ML090290246

Calvert Cliffs -Final Outlines (Folder 3)

ML090290246
Person / Time
Site:	Calvert Cliffs
Issue date:	10/30/2008
From:	Calvert Cliffs
To:	Operations Branch I
Hansell S
Shared Package
ML082600339	List: IR 05000317/2008302 ML082760115 ML083430602 ML083580024 ML090220477 ML090260359 ML090290231 ML090290235 ML090290239 ML090290246 ML090490182
References
TAC U01779
Download: ML090290246 (20)

Text

ES-401 PWR Examination Outline Form; s-4016 dl Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRC'r- 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). 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 fl 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. Systemslevolutions within 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-specific systems/evolutions that 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. 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.

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 relevar to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS. 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. 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. Usr PWR Examination Outline Form ES-401-2 ES-401 Emergency and - - # IR - 3.5 3.1 - - 4.4 4.2 2.9 32 39 34 45 31 "_ 41 32 43 35 35 31 29 3.9 11 ElAPE # / Name I Safety Function I! AG KIA Topic(s) 2 EE(2.03 - Reactor trip status panel 000007 (CE/E02) Reactor Trip - A Stabilization - Recovery I 1 000008 Pressurizer Vapor Space Accident I3 I 000009 Small Break LOCA I3 AK1.02 - Change in leak rate with change in pressure EK3.26 - Maintenance of RCS subcooling 2.2.44 - Ability to interpret control room indications to verify the status and operation X ? - of' a system, and understand how operator actions and directives affect plant and system conditions.

AK2.07 - RCP seals AA1.03 - PZR level trend AK1.01 - Loss of RHRS during all modes of operation 2.2.40 - Ability to apply technical Specifications for a system.

EA1.08 - Reactor trip switch pushbutton 1 EK1.01 - Use of steam tables 00001 1 Large Break LOCA I3 11 000015/17 RCP Malfunctions I 4 I 11 000022 Loss of Rx Coolant Makeup I2 I 000025 Loss of RHR System / 4 I 000026 Loss of Component Cooling Water I8 I 11 000029 ANVS I 1 I 11 000038 Steam Gen. Tube Rupture I3 I : CK- 2.4.45 - Ability to prioritize and interpret the obtain desired operating results during abnormal and emergency situations.

000040 (CEIEOS) Steam Line Rupture - Excessive Heat Transfer 1 4 000054 (CEIEO6) Loss of Main Feedwater I 4 000055 Station Blackout I6 EK3.02 - Actions contained in EOP for loss of offsite and onsite power AA2.73 - PZR heater odoff Y AA1.06 - Manual control of components for which automatic control is lost AA2.01 - That a loss of dc power has occurred; verification that substitute power sources have come on line 000057 Loss of Vital AC Inst. Bus 16 - X 000058 Loss of DC Power I6 000065 Loss of Instrument Air I8 AA2.01 - Cause and effect of low-pressure instrument air alarm

~_______ ~ 000077 Generator Voltage and Electric Grid Disturbances I6 AK2.06 - Reactor power 11 KIA Category Totals: I 3 I 3 I 3 I 3 I 3 I Group Point Total:

11 ES-401 PWR Examination Outline Form ES-401.gI - I-401 PWR Examination Outline Form ES-401-2 000074 (W/E06&E07)

Inad. Core Cooling I4 CE/A13 - Natural Circ.

I4 instrumentation, signals, interlocks, odes, and automatic and manual - IR 2.9 3.4 3.9 - - - 3.7 2.8 - 4.0 - 3.0 3.0 - 4.2 Form ES-401 ES-401 PWR Examination Outline amination Outline Form ES-401-2 11 ES-401 PWR 1 ~p 1- Reactor Operator K/A Topic(s) K6.14 - Starting Requirements

1. 11 System # I Name 003 Reactor Coolant Pump v 2.6 2.1.3 1 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. 4.6 003 Reactor Coolant Pump H X K5.14 - Reduction process of gas concentration in RCS: vent- accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)

K5.02 - Need for adequate subcooling 004 Chemical and Volume Control 2.5 - 3.4 005 Residual Heat Removal 006 Emergency Core Cooling 006 Emergency Core Cooling 007 Pressurizer ReliefIQuench Tank 008 Component Cooling Water I I A3.04 - Cooling water systems 3.8 2.5 K2.02 - Valve operators for accumulators I I K3.01- Containment 3.3 3.0 K2.02 - CCW pump, including emergency backup 008 Component Cooling Water 010 Pressurizer Pressure I-- Control 2.4.1 - Knowledge of EOP entry condition and immediate action steps. 4.6 X 3.1 Al.06 - RCS heatup and cooldown effect on pressure I I K6.10 - Permissive circuits 3.3 012 Reactor Protection 013 Engineered Safety Features Actuation 3.7 K1.18 - Premature reset of ESF actuation 2.8 K4.04 - Cooling of control rod drive motors 022 Containment Cooling K3 .O 1 - Containment equipment subject to damage by high or low temperature, humidity, and pressure 2.9 022 Containment Cooling 4.2 - 3.6 - - 026 Containment Spray 2.2.37 - Ability to determine safety related equipment.

026 Containment Spray PWR Examination Outline Form ES-401-2 11 II 11 11 ES-401 PWR Examination Outline Form ES-401 Form ES-401- d1 - ES-401 PWR Examination Outline ES-401 PWR Examination Outline Form ES-401 - 000015/17 RCP Malfunctions

/ 4 I - -

11 ES-401 PWR Examination Outline Form ES-401-2 11 It ES-401 I Emergency and Abnormal F I E/APE # / Name / Safety Function 11 000001 Continuous Rod Withdrawal

/ 1 I 000003 Dropped Control Rod / 1 00005 1 Loss of Condenser Vacuum 000033 Loss of Intermediate Range NI / 7 11 KIA Category Point Totals: 'R Ex it Evc 4 tion Outline Form ES-401-2 WA Topic(s) AA2.04 - Reactor power and its trend 4.3 3.6 2.4.1 - Knowledge of EOP entry conditions and immediate action steps.

AA2.01- Cause of low vacuum

'1 I condition I 2.7 I I- 2.4.20 - Knowledge of operational and notes.

X implications of EOP warnings, cautions, 4.3 2 I 2 I Group Point Total: 141 I- ll I ES-401 PWR Examination Outline Form ES-401-.dI - 11 ES-401 System #I Name Ir 005 Residual Heat Removal I 013 Engineered Safety Features Actuation 06 1 AuxiliaryEmergency Feedwater 073 Process Radiation Monitoring w 078 Instrument Air PV amination Outline Form ES-401-2 II WA Topic(s) A2.02 - Pressure transient protection during cold shutdown X 2.1.45 - Ability to identify and interpret diverse indications to validate the response of another indication.

A2.08 - Flow rates expected from various combinations of AFW pump discharge valves 2.4.6 - Knowledge of EOP mitigation strategies.

A2.01 - Air dryer and filter malfunctions Group Point Total:

02 IR 3.7 4.3 2.9 - 4.7 - 2.9 #

1G11 4 PWR Examina AG X :ion Outline 61 00 11 ES-401 KA PW stems - ' KK 45 23 X X Examination Out1 AA >erator WA Topic(s) A2.04 - Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs. control rod reactivity changes A2.17 - Malfunction of electrohydraulic control 2.2.31 -Ability to determine operability and/or availability of safetv related eauinment.

Form ES-401-2 Group Point Total: - IK - 3.8 - 2.9 - 4.6 KIA # Topic ~~ ~ Subtotal 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

~ 2.3.6 2.3.15 r ~~ ~ ~~ - Ability to approve release permits. radiation monitors and alarms, portable survey

3.8 Knowledge

of radiation monitoring systems, such as fixed instruments, personnel monitoring equipment, etc.

3.1 Subtotal

2.4.3 I Ability to identify post-accident instrumentation. - 3 2 3.7 Form ES-401 ES-401 Generic Knowledge

& Abilities Outline Facility:

Calvert Category 08 RO +P- 2.1.3 I Knowledge of shift or short-term relief turnover practices.

2.1.17 I Ability to make accurate, clear, and concise verbal reports 3.9 I -I - 1. Conduct of Operations 2.1.44 Knowledge of RO duties in the control room during fuel 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. Ability to interpret and execute procedure steps.

2.1.20 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. Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator. Knowledge of the process used to track inoperable alarms. 2.2.43 -I - 21 I 3.2 I Knowledge of radiation exposure limits under normal or 2.3-4 I emergency conditions.

1 3. Radiation Control 2.3.1 1 I Ability to control radiation releases.

4. Emergency Procedures I Plan 2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

3.7 2.4.1 1 F 2.4.45 ~~ Knowledge of abnormal condition procedures. Ability to prioritize and interpret the significance of each annunciator or alarm.

I Subtotal 12 - - Tier 3 Point Total 7

ES-401 Record of Rejected WAS Form ES-401 11 Randomly Selected K/A EA1.02 025 K2.02 A3.01 2.1.43 2.4.26 005 AA2.01 2.4.26 Reason for Rejection Replaced 029, EA1.02 with 029, EA1.08. WA EA1.02 is an inappropriate match for the E/APE # selected. CCNPP standard 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 have ice condensers. Replaced K2.02 with K3.04. Calvert Cliffs does not have an Integrated Control System.

Replaced A3.01 with A3.02. Calvert Cliffs Reactor Coolant Waste Evaporators are retired-in-place 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 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 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 2.2.37 pairs the ability to determine operability and/or availability of safety related equipment with Area Radiation Monitoring.

CCNPP LOI-2206 Retake Exam Data ES-401 PWR Examination Outline Form ES-401 - Facility: Calvert Cliffs Date of Exam: December 10,2008 I I II Note: 1. 2. 3. 4. 5. 6. 7.* 8. 9. 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). 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. 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.

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 VAS 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 K/A categories. The generic (G) K/As in Tiers 1 and 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. 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.

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-2206 Retake Exam Data K/A Imp Vision Topics # ID E/APE # / Name / Safety Function Tier l/Group 1- Reactor Ope Cognitive

1. Level #ator 000007 (CE/EO2) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 EK2.03 3.5 420274 B 3 1( AK1.02 3.1 450851 N 2 21 EK3.26 4.4 426519 B 1 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System / 4 000011 Large Break LOCA / 3 I 2.2.44 I 4.2 AA1.03 3.2 AK1.O1 3.9 000015/17 RCP Malfunctions

/ 4 I AK2.07 I 2.9 000026 Loss of Component Cooling Water / 8 000029 ATWS 1 1 000038 Steam Gen. Tube Rupture

/ 3 2.2.40 3.4 450770 M 1 1 EA1.08 4.5 450651 M 2 27 EK1.O1 3.1 423208 B 2 2, 53 2.4.45 000040 (CEIEO5) Steam Line Rupture - Excessive Heat Transfer / 4 420393 I B I 2 I ! 4.1 450950 N 3 53 000054 (CE/E06) Loss of Main Feedwater

/ 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 EK3.3 3.2 428472 B 2 12 EK3.02 4.3 440704 B 1 < AA2.73 3.5 418107 B 2 t5 ~~ 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000065 Loss of Instrument Air / 8 AA1.06 3.5 450852 N 2 25 AA2.01 3.7 451132 N 2 23 AA2.01 2.9 451150 M 2 000077 Generator Voltage

& Electric Grid Disturbances

/ 6 AK2.06 3.9 450730 N 1 7 K/A Tooics E/APE # / Name / Safety Function Tier l/Group 2- Reactor OPI Imp # Vision ID Cognitive

1. - Type Level - 000067 Plant Fire On-site / 8 000059 Accidental Liquid RadWaste Rel.

/ 9 000061 ARM System Alarms

/ 7 I 2-2-42 I 3.9 AA2.02 2.9 AK3.02 3.4 000068 (BW/A06) Control Room Evac.

/ 8 000069 Loss of CTMT Integrity

/ 5 000074 (W/E06&E07)

Inad. Core Cooling 14 CE/A13 - Natural Circ. / 4 AK2.02 3.7 AA1.03 2.8 EA2.06 4.0 CE/A16 Excess RCS Leakage / 2 I AK1-2 I 3.0 CE/E09 Functional Recovery I m1.1 I 4.2 !rator 450933 I N I 2 I 13 440348 1 B I 2 I :4 ;i 425068 B

- - CCNPP LOI-2206 Retake Exam Data CCNPP LOI-2206 Retake Exam Data Tier 2 / Group 2 - Reactor Operator 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 ~ ~~ ~ ~ 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal ~~ ~ 086 Fire Protection -A+ b4.02

• K5.07 K1.06 I 2.6 2.4.6 1 A3.02 K3.04 I 2.7 K4.02 I 3.0 Vision 1 I Cognitive 1 Exan ID Type Level 451032 N 3 E3 451130 B 1 Ll 451050 N 2 i2 428225 B 2 ;3 428429 I B I 3 I 2 1 451033 451051 I N I 2 I ; 1 434432 I B I 1 1 ;8 CCNPP LOI-2206 Retake Exam Data Imp Vision ID Type E/APE # / Name / Safety Function I Tier 1 / Group I - Sr. Reactor Operator Cognitive

~ -- Level -- E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal

/ 1 000003 Dropped Control Rod / 1 000051 Loss of Condenser Vacuum 000033 Loss of Intermediate Range NI / 7 000015/17 RCP Malfunctions

/ 4 AA2.04 4.3 419089 B 1 82 (7) 2.4.1 3.6 451078 B 1 8:! (8) AA2.01 2.7 441651 M 2 88 (13) 2.4.20 4.3 451082 N 2 87 (12) -- .- 000027 Pressurizer Pressure Control System Malfunction

/ 3 Imp Vision ID Type E/APE # / Name / Safety Function 005 Residual Heat Removal A2.02 3.7 451100 N 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater

/ 4 Cognitive

1. 3 99 (24) Level ---- 000062 Loss of Nuclear Svc Water / 4 CE/EO2 Reactor Trip - Stabilization - Recovery / 1 4ifF AA2.10 3.6 2.4.23 I AA2.01 - Cognitive Exan # Vision ID Level 89 14) 77 :2) Tier 1 / Group 2 - Sr. Reactor Operator Tier 2 / Group 1 - Sr. Reactor Operator 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 015 Nuclear Instrumentation 045 Main Turbine Generator 072 Area Radiation Monitoring Tier 2 / Group 2 - Sr. Reactor Operator A2.04 3.8 451079 N 3 85 10) A2.17 2.9 425257 B 2 95 20) 2.2.37 4.6 451073 N 2 79 (4) - - K/A Imp Vision # Cognitive

-- Topics # -Type* ID E/APE # / Name / Safety Function Category RO RO RO SRO SRO RO Equipment Control RO SRO RO RO RO SRO SRO RO RO SRO SRO Emergency procedures

/ Plan Imp Vision Cognitive

1. K/A 2.1.3 3.7 450870 N 1 I9 2.1.17 3.9 426067 B 1 3 - Topics # ID Type Level 2.1.44 3.9 450934 N 1 14 2.1.20 4.6 445189 0 1 94 (19) 2.1.40 3.9 420627 B 1 7( (1) 2.2.1 4.5 425936 B 2 32 2.2.17 2.6 451170 N 1 34 2.2.43 3.3 451099 N 1 9E (23) 2.3.4 3.2 417947 B 1 70 2.3.11 3.8 420605 B 1 73 2.3.14 3.7 450890 M 2 31 2.3.6 3.8 Q51080 N 1 8 + (9) 2.3.15 3.1 424714 B 2 8t (11) 2.4.3 3.7 424951 B 1 30 ~- "- "- 2.4.5 3.7 419570 B 2 74 2.4.11 4.2 Q51095 N 2 9 (17) 2.4.45 4.3 451090 N 3 9tr (15) A Generic Knowledge

& Abilities Conduct of Ops Radiation Control CCNPP LOI-2206 Retake Exam Data ~ Bank Questions (Maximum of 75%) Modified Questions Parameter 43 (!j7O/o) 8 (32%) 8 (11~0) 3 (12%) I Reactor Operator Test 1 Sr. Reactor Operator Test I Memory 30 (40%) 7 (28%) New Questions (Minimum of 10 questions - 8 RO, 2 24 (32%) 14 (56%) Comprehension

/ Analysis (50 - 60% for RO exam) I 45 (60%) 18 (72%) 450993 451016 ~ Modified Questions 450990 420397 I Modified Question # I Original Question # 451110 451097 I Q50992 I 414583 428787 450364 450770 I 420383 QS065 1 I 419256 450930 I 424994 441651 441 134 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)