ML12270A389
| ML12270A389 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/24/2012 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML12270A389 (22) | |
Text
DRAFT ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility:
Date of Exam:
RO K/A Category Points SRO-Only Points Tier Group
KIKKKKIKAAAAG A2 G*
Total 112 3
5L6 1
2 3
4 Total
1.
i 333 33 3
18 3
3 6
Emergency&
2 2
1 1
9 2
2 4
Abnormal Plant
N/A
Evolutions Tier Totals 5
4 5
5 4
4 27 5
5 10
=
=
=
=
1 33233232322 28 2
3 5
Pnt 2
11011111111 10 ij 2
3 Systems Tier Totals 4
42 4
4 3
4 3
4 3
3 38 5
8
- 3. GenericknowiedgeandAbilitles 1
2 3
4 10 1
2 3
4 7
Categories 3
3 2
2 1
2 2
2 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier ofthe RO and SRO-only outlines (I.e., except for one category in TIer 3 of the SRO-only outline, the IerTotals@
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 )4 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 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.oniy portions, respectively.
6.
Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.
7.
The generic ((3) K/As In Tiers I 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 KAs.
8.
On the following pages, enter the K/A numbers, a brief description of each topic, the toplcsimportance 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 (3* 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 55.48..
DRAFT
008AK2.0l 009EK2.03 011 EA2.0l 015AK2.10 022AK1.03 026AG2.4.49 029EA1.03 038EK1.02 054AG2.4.4 055EA2.03 Pressurizer Vapor Space Accident/3 Small Break LOCA / 3 Large Break LOCA /3 RCP Malfunctions / 4 Loss of Rx Coolant Makeup /2 Loss of Component Cooling Water / 8 ATWS /
Steam Gen. Tube Rupture / 3 Loss of Main Feedwater / 4 Station Blackout / 6 2.7 2.7 flEIL1 3
E1iIZ1E 4.2 LILJEILJ 2.8 2.8 flEE1 3
3.4 IEOEI 4.6 EILIEIEI 3.5 3.2 OLILILJ 3.2 3.5 LJLJE1 4.5 4.7 LILILILI 3.9 4.7 EILIELI ElELI LI El LI LI LI C] LI Li LI LI LI LI LID I LI El LI LI LI LI LID LID EIDD LID LI LI LI LI LI LI IJ LI LI I LI LIE LI LILIELI LI LID DLI LI LIE LI DLIDD LID ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION:
IR 1(1 K2 1(3 1(4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO Valves SJGs Actions to be taken based on RCS temperature and pressure saturated and superheated RCP indicators and controls Relationship between charging flow and PZR level Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Charging pump suction valves from VCT operating switch Leak rate vs. pressure drop Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
Actions necessary to restore power 056AK3.02 Loss of Off-site Power / 6 4.4 4.7 LI LI I LI LI LI LI LI LI LI LI Actions contained in EOP for loss of offsite power Page 1 of 2 10126/2011 10:46 PM
ES-401, REV 9 T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
lB Ki 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 057AA1.04 Loss of Vital AC Inst. Bus /6 3.5 3.6 C] C] Li LI LI LI I1 [1 0 0 0 RWST and VCT valves 058AK3.02 Loss of DC Power / 6 4
4.2 Li C] II 0 LI Li Li Li Li El El Actions contained in EOP for loss of dc power 062AA1.06 Loss of Nuclear Svc Water /4 2.9 2.9 Li fl El Li Q Control of flow rates to components cooled by the SWS 065AG2.i.28 - Loss of Instrument Air /8 4.1 4.1 Li Li Li Li C][] Li Li U Knowledge of the purpose and function of major system components and controls.
iAK1.O1 Generator Voltage and Electric Grid 3.3 3.5 Li Li El L Li LI LI Li Li El Definition of the terms: volts, watts, amps, VARS, power Disturbances / 6 factor BEO4EA2.1 Inadequate Heat Transfer - Loss of 3.2 4.4 Li Li Li Li OLi Li 1 Li Li Li Facility conditions and selection of appropriate Secondary Heat Sink! 4 procedures during abnormal and emergency operations.
BEO5EK3.3 Steam Line Rupture-Excessive Heat 4.2 3.8 C] El [) U Li El U Li 0 Li [1 Manipulation of controls required to obtain desired Transfer /4 operating results during abnormal, and emergency situations.
Page2of2 10/26/2011 10:46PM
ES-401, REV 9 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 SRO 024AK3.O1 Emergency Boration I 1 4.1 4.4
[] fl [] [] [] [] [] [] [] ) [j When emergency boration is required 059AK3.04 Accidental Liquid RadWaste Rd. / 9 3.8 4.3 El Li LI LI LI El El LI El El Actions contained in EOP for accidental liquid radioactive-waste release O6OAK1.04 Accidental Gaseous Radwaste Rel. / 9 2.5 3.7
[] El El El LI [I El [I El El Calculation of offsite doses due to a release from the power plant 068AA1.07 Control Room Evac. 18 4.1 4.2
[] [] [] El
[J [J []
[] [
PZR heaters 074EK2.02 mad. Core Cooling/ 4 3.9 4
[]
[] [] [] []
] [] [] ]
PORV BAO1AG2.1.31 Plant Runback /1 4.6 4.3
[] J [J [J [] [] [] [] []
]
Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.
BAO4AK1.3 Turbine Trip / 4 3.2 3.3
[] El El El El El El El El El El Annunciators and conditions indicating signals, and remedial actions associated with the (Turbine Trip).
BEO8EA1.1 LOCA Cooldown
- Depress. / 4 4
3.7 El LI El El El El J LI El El El Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
BE14EA2.1 EOP Enclosures 3.4 4
El El El El LI LI El ] LI LI LI Facility conditions and selection of appropriated procedures during abnormal and emergency operations.
Page 1 of 1 10/26/2011 10:46 PM
ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
IR K1 K2 1<3 1<4 1<5 1<6 Al A2 A3 A4 G TOPIC:
RO SRO 003K2.02 Reactor Coolant Pump 2.5 2.6
[] j fl [J [] Q U fl fl []
CCW pumps 004K3.05 Chemical and Volume Control 3.8 4.2 1 U U U U U U Li []
PZR LCS 005A4.04 Residual Heat Removal 3.1 2.9 0 Q (] U U U ULi [J J
Controls and indicaticn for closed cooling water pumps 006K6.O1 Emergency Core Cooling 3.4 3*
[] Q C LI LI LI LI LI U U BlTiborated water sources 006K6.10 Emergency Core Cooling 2.6 2.8 U Li U U LI U LI [1 U LI Valves 007G2.1.7 Pressurizer Relief/Quench Tank 4.4 4.7 0 [] U U C C U U }
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and inslwment interpretation.
007K1.03 Pressurizer Relief/Quench Tank 3.0 3.2 U C U U U DLI U U U RCS 008K4.09 Component Cooling Water 27 2.9 U U U II U LI U U LI U U The standby feature for the CCW pumps 01 0G2.2.42 Pressurizer Pressure Control 3.9 4.6 U LI U U U U LI U U Li }
Ability to recognize stem parameters that are entry-level conditions for Technical Specifications 012K1.04 Reactor Protection 3.2 3.3 U U U U Li U LI U U U RPIS 0131<5.02 Engineered Safety Features Actuation 2.9 3.3 U U U U II U U U U U Li Safety system logic and reliability Page 1 of 3 1W26/2011 10:46PM
T2G1PWR EXAMINATION OUTLINE FORM ES-401-2 IR 1(1 1(2 1(3 1(4 1(5 1(6 Al A2 A3 A4 G TOPIC:
U Initiation of safeguards mode of operation
[] El [1 U [1 [1 C] U Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray U El I Cl U [J [] C] C]
Definition and causes of steamlwater hammer C] [][J [] C] ] El C] U Tripping of MFW pump turbine C] [] C] [] ] C] [] [] C]
Interactions when multi unit systems are cross tied U C]
C] DC] [] Cl C]
Pump head effects when control valve is shut
[1 U U C] I] U C] U C]
Effect on instrumentation and controls of switching power supplies C]UUUDUUUC]
Off-sitepowersources C]
Meters, annunciators, dials, recorders and indicating lights C]
EDIG room temperature C] UU U U 1C]U C] DC] IUU C] El ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO SRO 022A3.01 Containment Cooling 4.1 4.3 C]
C] C] C] [] C]
026K4.02 Containment Spray 3.1 i6
[] [1 0391(5.01 Main and Reheat Steam 2.9 3.1 C]
059A2.07 Main Feedwater 3.0 3.3 C] C]
061A1.03 Awdliary/EmergencyFeedwater 3.1 3.6 Cl U 0611(5.03 Au,dliary/Emergency Feedwater 2.6 2.9
[] El 062A1.03 AC Electrical Distribution 2.5 2.8 C] C]
0621(1.04 AC Electrical Distnbution 3.7 4.2 J []
063A3.01 DC Electrical Distribution 2.7 ai C] C]
064A1.05 Emergency Diesel Generator 25 25 C] C]
073A4.01 Process Radiation Monitoring 3.9 U C] U U C] C] C] U C]
U Effluent release Page 2 of 3 10126/2011 10:46PM
ES-401, REV 9 KA 0761<2.04 T2GI PWR EXAMINATION OUTLINE IR KI 1<2 1<3 1<4 K5 K6 Al A2 A3 A4 G RO SRO 2.5 a6 flJJLJrflQQ 2.5 2.8 DODD1DJfl 078A3.01 Instrument Air 3.1 3.2
[] fl [] [3 [] [3 [3 [3
[] [3 Air pressure 0781<2.02 Instrument Air 3.3 3.5
[3 (} [3 [3 [3 [3 [3 [3 [3 [3 [3 Emergency air conipresscx 103A2.05 Containment 2.9 3.9
[3 [3 [3 [3 [3 [3 [3 J [3 [3 [3 Emergencycontainmententry 1031<4.01 Containment 3.0 3.7
[3 [3 [3
[3 [3 [3 [3 [3 [] []
Vacuum breaker protechon NAME I SAFETY FUNCTION:
Service Water 0761<3.02 Service Water FORM ES-401-2 TOPIC:
Reactor building closed coding water Secondary closed coding water Page 3d 3 10/26/2011 10:46PM
002A3.03 0151<4.10 028A1.02 029A4.04 033G2.4.9 056A2.04 0681<6.10 072K5.01 079K1.01 Reactor Coolant Nuclear Instrumentation Hydrogen Recombiner and Purge Control Containment Purge Spent Fuel Pool Cooling Condensate Liquid Radwaste Area Radiation Monitoring Station Air 4.4 4.6 CflUE1DE1 3.2 3.5 DEIH1LJI1
LWL1EOL 3.5 36 3.8 4.2 2.6 2.8 LJLLJE 2.5 2.9 EU 2.7 3.0 E1LEDLH1 3.0 3.1 1ULJD E1LEJLI EL1U El LI ODU El LI El EIUEl LID LI LI LiDDLI El El El El ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION:
IR 1<1 1<2 1<3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:
RO SRO 0011<2.03 Control Rod Drive 2.7 3.1
[] Q LI i:i El One-line diagram of power supplies to logic circuits Pressure, temperatures and flows Redundant sources of information on power level Containment pressure Containment evacuation signal Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
Loss of condensate pumps Radiation monitors Radiation theory, including sources, types, units and effects lAS Page 1 of 10/2612011 10:46PM
Abdity to make accurate, clear and conctsa verbal reports.
Ability to execute procedure steps.
Knowledge of conservative decision making practices Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
Knowledge of less than one hour technical specification action statements for systems.
Knowledge of the process for making changes to procedures Ability to control radiation releases.
Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of the emergency plan.
Knowledge of the R0s responsibilities in emergency plan implementation.
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:
(R 1<1 K2 1<3 K4 K5 KG Al A2 A3 A4 G TOPIC:
RO SRO G2.l.17 Conduct of operations 3.9 4.0 fl El El El [1 El El El El El lJ G2.1.20 Conduct of operations 4.6 4.6 El El El El El El El El El El ll G2.1.39 Conductof operations 3.6 4.3 fl C] El El El El El El El El SJ G2.2.1 Equipment Control 4.5 4.4 El El El El El El El El El El ll G2.2.39 Equipment Control 3.9 El El El El El El LI El El El lJ G2.2.6 Equipment Control 3.0 3.6 El El El El El El El El El El fl G2.3.1 I Radiation Control 3.8 4.3 El El El El El El El El El El J G2.3.7 Radiation Control 3.5 3.6 El El El El El El El El El El ll G2.4.29 Emergency Procedures/Plans 3.1 4.4
[1 [1 El El El El El El El El Il G2.4.39 Emergency Procedures/Plans 3.9 3.8 El El El El El El El El El El l1 Page 1 of 1 10/26/2011 10:46PM
SRO T1G1 PWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO DLlOflOflflDDU ai 2.9 4.6 4.6 EDflEDflDOI 3.9 3.8 UU1DUELüD 3.6 4.5 3.2 4.4 DDDDOUDDU FORM ES-401-2 TOPIC:
Inadequate core coding Calculation of expected vahies of fI in the loop with RCP secured Ability to execute procedure steps.
Ability to use plant computer to evaluate system or component status.
Knowledge of conditions end limitations in the facility license.
Facility conditions and sdection of appropriate procedures during thnormal and emergency operations.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
008AA2.30 Pressurizer Vapor Space Accident / 3 015AA2.07 RCP Maltunctioris /4 025AG2.1.20 Loss of RHR System / 4 054AG2.1.19 Loss of Main Feedwater/4 058AG2.a38 Loss of DC Pcmer /6 BEO4EA2.1 Inadequate Heat Transfer - Loss of Secondary Heat Sink /4 Page 1 of 1 10/2612011 10:46PM
SRO Ti G2 PWR EXAMINATION OUTLINE IR K1K2K3K4K5K6AIA2A3A4G RO SRO 3.8 4.0 ELL1 4.5 4.6 ES-401, REV9 KA NAME I SAFETY FUNCTION:
001 AG2.1.32 Continuous Rod Withdrawal / 1 028AA2.10 Pressurizer Level Malfunction /2 BEO3EA2.2 Inadequate Subcooling Margin / 4 BE14EG2.4.2 EOP Enclosures FORM ES-401-2 TOPIC:
Ability to explain and apply all system limits and precautions.
Whether the automatic mode for PZR level control is functioning improperly, necessity of shift to manual modes Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
Page 1 of 1 10/26/2011 10:46 PM
SRO T2G1 PWR EXAMINATION OUTUNE iR K1 1(2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.8 4.3 1JJ 2.5 2.9 3.4 3.8 LJDOJ1JJ 3.3 4.0 4.0 4.7 UUOL1LJ FORM ES-401-2 TOPIC:
Knowledge of operational implications of EOP warnings, cautions and notes.
Overpressurization of the waste gas vent header pump failure or improper operation Knowledge of the specific bases for EOPs.
Knowledge of limiting conditions for operations and safety limits.
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
006G2.4.20 Emergency Core Cooling 007A2.04 Pressurizer Relief/Quench Tank 061 A2.08 Auxiliary/Emergency Feedwater 063G2.4.18 DC Electrical Distribution 064G2.2.22 Emergency Diesel Generator Page 1 of 1 10/26/2011 10:46 PM
SRO T2G2 PWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 2.9 3.2 3.2 4.2 jFJJfl 3.4 4.7 ES-401, REV9 KA NAME / SAFETY FUNCTION:
01 6A2.02 Non-nuclear Instrumentation 017G2.2.25 In-core Temperature Monitor 068G2.2.40 Liquid Radwaste FORM ES-401-2 TOPIC:
Loss of power supply Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Ability to apply technical specifications for a system.
Page 1 of 1 10/26/2011 10:46PM
ES-401, REV 9 SRO T3 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 G2.l.43 Conduct of operations 4.1 4.3
[]
fl Li [] Li [ Z1 gj Ability to use procedures to determine the effects on reactivity of plant changes G2.2.l 5 Equipment Control 3.9 4.3
[]
Li Li Li
[] Li Ability to determine the expected plant configuration using design and configuration control documentaion G2.2.40 Equipment Control 3.4 4.7 Li Li Li Li Li Li Li Ability to apply technical specifications for a system.
G2.3.14 Radiation Control 3.4 3.8 Li Li Li Li Li Li Li Li Li Li Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 Li Li Li Li Li Li Li Li Li Li Knowledge of radiation exposure limits under normal and emergency conditions G2.4.19 Emergency Procedures/Plans 3.4 4.1 Li Li Li Li Li Li Li Li Li Li Knowledge of EOP layout, symbols and icons.
G2.4.44 Emergency Procedures/Plans 2.4 4.4 Li LI Li Li Li Li Li LI LI El Il Knowledge of emergency plan protective action recommendations.
Page 1 of 1 10/26/2011 10:46PM
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
6/11112 Examination Level:
I Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-120, U3 SFP Boron and Volume Change Conduct of Operations D, R Calculation G 2.1.23 (4.34.4)
(Both) (20 mm)
Admin-127, Diverse verification of reactor Conduct of Operations N,R power G 2.1.45 (4.34.3)
(RO Only) (20 mm)
Equipment Control Admin-202, Determine SSF RCMUP Operability M,R G 2.2.42 (3.9/4.6)
(RO Only) (15 mm)
Radiological Control Admin-331, GWD Tank Release paperwork G 2.3.11 (3.8/4.3)
N,R (Both) (15 mm)
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 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination:
6111112 Examination Level:
I Administrative Topic Type Describe activity to be performed (see Note)
Code*
Admin-120, U3 SFP Boron and Volume Change Conduct of Operations D, R Calculation G 2.1.23 (4.3/4.4)
(Both) (20 mm)
Conduct of Operations Admin-141, Calculation of Primary to G 2.1.7 (4.4/4.7)
M,R Secondary Leak Rate and Unit Shutdown Requirements (SRO only) (16 mm)
Admin-211, Determine Tech Spec and SLC Equipment Control D,R requirements for inoperable ADV flowpath G 2.2.40 (3.4/4.7)
(SRO only) (20 mm)
Radiological Control N,R Admin-331, GWD Tank Release paperwork G2.3.11 (3.8/4.3)
(Both) (15 mm)
Admin-410, Determine Emergency Emergency Plan Classification Upgrade and Protective Action G 2.4.41 (2.9/4.6)
D,R Recommendations (SRO only) (20 mm)
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)
r 3
ES-301 Control R ni/1nP1ait Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I LI SRO-U LI Operating Test No.:
I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function a.
CR0-I 08, Recover a Dropped Rod OP/i/All 105/019, End. 4.15 (Recovery Of Dropped/Misaligned D, A, S 1
Safety Or Regulating Control Rod with Diamond In Automatic)
[KA: APE 005 AA2.03 (3.5/4.4)]_(15_mm) b.
CRO-208, Sample the Pressurizer and Respond to Indications of RCS Leakage N, A, 5 2
OP/i/A/i 103/004 End. 4.15 (Pzr Sampling)
[KA: SYS 002 A2.01 (4.3/4.4)]_(15_mm) c.
CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES)
M, A, EN, L, 3
[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5 d.
CRO-408, Start Fourth Reactor Coolant Pump OP/i/Ni 103/006 End. 4.4 (Starting 1 B2 RCP)
D, A, P, L, S 4P
[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm) e.
CRO-410, Remove Feedwater Pump From Hand Jack D, S 4S OP/i/A/i i06/002B End. 4.12 (Taking 1A FDWPT Off Hand Jack) [KA: SYS 059 A2.li (3.0*3.3*)] (15 mm) f.
CRO-604, Energizing MFB From CT-4 Using Live Bus N, L, S Transfer OP/0/N1106/019 End. 4.11 (Energizing MFB From 6
CT-4 Using Live Bus Transfer)
[KA: SYS 062 A4.01 (3.3/3.1)]_(15_mm) g.
CRO-703, Bypass ES Subsystem 2 N, S, OP/i/Ni 105/014 End. 4.9 (Removal and Restoration of ES 7
Channels)
[KA: SYS 016 A4.01 (2.9*/2.8*)]_(10_mm) h.
CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S AP/i/Ni700/13 (Dam Failure) 8
[KA: SYS 075 A2.Oi (3.0*/3.2)j (15 mm)
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.
NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, L, R 2
EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)
[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm) j.
NLO-032, Aligning Vacuum Pumps to a Units Vacuum System D, E 4S AP/27 End. 5.1 (Main Vacuum Pump Alignment)
[KA: APE 051 G2.1.20 (4.6/4.6)] (10 mm) k.
NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power)
D, A, E 7
[KA: BW/A02 AAI.1 (4.0/3.8)] (16 mm)
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 I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 / 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 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 (P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA 1I1I1 (S)imulator
ES-301 Controoirftln-Plarit Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I SRO-U Operating Test No.:
I 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-I 08, Recover a Dropped Rod OP/i/All 105/019, End. 4.15 (Recovery Of Dropped/Misaligned D, A, 5 1
Safety Or Regulating Control Rod with Diamond In Automatic)
[KA: APE 005 AA2.03 (3.5/4.4)] (15 mm) b.
CRO-208, Sample the Pressurizer and Respond to Indications of RCS Leakage N, A, 5 2
OP/1/A11103/004 End. 4.15 (Pzr Sampling)
[KA: SYS 002 A2.01 (4.3/4.4)] (15 mm) c.
CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES)
M, A, EN, L, 3
[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5 d.
CRO-408, Start Fourth Reactor Coolant Pump OP/1/A111031006 End. 4.4 (Starting 1B2 RCP)
D, A, P, L, S 4P
[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm) e.
CRO-410, Remove Feedwater Pump From Handjack D, S 4S OP/I/Ni 1061002B End. 4.12 (Taking 1A FDWPT Off Handjack)
[KA: SYS 059 A2.1 1 (3.0*3.3*)] (15 mm) f.
CRO-604, Energizing MFB From CT-4 Using Live Bus N, L, S Transfer OP/0/A11106/019 End. 4.11 (Energizing MFB From 6
CT-4 Using Live Bus Transfer)
[KA: SYS 062 A4.0i (3.3/3.1)] (15 mm) g.
N/A h.
CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S AP/1/N1700/13 (Dam Failure) 8
[KA: SYS 075 A2.Ol (3.0*/3.2)] (15 mm)
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
I.
NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, L, R 2
EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)
[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm) j.
NLO-032, Aligning Vacuum Pumps to a Units Vacuum System D, E 4S AP/27 End. 5.1 (Main Vacuum Pump Alignment)
[KA: APE 051 G2.1.20 (4.6/4.6)] (10 mm) k.
NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power)
D, A, E 7
[KA: BW/A02 AAI.1 (4.0/3.8)] (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 / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 /
1 (EN)gineered safety feature
- I I 1 (control room system)
(L)ow-Power I Shutdown 1 I I I 1
(N)ew or (M)odified from bank including 1 (A) 2 I 2 I 1
(P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:
Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I SRO-U Operating Test No.:
i 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.
b.
c.
CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES)
M, A, EN, L, 3
[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5 d.
CRO-408, Start Fourth Reactor Coolant Pump 0P111A111031006 End. 4.4 (Starting 1B2 RCP)
D, A, P, L, S 4P
[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm) e.
f.
g.
h.
CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S API1/A11700/13 (Dam Failure) 8
[KA: SYS 075 A2.01 (3.0*13.2)] (15 mm)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
I.
NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, R 2
EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)
[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm) j.
N/A k.
NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power)
D, A, E 7
[KA: BW/A02 AA1.1 (4.0/3.8)] (16 mm)
All RD 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 RD / SRO-l I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9/8/4 (E)mergency or abnormal in-plant 1 /
1 /
1 (EN)gineered safety feature
- /
/ 1 (control room system)
(L)ow-Power / Shutdown I I I I 1
(N)ew or (M)odified from bank including 1 (A) 2 /
2 I 1
(P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA (S)imulator