ML18032A237
| ML18032A237 | |
| Person / Time | |
|---|---|
| Site: | Summer, Vogtle  |
| Issue date: | 02/01/2018 |
| From: | Michael Meeks NRC/RGN-II/DRS/OLB |
| To: | Southern Nuclear Operating Co |
| References | |
| Download: ML18032A237 (26) | |
Text
Ex141 ,A1fLE t-4AJ OA/LY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility.
,4P ica, Voq/1e- L.Lks -
j 4 f V is1wiv U4if 5 23 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.
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- c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
- d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. .
7_ 4
- 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal 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 and U mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T 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 and quantitative 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 ,iJ A (2) task repetition from the last two NRC examinations is within the limits specified on the form L (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 on T the form.
H R 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 form U (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 H
- c. 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 9j4 appropriate exam sections. f/f E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
- c. Ensure that K/A importance ratings (except for plant-specific pnonties) are at least 2.5. q E
- d. Check for duplication and overlap among exam sections. i L e. Check the entire exam for balance of coverage.
- a. Author %Me 4
lL/7 ofjoic
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#) Rt.U.LO 6 (S
- d. 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.
- WiT[Ei1 &4#7 S4,ij/ /1/IA) ChitY ES-201, Page 26 of 28
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 A G G Total 1 2 3 4 5 6 1 2 3 Total
- 1. 1 18 3 6 Emergency &
2 9 2 4 Abnormal N/A N/A Plant Evolutions Tier Totals 4. 4. ft 27 10 i ZZ23333 28 3 Z 5 2
Pnt Systems Tier Totals 3 3 4 3 3 3 4 4 4 4 3 38 S 3 8
- 3. Generic Knowledge and Abilities 1 2 3 1 2 3 4 10 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 and SRO-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 a K/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 final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do
, not apply at the facility should be deleted with justification; operationally important, site-specific 1tT systems/evolutionsthatare not induded on the outline should be added. Refer to Section D.1.b of ES-401N for 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 be I selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
fjL.
7 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 must 4t 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 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). 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-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO A-301AK3.04 Rapid Power Reduction 3 Placing Digital Rod Control System in Low Power Mode A-307AA1.01 DAS Operation At Local Cabinets 3.4 0 Passive Core Cooling System 1 Uncontrolled Cooldown A-313AG2.4.4 - - 4.5 4.7 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for Emergency/Abnormal Operating Procedures.
A-323AA2.04 Loss of 6.9KV, 4160 Volt, or 480 3.2 3.7 Battery, battery charger, and battery bus status and/or Volt Bus Power voltage A-336AK1 .07 Malfunction of Protection and 2.7 Main and Startup Feedwater System Safety Monitoring System A-33iAK3o1 Passive Residual Heat Removal 3.3 Determining whether core makeup tank discharge Heat Exchanger Leak isolation valves are open A-342AK2.02 Reactor Coolant Pump Malfunctions 3.1 Reactor coolant pump trip in mode 3, 4, or 5 A-343AA2.03 Loss of Normal Residual Heat 2.8 2.7 Component Cooling Water System to Normal Residual Removal Heat Removal System heat exchanger flow E-1 EA1 .05 Loss of Reactor or Secondary 3.8 Diverse Actuation System Coolant E-2EG2.2.3o/ Faulted Steam Generator Isolation 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
E-3EK2.05 Steam Generator Tube Rupture 3.5 Allowing Reactor Coolant System pressure to rise above 1970 psig after safeguards are blocked below P-il, Pressurizer Pressure Below 1970 psig Page 1 of 2 02/04/2015 2:23 PM
ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO ES-0. 1 EA2.Oi Reactor Trip Response 3.4 3.7 Neutron flux ES-0.2Ek3.18 Natural Circulation Cooldown 3.1 Terminating the Reactor Coolant System depressurization to minimum allowable ES-i .1EG2.4.39J Passive Safety System Termination 4.24 Ability to verify system alarm setpoints and operate controls identified in the Alarm Response Procedure.
FR-C.1 EK2. ii Response to Inadequate Core 3.3 Running Normal Residual Heat Removal System pumps Cooling on time to reach cask loading pit low level FR-S.1EK1 .05 Response to Nuclear Power 3.9 Engineered Safeguards Actuation System Generation ATWS SDP-i EK1 .02 Response to Loss of RCS 3.4 Containment System Inventory During Shutdown SDP-2EA1 .03 Response to Loss of Normal 3.1 Chemical and Volume Control System (OE related)
Residual Heat Removal System During Shutdown Page 2 of 2 02/04/2015 2:23PM
ES-401, REV 9 SRO T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO A-323AA2.03 Loss of 6.9KV, 4160 Volt, or480 2.4 3.4 E E E D Standby diesel generator load Volt Bus Power A-329AA2.04 Loss of Instrument Air 3.2 3.2 DDE EDDED Reactor Coolant System temperature, steam generator level, and/or steam generator pressure (CE related)
A-336AG2.2.19 1 Malfunction of Protection and Safety 0 4.2 Knowledge of the bases in Technical Specifications for Monitoring System limiting conditions for operations and safety limits.
E-12G2.1.71 Loss of Reactor or Secondary 444.7 EDDEDDEDDD Ability to evaluate plant performance and make Coolant operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
FR-C.l EA2.04 Response to Inadequate Core 3.7 3.5 Pressurizer level and/or Reactor Coolant System hot ieg Cooling level FRH.1EG2.4.) Response to Loss of Heat Sink 4.2 4.1 Knowledge of annunciator alarms, indications, or fl response procedures.
Page 1 of 1 02/04/2015 2:23 PM
ES-401N 3 Form ES-401N-2 ES-401N AP-l000 Examination Outline Form ES-401N-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 2 K I A I A I G*
EIAPE # / Name / Safety Function 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 and Extraction Steam / 4 FR-l.1 Response to High Pressurizer Level / 2 A-314, Fuel Handling Incident / 8 P.) A)(. oa A-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 I 5
SDP-4, Response to Rising Nudear Flux During
() E-A2. .04 Shutdown/i S (5) FiZ.Ol SDP-5, Response to RCS Cold Overpressure During Shutdown I 3 SDP-6 Response to Unexpected RCS P. C P.) E I2..O4 Temperature 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 Generator Overpressure /4 FR-Z.2, Response to Containment Flooding / 5 FR-Z.3, Response to High Containment Radiation /
9 V 5 FR-Z.4, Response to Low Containment Pressure / ( (R) E 1(2.01 A-332, Turbine Trip Without Reactor Trip / 4 S (5)A 2 *17 ES-i .2, Post LOCA Cooldown and Depressurization / 4 A-321, Loss of Data Display and Processing System / 7 FR-P.1, Response to Imminent Pressurized Thermal Shock Condition /3 A-340, Reactor Coolant Leak /2 V FR-i .2, Response to Low Pressurized Level /2
/ FR-i .3, Response to Voids in Reactor Vessel /2 = = =
) E42.. 02.
ES-401 N, Page 40 of 51
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) 1 K1K KI AIAI fl<)AToPic(5) iR]#
EIAPE#I Name /Safety Function V A-326, Feedwater System Malfunctions / 4 v A-331, Loss of plant DC Power or Batteries /6 ) APuI* o2.
/ A-348, Degraded Grid /6 9/4 KIA Category Totals:
i 2 2. i I Group Point Total:
SRO 22.
ES-401N, Page 41 of 51
ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO A-306AG2.4.4J Evacuation of Control Room 4.5 4.7 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for Emergency/Abnormal Operating Procedures.
A-314AK3.02 Fuel Handling Incidents 3.6 Maintaining pressurizer/reactor cavity level and/or spent fuel pool level A-31 8AA1 .09 Condensate System Malfunctions 2.5 Steam Generator Blowdown System controls A-32oAk3o7 Loss of Circulating Water 3.3 Reducing turbine load A-331AA1.02 Loss of DC Power or AC 2.90 12OVAC Distribution Panels 1E Instrument Power FR-C.3EK1 .08 Response to Saturated Core 3.1 Reactor Coolant System Cooling FR-Z.4EK2.01 Low Containment Pressure 3.1 0 Containment integrity SDP-4EA2.04 Response to Rising Nuclear Flux 3.6 3.7 Reactor Coolant System boration flow During Shutdown SDP-6EK2.04 Response to Unexpected RCS 3.3 Component Cooling System failure Temperature Changes During Shutdown Page 1 of 1 02/04/2015 2:23 PM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SR0 A-304AG2.l.17 Steam Generator Tube Leak 3.9 3.8 ElEEElEEEElED Ability to use available indications to evaluate system or component status.
A-332AG2.1 .7 Turbine Trip Without Reactor Trip 4.4 4.7 E E E. E E El E D Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
FR-l.3EA2.02 Response to Voids in Reactor Reactor Coolant System temperature and pressure Vessel SDP-4EA2.01 Response to Rising Nuclear Flux 3.6 3.9 E E E E E E El Reactor Coolant System boron and/or shutdown margin During Shutdown El El El (02 related)
Page 1 of 1 02/06/2015 8:10AM
ES-401N 5 Form ES-401N-2 ES-401 N AP-1 000 Examination OunQ Form ES-40i N-2 Plant Systems Tier 2/Group 1Q)(ROJ KKKKKKAAAA G #
System Name! Safety Function K/A Topic(s) IR 1234561234 Reactor Coolant /2,4
( AZ .3!
- (P.A1.06__()2.l-35 Steam Generator /4 (R 142.04 cp.)g3.o Normal Residual Heat Removall4 Passive Residual Heat Removall4 R (P.) Ai. c PassiveCoreCooling/2 S W W (5)Aa.I (P. G/l.4,27 G 2. .44 Component Cooling Water / 8 (P) A3 .0 Pressurizer Pressure Control! 3 Automatic Depressurization /3 (R) G, Z .1. 2 I
.0 Reactor Thp System R)K.o3 Engineered Safeguards Actuation
( P.) A3. 13
/2 (R)X(3
- R)Az.o2.
Diverse Actuation/7 R CR) P..4.o, Passive Containment Cooling /5 Main Steam / 4 P (g)141.04-Main and Startup Feedwater/4 F. (P.)A2.33 AC Electrical Distribulion/6 5 P. (P.) A3.03 15) A2.02.
Class IE and Non 1E DC and (P.) K (,.D2 UPS/6 S (A) J41 .02. Cs) Al .0, Onsite Standby Power System / 6 P.
Service Water/4 -
(s)i 2.4.11-Compressed Air! 8 R) g;.eg Containment System / 5
( R) 3<4. D7 Ui.) i5.o2.
Reactor Coolant Pump/4 Chemical and Volume Control/i, P. (R) .04 2
KlACategoryPointTotals:
i 2 2. 3jII2_I3J3I3I3[3 GroupPointTotal: 28/5
.co 2.
ES-401N, Page 42 of 51
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO ADSG2.1 .21 / Automatic Depressurization 4.3 EDDLThD Ability to perform general and/or normal operating System procedures during any plant condition.
CASA1 .03 Compressed Air System 2.9 Instrument air supply pressure CASK3.17 - - Compressed Air System 3.1 Passive Core Cooling System (CE-related) 1 CCSG2.4.4 Component Coohng Water System 45 4.7 Ability to recognize abnormal indications for system E D EDZDD E operating parameters that are entry-level conditions for Emergency/Abnormal Operating Procedures.
CNSK4.07 Containment System 3.3 D Containment evacuation E D D CVSK2.04 Chemical and Volume Control 3.7 Containment isolation valves System DASA2.02 Diverse Actuation System 3.3 3.5 Reactor and turbine trip ECSA3.03 AC Electrical Distribution Systems 3.6 Start and loading of standby diesel generator ESASA3.13 - - Engineered Safeguards Actuation 4.3 Passive Residual Heat Removal Heat Exchanger System Actuation ESASK6.13 Engineered Safeguards Acuation 4.1 Passive Containment Cooling System Actuation System FWSA2.33 Main and Startup Feedwater 2.6 3.1 Startup feedwater pump low and high flow System Page 1 of 3 02/04/2015 2:23PM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO FWSA4.06 Main and Startup Feedwater 3.4 Startup feedwater control valve System IDSK6.02 ClasslEandNonlEDCand 3.5 Class 1 E battery charger failure UPS Systems MSSK1.04 Main Steam System 3.2 Engineered Safeguards Actuation System PCSA4.O1 Passive Containment Cooling 4.3 Passive Containment Cooling System Actuation System PPCSA3.Ol Pressurizer 3.6 Pressurizer normal spray valve operation System PRHRA1.Ol PassiveResidualHeatRemoval 3.2 Passive Residual Heat Removal System heat exchanger System pressure PXSA4.16 Passive Core Cooling System 4.4 Reactor Trip Actuation PXSG2.4.27/ Passive Core Cooling System 3.8 4 Knowledge of Non-Licensed operator tasks during an emergency and the resultant operational effects.
RCPK5.02 Reactor Coolant Pump System 2.7 Changing reactor coolant pump speed on pressurizer normal spray flow RCSA2.31 Reactor Coolant System 3.6 3.7 Reactor vessel flange leakage RNSK3.O1 Normal Residual Heat Removal 2.8 Chemical and Volume Control System System Page 2 of 3 02/04/2015 2:23PM
ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO RTSK3.06 Reactor Trip System 3.5 Passive Core Cooling System RTSK5.03 Reactor Trip System 4.3 Anticipated transient without scram coincident with D E turbine trip failure SGSA1.05 Steam Generator System 3.4 Reactor Coolant System temperature SGSK2.04 Steam Generator System 2.8 MSIV hydraulic pump SWSK4.06 Service Water System 2.7 Service Water System tower makeup ZOSK1.02 Onsite Standby Power System 3.1 Main AC Power System Page 3 of 3 02/04/2015 2:23 PM
ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO ECSA2.02 AC Electrical Distribution Systems 3.7 4.1 E E Loss of offsite power t
PXSA2.16 Passive Core Cooling System 3.8 4.3 Core makeup tank discharge isolation valve SGSG2.4.39/ Steam Generator System 4.2 4 Ability to verify system alarm setpoints and operate I controls identified in the Alarm Response Procedure.
SWSG2.4.l4/ Service Water System 3.4 4.1 , Knowledge of Emergency/Abnormal Operating Procedures layout. symbols, and icons.
ZOSA2.O1 Onsite Standby Power System 2.8 2.9 Standby Diesel and Auxiliary Boiler Fuel Oil System E E D ED D Page 1 of 1 02/04/2015 2:23 PM
ES-401N 6 Form ES4OIN-2 AP-1 000 Examination Ou e Form ES-401 N-2 ES-401 N Plant Systems Tier 2/Group 2 RO SRO
. KKKKKKAAAAG* IR #
System Name/ Safety Function A Topic(s) 1 2 3 4 5 6 1 2 3 4 Digital Rod Control/f (P.)A2..19 )2.4-. 3.
Pressurizer Level Control /2 S ) AZ .0 (g.) K2.03 Rod Position Indication/i Incore Instrument System / 7 Containment Air Filtration /8 Containment Hydrogen Control I 5
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 (P%) gA.ol Fire Protection /8 P. (R)I<.o3 SteamDumpControlSysteml4 Nuclear Instrumentation System! () A4.02. CS) AZ. 09 7
Uquid Radwaste System /9 KIA Category Point Totals:
_[ L iL , Group Point Total: 10/3 6Ic 2.
ES-401 N, Page 43 of 51
ES-401, REV9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO CDSA3.0l Condensate System 2.7 Condensate pump start CMSK6.08 Condenser Air Removal System 2.6 Condenser vacuum breakers CWSK4.0l Circulating Water System 3.1 C-9, Condenser Available DRCSA2.19 Digital Rod Control System 3 3.8 Group demand position indication failure MTSK1 .08 Main Turbine and Main Turbine 2.6 Main Steam System Control Systems NISA4.02 Nuclear Instrumentation System 3.7 Block Intermediate Range Neutron Flux High Reactor Trip RPISK2.03 Rod Position Indication System 2.8 Digital rod position indication coils SDCSK5.03 Steam Dump Control System 3.5 Changing steam flow effect on reactor power VESK3.0l Main Control Room HVAC 3.6 Control room habitability WGSA1 .02 Gaseous Radwaste System 2.5 - Carbon bed and/or vault temperatures Page 1 of 1 02/04/2015 2:23 PM
ES-401, REV9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO DRCSG2.4.36 Digital Rod Control System 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.
N ISA2.09 Nuclear Instrumentation System 3.5 3.6 Power Range nuclear Instrumentation detector failure (CE-related)
PLCSA2.08 Pressurizer Level Control System 3.8 3.7 Loss of coolant accident Page 1 of 1 02/06/2015 8:10AM
Form ES-401N-3 ES4OIN Generic Knowledge and Abilities Outline (Tier 3)
Facility: Vogk(e- Avuf s 3 4 /Vr_ 5e- 2 3 Date of Exam: N ov. ZD13 SRO-Only Category KIA # Topic IR IR 2.1. ....) de4erw.ie. O(rt lnef) 4.(,
2.1. Vv4,i. 34 Condu of Operations
- eS MaV, oike- oMtc, ,Aor Q cyi4 4
4.1 4.D Subtotal L.
2.2. 5 1o1iii 2 2.2.23 1jtc 4
( Lt .
2.2.30 uOS, +ti4?. 4. Z 2
Equipment 2.2.
Control 2.2.2-2.2. Iq+ > I kf TS. t Subtotal 3 2.3.5 cM4 £.ii42 f,sa. 3.
2.3. siw Fi.t. L-U, fr-.
Radiation Control 2.3. M 3. 1 Subtotal I 2.4. L)iflMk c2.?4tbvt no1 24.
Y-R ,iatL 4-.2 4.
2.4. 3 b Emergency 2.4.
Procedures / Plan 2.4.5 t4ar, A1,,g,rwi Q
4 , Pncs 2.4. 5 Subtotal 3 2-Tier 3 Point Total 10 7 7 ES-401N, Page 44 of 51
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.18 Conductof operations 4.6 4.3 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
G2.l .33 Conduct of operations 3.7 3.8 Knowledge of the stations requirements for verbal communications when implementing procedures.
G2.2.1 5 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.
G2.2.23 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.
G2.2.30 Equipment Control 4.2 4.4 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.
G2.3.5 Radiation Control 3.8 4.3 Ability to control radiation releases.
G2.3.6 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or aligning filters.
G2.4.15 Emergency Procedures/Plans 3.8 4.3 Knowledge of the operational implications of Emergency/Abnormal Operating Procedures warnings, cautions, and notes.
G2.4.17 Emergency Procedures/Plans 3.6 4.4 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
G2.4.38 Emergency Procedures/Plans 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material Page 1 of 1 02/04/2015 2:23 PM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G.2.3.9 Radiation Control 93.l Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, or personnel monitoring equipment.
G2.l.22 Conduct of operations 3.9 4.2 Ability to interpret reference materials, such as graphs, curves, tables.
G2.1 .27 - - Conduct of operations 4.44 Ability to locate and operate components, including local controls.
G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.2.26 Equipment Control 4.7 Ability to determine and/or interpret Technical Specifications with action statements of greater than one hour.
G2.4.5 Emergency Procedures/Plans 3.7 4.3 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
G2.4.7 Emergency Procedures/Plans 3.8 4.5 Knowledge of how Abnormal Operating Procedures are used in conjunction with Emergency Operating Procedures.
Page 1 of 1 02/04/2015 2:23 PM
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 performed Code*
Determine if you can replace a watch stander due to illness Conduct of Operations M, R G2.1.5 2.9 Calculate the volume of boric acid to be added using section 4.8 of Attachment 3 of Conduct of Operations N, R 3CVSS0P001 G2.1.21 4.3 Perform Normal Residual Heat Removal Pump 1A Quarterly Exercise Test Equipment Control N, R G2.2.8 3.7 Determine Best Route to Limit Personnel Exposure and not to Exceed Exposure Radiation Control N, R Limits G2.3.6 3.2 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 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 performed Code*
Determine which RO, if any, can replace a Conduct of Operations watch stander due to illness M, R G2.1.5 3.9 Determine if current conditions allow Mode Conduct of Operations 4 entry N, R G2.1.21 4.4 Perform Normal Residual Heat Removal Equipment Control Pump IA Quarterly Exercise Test N, R G2.2.26 4.7 Determine Emergency Exposure limits for a Radiation Control task and determine if the task can be N, R performed.
G2.3.8 3.8 Provide an updated Protective Action Emergency Plan Recommendation (PAR)
N, R G2.4.35 4.4 NOTE: All items (five total) are required for SROs. RD applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & 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* Safety Function
- a. Recover a dropped control rod.
Description:
The unit is at 65% power and rod H14 has fully dropped into the core. The candidate is directed to re-align rod H14 to its bank at 82 steps in accordance with 3-AOP-104 (Rod Control System Malfunction) Attachment 2 (Move Individual Rod M or 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 candidate is directed to perform a 150 gallon blended makeup to the RCS in accordance with 3-CVS-SOP-001 (Chemical and Volume N, S 2 Control System) Attachment 3 (RCS Makeup System Operation).
SF2 CVS A4.04 RO/SRO 3.5
Description:
The unit has been shutdown due to a steam generator tube leak. The candidate is directed to lower RCS pressure via ADS in accordance with 3-AOP-1 03 (Steam Generator Tube Leak) to less than 1920 psig. When attempting A, EN, L, M, to place Division A ADS in service to lower pressure, a S malfunction occurs requiting ADS Division B to be placed in service.
SF3 ADS A4.04 RO/SRO 4.1
U. Respond to Condensate System Malfunctions in Accordance With AOP-202
Description:
The unit is at 59% reactor power with CDS Pump A degraded. The candidate is directed to perform 3-AOP-202 (Condensate System Malfunctions) due to the reduced discharge pressure on CDS Pump A. During performance, CDS Pump A will trip and CDS Pump C will have a sheared shaft, requiring the candidate to manually run back the unit. Once the run back is complete, 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 in accordance with AOP-501 (Loss of Main Control Room Air N, S 8 Conditioning) 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. IRNI Excore Detector A failed after the trip. The candidate is required to perform 3-EOP-ES-0. 1 (Reactor Trip Response) steps 28 and
- 29. During performance, the candidate will restore blowdown to A, L, D, S 7 sample the steam generators and re-energize SRNI A at the PDSP.
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) is required. The candidate is directed to perform FR-Z.3. During performance, VFS valve failures require the candidate to restore A EN L D
, , , 9 a ventilation flowpath for VAS by securing VFS-MA-O1A, closing the 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. The candidate is directed to re-open the MSIVs, close the MSIV bypass valves, and place steam dumps in service holding 1085 psig. L N S 4P (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)
In-Plant JPMs not identified at the time of DRAFT submittal.
k.
All RD and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all five SRD-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RD / SRO-l / SRD-U A)lternate path 4-6 / 4-6 / 2-3 fC)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