ML111881094
| ML111881094 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/06/2011 |
| From: | NRC/RGN-II |
| To: | Duke Energy Corp |
| References | |
| 50-269/11-301, 50-270/11-301, 50-287/11-301, ES-401, ES-402 | |
| Download: ML111881094 (22) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: OCONEE Date of Exam: MAY 2011 ROKACapolyPomts SPO-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 18 3 3 6 Emergency &
Abnormal 2 1. .J_ L N/A 2 J_ N/A 1 9 2 2 4 Evolutkns TierTotals 5 4 5 5 4 4 27 5 5 10 1 32332323232 28 2 3 5 2.
Plant 2 11 111 01 111 1 10 0 1 2 3 Systems Tier Totals 4 3 4 4 3 3 3 4 3 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 KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the KIA 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.
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:
Reactor Trip Stabilization - Recovery 4 4.6 Actions contained in EQP for reactor trip El El
/1 008AK3.05 Pressurizer Vapor Space Accident / 3 4 4.5 ECCS termination or throttling criteria OO9EK1 .01 Small Break LOCA / 3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011 EK2.02 Large Break LOCA / 3 2.6 2.7 Pumps 015AG2.1.7 RCPMalfunctions/4 4.4 4.7 Abilitytoevaluateplantperformanceandmake operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
025AK1 .01 Loss of RHR System / 4 3.9 4.3 El Loss of RHRS during all modes of operation 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 El El El El El El El El El El Controllers and positioners Malfunction / 3 029EK2.06 ATWS / 1 2.9 3.1 El El El El El El El El El El Breakers, relays, and disconnects.
038EA1 .10 Steam Gen. Tube Rupture! 3 3.7 3.7 El El El El El El El El El El Control room radiation monitoring indicators and alarms 054AA1 .03 Loss of Main Feedwater / 4 3.5 3.7 El El El El El El El El El El AFW auxiliaries, including oil cooling water supply 055EA2.06 Station Blackout!6 3.7 4.1 Faults and lockouts that must be cleared prior to re energizing buses Page 1 of 2 8/17/2010 9:47 AM
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 056AK1 .01 Loss of Off-site Power! 6 3.7 4.2 Principle of cooling by natural convection 058AG2.4.l 1 Loss of DC Power! 6 4.0 4.2 Knowledge of abnormal condition procedures.
062AA2.04 Loss of Nuclear Svc Water / 4 2.5 2.9 LI The normal values and upper limits for the temperatures of the components cooled by SWS 065AA2.05 Loss of Instrument Air! 8 3.4 4.1 LI When to commence plant shutdown if instrument air pressure is decreasing 077AA1 .05 Generator Voltage and Electric Grid 3.9 4.0 Engineered Safety Features Disturbances! 6 BEO4EK3.3 -
Inadequate Heat Transfer Loss of 4.2 3.8 Manipulation of controls required to obtain desired Secondary Heat Sink! 4 LI LI LI LI LI LI LI LI LI LI operating results during abnormal, and emergency situations.
BEO5EG2.4.6 -
Steam Line Rupture Excessive Heat 3.7 4.7 Knowledge symptom based EOP mitigation strategies.
Transfer / 4 LI LI LI LI LI LI LI LI LI LI Page 2 of 2 8!17!2010 9:47 AM
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 003AA2.03 Dropped Control Rod / 1 3.6 3.8 Dropped rod, using in-core/ex-core instrumentation in-core or loop temperature measurements 005AK2.0l Inoperable/Stuck Control Rod / 1 2.5 2.5 Controllers and positioners 028AK1 .01 Pressurizer Level Malfunction /2 2.8 3.1 PZR reference leak abnormalities 032AA1 .01 Loss of Source Range NI / 7 3.1 3.4 Manual restoration of power 076AK3.06 High Reactor Coolant Activity / 9 3.2 3.8 Actions contained in EOP for high reactor coolant activity BA03AA1 .1 Loss of NNI-Y / 7 4 4 LI Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
BA05AK3.l Emergency Diesel Actuation / 6 3.2 3.4 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
BEO3EG2.4.45 Inadequate Subcooling Margin / 4 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.
BEO9EK1 .3 Natural Circ. / 4 3.5 3.5 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Cooldown).
Page 1 of 1 8/17/2010 9:47AM
ES-401, REV 9 T2G1 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 SAC 003A4.02 Reactor Coolant Pump 2.9 2.9 RCP motor parameters 004A1.07 Chemical and Volume Control 2.7 3.1 Maximum specified letdown flow 004K5.37 Chemical and Volume Control 2.6 3.1 Effects of boron saturation on ion exchanger behavior 005K4.01 Residual Heat Removal 3.0 3.2 Overpressure mitigation system 006K1 .08 Emergency Core Cooling 3.6 3.9 CVCS 007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 EJ Quench tank cooling 008A4.10 Component Cooling Water 3.1 3.1 Conditions that require the operation of two CCW coolers 008K1.03 ComponentCooling Water 2.8 3.0 PRMS 010K2.03 Pressurizer Pressure Control 2.8 3.0 Indicator for PORV position 012K3.02 Reactor Protection 3.2 3.3 T/G 013K6.01 Engineered Safety Features Actuation 2.7 3.1 Sensors and detectors Page 1 of 3 8/17/2010 9:47 AM
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 022K2.01 Containment Cooling 3.0 3.1 Containment cooling fans 026A2.08 Containment Spray 3.2 3.7 Safe securing of containment spray when it can be done) 026K3.0l Containment Spray 3.9 4.1 j CCS 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 059A4.03 Main Feedwater 2.9 2.9 Feedwater control during power increase and decrease 061 A2.06 Auxiliary/Emergency Feedwater 2.7 3.0 Back leakage of MFW 061 K6.0l Auxiliary/Emergency Feedwater 2.5 2.8 Controllers and positioners 062G2.4.47 AC Electrical Distribution 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
063G2.4.2 DC Electrical Distribution 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 064A1 .01 Emergency Diesel Generator 3.0 3.1 ED/G lube oil temperature and pressure Page 2 of 3 8/17/2010 9:47 AM
ES-401, REV 9 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:
RO SRO 064K6.08 Emergency Diesel Generator 3.2 3.3 Fuel oil storage tanks 073A2.Ol Process Radiation Monitoring 2.5 2.9 Erratic or failed power supply 073K5.Ol Process Radiation Monitoring 2.5 3.0 Radiation theory, including sources, types, units and effects 076A3.02 Service Water 3.7 3.7 Emergency heat loads 078K1 .03 Instrument Air 3.3 3.4 Containment air 103K4.06 Containment 3.1 3.7 U U U Containment isolation system Page3of 3 8/17/2010 9:47AM
ES-401, REV 9 T2G2 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 OO1A1.06 Control Rod Drive 4.1 4.4 El El El El El El [J Reactor power 011 K1 .05 Pressurizer Level Control 3.4 3.5 Reactor regulating system 014G2.1.20 Rod Position Indication 4.6 4.6 Ability to execute procedure steps.
017K3.0l In-core Temperature Monitor 3.5 3.7 Natural circulation indications 034A4.0l Fuel Handling Equipment 3.3 3.7 Radiation levels 041 A2.02 Steam Dump/Turbine Bypass Control 3.6 3.9 Steam valve stuck open 045A3.l 1 Main Turbine Generator 2.6 2.9 El El El El El El El El El El Generator trip 068K5.04 Liquid Radwaste 3.2 3.5 El El El El El El El El El El Biological hazards of radiation and the resulting goal of ALARA 075K2.03 Circulating Water 2.6 2.7 El El El El El El El El El El Emergency/essential SWS pumps 086K4.02 Fire Protection 3.0 3.4 El El El El El El El El El El Maintenance of fire header pressure Page 1 of 1 8/17/2010 9:47 AM
ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO G2.l .42 Conduct of operations 2.5 3.4 Knowledge of new and spent fuel movement procedures G2.l .8 Conduct of operations 3.4 4.1 Ability to coordinate personnel activities outside the control room.
G2.2.20 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.
G2.2.7 Equipment Control 2.9 3.6 Knowledge of the process for conducting special or infrequent tests G2.3.l 1 Radiation Control 3.8 4.3 El El El El El El El El El El Ability to control radiation releases.
G2.3.15 Radiation Control 2.9 3.1 El El El El El El El El El El Knowledge of radiation monitoring systems G2.3.7 Radiation Control 3.5 3.6 El El El El El El El El El El Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.32 Emergency Procedures/Plans 3.6 4.0 El El El El El El El El El El Knowledge of operator response to loss of all annunciators.
G2.4.39 Emergency Procedures/Plans 3.9 3.8 Knowledge of the ROs responsibilities in emergency plan implementation.
G2.4.8 Emergency Procedures/Plans 3.8 4.5 Knowledge of how abnormal operating procedures are used in conjunction with EOP5.
Page 1 of 1 8/17/2010 9:47AM
ES-401, REV 9 SRO 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:
Reactor Trip Stabilization - Recovery 4.3 4.6 Proper actions to be taken if the automatic safety func
/i tions have not taken place 009EG2.4.18 Small Break LOCA/3 3.3 4.0 Knowledge of the specific bases for EOPs.
015AA2.0l RCP Malfunctions / 4 3 3.5 Cause of RCP failure 040AA2.0l Steam Line Rupture - Excessive Heat 4.2 4.7 Occurrence and location of a steam line rupture from EJ Transfer! 4 pressure and flow indications 058AG2.2.22 Loss of DC Power! 6 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
062AG2.l .20 Loss of Nuclear Svc Water / 4 4.6 4.6 Ability to execute procedure steps.
Page 1 of 1 8/17/2010 9:47 AM
ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 037AG2.4.41 Steam Generator Tube Leak / 3 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
BAO4AA2.l Turbine Trip / 4 3.3 3.7 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
BAO8AG2.2.25 Refueling Canal Level Decrease / 8 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
BEO8EA2.l LOCA Cooldown - Depress. / 4 2.8 4.2 -
Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
Page 1 of 1 8/17/2010 9:47AM
ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 006G2.4.50 Emergency Core Cooling 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
007A2.02 Pressurizer Relief/Quench Tank 2.6 3.2 Abnormal pressure in the PRT 061 A2.03 Auxiliary/Emergency Feedwater 2.7 2.9 Flow rates expected from various combinations of AFW pump discharge valves 063G2.4.20 DC Electrical Distribution 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.
064G2.l .23 Emergency Diesel Generator Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Page 1 of 1 8/17/2010 9:47AM
ES-401, REV 9 SRO T2G2 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 01 6A2.01 Non-nuclear Instrumentation 3.0 3.1 Detector failure 01 7G2.l .7 In-core Temperature Monitor 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
068G2.l.32 Liquid Radwaste 3.8 4.0 Ability to explain and apply all system limits and precautions.
Page 1 of 1 8/17/2010 9:47AM
ES-401, REV 9 SRO T3 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 G2.l .35 Conduct of operations 2.2 3.9 Knowledge of the fuel handling responsibilities of SROs G2.2.15 Equipment Control 3.9 4.3 Ability to determine the expected plant configuration using design and configuration control documentaion G2.2.19 Equipment Control 2.3 3.4 Knowledge of maintenance work order. requirements.
G2.3.13 Radiation Control 3.4 3.8 El Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.29 Emergency Procedures/Plans 3.1 4.4 Knowledge of the emergency plan.
G2.4.9 Emergency Procedures/Plans 3.8 4.2 El El El El El El El El El El Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
Page 1 of 1 8/17/2010 9:47AM
ES-301 Administrative Topics Outline Form ES-301-1 May, 2011 Facility: Oconee Date of Examination: May, 2011 Examination Level: RO SRO Operating Test Number: I Administrative Topic Type Describe activity to be performed (see Note) Code*
Conduct of Operations D, R ADMIN-1 12 Calculate Requirements To
[KA G2.1 .25 (3.9/4.2)] Makeup To BWST (13 mm) Both Conduct of Operations D, R ADMIN-115 Calculate An Estimated Critical Boron Concentration
[KA G2.1.7 (4.4/4.7)]
RO only (15 mm)
Equipment Control M, R ADMIN-212 Determine LTOP Requirements
[KA G2.2.14 (3.9/4.3)] RO only (30 mm)
Radiation Control M, R ADMIN-305 Calculate the Maximum Permissible Stay Time Within Emergency
[KA G2.3.4 (3.2/3.7)] Dose Limits (EDLs)
(20 mm) Both 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 May, 2011 Facility: Oconee Date of Examination: May, 2011 Examination Level: RO El SRO Operating Test Number: i Administrative Topic Type Describe activity to be performed (see Note) Code*
Conduct of Operations D, R ADMIN-1 12 Calculate Requirements To
[KA G2.1 .25 (3.9/4.2)] Makeup To BWST (13 mm) Both Conduct of Operations M, R ADV1lN-124 Determine Minimum Shift Staffing Requirements
[KA G2.1.4 (3.3/3.8)]
SRO only (15 mm)
Equipment Control M, R ADMIN-213 SSF RCMUP Operability On Unit 3 .3.
[KA G2.2.12 (3.7/4.1)]
SRO only (15 mm)
Radiation Control M, R ADMIN-305 Calculate the Maximum Permissible Stay Time Within Emergency
[KA G2.3.4 (3.2/3.7)]
Dose Limits (EDLs)
(20 mm)
Both Emergency Plan D, R ADMIN-408 Determine Emergency Classification and Protective Action
[KA G2.4.38 (2.4/4.4)] Recommendations (20 mm) 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 Control Roomlln-Plant Systems Outline Form ES-301 -2 May, 2011 Facility: Oconee Date of Examination: May, 2011 Exam Level: RO SRO-l 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. CRO-108, Align Emergency Boration During an ATWS M,A,S EOP Rule 1 (ATWS/Unanticipated Nuclear Power 1 Production)
[KA: BW/E13 EA1.1_(3.4/3.2)1(5_mm)
- b. CRO-208, Remove IA Letdown Cooler from Service N, S 2 OP/1/A111041002 End. 4.5
[KA 004 G2.2.2_(4.6/4.1)]_(15_mm)
[KA: EPE-009 EK3.21 (4.2/4.5)] (12 mm) EN
- d. CRO-403, Start A Reactor Coolant Pump EDP End. 5.6, RCP Restart D, A, S, L 4P
[KA: 003 Al .01 (2.9/2.9)]_(15_mm)
. CRO-014, Depressurize SIGs and Feed With CBPs EOP, Rule 3 (Loss of Main or Emergency FDW) D, S, E, L 4S
[KA: APE-054 AA1.0l (4.5/4.4)]_(12_mm)
- f. CRO-501, Pump the Quench Tank OP/1/A/l 104/017 End. 4.1 (Pumping QT) N, S 5
[KA: 007 Al.01 (2.9/3.1)]_(10_mm)
- g. CRO-085, Adjust Radiation Monitor Setpoints OP/l&2/A/l 104/018, GWD System, End. 4.9 & 4.10 D, S 7 PT/0/A/230/01, Radiation Monitor Check
[KA: 073 A4.02_(3.7/3.7)]_(15_mm)
- h. CRO-Olla, Align Intake Canal for Recirculation on Dam Failure D, A, L, S 8 AP/13, Dam Failure
[KA: 075 G2.1.23 (4.3/4.4)]_(15_mm)
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. NLO-201, Secure the B DAC and Align for Standby FollowingaLossoflA N,A,E 8 OPIO/AIl 106/27 End. 4.35 (B Diesel Service Air Compressor Operation)
[KA: APE-065 AA1.04 (35*/34*)]_(12_mm)
- j. NLO-017, Align Cooling Water To HPIPs From Station ASWPs D, R, E 4S EOP End. 5.10 (Station ASW Pump Alignment)
[KA:_076 A2.01_(3.5*/3*7*)]_(16_mm)
- k. NLO-037, Place a Control Battery Charger in Service D 6 OP/1107/010, (Removal From Service and Restoration To Service of a Control Charger)
[KA: 063 K1.03 (2.9/3.5)]_(12_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 RD / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1 / 1 / 1 (N)ew or (M)odified from bank including 1 (A) 2/ 2/ 1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)
(R)CA (S)imulator
ES-301 Control Roomlln-Plant Systems Outline Form ES-301 -2 May, 2011 Facility: Oconee Date of Examination: May, 2011 Exam Level: RO D SRO-l 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 I JPM Title Type Code* Safety Function
- a. CRO-108, Align Emergency Boration During an ATWS M,A,S EOP Rule 1 (ATVVS/Unanticipated Nuclear Power 1 Production)
[KA: BW/E13 EAI.1 (3.4/3.2)]_(5_mm)
- b. CRO-208, Remove IA Letdown Cooler from Service N, S 2 OP/1/A/1104/002 End. 4.5
[KA 004 G2.2.2_(4.6/4.1)]_(15_mm)
[KA: EPEOO9 EK3.21 (4.2/4.5)] (12 mm)
- d. CRO-403, Start A Reactor Coolant Pump EOP End. 5.6, RCP Restart D, A, 5, L 4P
[KA: 003 A1.01_(2.9/2.9)]_(15_mm)
- e. CRO-014, Depressurize S/Gs and Feed With CBPs EOP, Rule 3 (Loss of Main or Emergency FDW) D, S, E, l 4S
[KA: APE-054 AA1.01 (4.5/4.4)]_(12_mm)
- f. CRO-501, Pump the Quench Tank OP/1/A/1104/017 End. 4.1 (Pumping QT) N, S 5
[KA: 007 A1.01 (2.9/3.1)]_(10_mm)
- g. N/A
- h. CRO-Olla, Align Intake Canal for Recirculation on Dam Failure D, A, L, 5 8 AP/13, Dam Failure
[KA: 075 G2.1.23_(4.3/4.4)]_(15_mm)
In-Plant Systems© (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i. NLO-201, Secure the B DAC and Align for Standby Following a Loss of IA N, A, F 8 OP/0/AIl 106/27 End. 4.35 (B Diesel Service Air Compressor Operation)
[KA: APEO65 AA1.04 (3 5*/34*)] (12 mm)
- j. NLO-O1 7, Align Cooling Water To HPIPs From Station ASWPs D, R, E 4S EOP End. 5.10 (Station ASW Pump Alignment)
[KA: 076 A2.01 (3 5*/3 7*)] (16 mm)
- k. NLO-037, Place a Control Battery Charger in Service D 6 OP/1107/010, (Removal From Service and Restoration To Service of a Control Charger)
[KA: 063 K1.03 (2.9/3.5)] (12 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 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 / 1 / 1 (N)ew or (M)odified from bank including 1 (A) 2I 2/ 1 (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 May, 2011 Facility: Oconee Date of Examination: May, 2011 Exam Level: RO SRO-l D SRO-L Operating Test No.:
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-108, Align Emergency Boration During an ATWS M,A,S EOP Rule 1 (ATWS/Unanticipated Nuclear Power Production)
[KA:_BW/E13 EA1.1_(3.4/3.2)1(5_mm)
- b. N/A
[KA: EPEOO9 EK3.21 (4.2/4.5)] (12 mm) EN
- d. NIA
- e. N/A
- f. N/A
- g. NIA
- h. CRO-Olla, Align Intake Canal for Recirc on Dam Failure D, A, L, S 8 AP/13, Dam Failure
[KA: 075 G2.1.23 (4.3/4.4)]_(15_mm)
In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. N/A
- j. NLO-017, Align Cooling Water To HPIPs From Station ASWPs D, R, E 4S EOP End. 5.10 (Station ASW Pump Alignment)
[KA: 076 A2.O1 (3*5*/37*)]_(16_mm)
- k. NLO-037, Place a Control Battery Charger in Service D 6 0P111071010, (Removal From Service and Restoration To Service of a Control Charger)
[KA: 063 K1.03 (2.9/3.5)]_(12_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 / SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 59/814 (E)mergency or abnormal in-plant 1 I? 1 / 1 (EN)gineered safety feature - I - / 1 (control room system)
(L)ow-Power / Shutdown 1 I? 1 I? 1 (N)ew or (M)odified from bank including 1 (A) 2I 2/ 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)
(R)CA (S)imulator