ML13025A010
| ML13025A010 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/22/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML13025A010 (23) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility:
OCONEE Date of Exam:
DECEMBER 2012
RO K/A CapoyPcnts
SRO-Only_Points Tier Group KKKKKKAAAAG A2 G
Total 1
2 3
4 5
6 1
2 3
4 Total 1.
1 3--
3 3.
3 3-3 1 8k.
3
3 -
6 Emergency &
Abnormal 2
2 N/A 2
L N/A j.
2 2
4_
Plant
Evolutions Tier Totals 5
4 5
5 4
4 27 5
5 10 1
2_
3-3_
2,- 2 2 3_
2_
28 2
3
5 2.
Plant 2
1.-
1-1.
1 0
1 1
1 1
1,-
1.-.-
10.-
0 1 -
2 3
Systems Tier Totals 4 4 3__
4 3 3
3 i
4 4
3 38 3
5 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 2-2 3-3 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-only 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.
Systems/evolutions 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 D.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 (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 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 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 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, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
r C.___3 i:_J
- WRITTEN EXAM SAMPLE PLAN ONLY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
OCONEE Date of Examination:
DECEMBER 2012 Initials Item Task Description
a b*
c#
1 a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
N/A w
R b.
Assess whether the outline was systematically and randomly prepared in accordance with N/A I
Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
T T
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
N/A E
N d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
N/A 2.
a.
Using Form ES-301-5, verify that the proposed scenario sets cover the required number N/A N/A N/A 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 N/A N/A N/A u
and mix of applicants in accordance with the expected crew composition and rotation L
schedule without compromising exam integrity, and ensure that each applicant can be A
tested using at least one new or significantly modified scenario, that no scenarios are T
duplicated from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
R c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative N/A N/A N/A 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:
N/A N/A N/A (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
/
(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-301 -1:
N/A N/A N/A (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 N/A N/A N/A 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 N/A in the appropriate exam sections.
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
N/A c.
Ensure that K/A importance ratings (except br plant-specific priorities) are at least 2.5.
N/A d.
Check for duplication and overlap among exam sections.
N/A N/A N/A L
e.
Check the entire exam for balance of coverage.
N/A
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
N/A
- a. Author Michael K. Meeks /
04/04/2012
- b. Facility Reviewer (*)
N/A
- 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
- WRITTEN EXAM SAMPLE PLAN ONLY
ES-401, REV 9 T1G1 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 007EA2.04 Reactor Trip
- Stabilization
- Recovery 4.6 4.4 El El El El El El El El El El If reactor should have tripped but has not done so,
/ 1 manually trip the reactor and carry out actions in ATWS EOP 008AK2.03 Pressurizer Vapor Space Accident / 3 2.5 2.4 El El El El El El El El El El Controllers and positioners 009EA2.33 Small Break LOCA /3 3.3 3.8 El El [] El El El []
RCS water inventory balance and Tech-Spec limits Oil EKO1-Large Break LOCA /
El El El El El El El El El El
,Z(D.7 Ld>t o Ltt--
9vit L-.3(o41 015AK3.04 RCP Malfunctions / 4 3.1 3.2 El El El El El El El El El El Reduction of power to below the steady state power-to-flow limit 025AK2.0l Loss of RHR System / 4 2.9 2.9 El El El El El El El El El El RHR heat exchangers 026AG2.4.50 Loss of Component Cooling Water / 8 4.2 4.0 El El El El El El El El El El Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
027AG2.4.49 Pressurizer Pressure Control System 4.6 4.4 El El El El El El El El El El Ability to perform without reference to procedures those Malfunction / 3 actions that require immediate operation of system components and controls.
029EA1.13 ATWS/1 4.1 3.9 El El El El El El El El El El Manual trip of main turbine 038EA2.07 Steam Gen. Tube Rupture / 3 4.4 4.8 El El El El El El El El El El Plant conditions from survey of control room indications 054AK1.01 Loss of Main Feedwater/4 4.1 4.3 Ll El El El El El El El El El El MEW line break depressurizes the S/G (similar to a steam line break)
Page 1 of 2 4/4/2012 9:49AM
ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
AC SAC 055EA1.05 Station Blackout / 6 3.3 3.6 J
Battery when approaching fully discharged 058AK3.0l Loss of DC Power! 6 3.4 3.7 Use of dc control power by D/Gs 062AA1.05 Loss of Nuclear Svc Water / 4 3.1 3.1 The CCWS surge tank, including level control and level alarms and radiation alarm 065AG2.l.23 Loss of Instrument Air! 8 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
077AK1.03 Generator Voltage and Electric Grid 3.3 3.4 Under-excitation Disturbances / 6 BEO4EK2.l Inadequate Heat Transfer - Loss of 3.8 4
U U U U U U Components, and functions of control and safety Secondary Heat Sink! 4 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
BEO5EK3.2 Steam Une Rupture
- Excessive Heat 3.5 4
U U U U U U U U U U Normal, abnormal and emergency operating procedures Transfer! 4 associated with (Excessive Heat Transfer).
Page 2 of 2 4/4/2012 9:49 AM
ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003AK2.05 Dropped Control Rod! 1 2.5 2.8 Control rod drive power supplies and logic circuits 005AG2.4.4 Inoperable/Stuck Control Rod / 1 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
028AA2.04 Pressurizer Level Malfunction / 2 2.6 3.1 Ammeters and running indicators for CVCS charging pumps 032AK3.02 Loss of Source Range NI / 7 3.7 4.1 Guidance contained in EOP for loss of source-range nuclear instrumentation 037AA1.08 Steam Generator Tube Leak! 3 3.3 3.1 Charging flow indicator BAO2AK3.4 Loss of NNI-X /7 3.7 3.7 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.
BA05AK1.3 Emergency Diesel Actuation / 6 3.8 3.7 Annunciators and conditions indicating signals, and remedial actions associated with the (Emergency Diesel Actuation).
BEO3EA1.1 Inadequate Subcooling Margin / 4 4.1 3.8 fl J
Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
BEO9EK1.1 Natural Circ. / 4 3.5 3.7 Li Components, capacity, and function of emergency systems.
Page 1 of 1 4/4/2012 9:50AM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRQ 003A4.03 Reactor Coolant Pump 2.8 2.5 RCP lube oil and lift pump motor controls 004A1.l0 Chemical and Volume Control 3.7 3.9
[] El El El El El El El Reactor power 004K6.26 Chemical and Volume Control 3.8 4.1 El El El El El El El El [] El Methods of pressure control of solid plant (PZR relief and water inventory) 005K4.06 Residual Heat Removal 2.7 3.0 El Function of RHR pump minitlow recirculation 005K5.0l Residual Heat Removal 2.6 2.9 Nil ductility transition temperature (brittle fracture) 006K6.l0 Emergency Core Cooling 2.6 2.8 El El El El El El El El El El Valves 007A4.0l Pressurizer Relief/Quench Tank 2.7 2.7 El El El El El El El El El El PRT spray supply valve 008K1.02 Component Cooling Water 3.3 3.4 El El El El El El El El El El Loads cooled by CCWS 010K2.01 Pressurizer Pressure Control 3.0 3.4 El El El El El El El El El El PZR heaters
01 2K3.04 Reactor Protection 3.8 4.1 El El El El El El El El El El ESFAS 012K5.0l Reactor Protection 3.3 3.8 El El El El El El El El El El DNB Page 1 of 3 4/4/2012 9:50AM
ES-401, REV 9 T2G1 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 lAS Fan motor thermal overload/high-speed operation Chillers Containment spray pumps Recirculation spray system Effect of steam removal on reactivity Feedwater pump suction flow pressure AFW SIG level control on automatic start Knowledge of surveillance procedures.
Knowledge of limiting conditions for operations and safety limits.
Breaker interlocks, permissives, bypasses and cross-ties.
013K1.14 Engineered Safety Features Actuation 3.1 3.4 El El El El El El El El El El 022A2.03 Containment Cooling 2.6 3.0 El El El El El El El 022K2.02 Containment Cooling 2.5 2.4 026K2.0l Containment Spray 3.4 3.6 026K3.02 Containment Spray 4.2 4.3 El El El El 039K5.08 Main and Reheat Steam 3.6 3.6 El El El El El El El El El El 059A3.03 Main Feedwater 2.5 2.6 El El El El El El El El 1 El El 061A3.03 Auxiliary/Emergency Feedwater 3.9 3.9 El El El El El El El El El El 062G2.2.12 AC Electrical Distribution 3.7 4.1 El El El El El El El El El El 063G2.2.22 DC Electrical Distribution 4.0 4.7 El El El El El El El El El El 063K4.02 DC Electrical Distribution 2.9 3.2 ElElElElElElElElElEl Page 2 of 3 4/4/2012 9:50AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
064A1.05 Emergency Diesel Generator 064A3.07 Emergency Diesel Generator 073A4.03 Process Radiation Monitoring 076A2.02 Service Water 078K1.04 Instrument Air 1 03K4.04 Containment T2G1 PWR EXAMINATION OUTLINE IA k1K2K3K4K5K6A1A2A3A4G SAC 2.5 3.7 3.2 3.1 2.9
3.2 TOPIC
ED/G room temperature Load sequencing Check source for operability demonstration Service water header pressure Cooling water to compressor Personnel access hatch and emergency access hatch FORM ES-401-2 RO
2.5 3.6 3.1 2.7 2.6 2.5 Page 3 of 3 4/4/2012 9:50AM
T2G2 PWR EXAMINATION OUTLINE JR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G ES-401, REV 9 KA NAME / SAFETY FUNCTION:
TOPIC:
FORM ES-401-2 RD SRO 011G2.1.7 Pressurizer Level Control 4.4 4.7 El El El El El El El El El El Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
014K4.06 Rod Position Indication 3.4 3.7
[]
El
] El El El Individual and group misalignment 017K6.0l In-core Temperature Monitor 2.7 3.0 El El El El El El El El El El Sensors and detectors 027A2.0l Containment Iodine Removal 3.0 3.3 El El El El El El El El El El High temperature in the filter system 034A4.02 Fuel Handling Equipment 3.5 3.9 El El El El El El El El El El Neutron levels 041 K2.0l Steam Dump/Turbine Bypass Control 2.8 2.9 El El El El El El El El El El ICS, normal and alternate power supply 045K3.01 Main Turbine Generator 2.9 3.2 El El El El El El El El El El Remainder of the plant 068A3.0l Liquid Radwaste 2.5 2.4 El El El El El El El El: 1 El El Evaporator pressure control 075K1.08 Circulating Water 3.2 3.2 El El El El El El El El El El Emergency/essential SWS 086A1.03 Fire Protection 2.7 3.2 El El El El El El El El El El Firedoors Page 1 of 1 4/4/2012 9:50AM
banthLradjatjop-eieases_
w*j or-dAhL VCaj, ci4 i Knowledge of radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.2 Emergency Procedures/Plans 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
G2.4.41 Emergency Procedures/Plans 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
G2.4.42 Emergency Procedures/Plans 2.6 3.8 Knowledge of emergency response facilities.
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRQ G2.1.3 Conductof operations 3.7 3.9 Knowledgeofshiftorshortterm relief turnoverpractices.
G2.l.40 Conduct of operations 2.8 3.9 Knowledge of refueling administrative requirements G2.2.l Equipment Control 4.5 4.4 Lj Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
G2.2.43 Equipment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms Radiation Control 38 3.g DDL1D G2.3.15 Radiation Control 2.9 3.1 LI El El LI Page 1 of 1 4/4/2012 9:50AM
ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 42 2.7 operationai-etLecis_
cded 2
e oEvtf r.cjcjctl y1-e op t/okt r1+ 1e rtoof4fJ y4iW&t or i-S1-e..
4
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1 3k-reJr.
KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
AC SRO 008AA2.10 Pressurizer Vapor Space Accident/3 3.6 3.6 Li High-pressure injection valves and controllers 015AA2.l0 RCP Malfunctions! 4 3.7 3.7 When to secure RCPs on loss of cooling or seal injection 025AG2.l.27 Loss of RHR System / 4 3.9 4
Knowledge of system purpose and or function.
054AA2.06 Loss of Main Feedwater /4 4
4.3 AFW adjustments needed to maintain proper T-ave. and S/G level 055EG2.2.3 Station Blackout / 6 3.8 3.9 LI (multi-unit license) Knowledge of the design, procedural and operational differences between units.
4.1 Li Li Li Li Li Li Li Li Li Li L
BE04EG+B.Lt.1nadequate Heat Transfer - Loss of Secondary Heat Sink! 4 Page 1 of 1 4/412012 9:50AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
001 AA2.0l Continuous Rod Withdrawal/i 069AG2.4.41 Loss of CTMT Integrity /5 BEO3EG2.i.32 Inadequate Subcooling Margin / 4 BE14EA2.1 EQP Enclosures SRO T1G2 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G RO SRO 4.2 4.2 ED DELI 2.9 4.6 3.8 4.0 DDDDLIDL1D FORM ES-401-2 TOPIC:
Reactor tripped breaker indicator Knowledge of the emergency action level thresholds and classifications.
Ability to explain and apply all system limits and precautions.
Facility conditions and selection of appropriated procedures during abnormal and emergency operations.
Page 1 of 1 4/4/2012 9:50AM
ES4O1, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
P0 SRO 004A2.l0 Chemical and Volume Control 3.9 4.2 Inadvertent boration/dilution 006G2.4.47 Emergency Core Cooling 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
061A2.02 Auxiliary/Emergency Feedwater 3.4 3.5 Air or MOV failure 063G2.2.25 DC Electrical Distribution 3.2 4.2 El El El El El El El Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
078G2.4. 18 Instrument Air 3.3 4.0 El El El El El El El El El El Knowledge of the specific bases for EOP5.
Page 1 of 1 4/4/2012 9:50AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
01 6G22.36 Non-nuclear Instrumentation 01 7A2.01 In-core Temperature Monitor 033G2.4.46 Spent Fuel Pool Cooling SRO T2G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 k5 K6 Al A2 A3 A4 G AC SRO 3.1 4.2 3.1 3.5 4.2 4.2 FORM ES-401-2 TOPIC:
Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Thermocouple open and short circuits Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 1 4/4/2012 9:50AM
SRO T3 PWR EXAMINATION OUTLINE IR ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 4.6 4.6 ED ED D ED DE1 DDDDDDDDDD L1D DDDDDDDDD DDDDDDDDE1 D
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.20 Conduct of operations G2.2.l1 Equipment Control 2.3 3.3 FORM ES-401-2 TOPIC:
Ability to execute procedure steps.
G2.2.23 Equipment Control 3.1 4.6 LI G2.3.ll G2.3.5 Radiation Control 3.8 4.3 Radiation Control 2.9 2.9 Knowledge of the process for controlling temporary design changes.
Ability to track Technical Specification limiting conditions for operations.
G2.4.26 Emergency Procedures/Plans 3.1 3.6 tttGffe+a+feH-feIeases-G2.4.6 Emergency Procedures/Plans 3.7 4.7 Ability to use radiation monitoring systems Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.
Knowledge symptom based EOP mitigation strategies.
Page 1 of 1 4/4/2012 9:50AM
k
\\.
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
12/17/12 LExammnati0 Level:
RO L1 SRO Operating Test Number:
1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations N R ADMIN-132, Determine makeup requirements G2.1.25 (3.9/4.2) (12 mm)
for Hotwell and minimum UST level. (Both)
Conduct of Operations D R ADMIN-124, Determine if RO License G2.1.4 (3.3/3.8) (15 mm)
requirements met (RO Only)
Equipment Control N R ADMIN-238, Perform NI Surveillance and G2.2.12 (3.7/4.1) (14 mm)
Determine Any Required Actions (RO Only)
Radiological Control ADMIN-305, Determine RP Requirements for an G2.3.7 (3.5/3.6) (14 mmn)
N,R Assigned Task (Both)
Emergency Plan 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)imu!ator, 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)
Facility: Oconee Date of Examination:
12/17/12 Examination Level:
1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations N R ADMIN-132, Determine makeup requirements G2.1.25 (3.9/4.2) (12 mm) for Hotwell and minimum UST level. (Both)
Conduct of Operations D R ADMIN-125, Determine if SRO License G2.1.4 (3.3/3.8) (15 mm)
requirements met (SRO only)
Equipment Control N R ADMIN-239, Perform NI Surveillance and G2.2.12 (3.7/4.1) (18 mm)
Determine Any Required Actions (SRO Only)
Radiological Control ADMIN-305, Determine RP Requirements for an G2.3.7 (3.5/3.6) (14 mm)
N,R Assigned Task (Both)
Emergency Plan ADMIN-407, Determine Emergency G2.4.38 (2.4/4.4) (20 mm)
M,R Classification and Complete Emergency Notification Form (SRO Only)
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)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 12/17/12 Exam Level: RO SRO-l SRO-U Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a.
CRO-112, ATWS With Failure of C HPIP M A EPI1/A11800/001 (Emergency Operating Procedure),
Rule 1 (ATWS/UNPP)
[KA:_BW/E13_EA1.1_(3.4/3.2)]_(5_mm) b.
CRO-214, RCS Leak While on DHR N A L 2
AP/1IA/17001026 (Loss of Decay Heat Removal)
End. 5.12 (RCS Makeup)
[KA: APEO25 AA1.02 (3.8/3.9)1 (16 mm) c.
CRO-310, Align Post Loca Boron Dilution Flowpath M A L 3
EP/1/N1800/0O1 (Emergency Operating Procedure),
LOCA CD tab
[KA: EPEO11 EA2.01 (4.2/4.7)] (12 mm) d.
CRO-412, Align ECCS suction with 1LPSW-4 failed M A, EN L
4P closed EPI1/A/18001001 (Emergency Operating Procedure), End.
5.12 (ECCS Suction Swap)
[KA: BW/E08 EA1.1 (4.0/3.7)] (20 mm) e.
CRO-401A, Following a loss of all FDW, Feed a dry SG M, L 4S with the TDEFWP EP/1 IA/i 800/001 (Emergency Operating Procedure),
Rule 3 (Loss of Main or Emergency FDW)
[KA: APE 054 AA2.04 (4.2/4.3)] (15 mm) f.
CRO-601, Synchronization with the grid following a D
6 load rejection AP/1/A/1700/001 (Unit Runback)
[KA: SYS 062 A4.07 (3.1*13.1*)] (20 mm) g.
CRO-701, Adjust RIA 40 setpoints N
7 AP/1/N1700/031 (Primary To Secondary Leakage)
End. 5.8 (Resetting 1 RIA-40 and OAC Setpoints)
[KA: APE 061 AA2.03 (3.0/3.3)] (18 mm) h.
CRO-802, Respond to a fuel handling accident in the N
L 8
Reactor Building.
AP/1/A/1700/009 (Spent Fuel Damage)
[KA: APE 036 AA1.01 (3.3/3.8)] (14 mm)
I.
4
In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
NLO-202, Swapping In Service Seal Return Coolers N E R 2
AP/1/A/1700/002 (Excessive RCS Leakage) End. 5.7 (Swapping In Service Seal Return Coolers)
[KA: SYS 002 A2.01 (4.3/4.4)] (19 mm) j.
NLO-605, Startup a Vital Bus Inverter D
6 OP/2/A/1 107/004 (Operation of Vital Bus, Computer, ICS, and Auxiliary lnverters) End. 4.2 (Startup of Vital Bus I nverters)
[KA: SYS 062 A3.04 (2.7/2.9)] (12 mm) k.
NLO-801, HPSW And LPSW AB Flood Isolation M A E 8
AP/3/A/1700/030 (Auxiliary Building Flooding) End. 5.1 (HPSW AB Flood Isolation) and 5.2 (LPSW AB Flood Isolation)
KA: BWAO7 AA2.2 (3.3/3.7)] (16 mm)
All 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 I SRO-l / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank 918/4 (E)mergency or abnormal in-plant 1 I 1 I 1
(EN)gineered safety feature
- I
/ 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1 (A) 2 I 2 I I
(P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 12/17/12 Exam Level: RO SRO-l SRO-U Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a.
CRO-112, ATWS With Failure of C HPIP M A 1
EP/1/A/1800/001 (Emergency Operating Procedure),
Rule 1 (ATWS/UNPP)
[KA: BW/E13 EA1.1 (3.4/3.2)] (5 mm) b.
CRO-214, RCS Leak While on DHR N A L 2
AP/1/N1700/026 (Loss of Decay Heat Removal)
End. 5.12 (RCS Makeup)
[KA: APE025 AA1.02 (3.8/3.9)] (16 mm) c.
CRO-310, Align Post Loca Boron Dilution Flowpath M A L 3
EP/1/A/1800/001 (Emergency Operating Procedure),
LOCA CD tab
[KA: BW/E08 EA1.3 (3.3/3.8)] (12 mm) d.
CRO-412, Align ECCS suction with 1 LPSW-4 failed M, A, EN, L 4P closed EPI1 IA/i 800/001 (Emergency Operating Procedure), End.
5.12 (ECCS Suction Swap)
[KA: BW/E08 EA1.1 (4.0/3.7)] (20 mm) e.
CRO-401A, Following a loss of all FDW, Feed a dry SG M, L 4S with the TDEFWP EP/1 /A/1 800/001 (Emergency Operating Procedure),
Rule 3 (Loss of Main or Emergency FDW)
[KA: APE 054 AA2.04 (4.2/4.3)] (15 mm) f.
N/A g.
CRO-701, Adjust RIA 40 setpoints N
7 AP/1/A/1700/031 (Primary To Secondary Leakage)
End. 5.8 (Resetting 1 RIA-40 and OAC Setpoints)
[KA: APE 061 AA2.03 (3.0/3.3)] (18 mm) h.
CRO-802, Respond to a fuel handling accident in the N
L 8
Reactor Building.
AP/1 /A/i 700/009 (Spent Fuel Damage)
[KA: APE 036 AA1.01 (3.3/3.8)] (14 mm)
-J
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
NLO-202, Swapping In Service Seal Return Coolers N E R 2
AP/l IA/i 700/002 (Excessive RCS Leakage) End. 5.7 (Swapping In Service Seal Return Coolers)
[KA: SYS 002 A2.01 (4.3/4.4)] (19 mm) j.
NLO-605, Startup a Vital Bus Inverter D
6 OP/2/N1 107/004 (Operation of Vital Bus, Computer, ICS, and Auxiliary Inverters) End. 4.2 (Startup of Vital Bus I nverters)
[KA: SYS 062 A3.04 (2.7/2.9)] (12 mm) k.
N/A All 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 I SAD-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrombank 9/<814 (E)mergency or abnormal in-plant 1 I 1 I 1
(EN)gineered safety feature
- I
/ 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1 (A) 2 1 2 /
1 (P)revious 2 exams 3 /
31 2 (randomly selected)
(R)CA (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 12/17/12 Exam Level: RO SRO-l SRO-U Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function a.
CR0-lI 2, ATWS With Failure of C HPIP M A EP/1 /A/1 800/001 (Emergency Operating Procedure),
Rule 1 (ATWS/UNPP)
[KA: BW/E13 EA1.1 (3.4/3.2)] (5 mm) b.
N/A c.
CRO-310, Align Post Loca Boron Dilution Flowpath M A L
3 EP/1/A/1800/001 (Emergency Operating Procedure),
LOCA CD tab
[KA: BW/E08 EA1.3 (3.3/3.8)] (12 mm) d.
CRO-412, Align ECCS suction with 1LPSW-4 tailed M A EN L
4P closed
EP/1 /A/1 800/001 (Emergency Operating
, End.
5.12 (ECCS Suction Swap)
[KA: BW/E08 EA1.1 (4.0/3.7)] (20 mm) e.
N/A f.
N/A g.
N/A h.
N/A
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
NLO-202, Swapping In Service Seal Return Coolers N E R 2
AP/1/AJ1700/002 (Excessive RCS Leakage) End. 5.7 (Swapping In Service Seal Return Coolers)
[KA: SYS 002 A2.01 (4.3/4.4)] (19 mm) j.
NLO-605, Startup a Vital Bus Inverter D
6 OP/2/A/1 107/004 (Operation of Vital Bus, Computer, ICS, and Auxiliary Inverters) End. 4.2 (Startup of Vital Bus Inverters)
[KA: SYS 062 A3.04 (2.7/2.9)] (12 mm) k.
NLO-801, HPSW And LPSW AB Flood Isolation M A E 8
AP/3/A11700/030 (Auxiliary Building Flooding) End. 5.1 (HPSW AB Flood Isolation) and 5.2 (LPSW AB Flood Isolation)
[KA: BWAO7 AA2.2 (3.3/3.7)] (16 mm)
All 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 / SP0-I I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 91<814 (E)mergency or abnormal in-plant I I 1 I? I (EN)gineered safety feature
- I I 1 (control room system)
(L)ow-Power I Shutdown 1 I 1 I 1
(N)ew or (M)odified from bank including 1 (A) 2 I 2 1 1
(P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA (S)imulator