.1.7 (3.7)

Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation.

JPM - Verify AOG Recombine Operation WA:

2.1.25 (2.8)

Ability to obtain and interpret station reference materials such as graphs / monographs / and tables which contain performance data.

JPM:

Prepare danger tagout for FPC system WA:

2.2.13 (3.6)

Knowledge of tagging and clearance procedures (3.6).

_i_i Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan NOTE:

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

  • Type Codes & Criteria:

(C)ontrol room (D)irect from bank (I 3 for ROs; I for SROs & RO retakes)

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

(P)revious 2 exams (I 1; randomly selected)

(S)imulator JPM:

ROe 6FcTLYAYD R

s m

m WA: 2.3.10 (2.9)

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

NUREG-1021, Revision 9

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

PNPS Date of Examination:

2/2007 Exam Level (circle one):

RO / SRO(I) / SRO (U)

Operating Test No.:

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Code*

System 1 JPM Title tain Primary Containment In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Safety Function 1

2 6

4 8

3 9

5 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

9 / - 8 /

4

> l / : l/\\l

- 1 / - 1 / - 1 22/,2/-

1 5 3 / :

3 1s 2 (randomly selected) 2 1 / - 1 / - 1 (E)mergency or abnormal in-plant NUREG-I 021, Revision 9

Appendix D Scenario Outline Form ES-D-1 Event Malf. No.

Event No.

Type*

Facility:

PILGRIM Scenario No.:

2 Op Test No.:

2007 NRC Examiners:

Operators:

initial Conditions:

Power is 2.5% with a startup in progress.

2.2.96, Attachment 15, preset checks are done on all feed pumps.

Event Description 0

Two Condensate pumps in service. Running additional second 0

condensate pump to wear it in.

Override - mode switch in RUN (mode switch failure) 2 3

4 5

Turnover:

N - CRS Transfer RMS to run.

NM21 E I-RO APRM " E fails downscale. (TS)

RD02 RDO 22 - 23 N/A C - RO C - RO N - BOP In service CRD flow control valve fails closed. (AOP)

Control rod 22 - 31 drifts outward. (TS) (AOP)

RFP 'A' intermittent TBCCW leak, place RFP 'B' in service.

Startup in progress from a refuel outage IAW PNPS 2.1. I. At 5% power, transfer RMS to run and resume pulling control rods.

"B" secondary condensate pump is being run to wear it in.

11 Critical Task:

Initiates ARI.

It Emergency Depressurization.

1 I N/A I R - RO I Pull rods to continue power ascension.

6 1

I I - BOP I RWCU Pump 'A' RBCCW Temp High, pump fails to auto trip.

7 I PC02 I M - ALL I RWCU leak leading to scram. (EOP)

RM07 a

RP14A I-RO Manual scram failure. ARI required.

9 RM07 M - ALL RWCU leak leads to Emergency Depressurization. (EOP - C) 10 I RH04B I c - BOP I SRV "B" fails to oDen.

fl (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Awendix D Scenario Outline Form ES-D-1 6

7 Facility:

PILGRIM Scenario No.:

4 Op Test No.:

2007 NRC Examiners:

Operators:

MS14D M-ALL RH04B C - BOP D SRV fails open. Manual reactor scam. (AOP) (EOP)

PASS H2/02 Sample valves fail to Isolate.

Initial Conditions:

Power is 100%.

HPCl 00s for Aux Oil Pump Replacement - 14 Day LCO.

RBCCW Pump A (P-20%) OOC, Tracking LCO.

LPRM 36-1 3-B is bypassed.

Turnover:

Shift TBCCW Pumps in preparation for vibration checks on B Pump.

Lower power to 90% for control rod pattern adjustment.

Critical Task:

Spray Drywell.

II Emergency Depressurization.

Event No.

Event Description 1

N 7

A

~~

~

~

~

~

p Shift TBCCW Pumps in preparation for vibration checks on B Pump.

2 1 NIA

-(R-RO 1 Reduce power with Recirc.

y p I T - A r 1 LPRM 36-45-8 fails upscale. (TS) (AOP) 4 1

T C 0 6 1 TBOP I EPR Pressure Oscillations. (TS) (AOP) 5 I RR20A I I - RO I B Recirc Flow Controller fails upscale. (TS) (AOP)

S I

I C - BOP I RBCCW to A RHR HX inlet valve fails shut.

D SRV tail pipe fails leading to Emergency Depressurization.

I pc22 IM-ALL I (EOP - C)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Event Type*

R-RO Facility:

PILGRIM Scenario No.:

3 Op Test No.:

2007 NRC Examiners:

Operators:

Event Description Insert control rods to lower reactor power to 50%

11 Initial Conditions:

0 Power is -55%.

1 2

3 4

5 6

7 8

9 10 0

Defeat Group V Isolation N/A N/A RR1 1A RR04B RD05A RRI 3A RR13B TC06 TCO 1 0

HPCl 00s for Aux Oil Pump Replacement - 14 Day LCO.

I - RO C-RO C-RO 0

0 LPRM 36-13-B is bypassed.

RBCCW Pump A (P-202A) OOC, Tracking LCO.

6 Recirc Loop flow unit failure (TS)

A CRD Pump Trip. (AOP)

A RRP Inner Seal Failure. A RRP Outer Seal Failure. (AOP) (TS)

Turnover:

C-RO C-RO Insert control rods to lower reactor power to 50% for emergency backwash.

The first two steps of the RPR array have been inserted.

First squib valve fails to open when fired.

RWCU M080 fails to isolate automatically.

Seawater Pump B amps are elevated. Remove Seawater Pump B from service and perform emergency backwash.

Engineering is standing by in the screen house to determine when to secure the backwash.

Critical Task:

Inject SLC.

I r

p Prevent all injection into the vessel except from SBLC and CRD.

II Insert all control rods via manual scram.

Remove Seawater pump B from service for emergency N-BoP I backwash.

C - RO I A RRP Dump motor vibration high.

p~

C - BOP I RCIC Steam Leak, failure to auto isolate. (TS)

M -ALL I Main Turbine Trio. ATWS. (EOPI

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