ML13248A017
| ML13248A017 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/04/2013 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| 50-269/13-301, 50-270/13-301, 50-287/13-301 | |
| Download: ML13248A017 (21) | |
Text
- WRflTEN EXAM SAMPLE PLAN ONLY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
OCONEE Date of Examination:
JUNE 2013 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 a41 N/A I
Section 0.1 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 o
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 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 mkithnzns 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.
G E
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
/7 N/A
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
N/A
d.
Check for duplication and overiap 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 /
10/11/2012
- b. Facility Reviewer (*)
N/A
- c. NRC Chief Examiner (#)
LltSlfDj /,A,1,4((J.
IZ/4120)Z
- d. NRC Supervisor 5et 41r4Ctc>
1 11/4/71)1; Note:
- Independent NRC reviewer initial items in Column ac; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
- WRflTEN EXAM SAMPLE PLAN ONLY -
ES-401 PWR Examination Outline Form ES-401-2 Facility:
000NEE Date of Exam:
JUNE 2013
ROKCaoPcnts SRO-Only_Points Tier Group 1
KIK K
KKKAAAAG A2 G*
Total 112 3
4 5
6 1
2 3
4 Total 1.
1 3
3 3
3 3
3 18 3
3 6
Emergency &
Abnormal 2
1 1
2 N/A
- 1. 1 N/A j
9 2
2 4
Plant Evolutions TierTotals 4
4 5
5 5
4 27 5
5 10 1
3 3
3 3
2 2
3 2
3 2
2 28 2
3 5
2.
Plant 2
L+/-
L+/-L+/-1.
10 0
1 2
3 Sys ems Tier Totals 4
4 4
4 3
3 4
3 4
3 2
38 3
5 8
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 7
Categories 3
3 2
2 2
2 1
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 outiines (i.e., exceptfor one category in Tier 3 ofthe 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, butthe topics must be relevant to the applicable evolution or system. Referto Section D.1.b of ES-401 forthe 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 ofthe 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.
ES-401, REV 9 T1G1 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 007EG2.2.42 Reactor Trip
- Stabilization
- Recovery 3.9 4.6 j J
j j
j Ability to recognize system parameters that are entry-I 1 level conditions for Technical Specifications 008AG2.4.45 Pressurizer Vapor Space Accident 1 3 4.1 4.3 J
j j
j j
Ability to prioritize and interpret the significance of each annunciator or alarm.
OO9EA1.01 Small Break LOCA I 3 4.4 4.3 j
RCS pressure and temperature 01 1 EG2.2.22 Large Break LOCA I 3 4.0 4.7 j
j J
Knowledge of limiting conditions for operations and safety limits.
01 5AK28 RCP Malfunctions I 4 2.6 2.6 CCWS 022AK1.04 Loss of Rx Coolant Makeup I 2 2.9 3
j Reason for changing from manual to automatic control of charging flow valve controller 025AK2.01 Loss of RHR System /4 2.9 2.9 RHR heat exchangers 026AA1.03 Loss of Component Cooling Water /8 3.6 3.6 El El LI El El LI El El El SWS as a backup to the CCWS 027AK3.02 Pressurizer Pressure Control System 2.9 3
El El El El El El El El El El Verification of alternate transmitter and/or plant computer Malfunction / 3 prior to shifting flow chart transmitters 029EK2.06 ATWS / 1 2.9 3.1 El J El El El El El El El El El Breakers, relays, and disconnects.
038EA2.03 Steam Gen. Tube Rupture /3 4.4 4.6 El El El El El El El El El El Which S/G is ruptured Pagelof2 10/11/2012 3:07PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
040AA2.04 Steam Line Rupture
- Excessive Heat Transfer / 4 054AA2.01 Loss of Main Feedwater /4 055EK1.02 Station Blackout /6 056AK3.01 Loss of Off-site Power / 6 057AA1.02 Loss of Vital AC Inst. Bus / 6 058AK1.01 Loss of DC Power /6 062AK3.03 Loss of Nuclear Svc Water /4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 4.5 4.7 4.3 4.4 4.1 4.4 as 3.9 3.8 3.7 2.8 3.1 4
4.2 FORM ES-401-2 TOPIC:
Conditions requiring ESFAS initiation Occurrence of reactor and/or turbine trip Natural circulation cooling Order and time to initiation of power for the load sequencer Manual control of PZR level Battery charger equipment and instrumentation Guidance actions contained in EOP for Loss of nuclear service water Page 2 of 2 10/11/2012 3:07PM
ES-401, REV 9 T1G2 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 OO5AA1.03 Inoperable/Stuck Control Rod / 1 3.4 3.4 j J Metroscope 032AK3.02 Loss of Source Range NI / 7 3.7 4.1 j
j j j J Guidance contained in EOP for loss of source-range nuclear instrumentation 051 AA1.04 Loss of Condenser Vacuum / 4 2.5 2.5 j [j Rod posWon 061AK3.02 ARM System Alarms / 7 3.4 3.6 J
j Guidance contained in alarm response for ARM system 069AG2.2.44 Loss of CTMT Integrity / 5 4.2 4.4 j
j j j J j 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 076AA2.02 High Reactor Coolant Activity / 9 2.8 3.4 j j j Corrective actions required for high fission product activity in RCS BAO7AK1.1 Flooding /8 3.53.5 LI LI LI LI LI LI LI El El El Components, capacity, and function of emergency systems.
BEO3EA2.2 Inadequate Subcooling Margin /4 3.5 4
El El LI El Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
BEO9EK2.2 Natural Circ./4 4
4 LI Facility s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
Page 1 of 1 10/11/2012 3:07PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 PZR spray flow Prevention of cold water accklents or transients Ability to explain and apply all system limits and precautions.
Refueling operations BIT/borated water sources Overpressurization of the waste gas vent header CCW pressure Requirements on and for the CCWS for different condi tions of the power plant PZR heaters Bypass-block circuits T-cold KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 003A1.06 Reactor Coolant Pump 2.9 3.1 j
j 003K4.02 Reactor Coolant Pump 2.5 2.7 j j j J j 004G2.1.32Chemical and Volume Control 3.8 4.0 005K3.07 Residual Heat Removal 3.2 3.6 El El El 006K6.01 Emergency Core Cooling 3.4 3.9 El El El El El El El El El El 007A2.04 Pressurizer Relief/Quench Tank 2.5 2.9 El El El El El El El [] El El El 008A1.03 Component Cooling Water 2.7 2.9 El El El El El El ] El El El El 008A3.04 Component Cooling Water 2.9 3.2 El El El El El El El El El El 010K2.01 Pressurizer Pressure Control 3.0 3.4 El El El El El El El El El El 012K6.04 Reactor Protection 3.3 3.6 El El El El El El El El El El Ol3Al.10 Engineered Safety Features Actuation 3.4 3.7 El El El El El El El El El El Page 1 of 3 10/11/2012 3:07PM
3.1 3.4 ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
022K4.02 Containment Cooling J
j j J Correlation of fan speed and flowpath changes with containment pressure 026G2.4.46 Containment Spray 4.2 4.2 j
j j j Ability to verify that the alarms are consistent with the plant conditions.
026K4.09 Containment Spray 3.7 4.1 j
j j J j
Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover) 039K5.O1 Main and Reheat Steam 2.9 3.1 j j j
j Definition and causes of steam/water hammer 059K1.04 Main Feedwater 3.4 3.4 j j j S/GS water level control system 061 K3.02 Auxiliary/Emergency Feedwater 4.2 4.4 j j j
S/G 061 K5.01 Auxiliary/Emergency Feedwater 3.6 3.9 LI LI LI LI LI LI LI LI LI Relationship between AFW flow and RCS heat transfer 062A3.05 AC Electrical Distribution 3.5 3.6 LI LI LI LI LI LI LI LI LI LI Safety-related indicators and controls 063A3.0l DC Electrical Distribution 2.7 3.1 LI LI LI LI LI LI LI LI LI LI Meters, annunciators, dials, recorders and indicating lights 064K2.01 Emergency Diesel Generator 2.7 3.1 LI LI LI LI LI LI LI LI LI LI Air compressor 073A4.03 Process Rachation Monitoring 3.1 3.2 LI LI LI LI LI LI LI LI LI LI Check source for operability demonstration Page 2 of 3 10/11/2012 3:07PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 073A4.03 Process Radiation Monitoring 3.1 3.2 El El El LI El LI El El
[
Check source for operability demonstration 076A2.02 Service Water 2.7 3.1 El El El LI [ El El El [ El Serce water header pressure 078K2.01 Instrument Air 2.7 2.9 El El El El El LI El El [1 El Instrument air compressor 078K3.0l Instrument Air 3.1 3.4 El El El El El El El El El El Containment air system 103K1.O1 Containment 3.6 3.9 CCS 103K1.03 Containment 3.1 3.5 El El El El El El El El El El Shield building vent system Page3of 3 10/11/2012 3:07PM
ES-401, REV 9 T2G2 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 001 K5.96 Control Rod Drive 3.2 3.4 J j j j j
j Sign changes (plus or minus) in reactivity, obtained when positive reactivities are added to negative reactivities 002K3.03 Reactor Coolant 4.2 4.6 Containment 014A4.03 Rod Posion Indication a6 2.7 El El Primary coil voltage measurement 01 5A1.04 Nuclear Instrumentation 3.5 3.7 El El El El Quadrant power tilt ratio 017K6.01 In-core Temperature Monitor 2.7 3.0 El ll El El El El Ej Sensors and detectors 029K4.03 Containment Purge 3.2 3.5 El El El El El El El El El El Automatic purge isolation 033K1.05 Spent Fuel Pool Cooling 2.7 2.8 El El El El El El El El El El RWST 041 K2.02 Steam Dump/Turbine Bypass Control 2.8 2.8 El El El El El El El El El El CS inverter breakers 068A3.01 Liquid Radwaste 2.5 2.4 El El El El El El El El El El Evaporator pressure control 075A2.Ol Circulating Water 3.0 3.2 El El El El El El El El El El Loss of intake structure Pagelofl 10/11/2012 3:07PM
ES-401, REV 9 T3 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 G2.114 Conduct of operations 3.1 3.1 J J j
j Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.
G2.l.45 Conductofoperations 4.3 4.3 j j j
J j j Ability to identify and interpret diverse indications to validate the response of another indication
.8 Conductof operations 3.4 4.1 j
j J
J j j Ability to coordinate personnel activities outside the control room.
G2.2.2 Equipment Control 4.6 4.1 J
J Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
G2.2.39 Equipment Control 3.9 4.5 j J
j j Knowledge of less than one hour technical specification action statements for systems.
G2.2.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.1 1 Radiation Control 3.8 4.3 J j J Ability to control radiation releases.
G2.3.4 Radiation Control 3.2 3.7 J J Knowledge of radiaon exposure limits under normal and emergency conditions G2.4.23 Emergency Procedures/Pns 3.4 4.4 j
j Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
Ga4.46 Emergency Procedures/Plans 4.2 4.2 El El El LI El LI LI LI LI Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 1 10/11/2012 3:07PM
ES-401, REV 9 SRO T1G1 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 007EA2.04 Reactor Trip
- Stabilization
- Recovery 4.6 4.4 j
j If reactor should have tripped but has not done so, I 1 manually trip the reactor and carry out actions in ATWS EOP 009EG2.4.21 Small Break LOCA /3 4.0 4.6 j J j Knowledge of the parameters and logic used to assess the status of safety functions 038EG2.4.20 Steam Gen. Tube Rupture /3 3.8 4.3 J j j Knowledge of operational implications of EOP warnings, cautions and notes.
057AA2.06 Loss of Vital AC Inst. Bus / 6 3.2 3.7 EJ j j
AC instrument bus alarms for the inverter and alternate power source 062AG2.1.28 Loss of Nuclear Svc Water /4 4.1 4.1 Knowledge of the purpose and function of major system components and controls.
BEO5EA2.1 Steam Line Rupture
- Excessive Heat 3
4.2 LI LI LI LI LI LI LI LI LI Facility conditions and selection of appropriate Transfer / 4 procedures during abnormal and emergency operations.
Pagelofl 10/11/2012 3:07PM
ES-401, REV 9 KA 003AG2.4.50 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 4.2 4.0 ElElElElElElElElElEl 2.53 ElElElElElElElElElEl 3.7 4.1 ElElElElElElElElElEl BAO5AA2.1 Emergency Diesel Actuation / 6 3.5 4.2 [ [ [ [] El El [1 El El El Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
NAME / SAFETY FUNCTION:
Dropped Control Rod / 1 005AA2.02 Inoperable/Stuck Control Rod / 1 FORM ES-401-2 iA.2.l2 Loss of Condenser Vacuum / 4 TOPIC:
Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Difference between jog and run rod speeds effect on CRDM of stuck rod Knowledge of surveillance procedures.
Page 1 of 1 10/11/2012 3:07PM
FORM ES-401-2 TOPIC:
Consequences of high or low CCW flow rate and tempera-ture; the flow rate at which the CCW standby pump will start Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Ability to verify that the alarms are consistent with the plant conditions.
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Feeding a dry S/G ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME/SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 008A2.07 Component Cooling Water 2.5 2.8 LI LI LI LI LI LI LI OlOG2.4.50 Pressurizer Pressure Control 4.2 4.0 LI LI LI LI LI LI LI LI LI LI 022G2.4.46 Containment Cooling 4.2 4.2 LI LI LI LI LI i LI LI LI LI 026G2.4.47 Containment Spray 4.2 4.2 LI LI LI LI LI LI LI LI LI LI 059A2.04 Main Feedwater 2.9 LI LI LI LI LI LI LI LI LI LI Page 1 of 1 10/11/2012 3:07PM
ES-401, REV 9 SRO T2G2 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 015G2.4.20 Nuclear Instrumentation 3.8 4.3 LI LI LI LI LI LI LI LI LI Knowledge of operational implications of EOP warnings, cautions and notes.
034G2.4.l 1 Fu Handling Equipment 4.0 4.2 LI LI LI LI LI LI LI LI LI LI []
Knowledge of abnormal condition procedures.
056A2.04 Condensate 2.6 2.8 LI LI LI LI LI LI LI LI LI LI Loss of condensate pumps Page 1 of 1 10/11/2012 3:07 PM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
G2.1.19 Conduct of operations G2.1.25 Conduct of operations G2.2.12 Equipment Control G2.2.5 Equipment Control G2.3.4 Radiation Control Ga4.34 Emergency Procedures/Plans G2.4.40 Emergency Procedures/Plans SRO T3 PWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G SRO 3.8 4.2 4.1 3.2 4.5 FORM ES-401-2 RO
3.9 3.9 3.7 2.2 3.2 4.2
2.7 TOPIC
Ability to use plant computer to evaluate system or component status.
Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
Knowledge of surveillance procedures.
Knowledge of the process for making design or operating changes to the facility Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of RO tasks performed outside the maui control room during an emergency and the resultant operational effects Knowledge of the SROs responsibilities in emergency plan implementation.
Page 1 of 1 10/11/2012 3:07PM
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6/10/13 Examination Level: RO X SRO Operating Test Number: 1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations
[KA G2.1.7 (4.4/4.7)]
M, R Admin-131, Perform manual RCS Leakage Calculation (RO ONLY) (18 min)
Conduct of Operations
[KA G2.1.19 (3.9/3.8)]
M, R Admin-140, Calculate an Estimated Critical Rod Position (BOTH) (17 min)
Equipment Control
[KA G2.2.12 (3.7/4.1)]
M, R Admin-240, Perform SG Downcomer Temperature Surveillance (RO ONLY) (18 min)
Radiological Control
[KA G2.3.4 (3.2/3.7)]
D, R Admin-306, Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDLs)
(BOTH) (20 min)
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)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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 06/10/13 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. CRO-106, Place Spare Deborating IX in Service OP/1/A/1103/004 C, Deborating IXs Encl. 4.9 (Spare Deborating IX for RCS Purification (Rx at Power))
[KA: 004 A4.17 (2.7/2.7)] (15 min)
D, L, S 1
[KA: 006 A4.08 (4.2/4.3)] (15 min)
D, L, S 2
[KA: EPE 011 EA1.04 (4.4/4.4)] (10 min)
D, A, EN, L, S
3
[KA: APE 054 AA1.01 (4.5/4.4)] (12 min)
D, L, S 4S
[KA: EPE 074 EA1.08 (4.2/4.2)] (3 min)
M, A, L, S 4P
- f. CRO-507, Perform EOP Encl. 5.35 (Containment Isolation)
Unit 1 EOP Encl. 5.35 (Containment Isolation)
[KA: 103 G2.1.23 (4.3/4.4)] (10 min)
M, A, L, S 5
- g. CRO-605, Energize Main Feeder Buses from CT-4 Unit 1 EOP Encl. 5.38 (Restoration of Power)
[KA: EPE 055 EA2.03 (3.9/4.7)] (15 min)
M, L, S 6
- h. CRO-902, Place Reactor Building Purge in Operation OP/1/A/1102/014, Encl. 4.1 (RB Purge Release)
[KA: 029 A2.03 (2.7/3.1)] (15 min)
M, A, L, S 8
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
NLO-100, Trip the Reactor from the Control Rod Drive Breakers Unit 3 EOP RULE 1 (ATWS/Unanticipated Nuclear Power Production)
[KA: EPE 029 EA1.11 (3.9*/4.1)] (4 min)
M, E 1
- j.
NLO-606, Makeup to Unit 1 CBAST from Unit 1 & 2 BAMT During a Unit 2 Blackout Unit 2 EOP Encl. 5.39 (Makeup to the BWST During Blackout)
[KA: B/WE14 EA1.1 (3.8/3.6)] (12 min)
N, E, R 6
- k. NLO-802, Start Diesel Air Compressors and Align to Service Air Header AP/2/A/1700/022 (Loss of Instrument Air) Encl. 5.4 (Emergency Start of the Diesel Air Compressor) and 5.7 (Manual Start of Diesel Air Compressors)
[KA: APE 065 AA1.04 (3.5*/3.4*)] (20 min)
D, A, E 8
All RO and SRO-I 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-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6/10/13 Examination Level: RO SRO X Operating Test Number: 1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations
[KA G2.1.7 (4.4/4.7)]
M, R Admin-130, Perform manual RCS Leakage Calculation and TS determination (SRO ONLY) (18 min)
Conduct of Operations
[KA G2.1.19 (3.9/3.8)]
M, R Admin-140, Calculate an Estimated Critical Rod Position (BOTH) (17 min)
Equipment Control
[KA G2.2.12 (3.7/4.1)]
N, R Admin-241, Complete a Surveillance Evaluation (SRO ONLY) (20 Minutes)
Radiological Control
[KA G2.3.4 (3.2/3.7)]
D, R Admin-306, Calculate the Maximum Permissible Stay Time Within Emergency Dose Limits (EDLs)
(BOTH) (20 min)
[KA G2.4.38 (2.4/4.4)]
M, R Admin-412, Determine Emergency Classification and complete the initial Emergency Notification form (SRO ONLY) (20 min)
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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 06/10/13 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. N/A
- b. N/A
[KA: EPE 011 EA1.04 (4.4/4.4)] (10 min)
D, A, EN, L, S
3
- d. N/A
[KA: EPE 074 EA1.08 (4.2/4.2)] (3 min)
M, A, L, S 4P
- f. N/A
- g. N/A
- h. CRO-902, Place Reactor Building Purge in Operation OP/1/A/1102/014, Encl. 4.1 (RB Purge Release)
[KA: 029 A2.03 (2.7/3.1)] (15 min)
M, A, L, S 8
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
NLO-100, Trip the Reactor from the Control Rod Drive Breakers Unit 3 EOP RULE 1 (ATWS/Unanticipated Nuclear Power Production)
[KA: EPE 029 EA1.11 (3.9*/4.1)] (4 min)
M, E 1
- j.
NLO-606, Makeup to Unit 1 CBAST from Unit 1 & 2 BAMT During a Unit 2 Blackout Unit 2 EOP Encl. 5.39 (Makeup to the BWST During Blackout)
[KA: B/WE14 EA1.1 (3.8/3.6)] (12 min)
N, E, R 6
- k. N/A All RO and SRO-I 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-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1