ML14078A120
| ML14078A120 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/19/2014 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-424/13-301, 50-425/13-301 | |
| Download: ML14078A120 (23) | |
Text
- wR/7TEAJ Ex,q,ii 5pt&
/,w ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
VCG-72. E Date of Examination:,i%P)çf 13 Initials Item Task Description
1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
A b.
Assess whether the outline was systematically and randomly prepared in accordance with I
Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
/4 T
A T
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
d.
Assess whether the justifications for deselected or rejected KJA statements are appropriate.
A 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, S
and major transients.
M b.
Assess whether there are enough scenario sets (and spares) to test the projected number U
and 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 A
at least one new or significantly modified scenario, that no scenarios are duplicated T
from the 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 W
distributed among the safety functions as specified on the form
/1)
I (2) task repetition from the last two NRC examinations is within the limits specified on the form T
(3) no tasks are duplicated from the applicants audit test(s)
(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 the form.
b.
Verify that the administrative outline meets the criteria specified on Form ES-3d -1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations
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 41/
in the appropriate exam sections.
/
b.
Assess whether the 10 CFR 55.41 /43 and 55.45 sampling is appropriate.
4 c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d.
Check for duplication and overlap among exam sections.
L e.
Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
a Author
/
2
//d/4e mg&pte4L
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Supervisor Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
ES-401 PWR Examination Outline Form ES-401-2 Facility:
VOGTLE Date of Exam:
APRIL 2013
SIRO-Only Points Tier Group 1
KKKKKKAAAAGI A2 G*
Total 1
2 3
4 5
6 1
2 3
4
- 1.Total
= = = = =
1.
1 333 33 318 3
3 6
Emergency &
Abnormal 2
j 2..
N/A
.. 2 N/A 1
9 2
2 4
Evoluhons TierTotals
+/-:+/-;+/- ::
Plant 2
+/-+/-L+/-2L!_L..L 10 1l 1
3 Systems Tier Totals £ 3
4 43 4
2 4
4 3
3 38 4
4 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2
[
3 4 J 7
Categories I
3 2
2 3
1 2
2 2
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-orily outline, the Tier Totals in each K/A category shall not be less than two).
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.
Systemsfevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section 0.1.b of ES-401 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 before selecting a second topic for any system or evolution.
5.
Absent a plant-specific priority, only those K/As having an importance rating (lR) 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 K/A categories.
7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section 0.1.b of ES-401 for the applicable 1</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 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).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the K/A catalog, arid enter the K/A numbers, descriptions, IRs, and point totals (if) on Form ES-401-3. Limit SRO selections to K/As that are linked tolD CFR 55.43.
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR Ki 1(2 1(3 K4 KS K6 Al A2 A3 A4 G TOPIC:
nO SRO 007EK1 02 Reactor Trip
- Stabilization - Recovery 3.4 3.8 fl [] [J [] E] H [J H [] [
/1 008AG2.4.2 Pressurizer Vapor Space Accident / 3 4.5 4.6 H Li LI [1 H H LILI Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
OO9EA1.04 SmallBreakLOCAI3 3.7 3.5
{ [J [] E] []
fl [] fl[}
CVCS 011 EK2.02 Large Break LOCA / 3 2.6 2.7 H 11 H H H El LI El El [1 [1 Pumps 015AK3.0l RCP Malfunctions 14 2.5 3.1 Li F]
H H Li H [1 Li [1 Li Potential damage from high winding and/or bearing temperatures 022AA2.01 Loss of Rx Coolant Makeup /2 3.2 3.8 Li LI [1 LI H H Li LI El F]
Whether charging line leak exists 025AG2.421 Loss of RHR System /4 4.0 4.6
[] Li Li El H [1 Li LI H El jJ Knowledge of the parameters and logic used to assess
the status of safety functions 026AA2,02 Loss of Component Cooling Water / 8 2.9 3.6 El El Li Li El LI Li E] LI El H The cause of possible CCW loss 029EK3.03 ATWS / 1 3.7 3.6
[1 El J H El Li Li El LI Li LI Opening BIT inlet and outlet valves 038EK1.03 Steam Gen. Tube Rupture /3 3.9 4.2 j] [_j LI El El H Li H [1 H H Natural circulation 054AA1.04 Loss of Main Feedwater /4 4.4 4.5 H H Li H LI H Li Li H H HPI, under total teedwater loss conditions Page 1 of 2 7/20/2012 8:43 AM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Steam Line Rupture-Excessive Heat Transfer / 4 Components, capacity, and function of emergency systems.
KA NAME I SAFETY FUNCTION:
IR 1(1 K2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 056AK3.02 Loss of Off-site Power /6 4.4 4.7 LI
[J [] [] [] []
LI Actions contained in EOP for loss of otfsite power 062AA1.02 Loss of Nuclear Svc Water 14 3.2 3.3
[] [] [] LI [} LI [J LI [] [] []
Loads on the SWS in the control room
065AG2.4.46 Loss of Instrument Air? 8 4.2 4.2 LI LI LI LI C] H LI LI H LI Ability to verify that the alarms are consistent with the plant conditions.
077AA202 Generator Voltage and Electric Grid 3.5 36 C] H [I LI LI [J LI Fi LI LI LI Voltage outside the generator capability curve Disturbances /6 WEO4EK2.1 LOCA Outside Containment /3 3.5 3.9 LI L] [I LI LI H LI LI [1 LI LI Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEO5EK2.2 Inadequate Heat Transfer - Loss of 3.9 4.2 C] [ LI LI LI LI LI [1 LI LI LI Facilitys heat removal systems, including primary Secondary Heat Sink / 4 coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.
WE12EK1.1 3.4 3.8 LILI[1LILILILILILILI Page 2 of 2 7/20/2012 8:43AM
TOPIC:
LI LI L] [1 LI LI I LI LI LI LI Fuel handling equipment during an incident LI [1 LI LI LI [J LI [J LI [3 [3 Failure of Condensate air ejector exhaust monitor 4.2
[3 [3 [3 LI LI LI [3 [] [3 [3 [3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
LI fl I1 [3 LI LI LI LI LI LI LI Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
[3 LI LI [3 LI LI LI LI LI LI Knowledge of operational implications ol EOP warnings, cautions and notes.
3.2
[3 [3 LI LI LI LI LI LI LI LI Operating behavior characteristics of the facility.
[1 LI LI [1 LI [1 LI El Li Components and functions ol control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 IR Kl 1(2 1(3 1(4 K5 1(6 Al A2 A3 A4 G RO SRO OO3AK1.07 Dropped Control Rod/i 3.1 3.9 LI LI El LI [I LI LI [3 LI El Effect of dropped rod an insertion limits and 8DM 036AA1.04 Fuel Handling Accident 18 037AA2.08 Steam Generator Tube Leak / 3 WEO2EA2.l SI Termination / 3 WEO3EK3.2 LOCA Cooldown
- Depress. /4 weO6EG2.4.20 Degraded Core Cooling /4 WE13EA1.2 Steam Generator Over-pressure /4 WE14EK2.1 Loss of CTMT Integrity/S 3.1 2.8 3.3 3.4 3.8 3.0 3.4 WE16EK3.2 High Containment Radiation / 9 2.9 3.3 u [1 Li LI LI Li LI LI LI LI Normal, abnormal and emergency operating procedures associated with (High Containment Radiation).
Page 1 of 1 7/2012012 8:43AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR 1<1 1<2 K3 1<4 K5 1<6 Al A2 A3 A4 G TOPIC:
RO SRO 003A2.05 Reactor Coolant Pump 2.5 2.8 fl Li [] Li []
[]
[] [] []
Effects of VCT pressure on ROP seal leakoff flows 003K5.02 Reactor Coolant Pump 2.8 3.2
[] [j [] [J f U Li [1 Li El fl Effects of RCP coastdown on RCS parameters 0041<5.27 Chemical and Volume Control 2.6 3.2 Li Ei [] Li
[] [] El [1 Li []
Reason for nitrogen purge of CVCS 0051<2.01 Residual Heat Removal 3.0 3.2
[] [] Li Li H C] Li El Li Li Li RHR pumps 006A3.08 Emergency Core Cooling 4.2 4.3 Li [1 Li Li Li [1 [1 Li Li Li Automatic transfer of ECCS flowpaths 007A3.01 Pressurizer Relief/Quench Tank 2.7 2.9 LI Li Li [1 Li El LI Li Li [1 Components which discharge to the PRT 0081<4.09 Component Cooling Water 2.7 2.9 Li Li Li l1 Li Li Li [1 Hi Li Li The standby feature for the CCW pumps 010K4.02 Pressurizer Pressure Control 3.0 3.4 LI Li Li 1 Li El Li Li LIE] El Prevention of uncovering PZR heaters 012A1.01 Reactor Protection 2.9 3.4 Li Li Li Li Li Li
[IL] Li Li Trip setpoint adjustment 0121<6.02 Reactor Protection 2.9 31 U Li Li LI Li Li Li Li Li Li Redundant 013G2.1.19 Engineered Safety Features Actuation 3.9 3.8
[1 Li Li Li Li Li Li Li Li Li ll Ability to use plant computer to evaluate system or component status.
Page 1 of 3 7/20/2012 8:43 AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 013K3.03 Engineered Safety Features Actuation 4.3 4.7
[] fl Li LI LI LI LI Li Li Li Containment 013K6.0l Engineered Safety Features Actuation 2.7 3.1 Li Li Li Li Li Li LI Li El Li Sensors and detectors 022A1.03 ContainmentCooling 3.1 3.4 Li Li [1 Li LI LI ] Li CE] Li [1 Containmenthumidity 026A4.05 Containment Spray 3.5 3.5 Li LI LI LI ci LIL] LI LI Li Containment spray reset switches 039A2.04 Main and Reheat Steam 3.4 3.7
[]
LI L] LI [J LI ] LI L] [1 Maltunctioning steam dump 059G2.2.22 Main Feedwater 4.0 4.7
[J
[] []
CE] Li [1 Li LI Knowledge of Hmiting conditions for operations and safety limits.
061K6.0l Auxiliary/Emergency Feedwater 2.5 2.6 Li [1 LI Li C ] Li Li [] Li Li Controllers and positioners 0621(1.02 AC Electncal Distribution 4,1 4.4 Li Li Li Li Li Li Li Li Li Li EDIG 0631(1.03 DC Electrical Distribution 2.9 3.5 ] [j [] Li Li Li LI [] LI Li El Battery charger and battery 064A4.05 Emergency Diesel Generator 3.1 3.2 L]
Li Li LI LI fl Transfer of ED/G control between manual and automatic 0641(1.03 Emergency Diesel Generator 3.6 4.0 f1] Li Li Li Li Li [1 Li Li [][]
Diesel fuel oil supply system Page 2 of 3 7/20/2012 8:43 AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR 1(1 K2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 073A2.02 Process Radiation MonitorIng 2.7 3.2 Q
j [] J L]
[ [j Detector taHure 0761(2.04 Service Water 2.5 2.6
[ fl [J [J [] fl [ {
fl Reactor building closed cooling water 0761(3.05 Service Water 3.0 3.2
[]
[] [. fl [] [] EJ [] [
RHR components, controls, sensors, indicators and alarms, including rad monitors 0781(4.02 Instrument Air 3.2 3.5 fl
], [J j fl [j [] f Cross-over to other air systems 103A3.0l Containment Containment isolation 3.9 4.2 LL1[E[1LJL]
1 03K3.0l Containment 3.3 3.7 L1L1JJLJLJ OLILILILJ Loss of containment integrity under shutdown conditions Page 3 of 3 7/2012012 8:43AM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR 1(1 1(2 1(3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 0021(5.10 Reactor Coolant 3.6 4.1 LI [] fl El fl [] [] fl [] []
Relationship between reactor power and RCS differential temperature 0111(2.02 Pressurizer Level Control 3.1 3.2 El
[] [] [] []
[] [] [] []
PZR heaters 015K6.0l Nuclear InstrumentatIon 2.9 3.2 El El El [Li El El [] El [L Sensors, detectors and indicators 016K3.12 Non-nuclear Instrumentation 3.4 3.6 El El I El El El El LI LI El El SIG 034A2.03 Fuel Handling Equipment 3.3 4.0 El [1 El LI El El El ] El [1 Li Mispositioned fuel element 035A4.05 Steam Generator 3.8 4.0 El El [1 El El El El El El El Level Control to enhance natural circulation 071 K4.05 Waste Gas Disposal 2.7 3.0
[] El El E+/-i [1 El El El El LI El Point of release 0721(1.04 Area Radiation Monitoring 3.3 3.5 I El El El El El El El El El El Control room ventilation 079G2.1.23 Station Air 4.3 4.4 El El [I El El El El El El El J Abitty to perform specific system and integrated plant procedures during all modes of plant operation.
086A3.03 Fire Protection 2.9 3.3 El El El LI El El El II i El El Actuation of tire detectors Page 1 of 1 7I22o12 8:43 AM
ES4O1 REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Kl K2 KS K4 K5 K6 Al A2 A3 A4 6 TOPIC:
RO SRO 62.1.15 Conduct of operations 2.7 3.4 El [J [] [] El [] []
C] El j Knowledge of administrative requirements for temporary management directives such as standug ortlers, night orders, Operations memos, etc.
62.1.29 Conduct of operations 4.1 4.0 C] Li. LI LI El Li LI Li Li Li [j Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.
62.1.43 Conduct of operations 4.1 4.3 C] LI Li El El El Li El Li fl Ability to use procedures to determine the effects on reactivity of plant changes 62.2.42 Equipment Control 3.9 4.6 El Li Li LI C] Li El Li Li LI [
Ability to recognize system parameters that are entry-level conditions for Technical Specifications 62.2.44 Equipment Control 4.2 4.4 Li [1 Li Li Li [I Li Li Li C] }
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 G2.3.1 1 Radiation Control 3.8 4.3 Li Li Lj Li Li Li Li Li Li Li t J Ability to control radiation releases.
62.3.12 Radiation Control 3.2 3.7 Li Li Li Li Li [1 Li Li El Li Knowledge of radiological safety principles pertaining to licensed operator duties 62.4.27 Emergency Procedures/Plans 3.4 3.9 Li Li El El El LI El LI El El Knowledge of afire in the plant procedures.
G2.4.32 Emergency ProceduresJPlans 3.6 4.0 Li Li LI Li LI El El El LI U Knowledge of operator response to loss of all annunciators.
G2A.9 Emergency Procedures/Plans 3.8 4.2 Li LI U LI El El LI El El El 1l Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
Page 1 of 1 7/20/2012 8:43 AM
SHO T1G1 PWR EXAMINATION OUTLINE NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO Pressurizer Vapor Space Accident /3 2.7 4.1 El El El El El El El [1 El El E1 ElElElElElElElElD ElElElElElElI1ElElEl ElElElElL1ElElElEl ElEl ElEl El El [JEl El ElElElElElElElElEl ES-401, REV 9 KA 008AG2.4.30 FORM ES-401-2 011 EA2.07 Large Break LOCA / 3 3.2 3.4 El 025AA2.04 Loss of RHR System / 4 3.3 3.6 El 029EG2.4.18 ATWSI 1 3.3 4.0 El TOPIC:
Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.
That equipment necessary for functioning of critical pump water seals is operable Location and isolability of leaks 056AG2.4.45 Loss of Ott-site Power/ 6 4.1 4.3 El 065AA2.02 Loss of Instrument Air / 8 2.4 2.6 El Knowledge of the specific bases for EOPs.
Ability to prioritize and interpret the significance of each annunciator or alarm.
Relationship of flow readings to system operation Page 1 of 1 7/20/2012 8:43 AM
FORM ES-401-2 TOPIC:
Ability to evaluate p4ant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Knowledge of limiting conditions for operations and safety limits.
Facility conditions and selectior of appropriate procedures during abnormal and emergency operations.
Adherence to appropriate procedures and operation within the limitations in the lacilitys license and amendments.
ES-401, REVS SRO T1G2 PWR EXAMINAflON OUTLINE KA NAME / SAFETY FUNCTION:
IR 1<1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 005AG2.l.7 Inoperable/Stuck Control Rod/i 4.4 4.7 fl [] El El Li El [1 El El LI 076AG2.2.22 High Reactor Coolant Activity /9 4.0 4.7 LI El LI LI U LI El El El El WEO3EA2.1 LOCA Cooldown - Depress. 14 3.4 4.2 Li El El LI El El LI l El LI L WEO9EA2.2 Natural Circ. / 4 3.4 3.8 Li Li LI LI El LI LI [] LI LI El Page 1 of 1 7120/2012 8:43AM
ES-401, REV 9 SF10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR 1(1 1(2 K3 1(4 KS 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 00502.1.32 Residual Heat Removal 3.8 4.0 Li [] [] [] []
[] [J Q []
Ablity to explain and apply all system limits and precautions.
008A2.02 Component Cooling Water 3.2 3,5 Li [1 Li Li Li Li Li [j Li [] []
High/low surge tank level 03902.2.25 Main and Reheat Steam 3.2 4.2 Li Li Li [1 Li C] [-1 Li El Li Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
062G2.2.44 AC Electrical Distribution 4.2 4.4 F] Li Li [1 Li Li El [1 Li 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 063A2.02 DC Electrical Distribution 2.3 3.1 Li Li C] [1 Li Li Li I LI [1 El Loss of ventilation during battery charging Page 1 of 1 7/20/2012 8:43 AM
ES-401, REV 9 KA 01 5A2.04 034Al.02 Fuel Handling Equipment 086G2.2,37 Fire Protection SRO T2G2 PWR EXAMINATION OUTLINE 1R Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SF10 3.3 3.8 2.9 3.7 E]EEHÜO 3.6 4.6 E[JL1L NAME / SAFETY FUNCTION:
Nuclear Instrumentation FORM ES-401-2 TOPIC:
Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs.
control rod reactivity changes Water level in the refueling canal Ability to determine operability and/or availability of safety related equipment Page 1 of 1 7/20/2012 843AM
ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORIIA ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l.5 Conduct of operations 2.9 3.9
[EJ Li fl Li j Li []
Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
G2.2.15 Equipment Control 3.9 4.3
[] [1 fl [] [] [J [] []
[J Ability to determine the expected plant configuration using design and configuration control documentaion (422.20 Equipment Control 2.6 3.8
[El [1 Li Li [J Li Li fl Li fl [
Knowledge of the process for managing troubleshooting activities.
(42.3.4 Radiation Control 3.2 3.7 Li Li Li Li Li Li Li Ii Li Li I1 Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 Li Li Li Li Li LI Li Li [1 fl [
Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.29 Emergency Procedures/Plans 3.1 4.4 LI Li LI Li Li Li LI LI Li Li Knowledge of the emergency plan.
(42.4.40 Emergency Procedures/Plans 2.7 4.5 LI Li Li El Li Li Li Li Li Li Knowledge of the SROs responsibilities in emergency plan implementation.
Page 1 of 1 7/20/2012 8:43AM
1V ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Voatle 1 & 2 Date of Examination:
04/15/2013 Examination Level:
201 3-30L.
Administrative Topic (see Type Describe activity to be performed Note)
Codes R M V-NRC-JP-14915-HL18 Conduct of Operations Calculate Quadrant Power Tilt Ratio
==
Description:==
With data provided, candidate will perform 14915-1, Data Sheet 7, for QPTR monitoring.
G2.1.7 (4.4 / 4.7)
V-NRC-JP-0001 2-HL1 8 Conduct of Operations R, M Identity On-Shift Manning Requirements for Conditions Provided
==
Description:==
Candidate will determine if the minimum on-shift staffing requirements are met and will determine if a crew member can fulfill two specific ERO positions.
G2.1.5 (2.9*13.9)
V-NRC-JP-14825-HL18 Equipment Control R, N Evaluate Surveillance Test Data DescrIptIon: Candidate will evaluate quarterly valve test surveillance data and determine if the required acceptance criteria are met.
G2.2.12 (3.7/4.1)
V-NRC-JP-00930-HL1 8 Radiation Control R, D, P Proper RWP Implementation
==
Description:==
Candidate will determine proper protective clothing requirements, projected dose, and whether the RWP is appropriate for the job task.
G2.3.7 (3.5 / 3.6)
Emergency Procedures/Plan N/A N/A NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- 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)odfled from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
RAT ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Voatle 1 & 2 Date of Examination:
04/15/2013 Examination Level:
Operating Test Number:
201 3-301 Administrative Topic (see Type Describe activity to be performed Note)
Code*
V-NRC-JP-1 491 5-HL18 Conduct of Operations R, M Evaluate Quadrant Power Tilt Ratio
==
Description:==
With data provided, candidate will perform 14915-1, Data Sheet 7, for QPTR monitoring, evaluate data, and take appropriate action.
G2.1.7 (4.4 / 4.7)
V-NRC-JP-COOl 2-HLi 8 Conduct of Operations R, M Evaluate On-Shift Manning Requirements for Conditions Provided
==
Description:==
Candidate will determine if the minimum on-shift staffing requirements are met and identify required actions any time minimum staffing requirements are not met.
G2.i.5 (2.9* / 3.9)
V-NRC-JP-1 4825-HLI 8 Equipment Control R, N Evaluate Surveillance Teat Data
==
Description:==
Candidate will evaluate quarterly valve test surveillance data, determine if the required acceptance criteria are met, and specify Technical Specification required actions.
G2.2.12 (3.7/4.1)
V-NRC-JP-00930-HL1 8 Radiation Control R, D, P Proper RWP Implementation
==
Description:==
Candidate will determine proper protective clothing requirements, projected dose, and whether the RWP is appropriate for the job task.
G2.3.7 (3.5 / 3.6)
kAFT V-NRC-JP-NMP-EP-1 1 2-HL1 8 Emergency Procedures/Plan ft D Determine Otfsite Protective Action Recommendations
==
Description:==
The candidate will determine PARs for the given emergency and complete the PAR Worksheet.
G2A.44 (4.4)
NOTE:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Ctass(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odifled from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
DRAFT Control Room/In-Plant Systems Outline Facility:
Vocitle 1 & 2 Date of Examination:
04/1 5/2013 Exam Level: RO SRO-l SRO-U Operating Test Number:
Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function a.
V-NRC-JP-13105-HL18: Increase Accumulator Level at Low D, EN, L, S 3
RCS Pressure
==
Description:==
The unit is in Mode 4 at 340 psig and stable. A leak on Accumulator #2 has been repaired, but low pressure and low level annunciators remain lit. The candidate is directed to restore Accumulator #2 level and pressure sufficiently to clear the low level and low pressure annunciators using 13105-1.
(RO I SRO-l / SRO-U) 006A1.13 (3.5 / 3.7) b.
V-NRC-JP-13011-HL18: Perform an RCS Cooldown Using D, L, S 4P RHR Train A
==
Description:==
A unit cooldown from Mode 4 to Mode 5 is in progress. RHR Train A warm-up is complete. The candidate is directed to initiate full RHR Train A flow and cool down the RCS to 315°F +/- 5°F without exceeding 100°F in any hour.
(RO / SRO-l / SRO-U) 005A4.01 (3.6 / 3.4) c.
V-NRC-JP-1 8009-FiLl 8: Transfer Steam Dumps to Steam A, 0, L, S 4S Pressure Mode DescriptIon: The reactor has been shut down due to a steam generator tube leak. The candidate will transfer steam dumps to the steam pressure mode using 1 8009-C, but they will not control properly and ARV usage will be required to control heat-up.
(RO / SRO-l I SRO-U) 039A2.04 (3.4 / 3.7)
(.
d.
V-NRC-JP-1 3009-HL1 8: Emergency Borate from the RWST A, D, P, S
==
Description:==
The candidate will be required to initiate an emergency boration in response to a ROD BANK LO-LO LIMIT alarm using 13009-1. The RWST flow path will be required for emergency boration due to equipment failures.
(RO I SRO-i) 024AA2.01 (3.8*/4.1) a.
V-NRC-JP-19001-HL18: Establish Safety Grade Letdown D, L, P, S 2
==
Description:==
The unit was manually tripped due to a non-isolable instrument air break. Candidate is required to place safety grade letdown in service and establish a 40 gpm flow rate to control RCS inventory.
(RO I SRO-l) 004A2.1 1 (3.6 I 4.2) t.
V-NRC-JP-13130-HLI8: Place Containment Hydrogen A, EN, L, M, P, S 5
Monitors In Service
==
Description:==
A LOCA has occurred and the candidate is directed to place the Containment Hydrogen Monitors in service using 13130-1. The Common Failure light will illuminate requiring the candidate to return the monitor to standby.
(RO / SRO-l) 028A4.03 (3.1 /3.3) g.
V-NRC-JP-13320-HL1B: Post-Accident Cleanup of the FHB N, S 8
Using the Normal Exhaust Units
==
Description:==
A spent fuel assembly was dropped in the Spent Fuel Pool. To expedite cleanup of airborne radioactivity, the candidate will be required to use 1 3320-C to perform post-accident clean up of the Fuel Handling Building using the normal exhaust units.
(RO / SRO-l) 034A2.01 (3.6 I 4.4) 4
h.
V-NRC-JP-13830-HL18: Establish Field Excitation Using D, S RO ONLY Manual Voltage Regulation for Main Generator 6
==
Description:==
The unit is starting up following a refueling outage.
The main turbine is at 1800 rpm and main generator? exciter preparations are complete. The candidate will use 13830-1 to establish main generator field excitation with manual voltage regulation.
(RO) 062A4.04 (2.6)
In-Plant Systems° (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
I V-NRC-JP-13903-HL18: Locally Emergency Start Diesel-A, 0, E 8
Driven Fire Pump
==
Description:==
With a diesel fire pump tagged out for repairs, a large fire caused fire header pressure to drop. The standby diesel fire pump failed to start, so the candidate will be dispatched to perform a local manual start of the standby diesel fire pump. The local pushbutton start for the first battery will not work, which will require the use of the second battery to start the engine.
(RO / SRO-l / SRO-U) 086A2.02 (3.013.3) j.
V-NRC-JP-17213-HL18: Respond to 1-RE-OO18 Alarm During a A, E, M, R 9
Liquid Radwaste Release
==
Description:==
During a liquid radwaste release, a high alarm is received on 1 -RE-0018. The candidate will be directed to respond to the Waste Process Liquid Panel (PLPP) and take the appropriate actions per 17213-1. 1-RE-0018 will not close, so manual isolation will be required.
(RO / SRO-l / SRO-tJ) 059AA2.05 (3.6 / 3.9) k.
V-NRC-JP-18O38-HL18: Start Emergency Diesel Generator A, E, L, N 6
From Outside the Control Room
==
Description:==
The control room has been evacuated and control has been established at the shutdown panels. To re-energize 2AA02, the candidate will locally start 2A EDG using Attachment B of 18038-2. After starting, high jacket water temperature will require tripping the diesel locally.
(RO I SAC-I) 064A1.03 (3.2 I 3.3)
AU RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 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 / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank S9/814 (E)mergency or abnormal in-plant 1 /
1 /
1 (EN)gineered safety feature
/
/ 1 (control room system)
(L)ow-Power I Shutdown 1 /
1 /
I (N)ew or (M)odified from bank including 1 (A) 2 / z 2 /
1 (P)revious 2 exams 3 I 3 /
2 (randomly selected)
(R)CA (S)imulator a