ML17075A380

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Final Outlines (Folder 3)
ML17075A380
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 01/16/2017
From:
Exelon Generation Co
To:
NRC Region 1
Shared Package
ML16076A445 List:
References
U01940
Download: ML17075A380 (5)
v • d • e


Text

Generati Appendix D Facility:

Limerick 1 & 2 Examiners:

Initial Conditions:

Unit 1 is at 90% power.

Turnover:

LIMERICK GENERATING STATION SIMULATOR EVALUATION GUIDE Scenario Outline Scenario No.: SEG-2007E Rev_2_

Operators:

Unit 2 is at 100% power.

Form ES-D-1 Op-Test No.:

1 Withdraw Control Rods per ReMA and raise Recirc flow to return to 100% Reactor power

'1 B' EHC Pump is blocked for pump replacement. Repairs are scheduled to be complete in two (2) hours. Maintain 100% power and support PMT of '1 B' EHC pump when it is returned to operations.

Event Malfunction Event Event No.

Number Type*

Description

1.

None R-RO Raise Power with Control Rods

2.

MRD016E C-RO Control Rod (46-15) uncoupled (Abnormal)

(46-15)

TS-SRO

3.

MAD149E C-RO

'1 N' SRV fails open I closes when Rx power lowered to <90 %

C-PRO (Abnormal)

MV1231 D C-RO Inadvertent Div 4 LOCA Signal (Abnormal)

4.

C-PRO MRH172D TS-SRO

'1 D' RHR Pump fails to auto start

5.

MRR441 C-PRO Small leak in Drywell (Abnormal)

6.

MMS067 M-ALL Large Steam Leak in Drywell

7.

MRH600B C-PRO

'1 B' RHR Pump Trips (Malfunction)

8.

MRH573A C-PRO HV-51-1 F024A Thermal Overload condition (Malfunction)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-2007E Rev002.doc SRRS: 30.126 Page 2 of 49

LIMERICK GENERATING STATION ion SIMULATOR EXERCISE GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-5006E Rev _o_

Op-Test No.:_1_.

Examiners:

Operators:

Initial Conditions:

Unit 1 is at _1QQ_ % power. Unit 2 is at 100 % power.

Turnover:

Maintain 100% Reactor QOwer Place '1 C' SLC PumQ in Automatic Injection Mode Qer S48.1.A, Standby Liguid Control System Set-UQ For Normal OQeration, steQ 4. 7 in QreQaration of a 1 B SLC System Outage Window.

Event Malfunction Event Event No.

Number Type*

Description

1.

MSL 1988 N-PRO Align '1 C' SLC Pump for automatic operation C41-S1C TS-SRO

2.

MPR020C C-RO

  1. 3 APRM fails upscale (Malfunction)

R-RO

3.

MRR430A C-PRO

'1 A' Reactor Recirc Pump shaft seizure resulting in TS-SRO Recirc Pump trip (Abnormal)

4.

MFH563C C-PRO Low Pressure FWH Level Transient (Abnormal)

5.

MPR003A C-RO Core Power Oscillations

6.

MFW252A M-ALL LOCA Inside Containment (T-111)

MRR440A

7.

MRC457B C-PRO RCIC controller in AUTO failure (Malfunction)

8.

MAD148D C-PRO

'1 M' SRV fails to open (Malfunction)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-5006E RevOOO.doc SRRS: 30.126 Page 2 of 47

Appendix D Facility:

Limerick 1 & 2 Examiners:

Initial Conditions:

LIMERICK GENERATING STATION ion SIMULATOR EVALUATION GUIDE Scenario Outline Scenario No.: SEG-7016E Rev 002 Operators:

Form ES-D-1 Op-Test No.:_

1 Unit 1 is at 100% power. Unit 2 is at 100% power.

Turnover:

Maintain 100%.

II Event Malfunction Event Event No.

Number Type*

Description R-RO

1.

MFW001 C-PRO HWC System Failure (Abnormal)

TS-SRO VIC104C8 C-RO

'1 C' RFP Min Flow Valve fails open, resulting in RFP Hi

2.

MFW250A MFW246A C-PRO Pump Vibration (Abnormal)

3.

MCW481A C-PRO

'1A' TECW Pump trip MCW486B

'1 B' TECW fails to auto start (Abnormal)

4.

MVl234C C-RO Reactor High Pressure Transmitter Failure (Abnormal)

TS-SRO

5.

MRP029D ATWS MSL559 M-ALL The ATWS is mitigated by the insertion of control rods via MRP407C T-215. (Major)

6.

MRD024 C-RO RDCS Inoperative after reactor shutdown (Malfunction)

7.

MMT002 C-PRO Turbine Trip I Bypass Valves Fail Closed (Malfunction)

MEH108 C-RO

8.

MRSW600A C-PRO

'QA' or 'QC' RHRSW Pump Trips (Malfunction)

MRSW600C (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-7016E Rev002.doc SRRS: 30.126 Page 2 of 43

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: 01 /17 /17 Examination Level: ROX SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

2.1.19 (Ability to use plant computers to evaluate system or component status. (CFR: 41.10 I 45.12)

Conduct of Operations R,D IMPORTANCE RO 3.9 SRO 3.8 Evaluate Jet Pump Operabilit~ (LOJPM6717)

G2.1.25 (Ability to interpret reference materials, such as Conduct of Operations R,N graphs, curves, tables, etc. (CFR: 41.10 I 43.5 I 45.12)

IMPORTANCE RO 3.9 SRO 4.2) Determine Maximum Generator VARS (LOJPM6719)

G2.2.6 Knowledge of the process for making changes to Equipment Control R,D procedures. (CFR: 41.10 I 43.3 I 45.13)

IMPORTANCE RO 3.0 SRO 3.6 Prepare a Partial Procedure (LOJPM6777)

G2.3.15 (Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey Radiation Control R, N instruments, personnel monitoring equipment, etc. (CFR:

41.12 I 43.4 I 45.9) IMPORTANCE RO 2.9 SRO 3.1)

Actions Reguired for Spiking ARM (LOJPM6728)

Emergency Procedures/Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items)

  • 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, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Limerick Date of Examination: 01/17/17 Examination Level: RO SROX Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

G2.1.5 (Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, Conduct of Operations R,D etc. (CFR: 41.10 I 43.5 I 45.12) IMPORTANCE RO 2.9*

SRO 3.9) Determination of Adeguate Shift Staffing (LOJPM6712)

G2.1.40 (Knowledge of refueling administrative Conduct of Operations R,N requirements. (CFR: 41.10 I 43.5 I 45.13) IMPORTANCE RO 2.8 SRO 3.9) Determine Acceptability of Installing Fuel Pool Gates (LOJPM6763)

G2.2.40 (Ability to apply Technical Specifications for a Equipment Control R,D system. (CFR: 41.10 I 43.2 I 43.5 I 45.3)

IMPORTANCE RO 3.4 SRO 4.7) Evaluate Jet Pump Operability (LOJPM6717)

G2.3.11 (Ability to control radiation releases.

(CFR: 41.11 I 43.4 I 45.10)

IMPORTANCE RO 3.8 SRO 4.3 Radiation Control R,M Calculate the Average Offgas Pre-Treatment Radioactivity Release Rate (LOJPM6720)

G2.4.41 (Knowledge of the emergency action level Emergency Procedures/Plan S,D thresholds and classifications. (CFR: 41.1 O I 43.5 I 45.11)

IMPORTANCE RO 2.9 SRO 4.6) ERP Classification and Reporting (LOJPM3097)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items)

  • 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, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

LIMERICK Date of Examination:

1/17/2017 Exam Level: RO

[g]

SRO-I D SRO-U D Operating Test No.:

1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Start a Reactor Recirculation Pump (System 202001 - Recirculation System; A,N,S 1 - Reactivity A3.02; 3.1/3.0) (LOJPM3121)

Control

b. RCIC Manual Slow Start Using FIC-49-1R600 (System 217000- RCIC; A4.04; D,S,P 2-Rx Water 3.6/3.6) (LOJPM3015)

Inventory Ctrl.

c. Main Turbine Bypass Valve Exercising (System 241000 - Rx/Turb Pressure N,S 3-Reactor Regulating System; A4.06; 3.9/3.9) (LOJPM3083)

Pressure Control

d. Shutdown Cooling Flow Adjustments (System 205000 - Shutdown Cooling; A4.04; A, D, EN, L, S 4 - Heat removal 3.4/3.3) (LOJPM3515) from core
e. Placing Safeguard Piping Fill System in Service (System 223001-Primary EN, L, N, S 5 - Containment Containment System and Auxiliaries; A2.01; 4.3/4.4) (LOJPM3118)

Integrity

f. Diesel Generator Fast Start From the MCR (System - 264000 - Emergency Diesel Generator; A4.04; 3.7/3.7) (LOJPM3130)

A,D,EN,S 6 - Electrical

g. Supply RECW to the Drvwell Coolers (System 400000 - Component Cooling D, L, S 8 - Plant service Water (CCWS); A2.01; 3.3/3.4) (LOJPM3028) systems
h. Manually Initiate a Control Room Radiation Isolation (System 290003 - Control D, EN,S 9 - Radioactivity Room HVAC; A4.01; 3.2/3.2) (LOJPM3024)

Release In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Bypassing a Control Rod From RMCS (System 201002 - Reactor Manual Control; D,R 1 - Reactivity A2.04; 3.2/3.1) (LOJPM2226)

Control

j. T-239 Defeating High RPV Level Interlocks (EPE295031 - Reactor Low Water E,N,R 2 - Reactor Water Level; EA 1.02; 4.5/4.5) (LOJPM2273)

Inventory

k. Start ESW Pump Per SE-1 (APE295016 - Control Room Abandonment; AA1.04; A, D, E, L, R 8-Plant service 3.1/3.2) (LOJPM2258) (Unit 2) systems All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 4

(C)ontrol room (D)irect from bank

S9/:58/:54 7

(E)mergency or abnormal in-plant

~1/<:1/<:1 2

(EN)gineered safety feature

~ 1 I<: 1 I<: 1 (control room system) 4 (L)ow-Power I Shutdown

~1/<:1/<:1 4

(N)ew or (M)odified from bank including 1 (A)

~2/<:2/<:1 4

(P)revious 2 exams

S 3 I ::; 3 I::; 2 (randomly selected) 1 (R)CA

~1/<:1/<:1 3

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

LIMERICK Date of Examination:

1/17/2017 Exam Level: RO D SRO-I [8J SRO-U D Operating Test No.:

1 Control Room Systems: 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Start a Reactor Recirculation Pump (System 202001 - Recirculation System; A,N,S 1 - Reactivity A3.02; 3.1/3.0) (LOJPM3121)

Control

b. RCIC Manual Slow Start Using FIC-49-1R600 (System 217000- RCIC; A4.04; D,S,P 2-Rx Water 3.6/3.6) (LOJPM3015)

Inventory Ctrl.

c.
d. Shutdown Cooling Flow Adjustments (System 205000 - Shutdown Cooling; A4.04; A, D, EN, L, S 4 - Heat removal 3.4/3.3) (LOJPM3515) from core
e. Placing Safeguard Piping Fill System in Service (System 223001-Primary EN, L, N, S 5 - Containment Containment System and Auxiliaries; A2.01; 4.3/4.4) (LOJPM3118)

Integrity

f. Diesel Generator Fast Start From the MCR (System - 264000 - Emergency Diesel A,D,EN,S 6 - Electrical Generator; A4.04; 3.7/3.7) (LOJPM3130)
g. Supply RECW to the Drywell Coolers (System 400000 - Component Cooling D, L, S 8 - Plant service Water (CCWS); A2.01; 3.3/3.4) (LOJPM3028) systems
h. Manually Initiate a Control Room Radiation Isolation (System 290003 - Control D,EN,S 9 - Radioactivity Room HVAC; A4.01; 3.2/3.2) (LOJPM3024)

Release In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Bypassing a Control Rod From RMCS (System 201002 - Reactor Manual Control; D,R 1 - Reactivity A2.04; 3.2/3.1) (LOJPM2226)

Control

j. T-239 Defeating High RPV Level Interlocks (EPE295031 - Reactor Low Water E,N,R 2 - Reactor Water Level; EA 1.02; 4.5/4.5) (LOJPM2273)

Inventory

k. Start ESW Pump Per SE-1 (APE295016 - Control Room Abandonment; AA 1.04; A,D,E,L,R 8-Plant service 3.1/3.2) (LOJPM2258) (Unit 2) systems All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 4

(C)ontrol room (D)irect from bank

S9/S8/:S4 7

(E)mergency or abnormal in-plant

<:1/:!:1/<:1 2

(EN)gineered safety feature

1 I~ 1 I;
: 1 (control room system) 4 (L)ow-Power I Shutdown

<:1/~1/<:1 4

(N)ew or (M)odified from bank including 1 (A)

<:2/~2/<:1 3

(P)revious 2 exams

S 3 Is 3 I :S 2 (randomly selected) 1 (R)CA

<:1/~1/<:1 3

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

LIMERICK Date of Examination:

1/17/2017 Exam Level: RO D SRO-I D SRO-U [8J Operating Test No.:

1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Start a Reactor Recirculation Pump (System 202001 - Recirculation System; A,N,S 1 - Reactivity A3.02; 3.1/3.0) (LOJPM3121)

Control

f. Diesel Generator Fast Start From the MCR (System - 264000 - Emergency Diesel A,D,EN,S 6 - Electrical Generator; A4.04; 3.7/3.7) (LOJPM3130)
h. Manually Initiate a Control Room Radiation Isolation (System 290003 - Control D,EN,S 9 - Radioactivity Room HVAC; A4.01; 3.2/3.2) (LOJPM3024)

Release In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. T-239 Defeating High RPV Level Interlocks (EPE295031 - Reactor Low Water E,N,R 2 - Reactor Water Level; EA 1.02; 4.5/4.5) (LOJPM2273)

Inventory

k. Start ESW Pump Per SE-1 (APE295016-Control Room Abandonment; AA1.04; A, D, E, L, R 8-Plant service 3.1/3.2) (LOJPM2258) (Unit 2) systems All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 3

(C)ontrol room (D)irect from bank S9/S8/S4 3

(E)mergency or abnormal in-plant

<:1/<:1/~1 2

(EN)gineered safety feature

<: 1 I<: 1 I~ 1 (control room system) 2 (L)ow-Power I Shutdown

<:1/<:1/~1 1

(N)ew or (M)odified from bank including 1 (A)

<:2/<:2/~1 2

(P)revious 2 exams s 3 Is 3 / S 2 (randomly selected) 0 (R)CA

<:1/<:1/~1 2

(S)imulator

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

Limerick January 2017 Date of Exam: 1/11,,

ILTNRC Exam Gro RO Kl A Category Points SRO-Only Points Tier K

K K

K K

K A

A A

A G

up 1

2 3

4 5

6 1

2 3

4 Total A2 G*

Total

1.

1 2

4 4

3 3

4 20 4

3 7

Emergenc y

2 1

1 1

1 2

1 7

2 1

3 Tier Plant Tot 3

5 5

4 5

5 27 6

4 10 Evolutions als 1

2 2

3 2

3 I

3 2

3 3

2 26 3

2 5

2.

2 1

1 1

2 1

1 1

1 1

1 1

12 0

2 1

3 Plant Systems Tier Tot 3

3 4

4 4

2 4

3 4

4 3

38 5

3 8

als

3. Generic Knowledge &

1 2

3 4

l 2

3 4

Abilities 10 7

Categories 3

3 2

2 2

2 2

I 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). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category.)

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 with justification; operationally important, site-specific systems/evolutions 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 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 KIAs 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 (I Rs) 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 a category 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.

G*

Generic KIAs

ES-401 2

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A 1 A2 G

KIA Topic(s)

AA2.0 l - Ability to determine and/or 295018 Partial or Total Loss of interpret the following as they apply to CCW/8 x

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Component temperatures EA2.04 - Ability to determine and/or interpret 295037 SCRAM Conditions the following as they apply to SCRAM Present and Reactor Power Above x

CONDIT!ON PRESENT AND REACTOR APRM Downscale or Unknown/ I POWER ABOVE APRM DOWNSCALE OR UNKNOWN : Suppression Pool Temperature AA2.17 - Ability to determine and interpret 600000 Plant Fire On-site I 8 x

the following as they apply to PLANT FIRE ON SITE: Systems that may be affected by the fire 2.2.36-Equipment Control: Ability to 295019 Partial or Total Loss of x

analyze the effect of maintenance activities, Inst. Air/ 8 such as degraded power sources, on the status of limiting conditions for operations.

295005 Main Turbine Generator x

2.4.6 - Emergency Procedures I Plan:

Trip/ 3 Knowledge ofEOP mitigation strategies.

2.4.47 - Emergency Procedures I Plan: Ability 295026 Suppression Pool High x

to diagnose and recognize trends in an Water Temp. I 5 accurate and timely manner utilizing the appropriate control room reference material.

AA2. I 0 - Ability to determine and/or 700000 Generator Voltage and interpret the following as they apply to x

GENERATOR VOLT AGE AND ELECTRIC Electric Grid Disturbances GRID DISTURBANCES: Generator overheating and the required actions.

AKI.OJ - Knowledge of the operational 295001 Partial or Complete Loss implications of the following concepts as they of forced Core Flow Circulation I x

apply to PARTIAL OR COMPLETE LOSS 1&4 OF FORCED CORE FLOW CIRCULATION

Natural circulation EKl.01 - Knowledge of the operational 295026 Suppression Pool High x

implications of the following concepts as they Water Temp./ 5 apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSH EK2.04 - Knowledge of the interrelations 295038 High Off-site Release x

between HIGH OFF-SITE RELEASE RATE Rate/ 9 and the following: Stack-gas monitoring system: Plant-Specific 295031 Reactor Low Water Level EK2.03 - Knowledge of the interrelations 12 x

between REACTOR LOW WATER LEVEL and the following: Low pressure core spray AK2.04 - Knowledge of the interrelations 600000 Plant Fire On-site I 8 x

between PLANT FIRE ON SITE and the following: Breakers, relays, and disconnects EK2.11 - Knowledge of the interrelations 295037 SCRAM Conditions between SCRAM CONDITION Present and Reactor Power Above x

PRESENT AND REACTOR POWER APRM Downscale or Unknown / I ABOVE APRM DOWNSCALE OR UNKNOWN and the following: RMCS:

Plant-Specific EK3.04 - Knowledge of the reasons for 295024 High Drywell Pressure I 5 x

the following responses as they apply to HIGH DRYWELL PRESSURE :

Emerqencv depressurization Imp.

Q#

3.4 76 4.1 77 3.6 78 4.2 79 4.7 80 4.2 81 3.8 82 3.5 39 3.0 40 4.2 41 4.2 42 2.5 43 3.8 44 3.7 45

ES-401 2

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A 1 A2 G

KIA Topic(s)

AK3.05 - Knowledge of the reasons for 295021 Loss of Shutdown the following responses as they apply to x

LOSS OF SHUTDOWN COOLING :

Cooling/ 4 Establishing alternate heat removal flow paths AK3.02 - Knowledge of the reasons for 295016 Control Room x

the following responses as they apply to Abandonment I 7 CONTROL ROOM ABANDONMENT :

Turbine trip AA 1.04 - Ability to operate and/or monitor 295003 Partial or Complete Loss x

the following as they apply to PARTIAL of AC I 6 OR COMPLETE LOSS OF A.C. POWER

D.C. electrical distribution system AA 1.02 - Ability to operate and/or monitor 295018 Partial or Total Loss of the following as they apply to PARTIAL CCW/8 x

OR COMPLETE LOSS OF COMPONENT COOLING WATER:

System loads AA 1.05 - Ability to operate and/or monitor 700000 Generator Voltage and the following as they apply to x

GENERATOR VOLTAGE AND Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

EnQineered safety features.

AA2.04 - Ability to determine and/or 295023 Refueling Ace Cooling x

interpret the following as they apply to Mode/ 8 REFUELING ACCIDENTS : Occurrence of fuel handlinQ accident EA2.01 - Ability to determine and/or 295028 High Drywell x

interpret the following as they apply to Temperature I 5 HIGH DRYWELL TEMPERATURE:

Drywell temperature AA2.03 - Ability to determine and/or 295005 Main Turbine Generator x

interpret the following as they apply to Trip I 3 MAIN TURBINE GENERATOR TRIP:

Turbine valve position 2.4.18 - Emergency Procedures I Plan:

295025 High Reactor Pressure I 3 x

Knowledge of the specific bases for EOPs.

2.4.4 -.Ability to recognize abnormal indications for system 295030 Low Suppression Pool x

operating parameters that are Water Level I 5 entry-level conditions for emergency and abnormal operating procedures.

2.4.46 - Emergency Procedures I Plan:

295006 SCRAM I 1 x

Ability to verify that the alarms are consistent with the plant conditions.

2.4.49 - Emergency Procedures I Plan:

295004 Partial or Total Loss of Ability to perform without reference to DCPwr/6 x

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

AK3.01 - Knowledge of the reasons for 295019 Partial or Total Loss of the following responses as they apply to Inst. Air I 8 x

PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR : Backup air system supply: Plant-Specific Kl A Category Totals:

2 4

4 3

3/4 4/3 Group Point Total:

Imp.

Q#

3.6 46 3.7 47 3.6 48 3.3 49 3.9 50 3.4 51 4.0 52 3.1 53 3.3 54 4.5 55 4.2 56 4.6 57 3.3 58 I

2017

ES-401 3

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

AA2.03 -Ability to determine and/or 295010 High Drywell Pressure I 5 x

interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell radiation levels 2.4.49 - Emergency Procedures I Plan:

295002 Loss of Main Condenser Ability to perfom1 without reference to Vac I 3 x

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

AA2.04 - Ability to determine and/or 2950 l 7 High Off-site Release Rate x

interpret the following as they apply to 19 HIGH OFF-SITE RELEASE RATE:

Source of off-site release AKI.01 - Knowledge of the operational 295012 High Drywell implications of the following concepts as x

they apply to HIGH DRYWELL Temperature I 5 TEMPERATURE : Pressure/temperature relationship AK2.04 - Knowledge of the interrelations 295014 Inadvertent Reactivity x

between INADVERTENT REACTIVITY Addition I l ADDITION and the following: Void concentration AK3.02 - Knowledge of the reasons for the 295017 High Off-site Release x

following responses as they apply to HIGH Rate I 9 OFF-SITE RELEASE RATE: Plant ventilation AA!.08 - Ability to operate and/or monitor 295008 High Reactor Water Level x

the following as they apply to HIGH 12 REACTOR WATER LEVEL : Feedwater system AA2.02 - Ability to determine and/or 295022 Loss ofCRD Pumps I 1 x

interpret the following as they apply to LOSS OF CRD PUMPS : CRD system status 2.1.31 - Conduct of Operations: Ability to 295002 Loss of Main Condenser x

locate control room switches, controls, and Vac I 3 indications, and to determine that they correctly reflect the desired plant lineup.

AA2.02 - Ability to determine and/or 295010 High Drywell Pressure I 5 x

interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell pressure Kl A Category Totals:

1 1

1 1

212 1/1 Group Point Total:

Imp.

Q#

3.6 83 4.4 84 4.3 85

3.

59 3

3.2 60

3.

61 3

3.

62 5

3.

63 3

4.

64 6

3.

65 8

I 713

ES-401 System # I Name K

K 1

2 400000 Component Cooling Water 215005 APRM I LPRM 263000 DC Electrical Distribution 215003 !RM 239002 SRVs 215003 !RM 217000 RCIC x

205000 Shutdown Cooling x

206000 HPCI x

300000 Instrument Air 4

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

K A

A2 A

A G

3 4

5 6

1 3

4 A2.04 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those x

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: Radiation monitoring system alarm Al.OJ -Ability to (a} predict the impacts of the following on the A VERA GE POWER RANGE MONITOR/LOCAL POWER x

RANGE MONITOR SYSTEM ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Power supply degraded 2.1.27 - Conduct of Operations:

x Knowledge of system purpose and I or function.

2.2.40 - Equipment Control: Ability x

to apply technical specifications for a system.

A2.06 - Ability to (a} predict the impacts of the following on the RELIEF/SAFETY VAL YES; and x

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

Reactor high pressure K5.01 - Knowledge of the operational implications of the x

following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

Detector operation K1.07 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: Leak detection K2.02 - Knowledge of electrical power supplies to the following:

Motor operated valves K2.04 - Knowledge of electrical power supplies to the following:

Turbine control circuits: BWR-2,3,4 K3.02 - Knowledge of the effect that a loss or malfunction of the x

(INSTRUMENT AIR SYSTEM) will have on the following:

Systems having pneumatic valves and controls Imp Q#

3.0 86 3.1 87 4.0 88 4.7 89 4.3 90 2.6 I

3.1 2

2.5 3

2.5 4

3.3 5

ES-401 System # I Name K

K 1

2 259002 Reactor Water Level Control 262001 AC Electrical Distribution 218000 ADS 209001 LPCS 263000 DC Electrical x

Distribution 264000 EDGs 400000 Component Cooling Water 203000 RHR/LPCI: Injection Mode 223002 PCIS/Nuclear Steam Supply Shutoff 4

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

K A

A2 A

A G

3 4

5 6

1 3

4 K3.02 - Knowledge of the effect that a loss or malfunction of the x

REACTOR WATER LEVEL CONTROL SYSTEM will have on following: Reactor feedwater svstem K4.04 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION x

design feature(s) and/or interlocks which provide for the following: Protective relaying K4.01 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM x

design feature(s) and/or interlocks which provide for the following: Prevent inadvertent initiatior of ADS logic K5.04 - Knowledge of the operational implications of the x

following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM : Heat removal (transfer) mechanisms Kl.02 - Knowledge of the physical connections and/or cause-effect relationships between D.C.

ELECTRICAL DISTRIBUTION and the following: Battery charger and battery K6.07 - Knowledge of the effect that a loss or malfunction of the x

following will have on the EMERGENCY GENERA TORS (DIESEUJET) : Cooling water system K3.01 - Knowledge of the effect x

that a Joss or malfunction of the CCWS will have on the following: Loads cooled by CCWS A 1.09 - Ability to predict and/or monitor changes in parameters associated with operating the x

RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Component cooling water systems A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT x

ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:

SPDS/ERIS/CRIDS/GDS:

Plant-Specific Imp Q#

3.7 6

2.8 7

3.7 8

2.8 9

3.2 IO 3.8 II 2.9 12 2.9 13 2.5 14

ES-401 System #I Name K

K 1

2 239002 SRVs 215004 Source Range Monitor 262002 UPS (AC/DC) 212000 RPS 215005 APRM I LPRM

.211000 SLC 261000 SGTS 211000 SLC 261000 SGTS 263000 DC Electrical Distribution 4

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

K A

A2 A

A G

3 4

5 6

1 3

4 A2.02 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, x

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leakv SRV A2.05 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based x

on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic ooeration of detectors/system A3.01 - Ability to monitor automatic operations of the x

UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) including:

Transfer from preferred to alternate source A3.07 - Ability to monitor automatic operations of the x

REACTOR PROTECTION SYSTEM including: SCRAM air header pressure A4.06-Ability to manually x

operate and/or monitor in the control room: Verification of proper functioning/ operability A4.06 - Ability to manually x

operate and/or monitor in the control room: RWCU system isolation 2.1.27 - Conduct of Operations:

x Knowledge of system purpose and I or function.

2.2.36 - Equipment Control:

Ability to analyze the effect of x

maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

A4.05 - Ability to manually operate and/or monitor in the x

control room: Drywell to suppression chamber/torus differential pressure: Mark-I, II KS.01 - Knowledge of the operational implications of the following concepts as they apply x

to D.C. ELECTRICAL DISTRIBUTION : Hydrogen generation during battery charging.

Imp Q#

3.1 15 3.3 16 2.8 17 3.6 18 3.2 19 3.9 20 3.9 21 3.1 22 2.9 23 2.6 24

ES-401 System # I Name K

K 1

2 206000 HPCI 203000 RHR/LPCI: Injection Mode Kl A Category Totals:

2 2

4 Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

K A

A2 A

A G

3 4

5 6

1 3

4 A 1.06 - Ability to predict and/or monitor changes in parameters associated with operating the x

HIGH PRESSURE COOLANT INJECTION SYSTEM controls including: System flow: BWR-2,3,4 A3.02 - Ability to monitor automatic operations of the x

RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including:

Pump start 3

2 3

1 3

2/3 3

3 212 Group Point Total:

Imp Q#

3.8 25 4.0 26 I

2615

ES-401 System # I Name K

K 1

2 202002 Recirculation Flow Control 226001 RHR/LPCI: CTMT Spray Mode 290001 Secondary CTMT 245000 Main Turbine Gen. I x

Aux.

202001 Recirculation x

290001 Secondary CTMT 271000 Off-gas 256000 Reactor Condensate 286000 Fire Protection 5

Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

K A A2 A

A 3

4 5

6 1

3 4

G A2.04 - Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use x

procedures to correct, control. or mitigate the consequences of those abnormal conditions or operations:

Recirculation pump speed mismatch between loops: Plant-Specific 2.4.35 - Emergency Procedures I Plan: Knowledge of local auxiliary x

operator tasks during emergency and the resultant operational effects.

A2.03 - Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; x

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High area radiation Kl.09 - Knowledge of the physical connections and/or cause-effect relationships between MAIN TURBINE GENERA TOR AND AUXILIARY SYSTEMS and the following: D. C. electrical distribution K2.01 - Knowledge of electrical power supplies to the following:

Recirculation pumps: Plant-Specific K3.0I - Knowledge of the effect that a loss or malfunction of the x

SECONDARY CONTAINMENT will have on following: Off-site radioactive release rates K4.06 - Knowledge of OFFGAS SYSTEM design feature(s) x and/or interlocks which provide for the following: Decay of fission product gases to particulate dauahters K5.08 - Knowledge of the operational implications of the x

following concepts as they apply to REACTOR CONDENSATE SYSTEM: Heat removal (transfer) mechanisms K6.01 - Knowledge of the effect that a loss or malfunction of the x

following will have on the FIRE PROTECTION SYSTEM A.C.

electrical distribution: Plant-Specific Q

Imp.

3.2 91 4.0 92 3.6 93 2.7 27 3.2 28 4.0 29 2.7 30 2.6 31 3.1 32

ES-401 System # I Name K

K 1

2 219000 RHR/LPCI:

Torus/Pool Cooling Mode 214000 RPIS 288000 Plant Ventilation 230000 RHR/LPCI:

Torus/Pool Spray Mode 201001 CRD Hydraulic 223001 Primary CTMT and Aux.

KIA Category Totals:

1 1

5 Form ES-401-1 Limerick January 2017 IL T NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

K A

A2 A

A G

3 4

5 6

1 3

4 A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the x

RHR/LPCI:

TORUS/SUPPRESSION POOL COOLING MODE controls including: Suppression pool temperature A2.03 - Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM; and x

(b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Overtravel/in-out A3.01 - Ability to monitor automatic operations of the x

PLANT VENTILATION SYSTEMS including:

Isolation/initiation signals A4.13 - Ability to manually x

operate and/or monitor in the control room: Suppression chamber pressure 2.2.44 - Equipment Control:

Ability to interpret control room indications to verify the status x

and operation of a system, and understand how operator actions and directives effect plant and system conditions.

K4.04 - Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) x and/or interlocks which provide for the following: Prevents hydrogen from reaching an explosive mixture 1

2 1

1 1

1/2 1

1 1/1 Group Point Total:

Imp.

Q 4.0 33 3.6 34 3.8 35 4.0 36 4.2 37 3.5 38 I

12/3

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

Form ES-401-3 Facility:

Limerick January 2017 IL T NRC Date:

Exam Category KIA#

RO SRO-Only Topic IR Q#

IR Q#

2.1.13 Knowledge of facility requirements for 3.2 94 controllinq vital I controlled access.

2.1.36 Knowledge of procedures and limitations 4.1 99 involved in core alterations.

1.

Conduct 2.1.8 Ability to coordinate personnel activities 3.4 66 of Operations outside the control room.

Ability to explain and apply all system limits 2.1.32 and precautions.

3.8 67 2.1.25 Ability to interpret reference materials, such 3.9 75 as qraphs, curves, tables, etc.

Subtotal 3

2 2.2.20 Knowledge of the process for managing 3.8 95 troubleshooting activities.

2.2.43 Knowledge of the process used to track 3.3 98 inoperable alarms.

2.

2.2.21 Knowledge of pre-and post-maintenance 2.9 68 Equipment operability requirements.

Control Ability to analyze the effect of maintenance 2.2.36 activities, such as degraded power sources, 3.1 69 on the status of limiting conditions for operations.

2.2.39 Knowledge of less than one hour technical 3.9 74 specification action statements for systems.

Subtotal 3

2 Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 100 portable survey instruments, personell monitorinq equipment, etc.

Knowledge of radiation or contamination

3.

2.3.14 hazards that may arise during normal, 3.8 96 Radiation abnormal or emergency conditions or Control activities Knowledge of Radialogical Safety Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

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

Form ES-401-3 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.

Subtotal 2

2 Ability to take actions called for in the facility 2.4.38 emergency plan, including supporting or 4.4 97 actinq as emerqencv coordinator if required.

4.

Emergency 2.4.11 Knowledge of abnormal condition 4.0 72 Procedures I procedures.

Plan Knowledge of local auxiliary operator tasks 2.4.35 during emergency and the resultant 3.8 73 operational effects.

Subtotal 2

1 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/A's Form ES-401-4 Tier I Group Randomly Selected Reason for Rejection KIA K1.03 - Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: Battery ventilation 2/1 There are no DC components, all fans are MCC level 480 volt power (ac Q#1 263000 K1.03 control power) all solenoids dampers are ac powered. This leaves the cause and effect which would lead to duplication/overlap with Q 24 263000 K5.01 Hydrogen generation during battery charging.

K1.03 removed random number generator used to select from remaining KA's K1.02 selected Battery charger and battery AK3.03 Knowledge of the reasons for the following responses as they apply to LOSS OF SHUTDOWN COOLING: Increasing drywell cooling There is no procedural direction at LGS to increase Drywell 1/1 295021 AK3.03 cooling on a loss of Shutdown cooling, also the difficulty of any Q#46 question for this would be low and 4 plausible distractors would not be possible AK3.03 removed from 295021 AK3's random number generator used to reselect AK3.05 selected AA2.05 - Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS: Entry conditions of 1/1 295023 Refueling emergency plan Q51 Ace Cooling Mode I Unable to write an RO level question to AA2.05 8

AA2.05 removed random number generator used to select from the remaining 4 AA2.01-2.04 AA2. 04 Occurrence of fuel handling accident selected 2.4.41 - Emergency Procedures I Plan: Knowledge of the 111 295030 Low emergency action level thresholds and classifications. Unable to Q55 Suppression Pool write an RO question to this KIA Water Level I 5 Reselected with random number generator from generic 2.4 not already used in RO exam 2.4.4 selected EKI.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE:

Protection of the general public Ill 295038 High Off-site KA deselected due to inability to write question with required LOD due Q41 Release Rate I 9 to overlap with other questions in this exam or cert exam.

Unable to write questions with sufficient LOD for the remaining 2 EK I KAs Used random number generator to select EK2.04 2/1 215005 Average A4.01 IRM/APRM recorder. unable to write a question with Power Range Q19 Monitor/Local Power required LOO. used random number generator and reselected Ranae Monitor Svs A4.06 Verification of proper functioning/ operability 2.3.6 Ability to Unable to write a sufficiently difficult SRO question.

3 Q96 approve release Randomly selected 2.3.14 from remaining generic 2.3 permits.

1/1 Q77 295037 EA2.0.5 Unable to write a sufficiently difficult SRO question.

Reselected EA2.0.4 2/1 Q12 400000 Component Knowledge of the effect that a loss or malfunction of the CCWS will have on the Cooling Water following:K6.06 HTX and condenser reselected K3.0l : Loads cooled by CCWS

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