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ES-201 Examination Outline Quality Checklist Form ES-201-2
Facility. ,4P ica, Voq/1e- L.Lks -4jfV is1wiv U4if 5 2 3 Initials
Item Task Description —
1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N.
b. Assess whether the outline was systematically and randomly prepared in accordance with
T Section D.1 of ES-401 or ES-401 N and whether all K/A categories are appropriately sampled. 7_c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. 7_ 4d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. .
2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number ofnormal evolutions, instrument and component failures, technical specifications, and major
S transients. —
M b. Assess whether there are enough scenario sets (and spares) to test the projected number andU mix of applicants in accordance with the expected crew composition and rotation scheduleL without compromising exam integrity, and ensure that each applicant can be tested using atA least one new or significantly modified scenario, that no scenarios are duplicated from theT applicants’ audit test(s), and that scenarios will not be repeated on subsequent days. — —
c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative andquantitative criteria specified on Form ES-301-4 and described in Appendix D.
3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301 -2:(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed
W among the safety functions as specified on the form ,iJA (2) task repetition from the last two NRC examinations is within the limits specified on the formL (3) no tasks are duplicated from the applicants’ audit test(s)K (4) the number of new or modified tasks meets or exceeds the minimums specified on the form
(5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria onT the form.HR b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:o (1) the tasks are distributed among the topics as specified on the formU (2) at least one task is new or significantly modified
G (3) no more than one task is repeated from the last two NRC licensing examinations —
Hc. Determine if there are enough different outlines to test the projected number and mix of
applicants and ensure that no items are duplicated on subsequent days. —
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the 9j4appropriate exam sections. f/f
E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
E c. Ensure that K/A importance ratings (except for plant-specific pnonties) are at least 2.5. q
d. Check for duplication and overlap among exam sections. ‘i”
L e. Check the entire exam for balance of coverage.
f. Assess whether the exam fits the appropriate job level (RO or SRO 4 f—
a. Author %Me ofjoicb. Facility Reviewer (*) lL/74c. NRC Chief Examiner (#) Rt.U.LO —6 —(Sd. NRC Supervisor 6 fit.. r1ifl-. /Note: # Independent NRC reviewer initial items in Column ‘c”: chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines.
ES-401N AP-1000® Examination Outline Form ES-401N-2
Facility: I?t [Le.. Lc 3 4/VC-. jmet3 Date of Exam: veM4.e.r 20i 5‘ RO K/A Category Points SRO-OnIy_Points
Tier Group K K K K K K A A A A1 2 3 4 5 6 1 2 3
GTotal
G Total
1. 1 18 3 6
Emergency &2 — — 9 4Abnormal ‘ N/A ‘ ‘ N/A — 2
PlantEvolutions Tier Totals 4. 4. ft 27 10
i ZZ23333 28 3 Z 5
Pnt 2
SystemsTier Totals 3 3 4 3 3 3 4 4 4 4 3 38 S 3 8
3. Generic Knowledge and Abilities 1 2 310
1 2 3 4
Categories 3, 3
Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO andSRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals” in each K/A
1’ category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by aK/A 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 finalpoint total for each group and tier may deviate by ±1 from that specified in the table based on NRC revisions.The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do, not apply at the facility should be deleted with justification; operationally important, site-specific
1tT’ systems/evolutionsthatare not induded on the outline should be added. Refer to Section D.1.b of ES-401Nfor guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group‘L before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall beI ‘ selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.7fjL. 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7. The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must4t be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 N for the applicable K/As.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics’ importance ratings(IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group
V and tier totals for each category in the table above; if fuel handling equipment is sampled in other thanCategory A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1does not apply). LIRe dupliQate pages fer RO and RO-anly exams. Al/A -
- gef,a.,, 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and‘‘‘— point totals (#) on Form ES-401 N-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As
ES-401 N, Page 38 of 51
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ES-401N 3 Form ES-401N-2
ES-401N AP-l000® Examination Outline Form ES-401N-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 —
EIAPE # / Name / Safety FunctionK I A I A I G* KIA Topic(s) lR
A-31 1, Rod Control System Malfunction I 1
A-308, Loss of Control Room AC / 8
A-320, Loss of Circulating Water / 8 P. (P)A 143.oç
A-302, Emergency Boration / I
A-327, Startup Feedwater System Malfunction / 4
A-328, Malfunction of Feedwater Heaters andExtraction Steam / 4
FR-l.1 Response to High Pressurizer Level / 2
A-314, Fuel Handling Incident / 8 P.) A)(. oaA-304, Steam Generator Tube Leak/3 S (5) 2.. 1.j7
A-333, Main Turbine Malfunction / 4
FR-Z.1, Response to High Containment Pressure I5
SDP-4, Response to Rising Nudear Flux During — — — — () E-A2. .04 — —
Shutdown/i — — — — S — (5) FiZ.Ol — —
SDP-5, Response to RCS Cold OverpressureDuring Shutdown I 3
SDP-6 Response to Unexpected RCS P. C P.) E I2..O4Temperature Changes During Shutdown /4
A-306, Evacuation of Control Room /8 R (9.) AG 2 4.4
A-318, Condensate System Malfunctions /4 R CR) AA(.09
FR-C-2, Response to Degraded Core Cooling /4
FR-C.3, Response to Saturated Core Cooling / 4 ) E K I .0
FR-H.2, Response to Steam GeneratorOverpressure /4
FR-Z.2, Response to Containment Flooding / 5
FR-Z.3, Response to High Containment Radiation /9
FR-Z.4, Response to Low Containment Pressure / ( (R) E 1(2.015
A-332, Turbine Trip Without Reactor Trip / 4 — — — — — S (5)A 2 •17 — —
ES-i .2, Post LOCA Cooldown andDepressurization / 4
A-321, Loss of Data Display and ProcessingSystem / 7
FR-P.1, Response to Imminent PressurizedThermal Shock Condition /3
A-340, Reactor Coolant Leak /2
FR-i .2, Response to Low Pressurized Level /2
FR-i .3, Response to Voids in Reactor Vessel /2 = = = — ) E42.. 02.
V
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ES-401 N, Page 40 of 51
Vv’
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ES-401N 4 Form ES-401N-2
ES-401N AP-1000® Examination Outline Form ES-401N-2
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)
EIAPE#I Name /Safety FunctionK1K1 KI AIAI
fl<)AToPic(5) iR]#
A-326, Feedwater System Malfunctions / 4
A-331, Loss of plant DC Power or Batteries /6 ) APuI• o2.
A-348, Degraded Grid /6
KIA Category Totals: i 2 2. i I Group Point Total: 9/4
SRO 22.
ES-401N, Page 41 of 51
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02/0
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158:
10A
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ES-401N 5 Form ES-401N-2
ES-401 N AP-1 000® Examination OunQ
Plant Systems - Tier 2/Group 1Q)(ROJForm ES-40i N-2
KKKKKKAAAA GSystem Name! Safety Function K/A Topic(s) IR #
1234561234
Reactor Coolant /2,4 —
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(R 142.04
Normal Residual Heat Removall4 — — — — — — —
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ES-401N, Page 42 of 51
FOR
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Abi
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02/0
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152:
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02/0
4/20
152:
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Pag
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of3
02/0
4/20
152:
23PM
ES
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,R
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Pag
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02/0
4/20
152:
23PM
ES-401N 6 Form ES4OIN-2
6Ic 2.
ES-401 N AP-1 000® Examination Ou e Form ES-401 N-2
Plant Systems - Tier 2/Group 2 RO SRO
. KKKKKKAAAAG*System Name/ Safety Function
1 2 3 4 5 6 1 2 3 4‘A Topic(s) IR #
Digital Rod Control/f — — — — — — — —
(P.)A2..19 )2.4-. 3. —
Pressurizer Level Control /2 S )AZ .0
Rod Position Indication/i(g.) K2.03
Incore Instrument System / 7
Containment Air Filtration /8
Containment Hydrogen Control I5
Main Control Room HVAC /8 — —
— (R) K .0f —
Spent Fuel Pool Cooling / 8
Condensate! 4 R () A3 .0
CondenserAirRemoval/4 — — — — — — —— l’ —
Main Turbine and Main Turbine ( P.) K l.0 —
Controll4
Fuel Handling 18
Gaseous Radwaste /9 P. C ) Al o2. —
Radiation Monitoring /7
Circulating Water! 8 —
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Nuclear Instrumentation System!— —
— () A4.02. CS) AZ. 09 —
7
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KIA Category Point Totals: _[ L iL , Group Point Total: — 10/3
ES-401 N, Page 43 of 51
ES
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Pag
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02/0
4/20
152:
23PM
ES
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KA
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Pag
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02/0
6/20
158:
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ES4OIN Generic Knowledge and Abilities Outline (Tier 3) Form ES-401N-3
Facility: Vogk(e- Avuf s 3 4 /Vr_ 5e- 2’ 3 Date of Exam: N ov. ZD1’3
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ES-401N, Page 44 of 51
ES
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ES-301 Administrative Topics Outline Form ES-301-1
Facility: Vogtle Units 3&4 Date of Examination: 11/2015
Examination Level: RO Operating Test Number:
Administrative Topic (see Note) Type Describe activity to be performedCode*
Determine if you can replace a watchstander due to illness
Conduct of Operations M, RG2.1.5 2.9
Calculate the volume of boric acid to beadded using section 4.8 of Attachment 3 of
Conduct of Operations N, R 3CVSS0P001
G2.1.21 4.3
Perform Normal Residual Heat RemovalPump 1A Quarterly Exercise Test
Equipment Control N, RG2.2.8 3.7
Determine Best Route to Limit Personnel
Radiation ControlExposure and not to Exceed Exposure
N, R Limits
G2.3.6 3.2
NOTE: All items (five total) are required for SROs. RO applicants require only four items unless theyare retaking only the administrative topics (which would require all five items).
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1
Facility: Vogtle Units 3&4 Date of Examination: 11/2015
Examination Level: SRO Operating Test Number:
Administrative Topic (see Note) Type Describe activity to be performedCode*
Determine which RO, if any, can replace awatch stander due to illnessConduct of Operations M, RG2.1.5 3.9
Determine if current conditions allow Mode4 entryConduct of Operations N, RG2.1.21 4.4
Perform Normal Residual Heat RemovalPump IA Quarterly Exercise TestEquipment Control N, RG2.2.26 4.7
Determine Emergency Exposure limits for a
Radiation Control task and determine if the task can beN, R performed.
G2.3.8 3.8
Provide an updated Protective ActionRecommendation (PAR)Emergency Plan N, RG2.4.35 4.4
NOTE: All items (five total) are required for SROs. RD applicants require only four items unless theyare retaking only the administrative topics (which would require all five items).
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom(D)irect from bank ( 3 for ROs; 4 for SROs & RD retakes)(N)ew or (M)odified from bank ( 1)(P)revious 2 exams ( 1 randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
Facility: Vogtle Units 3&4 Date of Examination: 11/2015
Exam Level: RO SRO-l SRO-U Operating Test No.:
Control Room Systems: 8 for RO; 7 for SRO-l; 2 or 3 for SRO-j
System / JPM Title Type Code* SafetyFunction
a. Recover a dropped control rod.
Description: The unit is at 65% power and rod H14 has fullydropped into the core. The candidate is directed to re-align rodH14 to its bank at 82 steps in accordance with 3-AOP-104 (Rod
MControl System Malfunction) Attachment 2 (Move Individual Rodor Group to Realign Rods).
SF1 DRCS A4.09 RO/SRO 4.0
b. Perform RCS Blended Makeup
Description: With the unit at 80% reactor power, the candidateis directed to perform a 150 gallon blended makeup to the RCSin accordance with 3-CVS-SOP-001 (Chemical and Volume N, S 2Control System) Attachment 3 (RCS Makeup System Operation).
SF2 CVS A4.04 RO/SRO 3.5
c. Reduce RCS Pressure Using ADS Valves
Description: The unit has been shutdown due to a steamgenerator tube leak. The candidate is directed to lower RCSpressure via ADS in accordance with 3-AOP-1 03 (SteamGenerator Tube Leak) to less than 1920 psig. When attempting A, EN, L, M,to place Division A ADS in service to lower pressure, a Smalfunction occurs requiting ADS Division B to be placed inservice.
SF3 ADS A4.04 RO/SRO 4.1
U. Respond to Condensate System Malfunctions inAccordance With AOP-202
Description: The unit is at 59% reactor power with CDS PumpA degraded. The candidate is directed to perform 3-AOP-202(Condensate System Malfunctions) due to the reduced dischargepressure on CDS Pump A. During performance, CDS Pump Awill trip and CDS Pump C will have a sheared shaft, requiring thecandidate to manually run back the unit. Once the run back iscomplete, CDS Pump B will trip, requiring a Reactor Trip,securing all Main Feed Pumps, and securing SG blowdown.
SF4S CDS A4.04 ROISRO 2.8
e. Shutdown VES
Description: A spurious Main Control Room Isolation occurred.The candidate is required to remove VES from service inaccordance with AOP-501 (Loss of Main Control Room Air N, S 8Conditioning) Attachment 1 (Alternate MCR Cooling).
SF8 VES A4.01 RO/SRO 3.6
f. Manual Reset of SR High Flux Signal
Description: The unit tripped from 100% reactor power. IRNIExcore Detector A failed after the trip. The candidate is requiredto perform 3-EOP-ES-0. 1 (Reactor Trip Response) steps 28 and29. During performance, the candidate will restore blowdown to A, L, D, S 7sample the steam generators and re-energize SRNI A at thePDSP.
SF7 NIS K4.08 RO/SRO 4.0
g. Verify Containment Isolation in Accordance With FR-Z.3
Description: The unit was tripped due to a small RCS leak.Entry into FR-Z.3 (Response to High Containment Radiation) isrequired. The candidate is directed to perform FR-Z.3. During
A EN L Dperformance, VFS valve failures require the candidate to restore ‘ , , , 9a ventilation flowpath for VAS by securing VFS-MA-O1A, closingthe failed valves, and starting VFS-MA-02B.
FR-Z.3 EA1.03 RO/SRO 3.1
h. Warm the Main Steam Lines
Description: The unit is being held at 557 °F Tavg. Thecandidate is directed to re-open the MSIVs, close the MSIVbypass valves, and place steam dumps in service holding 1085
L N S 4Ppsig.(RD ONLY)
SF4P SGS A4.08 RD 2.8
In-Plant Systems* (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
k.
* All RD and SRO-l control room (and in-plant) systems must be different and serve different safetyfunctions; all five SRD-U systems must serve different safety functions; in-plant systems and functionsmay overlap those tested in the control room.
Type Codes Criteria for RD / SRO-l / SRD-U
A)lternate path 4-6 / 4-6 / 2-3fC)ontrol room(D)irectfrombank(E)mergency or abnormal in-plant 1 / 1 / 1(EN)gineered safety feature 1 / 1 / 1 (control room system)(L)ow-Power / Shutdown 1 / 1 / 1(N)ew or (M)odified from bank including 1 (A) 2 / 2 / 1(P)revious 2 exams 3 / 3 / 2 (randomly selected)(R)CA(S)imulator
In-Plant JPMs not identified at the time of
DRAFT submittal.
