Text

Draft - Outlines (Folder 2)
	ML16088A367
Person / Time
Site:	Limerick
Issue date:	03/24/2016
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;
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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)

Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1/18/16 Examination Level:

RO D SRO IZI Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.8 (Coordinate Personnel Activities Outside of Conduct of Operations D,R the Control Room) Reactivate SRO License (6710) 2.1.25 (Ability to interpret reference material such as Conduct of Operations graphs, curves, tables, etc.)

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 (0753)

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

G.2.4.21 Knowledge of the parameters and logic used Emergency Plan to assess the status of safety functions, such as D,R reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

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 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 (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)

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 responsibilities related to shift !staffing, such as Conduct of Operations D,R 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 hazards that may arise during normal, abnormal, and Radiation Control N,R 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 D 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 3.0 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/<: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

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO D SRO-I IZI SRO-U D 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 2

c.

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) 2012NRC D,P,A,S,EN 9

261000 A4.02 3.31

h. Control Rod Exercise Test (3107) 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 CAD Flow Cont in service (0200)

D,R 1

201001 A 1.03 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/;

:11;::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

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 IZI Operating Test No.:

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

System I J PM 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.

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 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/;<: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

Appendix D D-1 Facility:

Limerick 1 & 2 L

Examiners:

Initial Conditions:

Unit 1 is at 100 % power.

Turnover:

Scenario Outline Form ES-Scenario No.:

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

Operators:

Unit 2 is at 100% power.

RCIC is running per 849.1.0 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 Malfunction Event Event No.

Number Type*

Description

I I-PRO 1

E51-S37 R-RO Inadvertent RCIC Startup and injection E51-S37-PB TS-SRO (Abnormal)

MED015E C-PRO D 13 Dead Bus Transfer to 101 I 013 DIG fails to 2

MDG420C TS-SRO start (Malfunction)

VIC108B C-RO

'1 B' Condensate Pump Vibration requiring 3

MCN604B C-PRO

. shutdown (Abnormal) 4 MRR441 C-ALL Leak in the Drywall (Abnormal)

MHP447A E41-S20 MRR440A MED262A M-ALL LOCA with 5

MSL196A MSL196B Loss of High Pressure Injection Sources MSL196C MRC466 6

MCR547 C-RO Loss of CRD system due to clogged suction filter (Abnormal) 7 MCS183A C-PRO

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

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

Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4056E Rev _1_ Op-Test No.:

L 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 with steps complete to step __. Crew is to continue withdrawing control rods IAW rod move sheet until 4 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 E51-S37-PB I-PRO Inadvertent RCIC system start (Abnormal) 3 E51-S37 R-RO TS-SRO 4

MPC482A C-PRO 11 A' Drywell Chiller trip (Abnormal) 5 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) 6 (34-23) scram (Malfunction)

(58-35)

MED261 M-All Grid Instability Resulting in Loss of Offsite 7

MED263D C-PRO Power Fault on 014 SFGD BUS MHP447B C-PRO HPCI system failure on initiation 8

MDG420C (Malfunction)

D13 Diesel Auto Start Failure (Recoverable)

MRR440A M-All Small Break LOCA (1.5% ramped over 5 9

minutes) with D14 Diesel Trip on Bus Lockout MDG418D MRC466 C-PRO RCIC Turbine trip on overspeed 10 (Malfunction)

(Recoverable after RPV Level reaches -1 50")

(N)ormal, (R)eactivity, (l)nstrument, (C}ornponent, (M)ajor

Appendix D ES-D-1 Facility:

Limerick 1 & 2

_1 _.

Examiners:

Initial Conditions:

Scenario Outline Form Scenario No.:

SEG-6213E Rev_1_

Op-Test No.:

Operators:

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

Turnover:

Crew is reguired to cross-tie 114A LC to 124A LC 12er 893.7.A to remove 114A Reactor Area Load Center Transformer SuQQly Breaker for Maintenance. LC Transformer to service when maintenance is comQlete.

Event Malfunction Event Event No.

N1.,1mber Type*

Description 1

N/A N~PRO I Cross tie 114A to 124A Load Center G-PRO 2

MEH101C R-RO

3 Turbine Stop Valve fail closed (Abnormal)

TS-SRO C-RO 3

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

MED263A 011 Bus Lockout (Abnormal)

TS-SRO 5

MSL001B C-RO

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

MRP029B A TWS, SLC failure 6

MSL559 M-ALL C22-S1B (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 8

M-ALL MRC464A MSO exceeded in 2 areas 9

MAD1480 C-PRO

'1 M' SRV fails closed I*

(N)ormal, (R)eactivity, (l)nstrument,

{C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

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

1 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 I

C-PRO I

1 118 1-5 Loss of Isa-Phase Bus Cooling (Abnormal)

R-RO I

2 MRP029A I-RO RPS Level Instrument Failure MV12328 TS-SRO MCR412A MCR547 C-RO CRD Pump FaHL;Jre 3

MRD016C C-PRO CRD 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) 4 MSL559 C-RO with 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

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 A

A A

A G

Total A2 G*

Total 1

2 3

4 5

6 1

2 3

4

1.

1 4

3 3

3 4

le

3 20 4

3 7

Emergency 2

1 1

1

. x:

2 1

1 7

2 1

3 Plant Evolutions Tier 5

4 4

.. )

5 5

4 27 6

4 10 Totals 1

3 3

2 2

2 3

2 2

3 26 2

3 5

2.

Plant 2

1 1

1 2

1 12 0

1 2

3 Systems Tier Totals 4

4 3

3 3

4 3

3 3

4 4

38 3

5 8

3. Generic Knowledge & Abilities 1

2 3

4 I

2 3

4 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 NRG 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 KIA 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 (!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,

!Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs 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#

EA2.02 **Ability to dt:termine and/or 295024 High Drywell Pressure I 5 x

interpret the following as they apply to 4.0 76 HIGH DR YWELL PRESSURE: Drywell temperature AA2.07 - Ability to determine and/or 295016 Control Room x

interpret the following as they apply to 3.4 77 Abandonment I 7 CONTROL ROOM ABANDONMENT :

Suppression chamber prrssure AA2.02 - Ability t.o d.:terrnine andlllr 295003 Partial or Complete Loss of interpret the following as they apply to x

PARTIAL OR COMPLETE LOSS OF A.C.

4.3 78 AC/6 POWER : Reactor power, pressure, and level 2.4.47 - Emergency Procedures I Plan:

29503 l Reactor Low Water L..:vel I x

Ability to diagnose and recognize trends in 4.2 79 2

an accurntc and timely manner utilizing the annropriate control room reference material.

2.4.Yi.. Emergcnc)' Procedures I Plan:

295038 High Off~site Release Rate x

Knowledge of local au1'iliary 0perntor ta;;ks 4.0 80 19 during emergency and the resuhant op.:rational effects.

295018 Partial or Total Loss of 2.4.11 - Emergency Procedures I Plan:

CCW/8 x

Knowledge of abnormal c:ondition 1.2 81 prncc:dures.

EA2.rn - i\\hility to determine mid/or 295026 Suppression Pool High x

interpret the following: as they apply to 4.0 82 Watt:r Temp. I 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor presmre EKI.01 - Knowledge of the operational 295026 Suppression Pool High x

implications of the following concepts as 3.0 39 Water Temp. 15 they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Pump NPSH EKI.01 - Knowledge of the operational implications of the following concepts as 295024 High Drywell Pressure I 5 x

they apply to HIGH DRYWELL 4.1 40 PRESSURE : Drywell integrity: Plant-Specific AKI.02 - Knowledge of the operation 600000 Plant Fire On-site I 8 x

applications of the following concepts as 2.9 41 they apply to Plant Fire On Site: Fire Fighting 295030 Low Suppression Pool EK2.03 - Knowledge of the interrelations x

between LOW SUPPRESSION POOL 3.8 42 Water Level I 5 WATER LEVEL and the following: LPCS 295038 High Off-site Release Rate EK2.01 - Knowledge of the interrelations x

between HIGH OFF-SITE RELEASE 3.1 43 19 RATE and the followinQ: Radwaste AK2.03 - Knowledge of the interrelations 295021 Loss of Shutdown Cooling x

between LOSS OF SHUTDOWN 3.6 44 14 COOLING and the following:

AHR/shutdown coolina AK3.01 - Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss of x

PARTIAL OR COMPLETE LOSS OF 2.9 45 CCW/8 COMPONENT COOLING WATER:

Isolation of non-essential heat loads:

Plant-Soecific 295003 Partial or Complete Loss AK3.02 - Knowledge of the reasons for x

the following responses as they apply to 2.9 46 of AC/ 6 PARTIAL OR COMPLETE LOSS OF

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 AK3.03 - Knowledge of the reasons for 295005 Main Turbine Generator x

the following responses as they apply to 2.8 47 Trip/ 3 MAIN TURBINE GENERATOR TRIP:

Feedwater temperature decrease 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 1 x

PARTIAL OR COMPLETE LOSS OF 2.6 48

&4 FORCED CORE FLOW CIRCULATION

RMCS: Plant-Specific EA 1.04 - Ability to operate and/or 295025 High Reactor Pressure I 3 x

monitor the following as they apply to 3.8 49 HIGH REACTOR PRESSURE: HPCI:

Plant-Specific EA 1.10 - Ability to operate and/or monitor the following as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above x

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

Alternate boron injection methods:

Plant-Specific EA2.05 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to

.. x HIGH DRYWELL TEMPERATURE:

3.6 51 15 Torus/suppression chamber pressure:

Plant-Specific AA2.07 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and x

GENERATOR VOLTAGE AND 3.6 52 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES:

Operational status of engineered safety features.

AA2.06 - Ability to determine and/or 295006 SCRAM / 1 x

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 DCPwr/6 x

to interpret and execute procedure 4.6 54 steps.

295019 Partial or Total Loss of 2.1.27 - Conduct of Operations:

Inst. Air/ 8 x

Knowledge of system purpose and I or 3.9 55 function.

2.2.3 - Equipment Control: (multi-unit 295016 Control Room x

license) Knowledge of the design, 3.8 56 Abandonment I 7 procedural, and operational differences between units.

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

implications of the following concepts as 4.6 57

/2 they apply to REACTOR LOW WATER LEVEL : Adequate core cooling 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 KIA Category Totals:

4 3

3 3

414 3/3 Group Point Total:

I 2017

ES-401 3

2016 NRC Form ES-401-1 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)

Imp.

Q#

EA2.tl I - Ability to determine and I or x

500000 High CTMT Hydrogen interpret rhe following as they apply to Conc. / 5 HfGH PRlMARY CONT/1INMENT 3.5 83 HYDROGEN CONCENTRATIONS:

Hvdrogcn monitorin.g svstem availabilitv 2.1.7 **Conduct of Operations: Ability to evaluate plant performance and make 295007 High Reactor Pressure I 3 x

operational judgement~ hascd on operating 4.7 84 characteristics, reactor behavior, and instrument interpretion.

Ai\\2.02 - /\\hility to determine and/nr 295022 Loss of CRD Pumps I I x

inteq.>rd the following as they apply to 3.4 85 LOSS OF CRD PUMPS : CRD system status AKI.02 - Knowledge of the operational 295022 Loss of CRD Pumps I 1 x

implications of the following concepts as

3.

59 they apply to LOSS OF CRD PUMPS:

6 Reactivity control AK2.02 - Knowledge of the interrelations 295012 High Drywell x

between HIGH DRYWELL 3.6 60 Temperature I 5 TEMPERA TIJRE and the following:

Drvwell cooling AK3.02 - Knowledge of the reasons for the 295002 Loss of Main Condenser x

following responses as they apply to LOSS

3.

61 Vac/3 OF MAIN CONDENSER VACUUM :

4 Turbine trip AAI.09 - Ability to operate and/or monitor 295008 High Reactor Water Level x

the following as they apply to HIGH

3.

62 12 REACTOR WATER LEVEL : Ability to 3

drain: Plant-Soecific EA2.0l - Ability to determine and/or 295034 Secondary Containment interpret the following as they apply to

3.

x SECONDARY CONTAINMENT 63 Ventilation High Radiation/ 9 VENTILATION HIGH RADIATION:

8 Ventilation radiation levels 2.4.47 - Emergency Procedures I Plan:

295017 High Off-site Release x

Ability to diagnose and recognize trends in

4.

64 Rate I 9 an accurate and timely manner utilizing the 2

appropriate control room reference material.

EAI.05 - Ability to operate and/or monitor 295033 High Secondary the following as they apply to HIGH

3.

Containment Area Radiation x

SECONDARY CONTAINMENT AREA 9

65 Levels I 9 RADIATION LEVELS : Affected systems so as to isolate damaged portions Kl A Category Totals:

1 1

1 2

1/2 1/1 Group Point Total:

I 7/'J

ES-401 System #I Name K

K K

1 2

3 264000 EDGs 215005 APRM I LPRTvt 2120C~l RPS 4UU()OO Compllnent Conling Water 2moou RHR/LPCI: Injection Mode 206000HPCI 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

A.2.lfl-Ahilit.y to (a) predict the irnpac:ts of the following oll the EMERGENCY GENERATORS x

(D!ESEUJETJ; and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abn1.irmal condit.ions or operations: LOCA A2.rl2 - Ability to {a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR!LOC.A.L POWER x

RANGE MONITOR SYSTEM; and (b) based on those predictions.

use procedures to correct, control.

nr mitigate the.::onseqm:nccs nf those abnormal.::omlit.ions Upscale or downs.:ale trips 2.2.42 - Equipment Control::

Ability w recognize'. system x

parameters that are t'ntry-levd conditions for Technical Specificati<)llS.

2.2.4 ** Equipment Control: (multi**

unit license) Ability to explain the x

variations in control board layout~.

systems, instrnrnemation and proc:edural actions between units al a facilitv.

2.1 J l - Condud. <Jf Operatiuns:

Ability 10 loc:ate control rc>Pm x

switches, controls, and indkations, and to determine that they co!Tectl y reflect the desired plant lineup.

Kl.04-Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following: Reactor feedwater system: BWR-2,3,4 K 1.17 - 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 K2.01 - Knowledge of electrical power supplies to the following:

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

Explosive valves Imp Q#

,u 86 3.7 87 4.6 88 3.6 89 4.3 90 3.6 l

3.1 2

3.3 3

3.1 4

ES-401 System #I Name K

K K

1 2

3 218000 ADS x

215004 Source Range Monitor x

215005 APRM I LPRM 259002 Reactor Water Level Control 209001 LPCS 205000 Shutdown Cooling 400000 Component Cooling Water 203000 RHR/LPCI: Injection Mode 212000 RPS 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

K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following: Ability to raoidlv deoressurize the reactor K3.04 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR (SAM) SYSTEM will have on following: Reactor power and indication K4.02 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER x

RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following: Reactor SCRAM sianals K4.17 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design x

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

Simultaneous Manual and Auto operation of the system (i.e. 1 FP in Auto, 1 FP in Manual\\

KS.01 - Knowledge of the operational implications of the x

following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Indications of oumo cavitation KS.02 - Knowledge of the operational implications of the following concepts as they apply x

to SHUTDOWN COOLING SYSTEM (AHR SHUTDOWN COOLING MODE) : Valve ooeration K6.01 - Knowledge of the effect x

that a loss or malfunction of the following will have on the CCWS: Valves K6.04 - Knowledge of the effect that a loss or malfunction of the x

following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) : Keep fill svstem A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the x

REACTOR PROTECTION SYSTEM controls including:

RPS bus frequency: Plant-Soecific Imp Q#

4.5 5

3.7 6

4.1 7

3.1 8

2.6 9

2.8 10 2.7 11 3.3 12 2.6 13

ES-401 System #I Name K

K K

1 2

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

2016 NRG 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 x

associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: Off-site release levels A2.05 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, x

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Faulty or erratic ooeration of detectors/system A2.08 - Ability to (a) predict the 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 those abnormal conditions or operations: Initiation of emergency generator room fire protection system A3.02 - Ability to monitor automatic operations of the x

RELIEF/SAFETY VALVES including: SRV operation on high 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 gauaes 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) mitiaation 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 0#

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 223002 PCIS/Nuclear Steam Supply Shutoff 203000 RHR/LPCI: Injection x

Mode 205000 Shutdown Cooling x

Kl A Category Totals:

3 3

2 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

K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the x

PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF:

Containment instrumentation K 1.17 - Knowledge of the physical connections and/or cause-effect relationships between RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) and the following:

Reactor pressure K2.02 - Knowledge of electrical power supplies to the following:

Motor operated valves 2

2 3

2 2/2 2

2 3/3 Group Point Total:

Imp Q#

3.0 24 4.0 25 2.5 26 I

2615

ES-401 System #I Name K

K K

1 2

3 29l~J02 Reactor Vessel Internals 286\\lOO Fire Protedion 2l400URPIS 20!002RMCS x

223001 Primary CTMT and x

Aux.

288000 Plant Ventilation x

290002 Reactor Vessel Internals 271000 Off-gas 241000 Reactor/Turbine 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 following on the REACTOR VESSEL INTFRNAl.B x

and lb J based on those predictions. use procedures to correct, control. or rnitigate the conscqucnces of rhose abnormal conditions or operations: LOCA 2.2.25 - Equipment Control:

Knowledge of bases in technical x

spe.:ifications for limiting rnnditions for operntions and safety limits.

2.4.34 - Emergency Prm:edur.;s !

Plan: Knowledge of RO ta:;.ks x

performed outside the main control room during an emergency and the re;;ultant operational effect;;,

Kl.01 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR MANUAL CONTROL SYSTEM and the following: Control rod drive hydraulic system K2.09 - Knowledge of electrical power supplies to the following:

Drywell cooling fans: Plant-Specific K3.02 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION SYSTEMS will have on following:

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 K5.09 - 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 9l 4.2 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 System # I Name K

K K

1 2

3 256000 Reactor Condensate 201003 Control Rod and Drive Mechanism 214000RPIS 214000 RPIS 233000 Fuel Pool Cooling/Cleanup KIA Category Totals:

1 1

1 5

2016 NRG 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

A2.12 - Ability to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use x

procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of equipment component cooling water systems A3.01 - Ability to monitor automatic operations of the x

CONTROL ROD AND DRIVE MECHANISM including: Control rod position A4.01 - Ability to manually x

operate and/or monitor in the control room: RCIS rod action control bypass switches 2.4.2 - Emergency Procedures I Plan: Knowledge of system set x

points, interlocks and automatic actions associated with EOP entry conditions.

A4.10 - Ability to manually x

operate and/or monitor in the control room: Tank levels 1

1 1

1 111 1

2 1/2 Group Point Total:

Imp. a 3.1 34 3.7 35 3.2 36 4.5 37 2.5 38 I 12/3

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

Form ES-401-3 Facility:

2016 NRC Date:

RO SRO-Only Category KIA#

Topic IR Q#

IA 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, oxvqen and hvdroqen).

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

Subtotal 3

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 facilitv.

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 svstem 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 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, 2.9 71 portable survey instruments, personnel monitorina eauioment, etc.

Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 74 responsibilities, access to locked high-radiation areas, alianina filters, etc.

Subtotal 3

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

2.4.11 Knowledge of abnormal condition 4.2 99 procedures.

4.

Emergency 2.4.17 Knowledge of EOP terms and definitions.

3.9 72 Procedures I Ability to perform without reference to Plan 2.4.49 procedures those actions that require 4.6 73 immediate operation of system components and controls.

Subtotal 2

2 Tier 3 Point Total 10

..::~...

7

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

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)

Administrative Topics Outline Form ES-301-1 Facility:

LIMERICK Date of Examination:

1/18/16 Examination Level:

RO D SRO IZI Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

G.2.1.8 (Coordinate Personnel Activities Outside of Conduct of Operations D,R the Control Room) Reactivate SRO License (6710) 2.1.25 (Ability to interpret reference material such as Conduct of Operations graphs, curves, tables, etc.)

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 (0753)

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

G.2.4.21 Knowledge of the parameters and logic used Emergency Plan to assess the status of safety functions, such as D,R reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

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 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 (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)

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 responsibilities related to shift !staffing, such as Conduct of Operations D,R 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 hazards that may arise during normal, abnormal, and Radiation Control N,R 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 D 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 3.0 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/<: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

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

LIMERICK Date of Examination:

1/18/2016 Exam Level: RO D SRO-I IZI SRO-U D 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 2

c.

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) 2012NRC D,P,A,S,EN 9

261000 A4.02 3.31

h. Control Rod Exercise Test (3107) 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 CAD Flow Cont in service (0200)

D,R 1

201001 A 1.03 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/;

:11;::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

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 IZI Operating Test No.:

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

System I J PM 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.

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 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/;<: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

Appendix D D-1 Facility:

Limerick 1 & 2 L

Examiners:

Initial Conditions:

Unit 1 is at 100 % power.

Turnover:

Scenario Outline Form ES-Scenario No.:

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

Operators:

Unit 2 is at 100% power.

RCIC is running per 849.1.0 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 Malfunction Event Event No.

Number Type*

Description

I I-PRO 1

E51-S37 R-RO Inadvertent RCIC Startup and injection E51-S37-PB TS-SRO (Abnormal)

MED015E C-PRO D 13 Dead Bus Transfer to 101 I 013 DIG fails to 2

MDG420C TS-SRO start (Malfunction)

VIC108B C-RO

'1 B' Condensate Pump Vibration requiring 3

MCN604B C-PRO

. shutdown (Abnormal) 4 MRR441 C-ALL Leak in the Drywall (Abnormal)

MHP447A E41-S20 MRR440A MED262A M-ALL LOCA with 5

MSL196A MSL196B Loss of High Pressure Injection Sources MSL196C MRC466 6

MCR547 C-RO Loss of CRD system due to clogged suction filter (Abnormal) 7 MCS183A C-PRO

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

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

Appendix D Scenario Outline Form ES-D-1 Facility:

Limerick 1 & 2 Scenario No.:

SEG-4056E Rev _1_ Op-Test No.:

L 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 with steps complete to step __. Crew is to continue withdrawing control rods IAW rod move sheet until 4 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 E51-S37-PB I-PRO Inadvertent RCIC system start (Abnormal) 3 E51-S37 R-RO TS-SRO 4

MPC482A C-PRO 11 A' Drywell Chiller trip (Abnormal) 5 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) 6 (34-23) scram (Malfunction)

(58-35)

MED261 M-All Grid Instability Resulting in Loss of Offsite 7

MED263D C-PRO Power Fault on 014 SFGD BUS MHP447B C-PRO HPCI system failure on initiation 8

MDG420C (Malfunction)

D13 Diesel Auto Start Failure (Recoverable)

MRR440A M-All Small Break LOCA (1.5% ramped over 5 9

minutes) with D14 Diesel Trip on Bus Lockout MDG418D MRC466 C-PRO RCIC Turbine trip on overspeed 10 (Malfunction)

(Recoverable after RPV Level reaches -1 50")

(N)ormal, (R)eactivity, (l)nstrument, (C}ornponent, (M)ajor

Appendix D ES-D-1 Facility:

Limerick 1 & 2

_1 _.

Examiners:

Initial Conditions:

Scenario Outline Form Scenario No.:

SEG-6213E Rev_1_

Op-Test No.:

Operators:

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

Turnover:

Crew is reguired to cross-tie 114A LC to 124A LC 12er 893.7.A to remove 114A Reactor Area Load Center Transformer SuQQly Breaker for Maintenance. LC Transformer to service when maintenance is comQlete.

Event Malfunction Event Event No.

N1.,1mber Type*

Description 1

N/A N~PRO I Cross tie 114A to 124A Load Center G-PRO 2

MEH101C R-RO

3 Turbine Stop Valve fail closed (Abnormal)

TS-SRO C-RO 3

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

MED263A 011 Bus Lockout (Abnormal)

TS-SRO 5

MSL001B C-RO

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

MRP029B A TWS, SLC failure 6

MSL559 M-ALL C22-S1B (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 8

M-ALL MRC464A MSO exceeded in 2 areas 9

MAD1480 C-PRO

'1 M' SRV fails closed I*

(N)ormal, (R)eactivity, (l)nstrument,

{C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

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

1 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 I

C-PRO I

1 118 1-5 Loss of Isa-Phase Bus Cooling (Abnormal)

R-RO I

2 MRP029A I-RO RPS Level Instrument Failure MV12328 TS-SRO MCR412A MCR547 C-RO CRD Pump FaHL;Jre 3

MRD016C C-PRO CRD 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) 4 MSL559 C-RO with 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

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 A

A A

A G

Total A2 G*

Total 1

2 3

4 5

6 1

2 3

4

1.

1 4

3 3

3 4

le

3 20 4