ML090290246

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Final Outlines (Folder 3)
ML090290246
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/30/2008
From:
Calvert Cliffs
To:
Operations Branch I
Hansell S
Shared Package
ML082600339 List:
References
TAC U01779
Download: ML090290246 (20)
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Text

ES-401 PWR Examination Outline Form; s-4016 dl Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRCr-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall n:)t be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by f l 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.
3. Systemslevolutionswithin each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specificsystems/evolutionsthat are not include4 on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
4. 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.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Usr the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevar to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G on the SRO only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

PWR Examination Outline ES-401 Form ES-401-2 Emergency and -

1 ElAPE # / Name I Safety Function I! A 2

G KIA Topic(s) IR #

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A 000007 (CE/E02)Reactor Trip -

Stabilization - Recovery I 1 EE(2.03 - Reactor trip status panel 3.5 I 000008 Pressurizer Vapor Space AK1.02 - Change in leak rate with change in Accident I 3  ? pressure 3.1

- -

000009 Small Break LOCA I 3 EK3.26 - Maintenance of RCS subcooling X 4.4 -

2.2.44 - Ability to interpret control room indications to verify the status and operation 00001 1 Large Break LOCA I 3 ofa system, and understand how operator 4.2 actions and directives affect plant and system conditions.

1 000015/17 RCP Malfunctions I 4 I AK2.07 - RCP seals 2.9 1 000022 Loss of Rx Coolant Makeup I 2 I AA1.03 - PZR level trend 32 AK1.01 - Loss of RHRS during all modes of I 000025 Loss of RHR System / 4 operation 39 000026 Loss of Component Cooling Water I 8 I 2.2.40 - Ability to apply technical Specifications for a system. 34

_

1 000029 ANVS I 1 I EA1.08 - Reactor trip switch pushbutton 45 1 000038 Steam Gen. Tube Rupture I 3 I: 1 EK1.01 - Use of steam tables 31 000040 (CEIEOS) Steam Line Rupture -

Excessive Heat Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater I 4 CK- 2.4.45 - Ability to prioritize and interpret the obtain desired operating results during abnormal and emergency situations.

41 32 EK3.02 - Actions contained in EOP for loss 000055 Station Blackout I 6 of offsite and onsite power 43 Y AA2.73 - PZR heater odoff 35 AA1.06 - Manual control of components for 000057 Loss of Vital AC Inst. Bus 16 35

- which automatic control is lost AA2.01 - That a loss of dc power has 000058 Loss of DC Power I 6 X occurred; verification that substitute power 31 sources have come on line AA2.01 - Cause and effect of low-pressure 000065 Loss of Instrument Air I 8 instrument air alarm 29

~_______ ~

000077 Generator Voltage and Electric AK2.06 - Reactor power Grid Disturbances I 6 3.9 1 KIA Category Totals: I 3 I 3 I 3 I 3 I 3 I Group Point Total:

1 ES-401 PWR Examination Outline Form ES-401.gI -

I - 4 0 1 PWR Examination Outline

-

Form ES-401-2 IR

-

-2.9

-3.4 3.9

-3.7 2.8 000074 (W/E06&E07) Inad. Core Cooling I 4 4.0

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CE/A13 - Natural Circ. I 4 instrumentation, signals, interlocks, 3.0 odes, and automatic and manual 3.0

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4.2

-

- 9

ES-401 PWR Examination Outline Form ES-401- 41

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1 ES-401 PWR 1 amination Outline

~p 1- Reactor Operator Form ES-401-2 1

v System # I Name K/A Topic(s) #

003 Reactor Coolant Pump K6.14 - Starting Requirements 2.6 2.1.3 1 - Ability to locate control room switches, controls, and H

003 Reactor Coolant Pump X indications, and to determine that 4.6 they correctly reflect the desired plant lineup.

K5.14 - Reduction process of gas concentration in RCS: vent-accumulated non-condensable gases from PZR bubble space, 004 Chemical and Volume depressurized during cooldown or 2.5 Control by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)

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K5.02 - Need for adequate 005 Residual Heat Removal 3.4 subcooling 006 Emergency Core Cooling I I A3.04 - Cooling water systems 3.8 K2.02 - Valve operators for 006 Emergency Core Cooling 2.5 accumulators 007 Pressurizer ReliefIQuench Tank I I K3.01- Containment 3.3 K2.02 - CCW pump, including 008 Component Cooling Water 3.0 emergency backup I--

2.4.1 - Knowledge of EOP entry 008 Component Cooling Water X condition and immediate action 4.6 steps.

010 Pressurizer Pressure Al.06 - RCS heatup and cooldown 3.1 Control effect on pressure 012 Reactor Protection I I K6.10 - Permissive circuits 3.3 013 Engineered Safety K1.18 - Premature reset of ESF 3.7 Features Actuation actuation K4.04 - Cooling of control rod 2.8 022 Containment Cooling drive motors K3 .O 1 - Containment equipment subject to damage by high or low 2.9 022 Containment Cooling temperature, humidity, and pressure 026 Containment Spray 4.2

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2.2.37 - Ability to determine 026 Containment Spray 3.6 safety related equipment.

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PWR Examination Outline Form ES-401-2 1 II 1 1 1 ES-401 PWR Examination Outline 41 Form ES-401--

ES-401 PWR Examination Outline Form ES-401- - d1 ES-401 PWR Examination Outline Form ES-401-2

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000015/17 RCP Malfunctions / 4 I

-

-

1 ES-401 PWR Examination Outline Form ES-401-2 1 It ES-401 I 'R Ex tion Outline Form ES-401-2 Emergency and Abnormal F it Evc 4

I WA Topic(s)

E/APE # / Name / Safety Function 1 000001 Continuous Rod Withdrawal / 1 I AA2.04 - Reactor power and its trend 4.3 2.4.1 - Knowledge of EOP entry 000003 Dropped Control Rod / 1 3.6 conditions and immediate action steps.

00005 1 Loss of Condenser Vacuum 1' I AA2.01- Cause of low vacuum condition 2.4.20 - Knowledge of operational I 2.7 I I-000033 Loss of Intermediate Range NI / 7 X implications of EOP warnings, cautions, 4.3 and notes.

1 KIA Category Point Totals: 2 II2 Group Point Total:

1 4 1

I ES-401

- I ll PWR Examination Outline Form ES-401-.dI -

1 ES-401 PV amination Outline Form ES-401-2 I I I r System # I Name WA Topic(s) IR

I 005 Residual Heat Removal A2.02 - Pressure transient protection during cold shutdown 3.7 2.1.45 - Ability to identify and 013 Engineered Safety interpret diverse indications to X 4.3 Features Actuation validate the response of another indication.

A2.08 - Flow rates expected from 06 1 AuxiliaryEmergency various combinations of AFW 2.9 Feedwater pump discharge valves w

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073 Process Radiation 2.4.6 - Knowledge of EOP 4.7 Monitoring mitigation strategies.

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A2.01 - Air dryer and filter 078 Instrument Air malfunctions

-2.9 0 2 Group Point Total:

- 5

1 G 1 1 PWR Examina :ion Outline 11 ES-401 K

PW Examination Out1 stems - '

K K A A A A G

>erator WA Topic(s)

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Form ES-401-2 IK 4 5 6 1 2 3 4 A2.04 - Effects on axial

-

flux density of control rod alignment and sequencing, X xenon production and 3.8 decay, and boron vs.

control rod reactivity changes -

A2.17 - Malfunction of X electrohydraulic control 2.9 2.2.31 -Ability to

-

X determine operability

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and/or availability of 4.6 safetv related eauinment.

0 0 Group Point Total:

- 3

ES-401 Generic Knowledge & Abilities Outline Form ES-401 Facility: Calvert 08 Category KIA # Topic RO 2.1.3 2.1.17 I Knowledge of shift or short-term relief turnover practices.

I Ability to make accurate, clear, and concise verbal reports

+P- 3.9 I - I -

1.

Conduct 2.1.44 Knowledge of RO duties in the control room during fuel of Operations handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations. and supporting instrumentation.

+"-

2.1.20 Ability to interpret and execute procedure steps.

2.1.40 I Knowledge of refueling administrative requirements.

Subtotal 2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

2. 2.2.17 Knowledge of the process for managing maintenance Equipment activities during power operations, such as risk Control assessments, work prioritization, and coordination with the transmission system operator.

2.2.43 Knowledge of the process used to track inoperable - I -

alarms.

~~ ~

Subtotal 2 1 2.3-4 2.3.1 1 II Knowledge of radiation exposure limits under normal or emergency conditions.

Ability to control radiation releases.

I 3.2 I 1 - 1 -

3.

Radiation 2.3.14 Knowledge of radiation or contamination hazards that Control may arise during normal, abnormal, or emergency conditions or activities.

~

r ~~ ~ ~~

2.3.6 Ability to approve release permits. 3.8

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2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey 3.1 instruments, personnel monitoring equipment, etc.

Subtotal 3 2 -

2.4.3 I Ability to identify post-accident instrumentation. 3.7 2.4.5 Knowledge of the organization of the operating

4. procedures network for normal, abnormal, and emergency 3.7 Emergency F

evolutions.

Procedures I ~~

Plan 2.4.1 1 Knowledge of abnormal condition procedures.

2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm.

I Subtotal 1 2 Tier 3 Point Total 7

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ES-401 Record of Rejected WAS Form ES-401-4 -1 Randomly Reason for Rejection Selected K/A Replaced 029, EA1.02 with 029, EA1.08. WA EA1.02 is an inappropriate match for the E/APE # selected. CCNPP standard EA1.02 post-trip actions for an ATWS do not include boration from the RWST.

Replaced 025, K3.01 with 022, K3.01. Calvert Cliffs does not 025 have ice condensers.

Replaced K2.02 with K3.04. Calvert Cliffs does not have an K2.02 Integrated Control System.

Replaced A3.01 with A3.02. Calvert Cliffs Reactor Coolant A3.01 Waste Evaporators are retired-in-place 2.1.43 Replaced 2.1.43 with 2.1.19. Poor WAmatch to system Replaced KJA 2.4.26 with WA 2.4.1. WA 2.4.26 is an inappropriate match for the E/APE # selected. WA 2.4.26 pairel 2.4.26 knowledge of facility fire protection with a Dropped Control Rod. WA 2.4.1 pairs knowledge of EOP entry conditions and immediate action steps with a Dropped Control Rod.

Replaced 005 AA2.01 with 051 AA2.01 due to over sampling of 005 AA2.01 CEA Malfunctions.

Replaced KJA 2.4.26 with 2.2.37. WA 2.4.26 is an inappropriat match for the E/APE # selected. WA 2.4.26 paired knowledge of facility fire protection with Area Radiation Monitoring. WA 2.4.26 2.2.37 pairs the ability to determine operability and/or availability of safety related equipment with Area Radiation Monitoring.

CCNPP LOI-2206Retake Exam Data ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Date of Exam: December 10,2008 -

I I II Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by *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.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do na apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutionr that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. 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.
5. Absent a plant-specific priority, only those VAShaving 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.
6. Select SRO topics for Tiers 1and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicablr K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in othwr than Category A2 or G* on the SRO-only exam, enter it on the lei? side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

CCNPP LOI-2206Retake Exam Data Tier l/Group 1- Reactor Ope #ator K/A Imp Vision Cognitive #

E/APE # / Name / Safety Function Topics # ID Level 000007 (CE/EO2) Reactor Trip - Stabilization - Recovery / 1 EK2.03 3.5 420274 B 3 1(

000008 Pressurizer Vapor Space Accident / 3 AK1.02 3.1 450851 N 2 21 000009 Small Break LOCA / 3 EK3.26 4.4 426519 B 1 000011 Large Break LOCA / 3 I 2.2.44 I 4.2 000015/17 RCP Malfunctions / 4 I AK2.07 I 2.9 000022 Loss of Rx Coolant Makeup 1 2 AA1.03 3.2 53 000025 Loss of RHR System / 4 AK1.O1 3.9 420393 I B I 2 I  !

000026 Loss of Component Cooling Water / 8 2.2.40 3.4 450770 M 1 1 000029 ATWS 1 1 EA1.08 4.5 450651 M 2 27 000038 Steam Gen. Tube Rupture / 3 EK1.O1 3.1 423208 B 2 2, 000040 (CEIEO5) Steam Line Rupture - Excessive Heat 2.4.45 4.1 450950 N 3 53 Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4 EK3.3 3.2 428472 B 2 12 000055 Station Blackout / 6 EK3.02 4.3 440704 B 1 <

000056 Loss of Off-site Power / 6 AA2.73 3.5 418107 B 2 t5

~~

000057 Loss of Vital AC Inst. Bus / 6 AA1.06 3.5 450852 N 2 25 000058 Loss of DC Power / 6 AA2.01 3.7 451132 N 2 23 000065 Loss of Instrument Air / 8 AA2.01 2.9 451150 M 2 000077 Generator Voltage & Electric Grid Disturbances / 6 AK2.06 3.9 450730 N 1 7 Tier l/Group 2- Reactor OPI!rator E/APE # / Name / Safety Function K/A Tooics Imp

Vision ID Type Cognitive Level -- #

000059 Accidental Liquid RadWaste Rel. / 9 AA2.02 2.9 450933 I N I 2 I 13 000061 ARM System Alarms / 7 AK3.02 3.4 000067 Plant Fire On-site / 8 I 2-2-42 I 3.9 000068 (BW/A06) Control Room Evac. / 8 AK2.02 3.7 000069 Loss of CTMT Integrity / 5 AA1.03 2.8 1 I I i  ;

000074 (W/E06&E07) Inad. Core Cooling 1 4 EA2.06 4.0 440348 B 2 :4 CE/A13 - Natural Circ. / 4 CE/A16 Excess RCS Leakage / 2 I AK1-2 I 3.0 CE/E09 Functional Recovery I m1.1 I 4.2 425068 B

CCNPP LOI-2206 Retake Exam Data -

CCNPP LOI-2206Retake Exam Data Tier 2 / Group 2 - Reactor Operator

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E/APE # / Name / Safety Function 001 Control Rod Drive 027 Containment Iodine Removal 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpDurbine Bypass Control 055 Condenser Air Removal

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056 Condensate 068 Liquid Radwaste

~ ~

+A- b4.02 K5.07 K1.06 2.4.6 A3.02 I

1 2.6 Vision ID 451032 451130 451050 428225 428429 451033 1

I Type N

B N

B B

I I

Cognitive Level 3

1 2

2 3

1 I

Exan E3 L l i2

3 21 071 Waste Gas Disposal K3.04 I 2.7 451051 I N I 2 I ;1 I 434432 I I 1

~~ ~

086 Fire Protection K4.02 3.0 B 1 ;8

CCNPP LOI-2206Retake Exam Data I Tier 1/ Group I - Sr. Reactor Operator -

4ifF Vision Cognitive E/APE # / Name / Safety Function ID Level Exan #

000015/17 RCP Malfunctions / 4 89 14) 000027 Pressurizer Pressure Control System Malfunction / 3 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater / 4 AA2.10 2.4.23 AA2.01 I 3.6 77 :2) 000062 Loss of Nuclear Svc Water / 4 CE/EO2 Reactor Trip - Stabilization - Recovery / 1 Tier 1/ Group 2 - Sr. Reactor Operator E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal / 1 AA2.04 Imp 4.3 Vision I D 419089

- Type -

B Cognitive Level 1

-- 82 (7)

~

--

000003 Dropped Control Rod / 1 2.4.1 3.6 451078 B 1 8:! (8) 000051 Loss of Condenser Vacuum AA2.01 2.7 441651 M 2 88 (13)

.-

000033 Loss of Intermediate Range NI / 7 2.4.20 4.3 451082 N 2 87 (12)

-

Tier 2 / Group 1 Sr. Reactor Operator E/APE # / Name / Safety Function Imp Vision I D

Type Cognitive Level 3 99 (24)

005 Residual Heat Removal A2.02 3.7 451100 N 013 Engineered Safety Features Actuation I 2.1.45 1 4.3 I 451076 I N I 3 I 81) (5) 061 Auxiliary/Emergency Feedwater I A2.08 1 2.9 I 451098 I N I~~

2 I 93 (22)

~~ ____~

073 Process Radiation Monitoring 2.4.6 4.7 451110 M 2 1C') (25) 078 Instrument Air A2.01 2.9 451097 M 2 9F (21)

CCNPP LOI-2206 Retake Exam Data Tier 2 / Group 2 - Sr. Reactor Operator Cognitive E/APE # / Name / Safety Function K/A Topics Imp

  1. -TypVision e*I D --

015 Nuclear Instrumentation A2.04 3.8 451079 N 3 85 10)

-

045 Main Turbine Generator A2.17 2.9 425257 B 2 95 20)

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072 Area Radiation Monitoring 2.2.37 4.6 451073 N 2 79 (4)

A Generic Knowledge & Abilities

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K/A Imp Vision Cognitive #

Category Topics # ID Type Level RO 2.1.3 3.7 450870 N 1 I9 RO 2.1.17 3.9 426067 B 1 3 Conduct of Ops RO 2.1.44 3.9 450934 N 1 14 SRO 2.1.20 4.6 445189 0 1 94 (19)

SRO 2.1.40 3.9 420627 B 1 7( (1)

RO 2.2.1 4.5 425936 B 2 32 Equipment Control RO 2.2.17 2.6 451170 N 1 34 SRO 2.2.43 3.3 451099 N 1 9E (23)

~-

RO 2.3.4 3.2 417947 B 1 70

"

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RO 2.3.11 3.8 420605 B 1 73 Radiation Control RO 2.3.14 3.7 450890 M 2 31

-"

SRO 2.3.6 3.8 Q51080 N 1 8 + (9)

SRO 2.3.15 3.1 424714 B 2 8t (11)

RO 2.4.3 3.7 424951 B 1 30 RO 2.4.5 3.7 419570 B 2 74 Emergency procedures / Plan SRO 2.4.11 4.2 Q51095 N 2 9 (17)

SRO 2.4.45 4.3 451090 N 3 9tr (15)

CCNPP LOI-2206 Retake Exam Data

~

Parameter I Reactor Operator Test 1 Sr. Reactor Operator Test I Bank Questions 43 (!j7O/o) 8 (32%)

(Maximum of 75%)

Modified Questions 8 (11~0) 3 (12%)

New Questions (Minimum of 10 questions - 8 RO, 2 24 (32%) 14 (56%)

Memory 30 (40%) 7 (28%)

I Comprehension / Analysis 45 (60%) 18 (72%)

(50 - 60% for RO exam)

~

Modified Questions I Modified Question # I Original Question #

I Q50992 I 414583 450770 I 420383 QS065 1 I 419256 450930 I 424994 450993 450990 451016 420397 451110 428787 451097 450364 441651 441134 Q50890 442268 Q51150 420290

CCNPP LOI-2206 Retake Exam Data Key to symbols / abbreviations:

Type:

B = Bank Question M = Modified Question N = New Question Cognitive Level:

1 = Fundamental knowledge or simple memory (stpts, definitions, facts) 0 2 = Comprehension (recognition of system interactions) 0 3 = Analysis / Synthesis / Application (use of info to predict an event or outcome or to solve a problem)

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