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;
References
	TAC U01912
	Download: ML16088A367 (24)
	v • d • e

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 (0764)

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

G.2.2.12 (knowledge of surveillance procedures)

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

Equipment Control D,R G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and emergency conditions) Radioactive Spill Response Radiation Control N,R (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 the Control Room) Reactivate SRO License (6710)

Conduct of Operations D,R 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 (0753)

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.2.4.21 Knowledge of the parameters and logic used Emergency Plan to assess the status of safety functions, such as reactivity control, core cooling and heat removal, D,R 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 (6764)

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

G.2.2.12 (knowledge of surveillance procedures)

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

Equipment Control D,R G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and emergency conditions) Radioactive Spill Response Radiation Control N,R (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 Scenario Outline Form ES-D-1 Facility: Limerick 1 & 2 Scenario No.: SEG-4055E Rev _1_ Op-Test No.:

L Examiners: Operators:

Initial Conditions:

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

Turnover:

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 .,

E51-S37 R-RO Inadvertent RCIC Startup and injection 1 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 LOCA with 5 M-ALL MSL196A Loss of High Pressure Injection Sources MSL196B MSL196C MRC466 C-RO Loss of CRD system due to clogged suction filter 6 MCR547 (Abnormal)

C-PRO '1A' Core Spray Pump fails to auto start 7 MCS183A (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 MRD016F C-RO Control Rod (18-19 ) scrams (Abnormal) 2 (18-19) TS-SRO E51-S37-PB I-PRO Inadvertent RCIC system start (Abnormal) 3 R-RO E51-S37 TS-SRO 1

4 MPC482A C-PRO 1A' Drywell Chiller trip (Abnormal)

MED279A C-PRO Loss of 10-Y201 safeguard electrical panel 5 (Abnormal)

TS-SRO MRD016F C-RO 2nd and 3rd Control Rod (34-23) and (58-35) 6 (34-23)

(58-35) scram (Malfunction)

MED261 M-All Grid Instability Resulting in Loss of Offsite 7 Power MED263D C-PRO Fault on 014 SFGD BUS MHP447B C-PRO HPCI system failure on initiation 8 (Malfunction)

MDG420C 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 Scenario Outline Form ES-D-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 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 Loss of power to Div I RRCS TS-SRO C-.PRO 4 MED263A 011 Bus Lockout (Abnormal)

TS-SRO

'1 B' SLC Pump spuriously starts and injects 5 MSL001B C-RO (Abnormal)

MRP029B ATWS, SLC failure 6 MSL559 M-ALL (ARI successful on low level)

C22-S1B 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 MSO exceeded in 2 areas MRC464A 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

I 1 C-PRO 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 K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

1.

Emergency 1 4 3 3 *: 3 4

le

3 20 4 3 7

& 2 1 1 1 . x:.. 2 1 1 7 2 1 3 Plant Tier ..

Evolutions 5 4 4 ) 5 5 **.

4 27 6 4 10 Totals 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 1 2 3 Systems Tier 4 4 3 3 3 4 3 3 3 4 4 38 3 5 8 Totals 1 2 3 4 I 2 3 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 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 KlAs 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) KlAs 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 Form ES-401-1 2016 NRC 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 interpret the following as they apply to 295024 High Drywell Pressure I 5 x HIGH DR YWELL PRESSURE: Drywell 4.0 76 temperature AA2.07 - Ability to determine and/or 295016 Control Room interpret the following as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT :

3.4 77 Suppression chamber prrssure AA2.02 - Ability t.o d.:terrnine andlllr interpret the following as they apply to 295003 Partial or Complete Loss of AC/6 x PARTIAL OR COMPLETE LOSS OF A.C. 4.3 78 POWER : Reactor power, pressure, and level 2.4.47 - Emergency Procedures I Plan:

29503 l Reactor Low Water L..:vel I Ability to diagnose and recognize trends in 2

x an accurntc and timely manner utilizing the 4.2 79 annropriate control room reference material.

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

295038 High Off~site Release Rate Knowledge of local au1'iliary 0perntor ta;;ks 19 x during emergency and the resuhant 4.0 80 op.:rational effects.

2.4.11 - Emergency Procedures I Plan:

295018 Partial or Total Loss of 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 interpret the following: as they apply to Watt:r Temp. I 5 x SUPPRESSION POOL HIGH WATER 4.0 82 TEMPERATURE: Reactor presmre EKI.01 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as Water Temp. 15 x they apply to SUPPRESSION POOL HIGH 3.0 39 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 applications of the following concepts as 600000 Plant Fire On-site I 8 x they apply to Plant Fire On Site: Fire 2.9 41 Fighting EK2.03 - Knowledge of the interrelations 295030 Low Suppression Pool Water Level I 5 x between LOW SUPPRESSION POOL 3.8 42 WATER LEVEL and the following: LPCS EK2.01 - Knowledge of the interrelations 295038 High Off-site Release Rate 19 x between HIGH OFF-SITE RELEASE 3.1 43 RATE and the followinQ: Radwaste AK2.03 - Knowledge of the interrelations 295021 Loss of Shutdown Cooling between LOSS OF SHUTDOWN 14 x COOLING and the following:

3.6 44 AHR/shutdown coolina AK3.01 - Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss of PARTIAL OR COMPLETE LOSS OF CCW/8 x COMPONENT COOLING WATER:

2.9 45 Isolation of non-essential heat loads:

Plant-Soecific AK3.02 - Knowledge of the reasons for 295003 Partial or Complete Loss of AC/ 6 x the following responses as they apply to 2.9 46 PARTIAL OR COMPLETE LOSS OF

ES-401 2 Form ES-401-1 2016 NRC 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 the following responses as they apply to Trip/ 3 x MAIN TURBINE GENERATOR TRIP:

2.8 47 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 monitor the following as they apply to 295025 High Reactor Pressure I 3 x HIGH REACTOR PRESSURE: HPCI:

3.8 49 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 interpret the following as they apply to 295028 High Drywell Temperature . 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 GENERATOR VOLTAGE AND Electric Grid Disturbances x ELECTRIC GRID DISTURBANCES:

3.6 52 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 2.1.20 - Conduct of Operations: Ability 295004 Partial or Total Loss of DCPwr/6 x to interpret and execute procedure 4.6 54 steps.

2.1.27 - Conduct of Operations:

295019 Partial or Total Loss of 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 license) Knowledge of the design, Abandonment I 7 x procedural, and operational differences 3.8 56 between units.

EK1 .01 - Knowledge of the operational 295031 Reactor Low Water Level implications of the following concepts as

/2 x they apply to REACTOR LOW WATER 4.6 57 LEVEL : Adequate core cooling AA2.01 - Ability to determine and/or 295023 Refueling Ace Cooling interpret the following as they apply to Mode/ 8 x REFUELING ACCIDENTS: Area 3.6 58 radiation levels KIA Category Totals: 4 3 3 3 414 3/3 Group Point Total:

I 2017

ES-401 3 Form ES-401-1 2016 NRC 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 interpret rhe following as they apply to 500000 High CTMT Hydrogen Conc. / 5 x 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 inteq.>rd the following as they apply to 295022 Loss of CRD Pumps I I x LOSS OF CRD PUMPS : CRD system 3.4 85 status AKI .02 - Knowledge of the operational implications of the following concepts as 3.

295022 Loss of CRD Pumps I 1 x they apply to LOSS OF CRD PUMPS: 6 59 Reactivity control AK2.02 - Knowledge of the interrelations 295012 High Drywell between HIGH DRYWELL 3.6 Temperature I 5 x TEMPERATIJRE and the following:

60 Drvwell cooling AK3.02 - Knowledge of the reasons for the 295002 Loss of Main Condenser following responses as they apply to LOSS 3.

Vac/3 x OF MAIN CONDENSER VACUUM : 4 61 Turbine trip AAI.09 - Ability to operate and/or monitor 295008 High Reactor Water Level the following as they apply to HIGH 3.

12 x REACTOR WATER LEVEL : Ability to 3 62 drain: Plant-Soecific EA2.0l - Ability to determine and/or interpret the following as they apply to 295034 Secondary Containment 3.

Ventilation High Radiation/ 9 x SECONDARY CONTAINMENT 8

63 VENTILATION HIGH RADIATION:

Ventilation radiation levels 2.4.47 - Emergency Procedures I Plan:

295017 High Off-site Release Ability to diagnose and recognize trends in 4.

Rate I 9 x an accurate and timely manner utilizing the 2 64 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 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#

1 2 3 4 5 6 1 3 4 A.2.lfl- Ahilit.y to (a) predict the irnpac:ts of the following oll the EMERGENCY GENERATORS (D!ESEUJETJ; and (b) based on ,u 264000 EDGs x those predictions. use procedures to 86 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 RANGE MONITOR SYSTEM; 215005 APRM I LPRTvt x and (b) based on those predictions.

3.7 87 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 2120C~l RPS x parameters that are t'ntry-levd 4.6 88 conditions for Technical Specificati<)llS.

2.2.4 ** Equipment Control: (multi**

unit license) Ability to explain the 4UU()OO Compllnent Conling variations in control board layout~.

Water x systems, instrnrnemation and 3.6 89 proc:edural actions between units al a facilitv.

2.1 J l - Condud. <Jf Operatiuns:

Ability 10 loc:ate control rc>Pm 2moou RHR/LPCI: Injection x switches, controls, and indkations, 4.3 90 Mode 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 206000HPCI x PRESSURE COOLANT 3.6 l INJECTION SYSTEM and the following: Reactor feedwater system: BWR-2,3,4 K1 .17 - Knowledge of the physical connections and/or cause- effect relationships 262002 UPS (AC/DC) x between UNINTERRUPTABLE 3.1 2 POWER SUPPLY (A.C./D.C.)

and the following: Scram solenoid valves: Plant-Specific 262001 AC Electrical K2.01 - Knowledge of electrical Distribution x power supplies to the following: 3.3 3 Off-site sources of power K2.02 - Knowledge of electrical 211000 SLC x power supplies to the following: 3.1 4 Explosive valves

ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000 ADS x DEPRESSURIZATION SYSTEM 4.5 5 will have on following: Ability to raoidlv deoressurize the reactor K3.04 - Knowledge of the effect that a loss or malfunction of the 215004 Source Range Monitor x SOURCE RANGE MONITOR 3.7 6 (SAM) SYSTEM will have on following: Reactor power and indication K4.02 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER 215005 APRM I LPRM x RANGE MONITOR SYSTEM 4.1 7 design feature(s) and/or interlocks which provide for the following: Reactor SCRAM sianals K4.17 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design 259002 Reactor Water Level feature(s) and/or interlocks Control x which provide for the following:

3.1 8 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 209001 LPCS x following concepts as they apply 2.6 9 to LOW PRESSURE CORE SPRAY SYSTEM: Indications of oumo cavitation KS.02 - Knowledge of the operational implications of the following concepts as they apply 205000 Shutdown Cooling x to SHUTDOWN COOLING 2.8 10 SYSTEM (AHR SHUTDOWN COOLING MODE) : Valve ooeration K6.01 - Knowledge of the effect 400000 Component Cooling that a loss or malfunction of the Water x following will have on the 2.7 11 CCWS: Valves K6.04 - Knowledge of the effect that a loss or malfunction of the 203000 RHR/LPCI: Injection following will have on the Mode x RHR/LPCI: INJECTION MODE 3.3 12 (PLANT SPECIFIC) : Keep fill svstem A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 212000 RPS x REACTOR PROTECTION 2.6 13 SYSTEM controls including:

RPS bus frequency: Plant-Soecific

ES-401 4 Form ES-401-1 2016 NRG Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G 0#

1 2 3 4 5 6 1 3 4 A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS x STANDBY GAS TREATMENT 3.2 14 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, 215003 IRM x use procedures to correct, 3.3 15 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 264000EDGs x procedures to correct, control, or 3.3 16 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 239002 SRVs x RELIEF/SAFETY VALVES 4.3 17 including: SRV operation on high reactor pressure A3.01 - Ability to monitor automatic operations of the D.C.

263000 DC Electrical ELECTRICAL DISTRIBUTION Distribution x including: Meters, dials, 3.2 18 recorders, alarms, and indicating liahts A4.01 - Ability to manually 300000 Instrument Air x operate and/or monitor in the 2.6 19 control room: Pressure gauaes A4.05 - Ability to manually operate and/or monitor in the 217000RCIC x control room: Reactor water 4.1 20 level 2.4.9 - Emergency Procedures I Plan: Knowledge of low power I 223002 PCIS/Nuclear Steam shutdown implications in Supply Shutoff x accident (e.g., loss of coolant 3.8 21 accident or loss of residual heat removal) mitiaation strateaies.

2.4.20 - Emergency Procedures I Plan: Knowledge of operational 218000 ADS x implications of EOP warnings, 3.8 22 cautions, and notes.

2.1.30 - Conduct of Operations:

Ability to locate and operate 215004 Source Range Monitor x components, including local 4.4 23 controls.

ES-401 4 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the 223002 PCIS/Nuclear Steam PRIMARY CONTAINMENT Supply Shutoff x ISOLATION 3.0 24 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF:

Containment instrumentation K 1.17 - Knowledge of the physical connections and/or cause- effect relationships 203000 RHR/LPCI: Injection Mode x between RHR/LPCI: 4.0 25 INJECTION MODE (PLANT SPECIFIC) and the following:

Reactor pressure K2.02 - Knowledge of electrical 205000 Shutdown Cooling x power supplies to the following: 2.5 26 Motor operated valves Kl A Category Totals: 3 3 2 2 2 3 2 2/2 2 2 3/3 Group Point Total:

I 2615

ES-401 5 Form ES-401-1 2016 NRC Written Examination Outline Plant Systems -Tier 2 Group 2 System #I Name K K K K K K A A2 A A G Imp.

a 1 2 3 4 5 6 1 3 4 #

A2.01 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTFRNAl.B 29l~J02 Reactor Vessel ; and lb J based on those Internals x predictions. use procedures to 4.0 9l correct, control. or rnitigate the conscqucnces of rhose abnormal conditions or operations: LOCA 2.2.25 - Equipment Control:

Knowledge of bases in technical 286\lOO Fire Protedion x spe.:ifications for limiting 4.2 92 rnnditions for operntions and safety limits.

2.4.34 - Emergency Prm:edur.;s !

Plan: Knowledge of RO ta:;.ks 2l400URPIS x performed outside the main control 4.l 93 room during an emergency and the re;;ultant operational effect;;,

Kl .01 - Knowledge of the physical connections and/or cause- effect relationships between REACTOR 20!002RMCS x MANUAL CONTROL SYSTEM 3.2 27 and the following: Control rod drive hydraulic system K2.09 - Knowledge of electrical 223001 Primary CTMT and power supplies to the following:

Aux.

x Drywell cooling fans: Plant-2.7 28 Specific K3.02 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION 288000 Plant Ventilation x SYSTEMS will have on following:

2.9 29 Reactor building temperature:

Plant-Specific K4.05 - Knowledge of REACTOR VESSEL 290002 Reactor Vessel INTERNALS design feature(s)

Internals x and/or interlocks which provide 3.3 30 for the following: Natural circulation K5.09 - Knowledge of the operational implications of the following concepts as they apply 271000 Off-gas x to OFFGAS SYSTEM :

2.6 31 Hydrogen and oxygen recombination K6.06 - Knowledge of the effect that a loss or malfunction of the 241000 Reactor/Turbine following will have on the Pressure Regulator x REACTOR/TURBINE 3.8 32 PRESSURE REGULATING SYSTEM : Reactor pressure A1.10 - Ability to predict and/or monitor changes in parameters 239001 Main and Reheat associated with operating the Steam x MAIN AND REHEAT STEAM 3.8 33 SYSTEM controls including:

Reactor power

ES-401 5 Form ES-401-1 2016 NRG Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name K K K K K K A A2 A A G Imp.

a 1 2 3 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 256000 Reactor Condensate x procedures to correct, control, 3.1 34 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 201003 Control Rod and Drive Mechanism x CONTROL ROD AND DRIVE 3.7 35 MECHANISM including: Control rod position A4.01 - Ability to manually operate and/or monitor in the 214000RPIS x control room: RCIS rod action 3.2 36 control bypass switches 2.4.2 - Emergency Procedures I Plan: Knowledge of system set 214000 RPIS x points, interlocks and automatic actions associated with EOP 4.5 37 entry conditions.

A4.10 - Ability to manually 233000 Fuel Pool Cooling/Cleanup x operate and/or monitor in the 2.5 38 control room: Tank levels KIA Category Totals: 1 1 1 1 1 1 1 111 1 2 1/2 Group Point Total:

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#

Knowledge of new and spent fuel movement 2.1.42 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. Ability to direct personnel activities inside the 2.1.9 2.9 66 Conduct control room.

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

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

Subtotal 3 2 Ability to determine Technical Specification 2.2.35 4.5 95 Mode of Operation.

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

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

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

Subtotal 2 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 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, such as fixed radiation monitors and alarms, 2.3.15 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.

Knowledge of abnormal condition 2.4.11 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 procedures those actions that require 2.4.49 4.6 73 immediate operation of system components and controls.

Subtotal 2 2 Tier 3 Point Total ".; . 10 ..::~... 7

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

Replaced with 214000 RPIS 2.4.2 Q# 96 Duplicated in operating test 3 G3 I 2.3.6 replaced with 2.3.15 295022 I Q# 85 The subject KIA isn't relevant at the subject facility.

lI2 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 (0764)

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

G.2.2.12 (knowledge of surveillance procedures)

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

Equipment Control D,R G.2.3.14 (knowledge of radiation and contamination hazards that may arise during normal, abnormal, and emergency conditions) Radioactive Spill Response Radiation Control N,R (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 the Control Room) Reactivate SRO License (6710)

Conduct of Operations D,R 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 (0753)

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.2.4.21 Knowledge of the parameters and logic used Emergency Plan to assess the status of safety functions, such as reactivity control, core cooling and heat removal, D,R 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 (6764)

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

G.2.2.12 (knowledge of surveillance procedures)

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

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