ML111960033
| ML111960033 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/02/2011 |
| From: | NRC/RGN-II |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-348/11-301, 50-349/11-301, ES-401, ES-401-2 | |
| Download: ML111960033 (17) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: FARLEY Date of Exam: MAY 201 1 ROKIACajpoyPcnts SRO-Only_Points Tier Group KK KK K KAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 333 33 318 3 3 6 Emergency &
Abnormal 2 N/A I 2 N/A 1 9 2 2 4 Evokitions Tier Totals 4 5 5 4 5 4 27 5 5 10 2.
1 22332232333 28 3 J1 2 5 Plant 2 11111111110 10 0 2 I 3 Systems Tier Totals 3 3 4 4 3 3 4 3 4 4 3 38 5 3 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-4o1 for guidance regarding the elimination of inappropriate KJA 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 KJA5 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 D.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.
ES-401, REV 9 T1G1 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 009EA2.01 Small Break LOCA /3 4.2 4.8 El El El El El El El El El El Actions to be taken, based on RCS temperature and pressure, saturated and superheated 011 EK2.02 Large Break LOCA /3 2.6 2.7 El ElElElElElEl Pumps 01 5AK1 .04 RCP Malfunctions /4 2.9 3.1 El El El El El El El El LI El Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow 025AK1 .01 Loss of RHR System / 4 39 43 El El El El El El El El El El Loss of RHRS during all modes of operation 026AA1 .06 Loss of Component Cooling Water /8 2.9 2.9 El El El [ El El Control of flow rates to components cooled by the CCWS 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 029EK3.12 ATWSI 1 El El l El El El El El El El El Actions contained in EOP for ATWS 038EG2.4.l Steam Gen. Tube Rupture / 3 4.6 4.8 El El El El El El El El El El Knowledge of EOP entry conditions and immediate action steps.
055EA2.06 Station Blackout /6 3.7 4.1 El El El El El El El El El El Faults and lockouts that must be cleared prior to re energizing buses I) 056AG2.22r Loss of Off-site Power /6 4.0 4.7 El El El El El El El El El El Knowledge of limiting conditions for operations and safety limits.
057AA1 .04 Loss of Vital AC Inst. Bus / 6 3.5 3.6 El El El El El El El El El El RWST and VCT valves Page 1 of 2 9/15/2010 1:09PM
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:
lRO SRO 058AK3.01 Loss of DC Power / 6 3.4 3.7 Use of dc control power by D/Gs 062AA2.01 Loss of Nuclear Svc Water! 4 2.9 3.5 j Location of a leak in the SWS 065AK3.08 Loss of Instrument Air / 8 3.7 3.9 Actions contained in EOP for loss of instrument air 077AG2.4.45 Generator Voltage and Electric Grid 4.1 4.3 Ability to prioritize and interpret the significance of each Disturbances / 6 annunciator or alarm.
WEO4EK2.1 LOCA Outside Containment /3 3.5 3.9 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEO5EK1 .3 Inadequate Heat Transfer Loss of
- 3.9 4.1 LI LI LI LI LI LI LI LI LI LI Annunciators and conditions indicating signals, and Secondary Heat Sink! 4 remedial actions associated with the (Loss of Secondary Heat Sink).
WE11EA1.3 Loss of Emergency Coolant Recirc. ! 4 3.7 4.2 LI LI LI LI LI 7 L LI LI LI Desired operating results during abnormal and emergency situations.
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ES-401, REV 9 T1G2 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 001 AA1 .03 Continuous Rod Withdrawal / 1 3.4 3.2 Boric acid pump control switch 036AK3.02 Fuel Handling Accident / 8 2.9 3.6 El El El Interlocks associated with fuel handling equipment 037AK1 .01 Steam Generator Tube Leak / 3 2.9 3.3 i El El El El El El El El El El Use of steam tables 051 AA2.02 Loss of Condenser Vacuum / 4 3.9 4.1 El El El El El El El El El El Conditions requiring reactor and/or turbine trip 068AA2.04 Control Room Evac. /8 3.7 4 El El El El El El El 1 El El El S/G pressure 076AK2.0l High Reactor Coolant Activity / 9 2.6 3 El El El El El El El El El El Process radiation monitors WEO3EK2.l LOCA Cooldown - Depress. / 4 3.6 4.0 El 1 El El El El El El El El El Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.
WEO8EK3.2 RCS Overcooling - PTS / 4 3.6 4.0 El El El El El El El El El El Normal, abnormal and emergency operating procedures associated with (Pressurized Thermal Shock).
wel5EG2.4.2 Containment Flooding / 5 4.5 4.6 El El El El El El El El El El Knowledge of system set pojnts, interlocks and automatic actions associated with entry conditions.
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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 003K6.14 Reactor Coolant Pump 2.6 2.9 Starting requirements 004A3.l 1 Chemical and Volume Control 3.6 3.4 Charging/letdown 004K3.04 Chemical and Volume Control 3.7 3.9 J RCPS 005K5.05 Residual Heat Removal 2.7 3.1 El Plant response during solid plant: pressure change due to the relative incompressibility of water 006K2.01 Emergency Core Cooling 3.6 3.9 ECCS pumps 007A4.10 Pressurizer Relief/Quench Tank 3.6 3.8 Recognition of leaking POR V/code safety 008A2.Q Component Cooling Water 2.5 2.8 El El Consequences of high or low CCW flow rate and tempera- ture; the flow rate at which the CCW standby pump will start 01 0K1 .06 Pressurizer Pressure Control 2.9 3.1 El El El El El El El El El El CVCS 012A3.05 Reactor Protection 3.6 3.7 El El El El El El El El El El Single and multiple channel trip indicators 01 3K5.02 Engineered Safety Features Actuation 2.9 3.3 El El El El El El El El El El Safety system logic and reliability 022A1 .02 Containment Cooling 3.6 3.8 El El El El El El El El El El Containment pressure Page lof 3 9/15/2010 1:09PM
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 RD SRO 022A3.0l Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation 026G2.4.50 Containment Spray 4.2 4.0 Li Li Li Li Li ri Li Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
026K4.01 Containment Spray 4.2 4.3 Source of water for CSS, including recirculation phase after LOCA 039G2.1 .20 Main and Reheat Steam 4.6 4.6 Ability to execute procedure steps.
059A2.12 Main Feedwater 3.1 3.4 Failure of feedwater regulating valves 059K1 .02 Main Feedwater 3.4 3.4 AFW system O
061 K4.-1 Auxiliary/Emergency Feedwater 2.6 2.9 Li Li Li Li Li fl Li Li Li Reset of MFW reactor trip logic 061 K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 Li Li Li Li Li Li Li Li Li Li Controllers and positioners 062K3.03 AC Electrical Distribution 3.7 3.9 Li Li Li Li Li Li Li Li Li Li DC system 063A1 .01 DC Electrical Distribution 2.5 3.3 Li Li Li Li Li Li Li Li Battery capacity as it is affected by discharge rate 063K3.02 DC Electrical Distribution 3.5 3.7 Li Li Li Li Li Li Li Li Li Li Components using DC control power Page2of 3 9/15/2010 1:09PM
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 064A1 .04 Emergency Diesel Generator 2.8 2.9 Crankcase temperature and pressure 073A4.02 Process Radiation Monitoring 3.7 3.7 LI DEED LILIELILI Radiation monitoring system control panel 076A4.02 Service Water 2.6 2.6 LIED El El LI LI El LI SWS valves o8 076K2, Service Water 2.5 2.6 LI LI LI LI LI LI LI El El Reactor building closed cooling water 078G2.1 .32 Instrument Air 3.8 4.0 El ELIDE LI LI LI LI LI Ability to explain and apply all system limits and precautions.
103K4.04 Containment 2.5 3.2 LI El l LI El El LI LI El El Personnel access hatch and emergency access hatch Page 3 of 3 9/15/2010 1:09PM
ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
001 K6. Control Rod Drive 2.9 3.2 Purpose and position switch of alarm for high flux at shutdown 011 A4.0l Pressurizer Level Control 3.5 3.2 Charging pump and flow controls 015K5.l0 Nuclear Instrumentation 2.8 3.0 Ex-core detector operation 028K2.01 Hydrogen Recombiner and Purge 2.5 2.8 J Hydrogen recombiners Control 041 A3.03 Steam Dump/Turbine Bypass Control 2.7 2.8 Steam flow 045A1 .06 Main Turbine Generator 3.3 3.7 LI Expected response of secondary plant parameters following T/G trip 055K1 .06 Condenser Air Removal 2.6 2.6 LI LI LI LI LI LI LI LI LI LI PRM system 056A2.04 Condensate 2.6 2.8 LI LI LI LI LI LI LI LI LI LI Loss of condensate pumps 072K4.01 Area Radiation Monitoring 3.3 3.6 LI LI LI LI LI LI LI LI LI LI Containment ventilation isolation 075K3.07 Circulating Water 3.4 3.5 LI LI [] LI LI LI LI LI LI LI LI ESFAS Page 1 of 1 9/15/2010 1:09 PM
ES-401, REV 9 T3 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 Sf0 G2.1.25 Conductof operations 3.9 4.2 LI LI LI LI LI LI LI LI LI LI Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
G2.l.34 Conductof operations 2.7 3.5 LI LI LI LI LI LI LI LI LI LI Knowledge of primary and secondary chemistry limits G2.2.13 Equipment Control 4.1 4.3 LI LI LI LI LI LI LI LI LI LI Knowledge of tagging and clearance procedures.
G2.2.39 Equipment Control 3.9 4.5 LI LI LI LI LI LI LI LI LI LI Knowledge of less than one hour technical specification action statements for systems.
G2.3.13 Radiation Control 3.4 3.8 LI LI LI LI LI LI LI LI LI LI Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 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 G2.4.23 Emergency Procedures/Plans 3.4 4.4 LI LI LI LI LI LI LI LI LI LI Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
G2.4.25 Emergency Procedures/Plans 3.3 3.7 LI LI LI LI LI LI LI LI LI LI Knowledge of fire protection procedures.
G2.4.46 Emergency Procedures/Plans 4.2 4.2 LI LI LI LI LI LI LI LI LI LI Ability to verify that the alarms are consistent with the plant conditions.
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ES-401, REV 9 SRO T1G1 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 008AG2.4.41 Pressurizer Vapor Space Accident / 3 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.
054AG2.l .23 Loss of Main Feedwater /4 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.
- L 0 055EA2.08 Station Blackout / 6 3.9 4.7 J Actions necessary to restore power 058AG2.2.25 Loss of DC Power! 6 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
077AA2.l0 Generator Voltage and Electric Grid 3.6 3.8 Generator overheating and required actions Disturbances / 6 WE05EA2.l Inadequate Heat Transfer Loss of
- 3.4 4.4 El El El El fl El El Facility conditions and selection of appropriate Secondary Heat Sink / 4 procedures during abnormal and emergency operations.
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ES-401, REV 9 SRO 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:
j RO SRO 001 AA2.QW Continuous Rod Withdrawal / 1 4.4 4.6 El Uncontrolled rod withdrawal from available indications d 06lAA0 J ARM System Alarms / 7 3.2 4.1 Required actions if alarm channel is out of service 2
069AG2.2 Loss of CTMT Integrity / 5 3.8 3.9 fl (multi-unit license) Knowledge of the design, procedural and operational differences between units.
074EG2.4.20 mad. Core Cooling / 4 3.8 4.3 El El El El El El El El El El Knowledge of operational implications of EOP warnings, cautions and notes.
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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: R Kl K2 K3 k4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 006G2.4.9 Emergency Core Cooling 3.8 4.2 Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
012A2.05 Reactor Protection 3.1 3.2 Faulty or erratic operation of detectors and function generators 039A2.0 Main and Reheat Steam 2.4 2.7 Decrease in turbine load as it relates to steam escaping from relief valves o2 078A2.0l Instrument Air 2.4 2.9 DDE Air dryer and filter malfunctions 36 103G2.120 Containment 4.4 4.0 DD Ability to locate and operate components, including local controls.
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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:
pL AC SAC 028A2.ø1 Hydrogen Recombiner and Purge 3.4 3.6 Hydrogen recombiner power setting, determined by using Control plant data book 035A2.01 Steam Generator 4.5 4.6 Faulted or ruptured S/Gs 071 G2.2.38 Waste Gas Disposal 3.6 4.5 Knowledge of conditions and limitations in the facility license.
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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 G2.2.12 Equipment Control 3.7 4.1 Knowledge of surveillance procedures.
G2.2.18 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during shutdown operations.
G2.3.12 Radiation Control 3.2 3.7 fl Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.28 Emergency Procedures/Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.
G2.4.44 Emergency Procedures/Plans 2.4 4.4 Li Li Li LI LI Li Li Li Li Knowledge of emergency plan protective action recommendations.
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ES-301-1 Administrative Topics Outline Facility: Farley Nuclear Plant Date of Examination: May 9, 2011 Examination Level: RO X Sf0 X Operating Test Number: FA2011301 Administrative Topic Type Describe activity to be performed (see Note) Code*
A1.1.A
Title:
Critical Safety Function Status Tree Evaluation Conduct of Operations
Description:
Students will be provided a listing of plant parameters.
M, R SRO +RO This will require manually evaluating each status tree to determine the challenges to each tree and identify the highest priority challenge.
Al .2S
Title:
Determine Active License Status Conduct of Operations
Description:
The SRO will have to evaluate the status of 3 P0s to D, R determine their license status for sitting the control board position.
SRO only K/A: G2.1.4 (SRO3.8)
A2.l .A
Title:
A) Determine Isolation Boundaries for a CCW Equipment Control Pump (RO & SRO)
SRO +RO part A B) Identify the Required Tech Specs for the SRO part B only Condition. (SRO only)
Description:
Part A: Determine Isolation Boundaries for a CCW Pump N, R (mechanically) with a check valve that is spraying water and has to be isolated immediately; Determine the appropriate boundary points and required positions of components to safely isolate the ccw pump and; Part B: determine the required Tech Specs for the condition.
G2.2.41 (R0-3.5 SRO-3.9)
G2.2.40 (SRO-4.7)
A3.1 .A M, R
Title:
Determine Dose Rates, Projected Dose, and Radiation Control Dress out requirements
Description:
in preparation to adding oil to a RCP, the applicant will SRO +RO have to review the RWP and determine dose rates encountered, total projected dose, if the job can be done based on the dose and RWP provided and dressout requirements G2.3.4 (P0-3.2 SRO-3.7)
G2.3.7 (P0-3.5 SRO-3.6)
A4.1 .R P, M, S
Title:
Make Initial Notifications As Required for an Emergency Plan Emergency
Description:
Activate the ERO callout system and ensure RO only transmission of the EN form.
G2.4.43 (P0-3.2 SRO-3.8)
A4.1 .S N, R
Title:
Provide an updated PAR Emergency
Description:
PAR upgrade where a General Emergency already exists. The wind direction changes which requires a follow up Procedures/Plan notification and PAR upgrade.
SRO only G2.4.44 (SRO-4.4) Time critical JPM.
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) [0/1]
(N)ew or (M)odified from bank ( 1) [4/4]
(P)revious 2 exams ( 1: randomly selected) rum
ES-301-2 Control Roomlln-Plant Systems Outline Facility: Farlev Nuclear Plant Date of Examination: May 9, 201 1 Exam Level: RO fEl SRO-l fEl SRO-U-E1 Operating Test No.: FA2O1 1301 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. CRO-033A: Perform Corrective Actions For Recovery Of A A,D,E,S 1 Misaligned Rod OO3AA1 .02 P0-3.6 SRO-3.4 001 A2.1 1 RO-4.4 SRO-4.7 001A4.06 RO-2.9 SRO-3.2
- b. CRO-343C: Establish Letdown as required following a Spurious A, M, S 2 Letdown Isolation Signal and Stabilize Pressurizer Level 004A2.07 RO-3.4 SRO-3.7 004A4.05 P0-3.6 SRO-3.1 C. CRO-333D modified: Perform The Required Actions For Cold A, M, E, S 3 Leg Recirculation during a Large Break LOCA 011 EA1.11 RO-4.2 SRO-4.2
- d. CR0-NEW: Stop the RCP with a degraded seal per the A, E, L, N, S 4P guidance of step 8 of AOP-4.1 and complete the necessary lOAs of AOP-4.0 upon stopping the RCP.
003A2.02 R0-3.7 SRO-3.9 0151017AA1.05 RO-3.8 SRO-3.8 0151017AA1.08 RO-3.0 SRO-2.9
022A2.05 R0-3.1 SRO-3.5 W/EO15EA1.1__RO-2.9_SRO-3.0
- f. CRO-415A, Start the station Blackout DIG D, E, S 6 064A4.06 P0-3.9 SRO-3.9 055EA1 .02 P0-4.3 SRO-4.4
017A4.01 RO-3.8 SRO-4.1 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
- i. S0-590, Place The SJAE Filtration Unit In Service during a D, E 3 Steam Generator Tube Leak 037AA1.02 R0-3.1 SRO-2.9
- j. SO-449, Supply EMERGENCY AIR to SG ARVs from D, E 8 Emergency Air Compressors during a Loss of instrument air APEO65AA1 .04_R0-3.5 SRO-3.4
- k. S0-95B, Align the Recycle Holdup Tank To Drain To Waste D, R 9 Holdup Tank 068K1 .07 RO-2.7 SRO-2.9
@ 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 (A)lternate path 4-6 [5/5]
(C)ontrol room [0]
(D)irect from bank 8 [7/6]
(E)mergency or abnormal in-plant 1 [8/8]
(EN)gineered safety feature - (control room system) [N/A]
(L)ow- Power! Shutdown 1 [1]
(N)ew or (M)odified from bank including 1 (A) 2 [4/4]W/ 3(A)
(P)revious 2 exams 3 (randomly selected) [0]
(R)CA 1 [1/1]
(S)imulator [8/7]