ML13228A288

Final Outlines (Folder 3)

ML13228A288
Person / Time
Site:	Susquehanna
Issue date:	08/01/2013
From:	D'Antonio J Operations Branch I
To:	Public Service Enterprise Group
Jackson D
References
ES-401, ES-401-1, TAC U01868
Download: ML13228A288 (28)

Text

ES-401 Written Examination Outline Form ES-401-1 Facility:

SSES 2013 #1 Date of Exam:

08/20/12 Grou RO KIA Category Points SRO-Only Points Tier K

K K

K K

K A

A A

A G

Tota A2 G*

Total p

1 2

3 4

5 6

1 2

3 4

I

1.

1 3

5 3

3 3

3 20 4

3 7

Emergenc y

2 1

2 1

1 1

1 7

2 1

3 Tier Plant Total 4

7 4

4 4

4 27 6

4 10 Evolutions s

1 5

1 2

3 1

2 2

3 3

2 2

26 2

3 5

2.

2 1

1 1

1 1

1 2

1 1

1 1

12 0

1 2

3 Plant Systems Tier Total 6

2 3

4 2

3 4

4 4

3 3

38 3

5 8

s

3. Generic Knowledge & Abilities 1

2 3

4 1

2 3

4 10 7

Categories 2

3 2

3 2

2 1

2 Note

1.

Ensure that at least two topics from every applicable KIA 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 KIA 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 not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA 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 KAs 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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.*

The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIA's

8.

On the following pages, enter the KIA 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. If fuel handling equipment is sampled in other than Category /J.2 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 'r<JA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form E:S-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43

ES-401 2

SSES 201 ~~ #1 Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function KIA Topic(s)

AA2.04 -Ability to determine and/or 295003 Partial or Total Loss of X

interpret the following as they apply to 3.7 76 A. C.. Pwr I 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : System lineups EA2.02 -Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power X

SCRAM CONDITION PRESENT AND 4.2 77 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown I 1 DOWNSCALE OR UNKNOWN :

Reactor water level EA2.04 -Ability to determine and/or 295031 Reactor Low Water X

interpret the following as they apply to 4.8 78 Level I 2 REACTOR LOW WATER LEVEL:

Adequate core cooling 2.1.23 - Conduct of Operations: Ability 295023 Refueling Accidents I 8 X

to perform specific and integrated plant 4.4 79 procedures 295028 High Drywell 2.1.25 - Conduct of Operations: Ability Temperature I 5 X

to interpret reference materials such as 4.2 80 graphs, curves, tables, etc.

295019 Partial or Total Loss of 2.4.6-Emergency Procedures I Plan:

lnst. Air I 8 X

Knowledge of EOP mitigation 4.7 81 strategies.

EA2.02-Ability to determine and/or 295025 High Reactor Pressure I X

interpret the following as they applies to 4.2 82 3

HIGH REACTOR PRESSURE: Reactor power EK1.03-Knowledge of the operational 295030 Low Suppression Pool X

implications of the following concepts as 3.8 39 Water Level I 5 they apply to LOW SUPPRESSION POOL WATER LEVEL: Heat capacity EK1.01 - Knowledge of the operational 295025 High Reactor Pressure implications of the following concepts as

/3 X

they apply to HIGH REACTOR 3.9 40 PRESSURE : Pressure effects on reactor power AK1.01 -Knowledge of the operational 295006 SCRAM I 1 X

implications of the following concepts as 3.7 41 they apply to SCRAM : Decay heat

. generation and removal AK2.03-Knowledge of the 295019 Partial or Total Loss of interrelations between PARTIAL OR lnst. Air I 8 X

COMPLETE LOSS OF INSTRUMENT 3.2 42 AIR and the following: Reactor feedwater AK2.01 -Knowledge of the 600000 Plant Fire On-site I 8 X

interrelations between PLANT FIRE 2.6 43 ON SITE and the following: Sensors, detectors and valves AK2.01 -Knowledge of the interrelations between PARTIAL OR 295018 Partial or Total Loss of X

COMPLETE LOSS OF COMPONENT 3.3 44 CCW/8 COOLING WATER and the following:

System loads AK3.03-Knowledge of the reasons for 295016 Control Room the following responses as they apply to Abandonment I 7 X

CONTROL ROOM ABANDONMENT :

3.5 45 Disabling control room controls

ES-401 2

SSES 2013 #1 Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)

AK3.01 - Knowledge of the reasons for 295001 Partial or Complete the following responses as they apply to Loss of Forced Core Flow X

PARTIAL OR COMPLETE LOSS OF 3.4 46 Circulation /1 & 4 FORCED CORE FLOW CIRCULATION

Reactor water level response EK3.06-Knowledge of the reasons for 295037 SCRAM Conditions the following responses as they apply to SCRAM CONDITION PRESENT AND Present and Reactor Power X

REACTOR POWER ABOVE APRM 3.8 47 Above APRM Downscale or DOWNSCALE OR UNKNOWN :

Unknown/1 Maintaining heat sinks external to the containment AA 1.03-Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of X

PARTIAL OR COMPLETE LOSS OF 3.4 48 DC Pwr /6 D.C. POWER: A. C. electrical distribution EA 1.04-Ability to operate and/or 295028 High Drywell X

monitor the following as they apply to 3.9 49 Temperature HIGH DRYWELL TEMPERATURE:

15 Drvwell oressure EA 1.03-Ability to operate and/or monitor the following as they apply to 295026 Suppression Pool High X

SUPPRESSION POOL HIGH WATER 3.9 50 Water Temp. I 5 TEMPERATURE: Temperature monitoring AA2.04-Ability to determine and/or 295003 Partial or Complete interpret the following as they apply to 3.5 51 Loss X

PARTIAL OR COMPLETE LOSS OF of AC /6 A.C. POWER : System lineups AA2.02-Ability to determine and/or 295021 Loss of Shutdown interpret the following as they apply to 3.4 52 Cooling X

LOSS OF SHUTDOWN COOLING :

/4 RHR/shutdown coolina svstem flow EK2.09-Knowledge of the 295038 High Off-site Release interrelations between HIGH OFF-SITE Rate X

RELEASE RATE and the following::

2.9 53

/9 Post accident sample system (PASS):

Plant-Specific..

295024 High Drywell Pressure I 2.4.6-Emergency Procedures I Plan:

54 X

Knowledge of EOP mitigation 3.7 5

strateaies.

295005 Main Turbine 2.2.22 Equipment Control: Knowledge Generator X

of limiting conditions for operations and 4.0 55 Trio I 3 safetv limits.

2.1.19 - Conduct of Operations: Ability 700000 Generator Voltage and X

to use plant computers to evaluate 3.9 56 Electric Grid Disturbances system or component status.

AK2.04-Knowledge of the interrelations between REFUELING 295023 Refueling Ace Cooling X

ACCIDENTS and the following:

3.2 57 Mode /8 RMCS/Rod control and information system EA2.01 -Ability to determine and/or 295031 Reactor Low Water interpret the following as they apply to 4.6 58 Level X

REACTOR LOW WATER LEVEL:

12 Reactor water level KIA Category Totals:

3 5

3 3

3/4 3/:3 Group Point Total:

1 2017

ES-401 3

SSES 201:3 #1 Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 EAPE #I Name Safety Function G

KIA Topic(s)

Imp. I Q# ~

AA2.01 -Ability to determine and/or 295007 High Reactor Pressure X

interpret the following as they apply to 4.1 83

/3 HIGH REACTOR PRESSURE : Reactor pressure 2.4.30 - Emergency Procedures I Plan; 295035 Secondary Knowledge of events related to system Containment High Differential X

operation I status that must be reported 4.1 84 Pressure I 5 to internal organizations or external agencies, such as the state, the NRC, or the transmission system operator.

EA2.01 -Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation X

HIGH SECONDARY CONTAINMENT 3.. 9 85 Levels I 9 AREA RADIATION LEVELS: Area radiation levels EK1.02 - Knowledge of the operational 295034 Secondary implications of the following concepts as Containment X

they apply to SECONDARY 4.1 59 Ventilation High Radiation I 9 CONTAINMENT VENTILATION HIGH RADIATION: Radiation releases 295008 High Reactor Water AK2.08 - Knowledge of the interrelations between HIGH REACTOR Level X

WATER LEVEL and the following: Main 3.4 60 12 turbine: Plant-Specific EK3.01 - Knowledge of the reasons for 295032 High Secondary the following responses as they apply to Containment Area X

HIGH SECONDARY CONTAINMENT 3.5 61 Temperature/ 5 AREA TEMPERATURE :

Emergency/normal depressurization AA 1.03 -Ability to operate and/or 295007 High Reactor Pressure X

monitor the following as they apply to 3.4 62

/3 HIGH REACTOR PRESSURE : RCIC:

Plant-Specific EA2.01 -Ability to determine and/or 295029 High Suppression Pool X

interpret the following as they apply to 3.9 63 Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Sup_l)ression pool water level 295009 Low Reactor Water 2.4.35-Emergency Procedures I Plan:

Level X

Knowledge of local auxiliary operator 3.8 64 12 tasks during emergency and the resultant operational effects.

AK2.05-Knowledge of the 295010 High Drywell Pressure X

interrelations between HIGH DRYWELL 3.7 65 15 PRESSURE and the following: Drywell cooling and ventilation KIA Category Totals:

1 2

1 1

1/2 1/1 Group Point Total:

I 7/3

ES-401 259002 Reactor Water Level Control 205000 Shutdown Cooling 262001 AC Electrical Distribution 261000 SGTS 400000 Component Cooling Water 215004 Source Range Monitor 259002 Reactor Water Level Control 262001 AC Electrical Distribution 209001 LPCS 215005 APRM I LPRM 4

Form ES-401-1 SSES 201 ~~ #1 Written Examination Outline Plant Systems - Tier 2 Group 1 1~1~1~1~1~1~1~1.,1~1 1 1 G I A2.07 -Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b)

X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of comparator bias signal A2.09 -Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN X

COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Reactor low water level 2.4.11 - Emergency Procedures X

I Plan: Knowledge of abnormal condition procedures.

2.1.20 - Conduct of Operations:

X Ability to interpret and execute procedure steps.

2.2.42 - Equipment Control :

Ability to recognize system X

parameters that are entry-level conditions for Technical Specifications K1.02-Knowledge of the physical connections and/or cause-effect relationships X

between SOURCE RANGE MONITOR (SRM) SYSTEM and the pllowing: Reactor manual control K1.08-Knowledge of the physical connections and/or cause-effect relationships X

between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Recirculation system: Plant-Specific K2.01 -Knowledge of electrical X

power supplies to the following:

Off-site sources of power K2.03 - Knowledge of electrical X

power supplies to the following:

lnitation Logic K3.03-Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE X

MONITOR/LOCAL POWER RANGE MONITOR SYSTEM will have on following: Reactor manual control system: Plant-Specific 2.5 86 3.8 87 4.2 88 4.6 89 4.6 90 3.4 1

3.

2 2

3.

4 3

2.9 4

3.

5 3

ES-401 I Sy*tem #I Name 264000 EDGs X

218000 ADS 217000 RCIC 263000 DC Electrical Distribution X

300000 Instrument Air 205000 Shutdown Cooling 239002 SRVs 400000 Component Cooling Water 223002 PCIS/Nuclear Steam Supply Shutoff 4

Form ES-401-1 SSES 20121 #1 Written Examination Outline Plant Systems -Tier 2 Group 1 K3.02 - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following: A.C. electrical distribution K4.02 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM X

design feature(s) and/or interlocks which provide for the following: Allows manual initiation of ADS loqic K4.06 - Knowledge of REACTOR CORE ISOLATION X

COOLING SYSTEM (RCIC) design feature(s) and/or interlocks which provide for the following: Manual initiation K1.02-Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DIATRIBUTION and the following: Battery charger and battery K5.01 - Knowledge of the operational implications of the X

following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air compressors K6.02 - Knowledge of the effect that a loss or malfunction of the following will have on the X

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : D.C.

electrical power K6.05-Knowledge of the effect that a loss or malfunction of the X

following will have on the RELIEF/SAFETY VALVES:

Discharqe line vacuum breaker A 1.02 -Ability to predict and I or monitor changes in parameters X

associated with operating the CCWS controls including: CCW temperature A 1.02-Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT X

ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls includinq: Valve closures

3.

6 9

3.

8 7

3.5 8

3.

9 2

2.5 10

2.

7 11

3.

0 12

2.

13 8

3.

7 14

ES-401 System #I Name K

K K

1 2

3 215003 IRM 206000 HPCI 261000 SGTS 212000 RPS 211000 SLC 203000 RHRILPCI: Injection Mode 262002 UPS (AC/DC) 215004 Source Range Monitor 209001 LPCS 211000 SLC X

4 Form ES-401-1 SSES 201 ~~ #1 Written Examination Outline Plant Systems - Tielr 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

A2.01 -Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, X

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded A2.1 0 -Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b)

X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System isolation:

BWR-2,3,4 A3.03-Ability to monitor automatic operations of the X

STANDBY GAS TREATMENT SYSTEM including: Valve operation A3.07-Ability to monitor automatic operations of the X

REACTOR PROTECTION SYSTEM including: SCRAM air header pressure A4.08 -Ability to manually X

operate and/or monitor in the control room: System initiation:

Plant-Specific A4.09 -Ability to manually X

operate and/or monitor in the control room: System flow 2.1.32 -Conduct of Operations:

X Ability to explain and apply all system limits and precautions.

2.1.28-Knowledge of the X

purpose and function of major system components and controls.

A3.02 -Ability to monitor automatic operations of the X

LOW PRESSURE CORE SPRAY SYSTEM including:

Pump start K1.02-Knowledge of the physical connections and/or cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following: Core plate differential pressure indication Imp Q#

2.

8 15 3.9 16

3.

0 17

3.

6 18 4.2 19

4.

20 1

3.

8 21

4.

22 1

3.

8 23

2.

7 24

ES-401 System #I Name K

K K

1 2

3 262001 AC Electrical X

Distribution 239002 SRVs KIA Category Totals:

5 1

2 4

Form ES-401-1 SSES 201 ~~ #1 Written Examination Outline Plant Systems -Tier 2 Group 1 K

K K

A A2 A

~I G I 4

5 6

1 3

K3.06 Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: Reactor protection system A2.03 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV 3

1 2

2 3/2 3

2 2/3 Group Point Total:

I Imp I Q# I

3.

25 8

4.

1 26 I

26/5

ES-401 System #I Name K

K K

1 2

3 245000 Main Turbine Gen. I Aux.

201006 RWM 286000 Fire Protection 202002 Recirculation Flow X

Control 201001 CRD Hydraulic X

215002 RBM X

202001 Recirculation 219000 RHR!LPCI:

Torus/Pool Cooling Mode 290003 Control Room HVAC 268000 Radwaste 5

Form ES-401-1 SSES 2013 #1 Written Examination Outline Plant Systems -Tier 2 Group 2 K

K K

A A2 A

~I G I 4

5 6

1 3

A2.09-Ability to (a) predict the impacts of the following on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS :

X and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Turbine vibration X

2.2.12 - Knowledge of surveillance procedures 2.4.31 -Emergency Procedures X

I Plan: Knowledge of annunciator alarms, indications orresponse~procedures K1.03-Knowledge of the physical connections and/or cause-effect relationships between RECIRCULATION FLOW CONTROL SYSTEM and the following: Reactor core flow K2.05 - Knowledge of electrical power supplies to the following:

Alternate rod insertion valve solenoids: Plant-Specific K3.01 - Knowledge of the effect that a loss or malfunction of the ROD BLOCK MONITOR SYSTEM will have on following:

Reactor manual control system:

BWR-3,4,5 K4.05 - Knowledge of RECIRCULATION System X

design feature(s) and/or interlocks which provide for the following: Seal cooling K5.04 - Knowledge of the operational implications of the following concepts as they apply X

to RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE : Heat exchanger operation K6.02 - Knowledge of the effect that a loss or malfunction of the X

following will have on the CONTROL ROOM HVAC:

Component cooling water systems A 1.02 -Ability to predict and/or monitor changes in parameters X

associated with operating the RADWASTE controls including:

Off-site release I

Imp.

I~ I 2.8 91 3.4 92 4.1 93 3.7 27 4.5 28 3.3 29 2.9 30 2.9 31 2.7 32 2.6 33

ES-401 271000 Off-gas 201002 RMCS 259001 Reactor Feedwater 272000 Radiation Monitoring 201003 Control Rod and Drive Mechanism KJA Category Totals:

5 Form ES-401-1 SSES 201 ~~ #1 Written Examination Outline Plant Systems -Tier 2 Group 2 1~1~1~1~1~1~1~1 A21~1~1 G I A2.1 0 -Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use X

procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Offgas system high flow A3.03-Ability to monitor automatic operations of the X

REACTOR MANUAL CONTROL SYSTEM including:

Rod drift alarm A4.04 -Ability to manually X

operate and/or monitor in the control room: System valves.

2.4.49-Emergency Procedures I Plan: Ability to perform without X

reference to procedures those actions that require immediate operation of system components and controls.

A 1.02 -Ability to predict and/or monitor changes in parameters X

associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:

CRD drive pressure 1

1 1

1 1

1 2

1/1 1

1 1/2 Group Point Total:

3.1 34 3.2 35 3.1 36 4.6 37 2.8 38 I

12/3

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

Form ES-401-3 Facility:

SSES 2013 #1 Date:

08/20/12 Category Topic RO SRO-Only KIA#

IR Q#

IR Q#

2.1.39 Knowledge of conservative decision 4.3 94 making practices.

2.1.35 Knowledge of the fuel-handling 3.9 99 responsibilities of SRO's.

1.

Knowledge of Conduct of Operations Conduct 2.1.1 3.8 66 of Operations requirements Knowledge of procedures, guidelines, or 2.1.37 limitations associated with reactivity 4.3 67 management.

Subtotal 2

2 2.2.14 Knowledge of the process for controlling 4.3 95 equipment configuration or status.

2.2.40 Ability to apply technical specifications for 4.7 98 a system.

2.2.35 Ability to determine Technical 3.6 68

2.

Specification Mode of Operation.

Equipment Knowledge of bases in Iechnical Control 2.2.25 specifications for limiting conditions for 3.2 69 operations and safety limits.

Ability to manipulate the console controls 2.2.2 as required to operate tlhe facility 4.6 75 between shutdown and designated power levels Subtotal 3

2

3.

Knowledge of radiation monitoring Radiation 2.3.5 systems such as fixed radiation monitors 2.9 96 Control and alarms, portable survey instruments, personnel monitoring equipment, etc.

Knowledge of radiation monitoring 2.3.15 systems, such as fixed radiation monitors 2.9 70 and alarms, potable survey instruments, personnel monitoring equi~ment, etc.

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

Form ES-401-3 Knowledge of Radiologi1cal Safety Procedures pertaining to licensed operator duties, such as response to 2.3.13 radiation monitor alarms, containment 3.4 71 entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligninq filters, etc.

Subtotal 2

1 2.4.37 Knowledge of the lines of authority during 4.1 97 emergency plan implementation Knowledge of low power/shutdown 2.4.9 implications in accident (e.g., loss of 4.2 100 coolant accident or loss of residual heat removal}_ mitigation strategies

4.

Emergency 2.4.1 Knowledge of EOP entry conditions and 4.6 72 Procedures I immediate action steps.

Plan 2.4.29 Knowledge of the emeq~ency plan.

3.1 73 Ability to recognize abnormal indications 2.4.4 for system operating parameters which 4.5 74 are entry-level conditions for emergency and abnormal operating procedures.

Subtotal 3

2 Tier 3 Point Total 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA

(#4) K2.02-Knowledge of electrical power supplies to the following: Valve power.

Low discriminatory value.

2 I 1 209001 I K2.02 Randomly selected 209001 I K2.03-Knowledge of electrical power supplies to the following: Initiation Logic

(#9) K5.01 -Knowledge of the operational implications of the following concepts as they apply to D.C. ELECTRICAL DISTRIBUTION : Hydrogen generation during battery charging.

Low discriminatory value.

2 I 1 263000 I K5.01 Randomly selected 263000 K1.02-Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DIATRIBUTION and the following: Battery charger and battery

(#1 0) K5.13 - Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Filters.

Same KA randomly selected on 2010 NRC exam.

2 I 1 300000 I K5.13 Randomly selected 300000 I K5.01 -Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air Compressors

(#17) A3.02 -Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Fan start Same KA randomly selected on 2011 NRC exam.

2 I 1 261000 I A3.02 Randomly selected 261000 I A3.03-Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Valve operation

(#22) 2.2.36 - Equipment Control: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

This is an SRO function.

2 I 1 215004 I 2.2.36 Randomly selected 215004 I 2.1.28 - Knowledge of the purpose and function of major system components and controls.

ES-401 Record of Rejected K/A's Form ES-401-4

(#25) K3.04-Knowledge of the effect that a loss or malfunction of the A. C. ELECTRICAL DISTRIBUTION will have on following: Uninterruptible power supply.

UPS/Battery topic oversampled.

2/1 262001 I K3.04 Randomly selected 262001 I K3.06 Knowledge of the effect that a loss or malfunction of the A. C. ELECTRICAL DISTRIBUTION will have on following: Reactor protection system

(#26) 2.4.35 - Emergency Procedures I Plan: Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects. (low reactor water level)

Remote panel functions oversampled (#64 & #45) 2/1 239002/2.4.35 Randomly selected 239002 I A2.03 Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV

(#37) 2.2.39 - Equipment Control: Knowledge of less than one hour technical specification action statements for systems.

There are NO 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less TS for this system.

2/1 272000 I 2.2.39 Randomly selected 2.4.49 -Ability to perform without reference to procedures those actions that require immediate operation of system components and controls

(#38) A3.01 -Ability to monitor automatic operations of the CONTROL ROD AND DRIVE MECHANISM including:

Control rod position.

System/concept oversampled.

2/2 201003 I A3.01 Randomly selected 201003 I A 1.02 -Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including: CRD drive pressure

(#53) EA2.02-Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Total number of curies released This is a Rad Pro function.

1 /1 295038/ EA2.02 Randomly selected 295038 I EK2.09 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:: Post accident sample system (PASS):

Plant-Specific.

ES-401 Record of Rejected KIA's Form ES-401-4

(#55) 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I status that must be reported to internal organizations or external agencies, such as the state, the NRC, or the transmission system 1 11 295005 I 2.4.30 operator.

SRO level function.

Randomly selected 295005 I 2.2.22 - Knowledge limiting conditions for operations and safety limits.

(#56) 700000 I 2.2.12 - Equipment Control: Knowledge of surveillance procedures.

No surveillance procedures associated with Grid Disturbance.

1 11 700000 I 2.2.12 Randomly selected 700000 I 2.1.19 - Conduct of Operations: Ability to use plant computers to evaluate system or component status.

(#66) 2.1.31 -Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

This concept is significantly tested in the operating portion 311 2.1.31 of the exam.

Randomly selected 2.1.1 - Knowledge of Conduct of Operations requirements

(#70) 2.3.12-Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

313 2.3.12 Very similar to #71 Randomly selected-2.3.15-Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, potable survey instruments, personnel monitoring equipment, etc.

(#75) 2.2.4- (multi-unit license) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

312 2.2.4 Same KIA used on previous exam.

Randomly selected 2.2.2 -Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels

ES-401 Record of Rejected KIA's Form ES-401-4

(#78) AA2.05-Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT : Drywell pressure.

No specific procedural reference to develop a 1 I 1 295016 I AA2.05 discriminating SRO level question. APE also tested in #45 Randomly selected 295031 EA2.04-Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling

(#79) 2.1.27 - Conduct of Operations: Knowledge of system purpose and I or function.

Not discriminatory at the SRO level.

1 I 1 295023 I 2.1.27 Randomly selected 2.1.23 -Ability to perform specific and integrated plant procedures during all modes of operation

(#80) 2.1.31 -Conduct of Operations: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

This concept is significantly tested in the operating portion 1 I 1 295028 I 2.1.31 of the exam.

Randomly selected 2.1.25 - Ability to interpret reference materials such as graphs, curves, tables, etc. (High drywell temperature)

(#82) 2.2.12 - Equipment Control: Knowledge of surveillance procedures.

No surveillance procedure associated with this EPE.

1 I 1 295025 I 2.2.12 Randomly selected EA2.02-Ability to determine and/or interpret the following as they applies to HIGH REACTOR PRESSURE: Reactor power

(#85) EA2.02-Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Equipment operability.

1 I 2 295033 I EA2.02 Same general EOP topic/area covered in #61 Randomly selected EA2.01 -Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area radiation levels

ES-401 Record of Rejected KIA's Form ES-401-4

(#97) 2.4.41 - Knowledge of the emergency action level thresholds and classifications.

Oversample (see #81 and #85) 3/4 2.4.41 Randomly selected 2.4.37 - Knowledge of the lines of authority during emergency plan implementation.

(#92) 2.2.25 - Equipment Control: Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2/2 201002 I 2.2.25 The RMCS is not referenced in Tech Specs, the TRM or in LCOs and Safety Limits. Also, 2.2.25 used on #69 Randomly selected 201006 2.2.12-Knowledge of surveillance procedures (RWM).

(#90) 2.1.28 - Conduct of Operations: Knowledge of the purpose and function of major system components and controls.

Not discriminating at the SRO level 2/2 400000 /2.1.28 Randomly selected 2.2.42 - Equipment Control : Ability to recognize system parameters that are entry-level conditions for TE3chnical Specifications

(#1 00) Emergency Procedures/Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.

This is common RO & SRO knowledge level topic 3/4 2.4.20 Randomly selected 2.4.9-Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies

ES-301 Facility: Susquehanna Examination Level: RO Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Administrative Topics Outline Form ES-301-1 Type Code*

M,R M,R D, R Date of Examination: May 2013 Operating Test Number: 2013 Describe activity to be performed Calculate Drywall Leakage S0-1 00-006, KIA 2.1.7 (4.4)

Determine Work Hour Controls NDAP-QA-0025, KIA 2.1.5 (2.9)

Perform ~let Pump Operability Check S0-1 00-007, KIA 2.2.12 (3. 7)

!l-I t

~

Activate Fire Brigade Emergency Procedures/Plan D, S ON-013-001 Attachment L, KIA 2.4.27 (3.4)

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.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; ::;; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (;;:: 1)

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination: May 2013 Examination Level: SRO Operating Test Number: 2013 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Calculate Drywell Leakage and Determine Technical Conduct of Operations M,R Specification Impact S0-100-006, KIA2.1.7 (4.7)

Determine Work Hour Controls Conduct of Operations M,R NDAP-QA-0025, KIA 2.1.5 (3.9)

P,D, R Perform LPRM Upscale Alarm Operability Tracking and Equipment Control Determine Required Actions NRC 2/2011 01-078-001, KIA 2.2.14 (4.3)

Determine Ability to Bypass Secondary Containment Radiation Control D,R Zone 2 Isolation OP-234-002, KIA 2.3.13 (3.8)

Classify Emergency Conditions and Make Notification Emergency Procedures/Plan M,R EP-PS-1 00, KIA 2.4.41 (4.6)

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.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank(:::; 3 for ROs; :::; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (<:: 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susquehanna Date of Examination: May 2013 Exam Level: RO Operating Test No.: 2013 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Synchronize Diesel Generator D; Voltage Regulator Failure D,A,EN,S 6

KIA 264000 A4.04 (3.7/3.7), S0-024-001 D

b. Lineup RHRSW to the Spent Fuel Pool P,D,S 9

KIA 233000 A2.02 (3.1/3.3), ON-135-001 2011 NRC

c. Swap Core Spray Loops KIA 209001 A4.01 (3.8/3.6}, OP-151-001 N, EN, L, S 2

d. Reset Recirc Runback; Pump Speed Oscillates KIA 202002 A4.07 (3.3/3.2), ON-164-002 M,A,S 1

e. Main Steam Line Isolation Recovery D, L, S 3

KIA 239001 A4.01 (4.2/4.0), ON-184-001

f. Start HPCI in Pressure Control Mode; Pump Suction Clogging M,A, EN,S 4

KIA 206000 A4.04 (3.7/3.7}, OP-152-001

g. Perform Control Room Evacuation Immediate Actions; High Pressure Injection Sources Misaligned M,A, EN,S 7

KIA 212000 A4.01 (4.6/4.6), ON-100-109

h. Vent the Drywell (RO Only)

D,EN,S 5

KIA 223001 A2.07 (4.2/4.3), OP-173-003 In-Plant Systems (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i.

Pull Scram Fuses; Vent Scram Air Header KIA295037 EA1.01 (4.6/4.6}, ES-158-001, E0-100-113 M,A, E, R 7

j. Start Containment Hydrogen Recombiner in Manual P, D, E, L 5

KIA 223001 A2.01 (4.3/4.4), OP-173-001 2010 NRC

k. Establish RPV Alternate Injection with Fire Protection (A LOOP)

D, E, L 8

KIA 295031 EA1.01 (4.4/4.4), OP-149-001 All RO and SR0-1 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.

• Type Codes (A)Iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator Simulator Pairings:

A then B D then H F then E C alone G alone Criteria for RO I SR0-11 SRO-U 4-6 14-6 I 2-3 S91S81S4

<:11<:11<:1

- I -

I <:1 (control room system)

<:11<:11<:1

<:21<:21<:1 s 3 I s 3 I s 2 (randomly selected)

<:11<:11<:1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susquehanna Date of Examination: May 2013 Exam Level: SR0-1 Operating Test No.: 2013 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Synchronize Diesel Generator D; Voltage Regulator Failure D,A,EN,S 6

KIA 264000 A4.04 (3.7/3.7), S0-024-001 D

b. Lineup RHRSW to the Spent Fuel Pool P,D,S 9

KIA 233000 A2.02 (3.1/3.3), ON-135-001 2011 NRC

c. Swap Core Spray Loops N, EN, L, S 2

KIA 209001 A4.01 (3.8/3.6), OP-151-001

d. Reset Recirc Runback; Pump Speed Oscillates KIA 202002 A4.07 (3.3/3.2), ON-164-002 M,A,S 1

e. Main Steam Line Isolation Recovery KIA 239001 A4.01 (4.2/4.0), ON-184-001 D, L, S 3

f. Start HPCI in Pressure Control Mode; Pump Suction Clogging M,A, EN,S 4

KIA 206000 A4.04 (3.7/3.7), OP-152-001

g. Perform Control Room Evacuation Immediate Actions; High Pressure Injection Sources Misaligned M,A,EN,S 7

KIA 212000 A4.01 (4.6/4.6), ON-100-109 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i.

Pull Scram Fuses; Vent Scram Air Header M,A,E, R 7

KIA 295037 EA 1.01 (4.6/4.6), ES-158-001 I E0-1 00-113

j. Start Containment Hydrogen Recombiner in Manual P, D, E, L 5

KIA 223001 A2.01 (4.3/4.4), OP-173-001 2010 NRC

k. Establish RPV Alternate Injection with Fire Protection (A LOOP)

D, E, L 8

KIA 295031 EA1.01 (4.4/4.4), OP-149-001 All RO and SR0-1 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.

• Type Codes (A)Iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator Simulator Pairings:

A then B D then H F then E C alone G alone Criteria for RO I SR0-11 SRO-U 4-6 I 4-6 I 2-3

591::581::54

<:11<:11<:1

- I - I :::1 (control room system)

<:11<:11<:1

<:21<:21<: 1

3 I

::; 3 I:::; 2 (randomly selected)

<:11<:11<:1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Susquehanna Date of Examination: May 2013 Exam Level: SRO-U Operating Test No.: 2013 Control Room Systems (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Synchronize Diesel Generator D; Voltage Regulator Failure D,A, EN,S 6

KIA 264000 A4.04 (3.7/3.7}, S0-024-001D

c. Swap Core Spray Loops KIA 209001 A4.01 (3.8/3.6), OP-151-001 N, EN, L,S 2

f. Start HPCI in Pressure Control Mode; Pump Suction Clogging M,A, EN,S 4

KIA 206000 A4.04 (3.7/3.7), OP-152-001 In-Plant Systems (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i.

Pull Scram Fuses; Vent Scram Air Header KIA 295037 EA1.01 (4.6/4.6}, ES-158-001, E0-100-113 M,A,E, R 7

k. Establish RPV Alternate Injection with Fire Protection (A LOOP)

KIA 295031 EA1.01 (4.4/4.4), OP-149-001 D, E, L 8

All RO and SR0-1 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.

• Type Codes (A)Iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator Simulator Pairings:

A then B D then H F then E C alone G alone Criteria for RO I SR0-11 SRO-U 4-6 I 4-6 I 2-3

591:581:54

~11~11~1

- I -

I

~1 (control room system)

~11~11~1

~21~21~1

5 3 I :5 3 I :5 2 (randomly selected)

~11~11~1

Appendix D Scenario Outline Form ES-D-1 Facility: Susquehanna Scenario No.: NRC-1 Op-Test No.: 2013 Examiners:

Operators:

Initial Conditions: The plant is operating at approximately 100% power. EHC pump A is out of service for maintenance. RCIC is out of service for maintenance.

Turnover: Transfer Bus 1A202 to the alternate supply per OP-104-001 section 2.1.4. Then lower Reactor power with Recirculation flow to approximately 92% per G0-1 00-012 section 5.3 and Reactivity Manipulation Package.

Event Malf.

Event Event No.

No.

Type*

Description N-Transfer Bus 1A202 to the Alternate Supply 1

N/A

BOP, SRO OP-104-001 R-Lower Reactor Power with Recirculation Flow to 92%

2 N/A

ATC, SRO G0-100-012 cmfNB03 PSB 211NOZ3A cmfRL02 C72 Division 1 RPS reactor pressure transmitter fails 3

1K14A 1-SRO IMF AR-1 03-001 (B02), Technical Specifications cmfRL02 C72 1K14E 4

mfFW145007 A C-All Feedwater Pump A High Vibrations with Delayed Pump Trip AR-101-001 (A16), OP-145-001, ON-164-002 cmfRL02_E11 C-RHR Pump B Spurious Start and Suction Flange Leak into Reactor 5

1K11A

BOP, Building mfRH149004B SRO ON-169-002, E0-000-104, Technical Specifications mfHP152009 HPCI Steam Leak into Reactor Building 6

M-All mfHP152003 E0-000-104, ON-100-101, E0-000-102 cmfMV06 HV 155F062 cmfMV06 HV HPCI Fails to Automatically Isolate, HPCIIsolation Valves Stick 155F063 I-BOP, Mid-Position When Manually Closed 7

cmfMV09 HV SRO 155F062 E0-000-1 04, E0-000-112 cmfMV09 HV 155F003 mfRD155006 Multiple Control Rods Fail to Insert 8

C-All cmfSC04 E0-000-1 02, E0-000-113

_(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)aior

Appendix D Scenario Outline Form ES-D-1 Facility: Susquehanna Scenario No.: NRC-2.

Op-Test No.: 2013 Examiners:

Operators:

Initial Conditions: The plant is operating at approximately 100% power. EHC pump A is out of service for maintenance. RCIC is out of service for maintenance.

Turnover: Perform half scram testing for RPS scram channel A1 per S0-158-001.

Event Malf.

Event Event No.

No.

Type*

Description N-Perform Half Scram Testing 1

N/A

BOP, SRO S0-158-001 rfDB105 MCC 1 B217 De-Energizes, Loss of Power to Drywell Spray Valves, 2

C-All Loss of RPS Bus A 101 ON-158-001, Technical Specifications R-Power Reduction Due to Minimum Generation Emergency 3

Report

ATC, Notification SRO 01-AD-029, G0-100-012 mfHP1520 I-BOP, HPCI Inadvertent Initiation 4

04 SRO ON-156-001, Technical Specifications cmiTH02_

Recirculation Pump A High Temperature 5

TE14357A C-All 1A2 AR-102-001 (G03), ON-164-002, Technical Specifications cmfBR03 1A10201 Electrical Fault on Bus 11 B 6

C-All cmfBR03 ON-103-003, ON-100-101, E0-000-102 1A10204 7

mfRR1640 M-All Reactor Coolant Leak in Drywell 11A E0-000-1 02, E0-000-1 03 8

mfFW1440 C-All Trip of Condensate Pumps 1 A and 1 C 03A(C)

E0-000-102 9

mfHP1520 C-All HPCI Trip 15 E0-000-102, E0-000-112 mfAD1830 C-ADS Fails to Automatically Initiate 10 01

BOP, SRO E0-000-1 02, E0-000-*112 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: Susquehanna Scenario No.: NRC-3 Op-Test No.: 2013 Examiners:

Operators:

Initial Conditions: The plant is operating at approximately 90% power. Core Spray pump A is out of service for maintenance.

Turnover: Swap EHC pumps per OP-193-003 section 2.9. Then raise Reactor power with Recirculation flow per G0-100-012 section 5.4 and Reactivity Manipulation Package.

Event Malf.

Event Event No.

No.

Type*

Description N-Swap EHC Pumps 1

N/A

BOP, SRO OP-193-003 R-Raise Reactor Power with Recirculation Flow 2

N/A

ATC, SRO G0-100-012 C-EHC Oscillations 3

mfTC1930

ATC, 03 SRO ON-193-001 cmfRV04_

C-SRV Inadvertently Opens 4

PSV141F1

BOP, 3K SRO ON-183-001, Technical Specifications cmfMV01 C-Suppression Pool Cooling Valve Breaker Trip 5

HV151F02

BOP, 4A(B}

SRO OP-149-005, Technical Specifications mfMS1830 10K SRV Leaks with Cracked Tailpipe 6

C-All mfMS1830 ON-100-101, E0-000-102, E0-000-103 13K mfRP1580 Electrical A TWS 7

04A(B)(C)(

M-All D)

E0-000-102, E0-000-113 C-CRD Pumps Trip on Low Suction Pressure 8

rfRD15502

BOP, 2

SRO E0-000-113 mfSL1530 C-SLC Squib Valves Fail to Open on Start of First Pump, Subsequent 9

01A(B)

BOP, SLC Pump Starts and Trips cmfPM03 SRO 1P208A(B)

E0-000-113 (N)ormal, (R)eactivitv, (l)nstrument, IC)omponent, (M)aior