ML16064A160

Final Outlines (Folder 3)

ML16064A160
Person / Time
Site:	Limerick
Issue date:	03/01/2016
From:	D'Antonio J Operations Branch I
To:	Exelon Generation Co
Shared Package
ML15286A047	List: IR 05000352/2016301 ML16008A170 ML16064A159 ML16064A160 ML16064A162 ML16064A163 ML16088A361 ML16088A367 ML16090A027 ML16145A333 ML18149A504
References
TAC U01912
Download: ML16064A160 (16)

Text

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

2016 NRC Date of Exam:

RO Kl A Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total

).

~r.. a.

1.

1 4

3 3 1t 3

4

~

3 20 4

3 7

Emergency n:*

2 1

1 1

• )~ 2 1

1 7

2 1

3 Plant Tier l'*:r~~

Evolutions Totals 5

4 4

5 5 **;;:;

4 27 6

4 10 1

3 3

2 2

2 3

2 2

2 2

3 26 2

3 5

2.

Plant 2

1 1

1 1

1 1

1 1

1 2

1 12 0

i 2

3 Systems Tier Totals 4

4 3

3 3

4 3

3 3

4 4

38 3

5 8

1 2

3 4

I

") "

4

3. Generic Knowledge & Abilities 10 7

Categories 3

2 3

2 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). (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 Kl As 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 Kl A categories.

7.

The generic (G) Kl As 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 KIAs.

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.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA 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.

G*

Generic KIAs

ES-401 2

2016 NRC Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

Imp.

Q#

A.C. POWER : Selective tripping k.:*

AK3.03 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to Trip/3 x

{;

MAIN TURBINE GENERATOR TRIP:

2.8 47 Feedwater temperature decrease

. :1>*** ' t*

AA 1.03 - Ability to operate and/or 295001 Partial or Complete Loss monitor the following as they apply to of Forced Core Flow Circulation I l x

i>:Yi

';Ye PARTIAL OR COMPLETE LOSS OF 2.6 48

&4 FORCED CORE FLOW CIRCULATION

RMCS: Plant-Soecific

j EA 1. 04 - Ability to operate and/or 295025 High Reactor Pressure I 3 x

(f,:*:;. monitor the following as they apply to 3.8 49

.....*.* v 1;1;~:'

HIGH REACTOR PRESSURE: HPCI:

Plant-Soecific

~;~'

EA 1.10 - Ability to operate and/or monitor the following as they apply to 295037 SCRAM Conditions I>

SCRAM CONDITION PRESENT AND Present and Reactor Power Above x

I,. ~f:

REACTOR POWER ABOVE APRM 3.7 50 APRM Downscale or Unknown I 1 DOWNSCALE OR UNKNOWN :

Alternate boron injection methods:

{

Plant-Soecific

'******** * '?>:

EA2.05 - Ability to determine and/or 295028 High Drywell Temperature

.Y

0) interpret the following as they apply to 15

?:~.

HIGH DRYWELL TEMPERATURE:

3.6 51

• ? **

Torus/suppression chamber pressure:

,f;..

Plant-Soecific lz

• ~: ;:1;~

AA2.07 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND 3.6 52 Electric Grid Disturbances I

ELECTRIC GRID DISTURBANCES:

'i~~*

Operational status of engineered safety features.

i't'~

~**1?/f*

AA2.06 - Ability to determine and/or 295006 SCRAM I 1 interpret the following as they apply to 3.5 53 SCRAM : Cause of reactor SCRAM 295004 Partial or Total Loss of

• ~'*****

. \\, ;; 2.1.20 - Conduct of Operations: Ability to interpret and execute procedure 4.6 54 DCPwr/6 I::\\ >.* ?:*~;. steos.

295019 Partial or Total Loss of

,\\/'

,:t>***

2. 1.27 - Conduct of Operations:

Inst. Air I 8 ti Knowledge of system purpose and I or 3.9 55 function.

/ ;}*?

• • • . ~:

2.2.3 - Equipment Control: (multi-unit 295016 Control Room license) Knowledge of the design, 3.8 56 Abandonment I 7 I

procedural, and operational differences between units.

~j.***

/),*

EK1.01 - Knowledge of the operational 295031 Reactor Low Water Level x

implications of the following concepts as 12 they apply to REACTOR LOW WATER 4.6 57 LEVEL : Adeauate core coolina Ii AA2.01 - Ability to determine and/or 295023 Refueling Ace Cooling x

interpret the following as they apply to 3.6 58 Mode/ 8 REFUELING ACCIDENTS : Area radiation levels Kl A Category Totals:

4 3

3 3

414.

3/3 Group Point Total:

I 2017

ES-401 System # I Name K

K K

1 2

3 264000 EDGs 215005 APRM I LPRM 212000 RPS 400000 Component Cooling Water 203000 RHR/LPCl: Injection Mode 206000 HPCI x

262002 UPS (AC/DC) x 262001 AC Electrical Distribution x

211000 SLC x

4 2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

A2. l 0 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS I;:~*, __.

(D !ESEU JET) : imd (b) based on rhose predi..:tions, use procedures to correct, contml, or rnitig:.ue the con;equences of those abnormal conditiorn, or operations: LOC A A2.02 - Ability to (a) predict the Ii,::.

impacts of the following on the I..

AVERAGE PO\\VER RANGE

~~J; MONITORfLOCAL POWER RA'l'GE MONITOR SYSTElvl; and (b) based on those predictions.

use procedure;; to correct, control,

,/

or mitigate the consequences uf those abnormal ~onditions Upscale or downscale trins 1 *::;*:

2.2.42 - Equipment Cuntrol::

Ir Ability to recogni?,e system x

parameters that are entry-lewl

.ffi;:;

'.,l conditions for Technic1tl Specifications.

. \\'.

. -:; 2.2.4 - Equipment Control: (multi**

I*

unit license) Ability to explain the

• _~;4' i.x variations in control board layouts.

systems, instmrnentation and procedural actions between units at

• 'i

  ?J a facility.

2. l.31 - CondLL<.:t of Operations:

1:1c..

Ability to locate control room switches, controls, and indications, i *::

and to determine that they correctly I**

reflect the desired plant lineun.

Kl.04 - Knowledge of the physical I;:

connections and/or cause-effect relationships between HIGH

_:\\~(

PRESSURE COOLANT INJECTION SYSTEM and the following: Reactor feedwater system: BWR-2,3,4 K1.17 - Knowledge of the physical connections and/or cause-effect relationships between UNINTERRUPTABLE

"<\\!>

POWER SUPPLY (A.C./D.C.)

and the following: Scram solenoid valves: Plant-Specific I

K2.01 - Knowledge of electrical I:

power supplies to the following:

Off-site sources of power K2.02 - Knowledge of electrical power supplies to the following:

Exolosive valves Imp Q#

4.2 86 3.7 87 4.6 88 3.6 89 4.3 90 3.6 1

3.1 2

3.3 3

3.1 4

ES-401 System # I Name K

K K

1 2

3 261000 SOTS 215003 IRM 264000EDGs 239002 SRVs 263000 DC Electrical Distribution 300000 Instrument Air 217000 RCIC 223002 PCIS/Nuclear Steam Supply Shutoff 218000 ADS 215004 Source Range Monitor 4

2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

• . ¥ A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the x r STANDBY GAS TREATMENT j

SYSTEM controls including: Off-site release levels

(

A2.05 - Ability to (a) predict the impacts of the following on the I.

INTERMEDIATE RANGE

.)/

MONITOR (IRM) SYSTEM ; and

',.~

(b) based on those predictions, x'r use procedures to correct,

//

control, or mitigate the consequences of those

'.*/

abnormal conditions or operations: Faulty or erratic

.. /.

{..

operation of detectors/system A2.08 - Ability to (a) predict the I.

impacts of the following on the EMERGENCY GENERATORS (DIESEUJET) ; and (b) based on those predictions, use x*

procedures to correct, control, or mitigate the consequences of 1*.

those abnormal conditions or operations: Initiation of 1 **

Ix. '

emergency generator room fire I> "3 protection system A3.02 - Ability to monitor I*

automatic operations of the x

RELIEF/SAFETY VALVES h

including: SRV operation on

. ;/' hiah reactor pressure A3.01 - Ability to monitor automatic operations of the D.C.

x ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating

• • .., liahts A4.01 - Ability to manually x

operate and/or monitor in the control room: Pressure aauaes A4.05 - Ability to manually x

operate and/or monitor in the control room: Reactor water level 2.4.9 - Emergency Procedures I

+

Plan: Knowledge of low power I x

shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitiqation strateaies.

2.4.20 - Emergency Procedures x

I Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.

2.1.30 - Conduct of Operations:

x Ability to locate and operate components, including local controls.

Imp Q#

3.2 14 3.3 15 3.3 16 4.3 17 3.2 18 2.6 19 4.1 20 3.8 21 3.8 22 4.4 23

ES-401 System # I Name K K K

1 2

3 290002 Reactor Vessel Internals 286000 Fire Protection 214000 RP!S 201002RMCS x

223001 Primary CTMT and x

Aux.

288000 Plant Ventilation x

290002 Reactor Vessel Internals 271000 Off-gas 241000 ReactoriTurbine Pressure Regulator 239001 Main and Reheat Steam 5

2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K A A2 A

A G

4 5

6 1

3 4

A2.01 - Ability to (a) predict the impacts of the fr,Jlowing on the REACTOR VESSEL INTERNALS

• • • *i.

and ( b) based on those predictions, use procedures to correct, control. or mitigate the I*

consequences of ihose abnormal conditions or operations: LOCA 2.2.25 - Equipment Control:

Knowledge of bases in technical sped ficat.ions for limiting

~;

,*onditions for operations and safety limits.

2.4.34 - Emergency Prcxedures i Plan: Knowledge of RO tasks

.. c.;;,

X *. performed outside thi.: main control room during an emergency and the

. resultam operational effects.

\\' w.

1/':~ ~.

Kl.01 - Knowledge of the physical connections and/or cause-effect 1)**

relationships between REACTOR o.;','

MANUAL CONTROL SYSTEM

• )~

1;..

and the following: Control rod drive hydraulic system K2.09 - Knowledge of electrical

'J3,i1/~:

power supplies to the following:

.'i/""1' Drywell cooling fans: Plant-Specific

)~i K3.02 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION

./>'

SYSTEMS will have on following:

I\\;;

Reactor building temperature:

Plant-Specific K4.05 - Knowledge of

.. REACTOR VESSEL x

INTERNALS design feature(s) and/or interlocks which provide for the following: Natural

)

circulation KS.09 - Knowledge of the operational implications of the x

following concepts as they apply to OFFGAS SYSTEM :

Hydrogen and oxygen recombination K6.06 - Knowledge of the effect that a loss or malfunction of the x

following will have on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM : Reactor pressure A 1.10 - Ability to predict and/or monitor changes in parameters x

associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including:

Reactor power Imp. a 4.0 91 4.'.?.

92 4.l 93 3.2 27 2.7 28 2.9 29 3.3 30 2.6 31 3.8 32 3.8 33

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

Form ES-401-3 Facility:

2016 NRG Date:

Category KIA#

Topic RO SRO-Only IR Q#

IR Q#

2.1.42 Knowledge of new and spent fuel movement 3.4 94 procedures.

Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew complement, 3.9 98 overtime limitations, etc.

1.

2.1.9 Ability to direct personnel activities inside the 2.9 66 Conduct control room.

of Operations Knowledge of industrial safety procedures 2.1.26 (such as rotating equipment, electrical, high 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.6 Ability to manage the control room crew 3.8 75 durinq plant transients.

Subtotal

,... '. f 3

• .;:, i~

2 2.2.35 Ability to determine Technical Specification 4.5 95 Mode of Operation.

Ability to perform pre-startup procedures for 2.2.1 the facility, including operating those controls 4.4 100 associated with plant equipment that could affect reactivity.

2.

(multi-unit license) Ability to explain the Equipment 2.2.4 variations in control board layouts, systems, 3.6 68 Control instrumentation and procedural actions between units at a facility.

Ability to interpret control room indications to 2.2.44 verify the status and operation of a system, 4.2 69 and understand how operator actions and directives effect plant and system conditions.

Subtotal

[;

2 2

Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, 3.1 96 portable survey instruments, personnel

3.

monitorinq equipment, etc.

Radiation Control 2.3.11 Ability to control radiation releases.

3.8 70

ES-401 Record of Rejected Kl A's Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected Kl A Q# 37 At LGS, there are no times when the RBM is used 212 215002 I 2.4.18 during Emergency Procedure use. This is due to the RBM supporting Control Rod Withdraw only.

Replaced with 214000 RPIS 2.4.2 3

G3 I 2.3.6 Q# 96 Duplicated in operating test replaced with 2.3.15 l I 2 295022 I Q# 85 The subject KIA isn't relevant at the subject facility.

AA2.03 Replaced with 295022 Loss of CRD Pumps AA2.02 I

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1/18/16 Examination Level:

RO

~

SRO D Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.20 (Ability to interpret and execute procedure steps) Evaluate Valve Stroke Data ST-6-107-200-0 Conduct of Operations D,R (0764)

G. 2.1.8 (Ability to coordinate personnel activities outside the control room) - Fire Alarm In Inverter Conduct of Operations N,R Room JPM (0715)

G.2.2.12 (knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod Equipment Control D,R withdrawal Check (0752)

G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and Radiation Control N,R emergency conditions) Radioactive Spill Response (3122)

Emergency Plan NIA 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 (s 3 for ROs; s 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:

LIMERICK Date of Examination:

1 /18/16 Examination Level:

RO

~

SRO D Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.20 (Ability to interpret and execute procedure steps) Evaluate Valve Stroke Data ST-6-107-200-0 Conduct of Operations D,R (6764)

G. 2.1.8 (Ability to coordinate personnel activities outside the control room) - Fire Alarm In Inverter Conduct of Operations Room N,R JPM (3715)

G.2.2.12 (knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod Equipment Control D,R withdrawal Check (6752)

G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and Radiation Control N,R emergency conditions) Radioactive Spill Response (3122)

Emergency Plan NIA 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)

Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1 /18/16 Examination Level:

RO D SRO

~

Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.4 Knowledge of individual licensed operator Conduct of Operations D,R responsibilities related to shift !staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.)

Reactivate SRO License (6710) 2.1.25 (Ability to interpret reference material such as graphs, curves, tables, etc.)

Conduct of Operations D,R Evaluate valve data -JPM (6766)

G.2.2.12 (Knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod withdrawal Equipment Control D,R Check (6753)

G2.3.14 (knowledge of radiation and contamination Radiation Control N,R hazards that may arise during normal, abnormal, and emergency conditions) Radiation Transportation Accident assessment (Time Critical) (3123)

G.2.4.41 Knowledge of the emergency action level Emergency Plan D,R thresholds and classifications.

ERP Classification and Reporting (Time Critical)

(3124)

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 (s; 3 for ROs; s; 4 for SROs & RO retakes)

(N)ew or (M}odified from bank (~ 1)

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

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO 181 SRO-I D SRO-U 0 Operating Test No.:

1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-!:!

System I JPM Title Type Code*

Safety Function

a. Response to EHC Leaks (3109) 241000 A4.08 3.5 N,S 3

b. RCIC Manual Slow Start (3022) 217000 A2.08 3.0 D,A,S,EN 2

c. Shutdown D11 Diesel Generator (3027) 264000 A4.04 3.7 D,S 6

d. Reset Group 2A NSSSS Isolation (3071) 223002 A4.03 3.6 D,S,L 5

e. Resetting ASD Speed Hold (3529) 202001 A 1.01 3.6 D,A,S 4

f. Alternate Cooling of RECW (3052) 400000 A2.01 3.3 D,S,L 8

g. SBGT Manual Start with Charcoal Encl Hi Temp (3528) 2012 NRC D,P,A,S,EN 9

261000 A4.02 3.31

h. Control Rod Exercise Test (3034) 201003 A2.01 3.4 N,A,S 1

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

i.

D11 Diesel Local Start (2236) 264000 A2.09 3. 7 N,A,E,EN 6

j. Placing Alternate CRD Flow Cont in service (2200)

D,R 1

201001 A1.03 2.9

k. Bypassing Rx HVAC Isolation (3214) 288000 A2.01 3.3 D,R,E,EN 9

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 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant

<?:1/<?:1/<?:1 (EN)gineered safety feature

<:1 I <:1 I=:: 1 (control room system)

(L)ow-Power I Shutdown

<?:1/<?:1/'2:1 (N)ew or (M)odified from bank including 1 (A)

<?:2/<?:2/'2:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA

<?:1/<?:1/'2:1 (S)imulator

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO D SRO-I D SRO-U ~

Operating Test No.:

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

Safety Function

a. Response to EHC Leaks (3109) 241000 A4.08 3.5 N,S 3

b. RCIC Manual Slow Start (3022) 217000 A2.08 3.

D,A, S,EN 2

c.

d. Reset Group 2A NSSSS Isolation (3071) 223002 A4.03 3.6 D,S, L 5

e.

f.

g.

I

h.

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

i.

D11 Diesel Local Start (2236) 264000 A2.09 3.7 N,A,E,EN 6

j. Placing Alternate CAD Flow Cont in service (0200)

D, R 1

201001 A1.03 2.9 K

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 (C)ontrol room (D)irect from bank

59/:58/:54 (E)mergency or abnormal in-plant

<:1/<:1/<:1 (EN)gineered safety feature

<:1 I <:1 I:=: 1 (control room system)

(L)ow-Power I Shutdown

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

<:2/<:2/<:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA

<:1/<:1/<:1 (S)imulator

~

LIMERICK GENERATING STATION

~ Exelon Generation,SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4055E Rev _1_ Op-Test No.:

1 Examiners:

Operators: ---------.----

Initial Conditions:

Unit 1 is at 100 % power. Unit2 is at 100% power.

Turnover:

RCIC is running per S49.1.D for oil sampling. S49.1.D is complete up to and including step 4.3.7. RCIC will be shutdown when sampling is complete.

Event No.

1 2

3 4

5 6

7 Malfunction Number E51-S37 E51-S37-PB MED015E MDG420C VIC108B MCN604B MRR441 MHP447A E41-S20 MRR440A MED262A MSL196A MSL196B MSL196C MRC466 MCR547 MCS183A Event Type*

I-PRO C-RO TS-SRO C-PRO TS-SRO R-RO C-PRO C-ALL M-ALL C-RO C-PRO Event Description Inadvertent RCIC Startup and injection (Abnormal)

D13 Dead Bus Transfer to 101 I 013 DIG fails to start (Malfunction)

'1 B' Condensate Pump Vibration requiring shutdown (Abnormal)

Leak in the Drywell (Abnormal)

LOCA with Loss of High Pressure Injection Sources Loss of CRD system due to clogged suction filter (Abnormal)

'1 A' Core Spray Pump fails to auto start (Malfunction)

(N)orm~J:,,'l';*N.. *(~)~~~tivity, (l)~~{~~~~ri~;..

~. ;.'

A, *

• .* (C)ompotie11t~h ::'.L;'.? (M)ajor.:.

. *..* *.. ;<c SEG-4055E Rev001.doc SRRS: 30.126 Page 2 of 45

LIMERICK GENERATING STATION

~

Exelon Generation, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4056E Rev_1_ Op-Test No.:

1.

Examiners:

Operators:

Initial Conditions: Unit 1 is at_§_% power with a startup in progress. Unit 2 is at 100% power.

Turnover: Startup is in progress per GP-2. Crew is to continue withdrawing control rods IAW rod move sheet until 2 Bypass Valves are open in preparation to enter OPCON 1.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A R-RO Withdraw control rods to raise power 2

MRD016F C-RO Control Rod ( 18-19 ) scrams (Abnormal)

(18-19)

TS-SRO 3

MPC482A C-PRO

'1A' Drywell Chiller trip (Abnormal) 4 MED279A C-PRO Loss of 10-Y201 safeguard electrical panel TS-SRO (Abnormal)

MRD016F C-RO 2nd and 3rd Control Rod (34-23) and (58-35) 5 (34-23) scram (Malfunction)

(58-35) 6 MED261 M-All Grid Instability Resulting in Loss of Offsite Power 7

MHP447B C-PRO HPCI system failure on initiation (Malfunction) 8 MDG420C C-PRO 013 Diesel Auto Start Failure (Recoverable)

(Malfunction) 9 MRR440A M-All Small Break LOCA (1.5% ramped over 5 minutes) (Malfunction) 10 MRC466 C-PRO RCIC Turbine trip on overspeed (Malfunction)

(Recoverable after RPV Level reaches -120")

(N)ormal, (R)eactivity, (l)nstru ment, (C)omponent, (M)ajor SEG-4056E Rev001.doc SRRS: 30.126 Page 2 of 45

LIMERICK GENERATING STATION

~* Exelon Generation, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-0-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-6213E Rev_1_

Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:

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

Turnover:

Crew is reguired to cross-tie 114A LC to 124A LC ger S93. 7.A to remove 114A Reactor Area Load Center Transformer Su1212ly Breaker for Maintenance. LC Transformer to service when maintenance is comQlete.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N-PRO Cross tie 114A to 124A Load Center C-PRO 2

MEH101C R-RO

1. 3 Turbine Stop Valve fail closed (Abnormal)

TS-SRO 3

MRP406A TS-SRO Loss of power to Div I RRCS 4

MED263A C-PRO TS-SRO 011 Bus Lockout (Abnormal) 5 MSL001B C-RO

'1 B' SLC Pump spuriously starts and injects (Abnormal)

MRP029B A TWS, SLC failure 6

MSL559 M-ALL C22-S1 B (ARI successful on low level) 7 C11A-S16 C-RO Control Rod Continuous Insert pushbutton fails MRC465 RCIC steam leak with failure to auto isolate results in MSO 8

M-ALL MRC464A exceeded in 2 areas 9

MAD148D C-PRO

'1 M' SRV fails closed (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-6213E Rev001.doc SRRS: 30.126 Page 2 of 41

~

LIMERICK GENERATING STATION

~ Exelon Generation,, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.: SEG-6214E Rev _1_ Op-Test No.: __

Examiners:

Operators:

Initial Conditions:

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

Turnover:

No equipment is known to be inoperable.

Event Malfunction Event Event No.

Number Type*

Description 1

118 1-5 C-PRO Loss of lso-Phase Bus Cooling (Abnormal)

R-RO 2

MRP029A I-RO RPS Level Instrument Failure (Abnormal)

MV1232B TS-SRO MCR412A MCR547 C-RO CRD Pump Failure 3

MRD016C C-PRO c*RD System Failure (Abnormal)

(10-11)

TS-SRO HCU Accumulator(s) Trouble (34-35)

(42-23)

MRD557 M-ALL ATWS (Scram Air Header fails to depressurize) with 4

MSL559 C-RO Turbine Trip MMT002 5

MAD148C C-PRO

'1 M' SRV fails open (electrical) 6 MRC4578 C-PRO RCIC fails in automatic (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-6214E Rev001.doc SRRS: 30.126 Page 2 of 41

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

2016 NRC Date of Exam:

RO Kl A Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

Total A2 G*

Total

).

~r.. a.

1.

1 4

3 3 1t 3

4

~

3 20 4

3 7

Emergency n:*

2 1

1 1

• )~ 2 1

1 7

2 1

3 Plant Tier l'*:r~~

Evolutions Totals 5

4 4

5 5 **;;:;

4 27 6

4 10 1

3 3

2 2

2 3

2 2

2 2

3 26 2

3 5

2.

Plant 2

1 1

1 1

1 1

1 1

1 2

1 12 0

i 2

3 Systems Tier Totals 4

4 3

3 3

4 3

3 3

4 4

38 3

5 8

1 2

3 4

I

") "

4

3. Generic Knowledge & Abilities 10 7

Categories 3

2 3

2 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). (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 Kl As 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 Kl A categories.

7.

The generic (G) Kl As 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 KIAs.

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.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA 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.

G*

Generic KIAs

ES-401 2

2016 NRC Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G

KIA Topic(s)

Imp.

Q#

A.C. POWER : Selective tripping k.:*

AK3.03 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to Trip/3 x

{;

MAIN TURBINE GENERATOR TRIP:

2.8 47 Feedwater temperature decrease

. :1>*** ' t*

AA 1.03 - Ability to operate and/or 295001 Partial or Complete Loss monitor the following as they apply to of Forced Core Flow Circulation I l x

i>:Yi

';Ye PARTIAL OR COMPLETE LOSS OF 2.6 48

&4 FORCED CORE FLOW CIRCULATION

RMCS: Plant-Soecific

j EA 1. 04 - Ability to operate and/or 295025 High Reactor Pressure I 3 x

(f,:*:;. monitor the following as they apply to 3.8 49

.....*.* v 1;1;~:'

HIGH REACTOR PRESSURE: HPCI:

Plant-Soecific

~;~'

EA 1.10 - Ability to operate and/or monitor the following as they apply to 295037 SCRAM Conditions I>

SCRAM CONDITION PRESENT AND Present and Reactor Power Above x

I,. ~f:

REACTOR POWER ABOVE APRM 3.7 50 APRM Downscale or Unknown I 1 DOWNSCALE OR UNKNOWN :

Alternate boron injection methods:

{

Plant-Soecific

'******** * '?>:

EA2.05 - Ability to determine and/or 295028 High Drywell Temperature

.Y

0) interpret the following as they apply to 15

?:~.

HIGH DRYWELL TEMPERATURE:

3.6 51

• ? **

Torus/suppression chamber pressure:

,f;..

Plant-Soecific lz

• ~: ;:1;~

AA2.07 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and GENERATOR VOLTAGE AND 3.6 52 Electric Grid Disturbances I

ELECTRIC GRID DISTURBANCES:

'i~~*

Operational status of engineered safety features.

i't'~

~**1?/f*

AA2.06 - Ability to determine and/or 295006 SCRAM I 1 interpret the following as they apply to 3.5 53 SCRAM : Cause of reactor SCRAM 295004 Partial or Total Loss of

• ~'*****

. \\, ;; 2.1.20 - Conduct of Operations: Ability to interpret and execute procedure 4.6 54 DCPwr/6 I::\\ >.* ?:*~;. steos.

295019 Partial or Total Loss of

,\\/'

,:t>***

2. 1.27 - Conduct of Operations:

Inst. Air I 8 ti Knowledge of system purpose and I or 3.9 55 function.

/ ;}*?

• • • . ~:

2.2.3 - Equipment Control: (multi-unit 295016 Control Room license) Knowledge of the design, 3.8 56 Abandonment I 7 I

procedural, and operational differences between units.

~j.***

/),*

EK1.01 - Knowledge of the operational 295031 Reactor Low Water Level x

implications of the following concepts as 12 they apply to REACTOR LOW WATER 4.6 57 LEVEL : Adeauate core coolina Ii AA2.01 - Ability to determine and/or 295023 Refueling Ace Cooling x

interpret the following as they apply to 3.6 58 Mode/ 8 REFUELING ACCIDENTS : Area radiation levels Kl A Category Totals:

4 3

3 3

414.

3/3 Group Point Total:

I 2017

ES-401 System # I Name K

K K

1 2

3 264000 EDGs 215005 APRM I LPRM 212000 RPS 400000 Component Cooling Water 203000 RHR/LPCl: Injection Mode 206000 HPCI x

262002 UPS (AC/DC) x 262001 AC Electrical Distribution x

211000 SLC x

4 2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

A2. l 0 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS I;:~*, __.

(D !ESEU JET) : imd (b) based on rhose predi..:tions, use procedures to correct, contml, or rnitig:.ue the con;equences of those abnormal conditiorn, or operations: LOC A A2.02 - Ability to (a) predict the Ii,::.

impacts of the following on the I..

AVERAGE PO\\VER RANGE

~~J; MONITORfLOCAL POWER RA'l'GE MONITOR SYSTElvl; and (b) based on those predictions.

use procedure;; to correct, control,

,/

or mitigate the consequences uf those abnormal ~onditions Upscale or downscale trins 1 *::;*:

2.2.42 - Equipment Cuntrol::

Ir Ability to recogni?,e system x

parameters that are entry-lewl

.ffi;:;

'.,l conditions for Technic1tl Specifications.

. \\'.

. -:; 2.2.4 - Equipment Control: (multi**

I*

unit license) Ability to explain the

• _~;4' i.x variations in control board layouts.

systems, instmrnentation and procedural actions between units at

• 'i

  ?J a facility.

2. l.31 - CondLL<.:t of Operations:

1:1c..

Ability to locate control room switches, controls, and indications, i *::

and to determine that they correctly I**

reflect the desired plant lineun.

Kl.04 - Knowledge of the physical I;:

connections and/or cause-effect relationships between HIGH

_:\\~(

PRESSURE COOLANT INJECTION SYSTEM and the following: Reactor feedwater system: BWR-2,3,4 K1.17 - Knowledge of the physical connections and/or cause-effect relationships between UNINTERRUPTABLE

"<\\!>

POWER SUPPLY (A.C./D.C.)

and the following: Scram solenoid valves: Plant-Specific I

K2.01 - Knowledge of electrical I:

power supplies to the following:

Off-site sources of power K2.02 - Knowledge of electrical power supplies to the following:

Exolosive valves Imp Q#

4.2 86 3.7 87 4.6 88 3.6 89 4.3 90 3.6 1

3.1 2

3.3 3

3.1 4

ES-401 System # I Name K

K K

1 2

3 261000 SOTS 215003 IRM 264000EDGs 239002 SRVs 263000 DC Electrical Distribution 300000 Instrument Air 217000 RCIC 223002 PCIS/Nuclear Steam Supply Shutoff 218000 ADS 215004 Source Range Monitor 4

2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

• . ¥ A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the x r STANDBY GAS TREATMENT j

SYSTEM controls including: Off-site release levels

(

A2.05 - Ability to (a) predict the impacts of the following on the I.

INTERMEDIATE RANGE

.)/

MONITOR (IRM) SYSTEM ; and

',.~

(b) based on those predictions, x'r use procedures to correct,

//

control, or mitigate the consequences of those

'.*/

abnormal conditions or operations: Faulty or erratic

.. /.

{..

operation of detectors/system A2.08 - Ability to (a) predict the I.

impacts of the following on the EMERGENCY GENERATORS (DIESEUJET) ; and (b) based on those predictions, use x*

procedures to correct, control, or mitigate the consequences of 1*.

those abnormal conditions or operations: Initiation of 1 **

Ix. '

emergency generator room fire I> "3 protection system A3.02 - Ability to monitor I*

automatic operations of the x

RELIEF/SAFETY VALVES h

including: SRV operation on

. ;/' hiah reactor pressure A3.01 - Ability to monitor automatic operations of the D.C.

x ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating

• • .., liahts A4.01 - Ability to manually x

operate and/or monitor in the control room: Pressure aauaes A4.05 - Ability to manually x

operate and/or monitor in the control room: Reactor water level 2.4.9 - Emergency Procedures I

+

Plan: Knowledge of low power I x

shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitiqation strateaies.

2.4.20 - Emergency Procedures x

I Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.

2.1.30 - Conduct of Operations:

x Ability to locate and operate components, including local controls.

Imp Q#

3.2 14 3.3 15 3.3 16 4.3 17 3.2 18 2.6 19 4.1 20 3.8 21 3.8 22 4.4 23

ES-401 System # I Name K K K

1 2

3 290002 Reactor Vessel Internals 286000 Fire Protection 214000 RP!S 201002RMCS x

223001 Primary CTMT and x

Aux.

288000 Plant Ventilation x

290002 Reactor Vessel Internals 271000 Off-gas 241000 ReactoriTurbine Pressure Regulator 239001 Main and Reheat Steam 5

2016 NRC Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K A A2 A

A G

4 5

6 1

3 4

A2.01 - Ability to (a) predict the impacts of the fr,Jlowing on the REACTOR VESSEL INTERNALS

• • • *i.

and ( b) based on those predictions, use procedures to correct, control. or mitigate the I*

consequences of ihose abnormal conditions or operations: LOCA 2.2.25 - Equipment Control:

Knowledge of bases in technical sped ficat.ions for limiting

~;

,*onditions for operations and safety limits.

2.4.34 - Emergency Prcxedures i Plan: Knowledge of RO tasks

.. c.;;,

X *. performed outside thi.: main control room during an emergency and the

. resultam operational effects.

\\' w.

1/':~ ~.

Kl.01 - Knowledge of the physical connections and/or cause-effect 1)**

relationships between REACTOR o.;','

MANUAL CONTROL SYSTEM

• )~

1;..

and the following: Control rod drive hydraulic system K2.09 - Knowledge of electrical

'J3,i1/~:

power supplies to the following:

.'i/""1' Drywell cooling fans: Plant-Specific

)~i K3.02 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION

./>'

SYSTEMS will have on following:

I\\;;

Reactor building temperature:

Plant-Specific K4.05 - Knowledge of

.. REACTOR VESSEL x

INTERNALS design feature(s) and/or interlocks which provide for the following: Natural

)

circulation KS.09 - Knowledge of the operational implications of the x

following concepts as they apply to OFFGAS SYSTEM :

Hydrogen and oxygen recombination K6.06 - Knowledge of the effect that a loss or malfunction of the x

following will have on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM : Reactor pressure A 1.10 - Ability to predict and/or monitor changes in parameters x

associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including:

Reactor power Imp. a 4.0 91 4.'.?.

92 4.l 93 3.2 27 2.7 28 2.9 29 3.3 30 2.6 31 3.8 32 3.8 33

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

Form ES-401-3 Facility:

2016 NRG Date:

Category KIA#

Topic RO SRO-Only IR Q#

IR Q#

2.1.42 Knowledge of new and spent fuel movement 3.4 94 procedures.

Ability to use procedures related to shift 2.1.5 staffing, such as minimum crew complement, 3.9 98 overtime limitations, etc.

1.

2.1.9 Ability to direct personnel activities inside the 2.9 66 Conduct control room.

of Operations Knowledge of industrial safety procedures 2.1.26 (such as rotating equipment, electrical, high 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.6 Ability to manage the control room crew 3.8 75 durinq plant transients.

Subtotal

,... '. f 3

• .;:, i~

2 2.2.35 Ability to determine Technical Specification 4.5 95 Mode of Operation.

Ability to perform pre-startup procedures for 2.2.1 the facility, including operating those controls 4.4 100 associated with plant equipment that could affect reactivity.

2.

(multi-unit license) Ability to explain the Equipment 2.2.4 variations in control board layouts, systems, 3.6 68 Control instrumentation and procedural actions between units at a facility.

Ability to interpret control room indications to 2.2.44 verify the status and operation of a system, 4.2 69 and understand how operator actions and directives effect plant and system conditions.

Subtotal

[;

2 2

Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, 3.1 96 portable survey instruments, personnel

3.

monitorinq equipment, etc.

Radiation Control 2.3.11 Ability to control radiation releases.

3.8 70

ES-401 Record of Rejected Kl A's Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected Kl A Q# 37 At LGS, there are no times when the RBM is used 212 215002 I 2.4.18 during Emergency Procedure use. This is due to the RBM supporting Control Rod Withdraw only.

Replaced with 214000 RPIS 2.4.2 3

G3 I 2.3.6 Q# 96 Duplicated in operating test replaced with 2.3.15 l I 2 295022 I Q# 85 The subject KIA isn't relevant at the subject facility.

AA2.03 Replaced with 295022 Loss of CRD Pumps AA2.02 I

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1/18/16 Examination Level:

RO

~

SRO D Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.20 (Ability to interpret and execute procedure steps) Evaluate Valve Stroke Data ST-6-107-200-0 Conduct of Operations D,R (0764)

G. 2.1.8 (Ability to coordinate personnel activities outside the control room) - Fire Alarm In Inverter Conduct of Operations N,R Room JPM (0715)

G.2.2.12 (knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod Equipment Control D,R withdrawal Check (0752)

G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and Radiation Control N,R emergency conditions) Radioactive Spill Response (3122)

Emergency Plan NIA 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 (s 3 for ROs; s 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:

LIMERICK Date of Examination:

1 /18/16 Examination Level:

RO

~

SRO D Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.20 (Ability to interpret and execute procedure steps) Evaluate Valve Stroke Data ST-6-107-200-0 Conduct of Operations D,R (6764)

G. 2.1.8 (Ability to coordinate personnel activities outside the control room) - Fire Alarm In Inverter Conduct of Operations Room N,R JPM (3715)

G.2.2.12 (knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod Equipment Control D,R withdrawal Check (6752)

G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and Radiation Control N,R emergency conditions) Radioactive Spill Response (3122)

Emergency Plan NIA 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)

Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1 /18/16 Examination Level:

RO D SRO

~

Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.4 Knowledge of individual licensed operator Conduct of Operations D,R responsibilities related to shift !staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.)

Reactivate SRO License (6710) 2.1.25 (Ability to interpret reference material such as graphs, curves, tables, etc.)

Conduct of Operations D,R Evaluate valve data -JPM (6766)

G.2.2.12 (Knowledge of surveillance procedures)

Review ST-6-047-370-1, Pre Control Rod withdrawal Equipment Control D,R Check (6753)

G2.3.14 (knowledge of radiation and contamination Radiation Control N,R hazards that may arise during normal, abnormal, and emergency conditions) Radiation Transportation Accident assessment (Time Critical) (3123)

G.2.4.41 Knowledge of the emergency action level Emergency Plan D,R thresholds and classifications.

ERP Classification and Reporting (Time Critical)

(3124)

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 (s; 3 for ROs; s; 4 for SROs & RO retakes)

(N)ew or (M}odified from bank (~ 1)

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

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO 181 SRO-I D SRO-U 0 Operating Test No.:

1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-!:!

System I JPM Title Type Code*

Safety Function

a. Response to EHC Leaks (3109) 241000 A4.08 3.5 N,S 3

b. RCIC Manual Slow Start (3022) 217000 A2.08 3.0 D,A,S,EN 2

c. Shutdown D11 Diesel Generator (3027) 264000 A4.04 3.7 D,S 6

d. Reset Group 2A NSSSS Isolation (3071) 223002 A4.03 3.6 D,S,L 5

e. Resetting ASD Speed Hold (3529) 202001 A 1.01 3.6 D,A,S 4

f. Alternate Cooling of RECW (3052) 400000 A2.01 3.3 D,S,L 8

g. SBGT Manual Start with Charcoal Encl Hi Temp (3528) 2012 NRC D,P,A,S,EN 9

261000 A4.02 3.31

h. Control Rod Exercise Test (3034) 201003 A2.01 3.4 N,A,S 1

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

i.

D11 Diesel Local Start (2236) 264000 A2.09 3. 7 N,A,E,EN 6

j. Placing Alternate CRD Flow Cont in service (2200)

D,R 1

201001 A1.03 2.9

k. Bypassing Rx HVAC Isolation (3214) 288000 A2.01 3.3 D,R,E,EN 9

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 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant

<?:1/<?:1/<?:1 (EN)gineered safety feature

<:1 I <:1 I=:: 1 (control room system)

(L)ow-Power I Shutdown

<?:1/<?:1/'2:1 (N)ew or (M)odified from bank including 1 (A)

<?:2/<?:2/'2:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA

<?:1/<?:1/'2:1 (S)imulator

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO D SRO-I D SRO-U ~

Operating Test No.:

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

Safety Function

a. Response to EHC Leaks (3109) 241000 A4.08 3.5 N,S 3

b. RCIC Manual Slow Start (3022) 217000 A2.08 3.

D,A, S,EN 2

c.

d. Reset Group 2A NSSSS Isolation (3071) 223002 A4.03 3.6 D,S, L 5

e.

f.

g.

I

h.

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

i.

D11 Diesel Local Start (2236) 264000 A2.09 3.7 N,A,E,EN 6

j. Placing Alternate CAD Flow Cont in service (0200)

D, R 1

201001 A1.03 2.9 K

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 (C)ontrol room (D)irect from bank

59/:58/:54 (E)mergency or abnormal in-plant

<:1/<:1/<:1 (EN)gineered safety feature

<:1 I <:1 I:=: 1 (control room system)

(L)ow-Power I Shutdown

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

<:2/<:2/<:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA

<:1/<:1/<:1 (S)imulator

~

LIMERICK GENERATING STATION

~ Exelon Generation,SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4055E Rev _1_ Op-Test No.:

1 Examiners:

Operators: ---------.----

Initial Conditions:

Unit 1 is at 100 % power. Unit2 is at 100% power.

Turnover:

RCIC is running per S49.1.D for oil sampling. S49.1.D is complete up to and including step 4.3.7. RCIC will be shutdown when sampling is complete.

Event No.

1 2

3 4

5 6

7 Malfunction Number E51-S37 E51-S37-PB MED015E MDG420C VIC108B MCN604B MRR441 MHP447A E41-S20 MRR440A MED262A MSL196A MSL196B MSL196C MRC466 MCR547 MCS183A Event Type*

I-PRO C-RO TS-SRO C-PRO TS-SRO R-RO C-PRO C-ALL M-ALL C-RO C-PRO Event Description Inadvertent RCIC Startup and injection (Abnormal)

D13 Dead Bus Transfer to 101 I 013 DIG fails to start (Malfunction)

'1 B' Condensate Pump Vibration requiring shutdown (Abnormal)

Leak in the Drywell (Abnormal)

LOCA with Loss of High Pressure Injection Sources Loss of CRD system due to clogged suction filter (Abnormal)

'1 A' Core Spray Pump fails to auto start (Malfunction)

(N)orm~J:,,'l';*N.. *(~)~~~tivity, (l)~~{~~~~ri~;..

~. ;.'

A, *

• .* (C)ompotie11t~h ::'.L;'.? (M)ajor.:.

. *..* *.. ;<c SEG-4055E Rev001.doc SRRS: 30.126 Page 2 of 45

LIMERICK GENERATING STATION

~

Exelon Generation, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4056E Rev_1_ Op-Test No.:

1.

Examiners:

Operators:

Initial Conditions: Unit 1 is at_§_% power with a startup in progress. Unit 2 is at 100% power.

Turnover: Startup is in progress per GP-2. Crew is to continue withdrawing control rods IAW rod move sheet until 2 Bypass Valves are open in preparation to enter OPCON 1.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A R-RO Withdraw control rods to raise power 2

MRD016F C-RO Control Rod ( 18-19 ) scrams (Abnormal)

(18-19)

TS-SRO 3

MPC482A C-PRO

'1A' Drywell Chiller trip (Abnormal) 4 MED279A C-PRO Loss of 10-Y201 safeguard electrical panel TS-SRO (Abnormal)

MRD016F C-RO 2nd and 3rd Control Rod (34-23) and (58-35) 5 (34-23) scram (Malfunction)

(58-35) 6 MED261 M-All Grid Instability Resulting in Loss of Offsite Power 7

MHP447B C-PRO HPCI system failure on initiation (Malfunction) 8 MDG420C C-PRO 013 Diesel Auto Start Failure (Recoverable)

(Malfunction) 9 MRR440A M-All Small Break LOCA (1.5% ramped over 5 minutes) (Malfunction) 10 MRC466 C-PRO RCIC Turbine trip on overspeed (Malfunction)

(Recoverable after RPV Level reaches -120")

(N)ormal, (R)eactivity, (l)nstru ment, (C)omponent, (M)ajor SEG-4056E Rev001.doc SRRS: 30.126 Page 2 of 45

LIMERICK GENERATING STATION

~* Exelon Generation, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-0-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-6213E Rev_1_

Op-Test No.:

1 Examiners:

Operators:

Initial Conditions:

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

Turnover:

Crew is reguired to cross-tie 114A LC to 124A LC ger S93. 7.A to remove 114A Reactor Area Load Center Transformer Su1212ly Breaker for Maintenance. LC Transformer to service when maintenance is comQlete.

Event Malfunction Event Event No.

Number Type*

Description 1

N/A N-PRO Cross tie 114A to 124A Load Center C-PRO 2

MEH101C R-RO

1. 3 Turbine Stop Valve fail closed (Abnormal)

TS-SRO 3

MRP406A TS-SRO Loss of power to Div I RRCS 4

MED263A C-PRO TS-SRO 011 Bus Lockout (Abnormal) 5 MSL001B C-RO

'1 B' SLC Pump spuriously starts and injects (Abnormal)

MRP029B A TWS, SLC failure 6

MSL559 M-ALL C22-S1 B (ARI successful on low level) 7 C11A-S16 C-RO Control Rod Continuous Insert pushbutton fails MRC465 RCIC steam leak with failure to auto isolate results in MSO 8

M-ALL MRC464A exceeded in 2 areas 9

MAD148D C-PRO

'1 M' SRV fails closed (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-6213E Rev001.doc SRRS: 30.126 Page 2 of 41

~

LIMERICK GENERATING STATION

~ Exelon Generation,, SIMULATOR EVALUATION GUIDE Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.: SEG-6214E Rev _1_ Op-Test No.: __

Examiners:

Operators:

Initial Conditions:

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

Turnover:

No equipment is known to be inoperable.

Event Malfunction Event Event No.

Number Type*

Description 1

118 1-5 C-PRO Loss of lso-Phase Bus Cooling (Abnormal)

R-RO 2

MRP029A I-RO RPS Level Instrument Failure (Abnormal)

MV1232B TS-SRO MCR412A MCR547 C-RO CRD Pump Failure 3

MRD016C C-PRO c*RD System Failure (Abnormal)

(10-11)

TS-SRO HCU Accumulator(s) Trouble (34-35)

(42-23)

MRD557 M-ALL ATWS (Scram Air Header fails to depressurize) with 4

MSL559 C-RO Turbine Trip MMT002 5

MAD148C C-PRO

'1 M' SRV fails open (electrical) 6 MRC4578 C-PRO RCIC fails in automatic (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor SEG-6214E Rev001.doc SRRS: 30.126 Page 2 of 41