ML14091A139

Initial Exam 2013-301 Draft Administrative Documents

ML14091A139
Person / Time
Site:	Farley
Issue date:	04/01/2014
From:	Division of Reactor Safety II
To:	Southern Nuclear Operating Co
References
Download: ML14091A139 (18)

Text

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total 1

18 6

2 9

4

1.

Emergency &

Abnormal Plant Evolutions Tier Totals N/A N/A 27 10 1

28 5

2 10 3

2.

Plant Systems Tier Totals 38 8

1 2

3 4

10 1

2 3

4 7

3. Generic Knowledge and Abilities Categories

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 ATier 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 that are not included on the outline should be added. Refer to section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.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 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..

3 3

3 3

3 3

2 1

2 1

2 1

5 4

5 4

5 4

2 3

2 3

3 2

3 3

2 2

3 1

1 0

1 1

1 1

1 1

1 1

3 4

2 4

4 3

4 4

3 3

4 2

2 3

1 3

2 2

2 3

3 6

2 2

5 5

10 3

2 2

1 3

18 27 38 9

28 10 4

3 5

8 2

1 4

4

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Trip - Stabilization - Recovery

/ 1 Occurrence of a reactor trip 007EA2.06 4.3 4.5 Pressurizer Vapor Space Accident / 3 Thermodynamics and flow characteristics of open or leak-ing valves 008AK1.01 3.2 3.7 Small Break LOCA / 3 S/Gs 009EK2.03 3

3.3 Large Break LOCA / 3 Pumps 011EK2.02 2.6 2.7 RCP Malfunctions / 4 Abnormalities in RCP air vent flow paths and/or oil cooling system 015AA2.02 2.8 3

Loss of Rx Coolant Makeup / 2 Reason for changing from manual to automatic control of charging flow valve controller 022AK1.04 2.9 3

Loss of RHR System / 4 RCS/RHRS cooldown rate 025AA1.01 3.6 3.7 Loss of Component Cooling Water / 8 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

026AG2.4.30 2.7 4.1 Steam Gen. Tube Rupture / 3 Prevention of secondary PORV cycling 038EK3.02 4.4 4.5 Loss of Main Feedwater / 4 Status of MFW pumps regulating and stop valves 054AA2.05 3.5 3.7 Loss of Off-site Power / 6 Actions contained in EOP for loss of offsite power 056AK3.02 4.4 4.7 Page 1 of 2 6:24 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Loss of Nuclear Svc Water / 4 Flow rates to the components and systems that are serviced by the SWS; interactions among the components 062AA1.07 2.9 3

Loss of Instrument Air / 8 Ability to identify post-accident instrumentation.

065AG2.4.3 3.7 3.9 Generator Voltage and Electric Grid Disturbances / 6 Actions contained in abnormal operating procedures for voltage and grid disturbances 077AK3.02 3.6 3.9 LOCA Outside Containment / 3 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE04EA1.1 4.0 4.0 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

we05EG2.4.2 4.5 4.6 Loss of Emergency Coolant Recirc. / 4 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE11EK2.1 3.6 3.9 Steam Line Rupture - Excessive Heat Transfer / 4 Components, capacity, and function of emergency systems.

WE12EK1.1 3.4 3.8 Page 2 of 2 6:24 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Continuous Rod Withdrawal / 1 Reactor tripped breaker indicator 001AA2.01 4.2 4.2 Fuel Handling Accident / 8 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

036AG2.1.7 4.4 4.7 Steam Generator Tube Leak / 3 Use of steam tables 037AK1.01 2.9 3.3 Loss of Condenser Vacuum / 4 Loss of steam dump capability upon loss of condenser vacuum 051AK3.01 2.8 3.1 Accidental Liquid RadWaste Rel. / 9 Radioactive-liquid monitors 059AK2.01 2.7 2.8 Control Room Evac. / 8 ED/G 068AK2.07 3.3 3.4 High Reactor Coolant Activity / 9 Failed fuel-monitoring equipment 076AA1.04 3.2 3.4 RCS Overcooling - PTS / 4 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects we08EG2.4.34 4.2 4.1 Containment Flooding / 5 Desired operating results during abnormal and emergency situations.

WE15EA1.3 2.8 3.0 Page 1 of 1 6:24 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Coolant Pump RCP lube oil and bearing lift pumps 003A3.05 2.7 2.6 Chemical and Volume Control RCP seal injection 004K3.08 3.6 3.8 Residual Heat Removal Pressure transient protection during cold shutdown 005A2.02 3.5 3.7 Emergency Core Cooling Relationship between ECCS flow and RCS pressure 006K5.06 3.5 3.9 Pressurizer Relief/Quench Tank Method of forming a steam bubble in the PZR 007K5.02 3.1 3.4 Component Cooling Water CCW pump, including emergency backup 008K2.02 3.0 3.2 Pressurizer Pressure Control Heater failures 010A2.01 3.3 3.6 Reactor Protection Reactor trip breakers 012A4.06 4.3 4.3 Engineered Safety Features Actuation Ability to use plant computer to evaluate system or component status.

013G2.1.19 3.9 3.8 Containment Cooling Containment humidity 022A1.03 3.1 3.4 Containment Cooling Automatic containment isolation 022K4.03 3.6 4.0 Page 1 of 3 6:25 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Ice Condenser Upper and lower doors of the ice condenser 025K6.01 3.4 3.6 Containment Spray Containment spray pumps 026K2.01 3.4 3.6 Main and Reheat Steam RMS 039K1.09 2.7 2.7 Main Feedwater MFW turbine trip indication 059A4.01 3.1 3.1 Main Feedwater 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 059G2.2.44 4.2 4.4 Auxiliary/Emergency Feedwater Recognition of leakage, using sump level changes 061A3.05 2.5 2.5 Auxiliary/Emergency Feedwater Relationship between AFW flow and RCS heat transfer 061K5.01 3.6 3.9 AC Electrical Distribution Major system loads 062K3.01 3.5 3.9 DC Electrical Distribution Battery capacity as it is affected by discharge rate 063A1.01 2.5 3.3 Emergency Diesel Generator ESFAS controlled or actuated systems 064K3.02 4.2 4.4 Emergency Diesel Generator Air receivers 064K6.07 2.7 2.9 Page 2 of 3 6:25 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Process Radiation Monitoring Detector failure 073A2.02 2.7 3.2 Process Radiation Monitoring Ability to recognize system parameters that are entry-level conditions for Technical Specifications 073G2.2.42 3.9 4.6 Service Water Reactor building closed cooling water 076K2.04 2.5 2.6 Service Water Automatic opening features associated with SWS isolation valves to CCW heat exchanges 076K4.03 2.9 3.4 Instrument Air Sensor air 078K1.01 2.8 2.7 Containment Vacuum breaker protection 103K4.01 3.0 3.7 Page 3 of 3 6:25 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Level Control PZR heaters 011K2.02 3.1 3.2 Rod Position Indication Reasons for differences between RPIS and step counter 014K5.01 2.7 3.0 In-core Temperature Monitor Sensors and detectors 017K6.01 2.7 3.0 Containment Purge Radiation levels 029A1.02 3.4 3.4 Spent Fuel Pool Cooling Adequate SDM (boron concentration) 033K4.05 3.1 3.3 Steam Generator Faulted or ruptured S/Gs 035A2.01 4.5 4.6 Main Turbine Generator ESFAS 045K1.19 3.4 3.6 Condenser Air Removal Automatic diversion of CARS exhaust 055A3.03 2.5 2.7 Waste Gas Disposal ARM and PRM systems 071K3.05 3.2 3.2 Station Air Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 079G2.4.34 4.2 4.1 Page 1 of 1 6:26 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 Conduct of operations Ability to make accurate, clear and concise logs, records, status boards and reports.

G2.1.18 3.6 3.8 Conduct of operations Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.1.5 2.9 3.9 Equipment Control Knowledge of the process for managing troubleshooting activities.

G2.2.20 2.6 3.8 Equipment Control Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.2.25 3.2 4.2 Radiation Control Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.12 3.2 3.7 Radiation Control Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.13 3.4 3.8 Radiation Control Knowledge of radiation exposure limits under normal and emergency conditions G2.3.4 3.2 3.7 Emergency Procedures/Plans Knowledge of operational implications of EOP warnings, cautions and notes.

G2.4.20 3.8 4.3 Emergency Procedures/Plans Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

G2.4.23 3.4 4.4 Emergency Procedures/Plans Knowledge of the emergency plan.

G2.4.29 3.1 4.4 Page 1 of 1 6:27 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Vapor Space Accident / 3 Knowledge of limiting conditions for operations and safety limits.

008AG2.2.22 4.0 4.7 ATWS / 1 CVCS centrifugal charging pump operating indication 029EA2.04 3.2 3.3 Loss of Main Feedwater / 4 Occurrence of reactor and/or turbine trip 054AA2.01 4.3 4.4 Station Blackout / 6 Knowledge of surveillance procedures.

055EG2.2.12 3.7 4.1 Loss of DC Power / 6 125V dc bus voltage, low/critical low, alarm 058AA2.02 3.3 3.6 Generator Voltage and Electric Grid Disturbances / 6 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

077AG2.4.9 3.8 4.2 Page 1 of 1 6:27 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Emergency Boration / 1 When boron dilution is taking place 024AA2.06 3.6 3.7 Loss of Condenser Vacuum / 4 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

051AG2.1.7 4.4 4.7 SI Termination / 3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE02EA2.1 3.3 4.2 Degraded Core Cooling / 4 Knowledge of system purpose and or function.

we06EG2.1.27 3.9 4

Page 1 of 1 6:28 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Chemical and Volume Control Loss of PZR level (failure mode) 004A2.02 3.9 4.2 Emergency Core Cooling Knowledge of limiting conditions for operations and safety limits.

006G2.2.22 4.0 4.7 Main Feedwater Failure of feedwater regulating valves 059A2.12 3.1 3.4 Emergency Diesel Generator 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 064G2.2.44 4.2 4.4 Process Radiation Monitoring Erratic or failed power supply 073A2.01 2.5 2.9 Page 1 of 1 6:28 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Control Rod Drive Rod-misalignment alarm 001A2.17 3.3 3.8 Hydrogen Recombiner and Purge Control LOCA condition and related concern over hydrogen 028A2.02 3.5 3.9 Waste Gas Disposal Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

071G2.4.9 3.8 4.2 Page 1 of 1 6:29 PM 9/14/2012

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 Conduct of operations Ability to make accurate, clear and concise logs, records, status boards and reports.

G2.1.18 3.6 3.8 Conduct of operations Knowledge of the stations requirements for verbal communication when implamenting procedures G2.1.38 3.7 3.8 Equipment Control Knowledge of pre-and post-maintenance operability requirements.

G2.2.21 2.9 4.1 Equipment Control Ability to track Technical Specification limiting conditions for operations.

G2.2.23 3.1 4.6 Radiation Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.14 3.4 3.8 Radiation Control Ability to aprove release permits G2.3.6 2.0 3.8 Emergency Procedures/Plans Knowledge symptom based EOP mitigation strategies.

G2.4.6 3.7 4.7 Page 1 of 1 6:31 PM 9/14/2012

ES-301-1 Administrative Topics Outline Facility: Farley Nuclear Plant Date of Examination: June 17, 2013 Examination Level: RO X Operating Test Number: FA2013-301 Administrative Topic (see Note)

Type Code*

Describe activity to be performed

a. A.1.a Conduct of Operations R, N

Title:

Evaluate Inoperable Plant Computer Based Alarms and perform STP-37.0, Power Distribution Surveillance Plant Computer Inoperable.

This will be a task to determine Acceptance Criteria by comparing GRPI to DRPI, and evaluating AFD against the COLR limits.

G2.1.37 4.3/4.6

b. A.1.b Conduct of Operation R, D Title : Determine the minimum amount and duration required for an RCS boration.

Given an RCS Temp < 525ºF and an emergency boration flowrate, determine the amount of boration required & the time of boration per AOP-27.0. [calculate per step 9.3]

G2.1.7 4.4/4.7 G2.1.25 3.9/4.2 G2.1.20 4.6/4.6

c. A.2 Equipment Control R, N

Title:

RCP seal injection leakage test.

This will be a task to determine / calculate RCP SI leakage and evaluate Acceptance Criteria per STP-8.0, RCP Seal Injection Leakage Test.

G2.2.12 3.7/4.1

d. A.3 Radiation Control R, D

Title:

Determine if total personnel exposure for a Containment entry is acceptable without exceeding the dose margin limits and which route allows the lowest exposure.

G2.3.4 3.2/3.7 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 4

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) 2 (N)ew or (M)odified from bank ( 1) 2 (P)revious 2 exams ( 1; randomly selected) 0

ES-301-1 Administrative Topics Outline Facility: Farley Nuclear Plant Date of Examination: June 17, 2013 Examination Level: SRO X Operating Test Number: FA2013-301 Administrative Topic (see Note)

Type Code*

Describe activity to be performed

a. A.1.a Conduct of Operations R, N

Title:

Evaluate Inoperable Plant Computer Based Alarms and perform STP-37.0, Power Distribution Surveillance Plant Computer Inoperable.

This will be a task to determine Acceptance Criteria by comparing GRPI to DRPI, and evaluating AFD against the COLR limits, then evaluate Tech Specs to determine if action is required. (SRO)

G2.1.37 4.3/4.6

b. A.1.b Conduct of Operation R, D Title : Determine the minimum amount and duration required for an RCS boration.

Given an RCS Temp < 525ºF and an emergency boration flowrate, determine the amount of boration required & the time of boration per AOP-27.0 [calculate per step 9.3]

G2.1.7 4.4/4.7 G2.1.25 3.9/4.2 G2.1.20 4.6/4.6

c. A.2 Equipment Control R, N

Title:

RCP seal injection leakage test.

This will be a task to determine calculate RCP SI leakage and evaluate Acceptance Criteria per STP-8.0, RCP Seal Injection Leakage Test, then evaluate Tech Specs. (SRO)

G2.2.12 3.7/4.1

d. A.3 Radiation Control R, D Determine if total personnel exposure for a Containment entry is acceptable without exceeding the dose margin limits and which route allows the lowest exposure.

G2.3.4 3.2/3.7

e. A.4 Emergency Procedures/Plan SRO ONLY R, D

Title:

Classify an Emergency Event per NMP-EP-110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

G2.4.41 SRO 4.6 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 5

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) 3 (N)ew or (M)odified from bank ( 1) 2 (P)revious 2 exams ( 1; randomly selected) 0

ES-301-2 Control Room/In-Plant Systems Outline Facility:

Farley Nuclear Plant Date of Examination: June 17, 2013 Exam Level: RO SRO-I SRO-U-Operating Test No.:

FA2013301 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-065C : Perform an Emergency Boration per ESP-0.1 024AA2.02 RO-3.9 SRO-4.4 024AA2.01 RO-3.8 SRO-4.1 A, D, L, S 1

b.

CRO-406A: Verify CTMT Isolation Phase A Is Actuated And Aligned 013A4.01 RO-4.5 SRO-4.8 A, D, L, S 2

c.

CRO-333C: Perform The Required Actions For Transfer to Simultaneous Cold Leg and Hot Leg Recirculation 006A4.07 RO-4.4 SRO-4.4 011EA1.11 RO-4.2 SRO-4.2 A, D, L, S 3

d.

CRO-043: (modified) Start the 1C RCP.

003A1.01 RO-2.9 SRO-2.9 003A2.02 RO-3.7 SRO-3.9 A, L, M, S 4P

e.

CRO-239: (modified) Align Service Water to the AFW System 061A1.05 RO-3.6 SRO-3.7 061K1.07 RO-3.6 SRO-3.8 061K4.01 RO-4.1 SRO-4.2 L, M, S 4S

f.

CRO-406E :Two Train Verification Of ECCS Equipment 064A4.06 RO-3.9 SRO-3.9 A, D, S, L 6

g.

CRO-071: Lower The Refueling Cavity Level Using The Residual Heat Removal System 034A1.02 RO-2.9 SRO-3.7 D, S, L 8

h.

CRO-395D, Display Individual CETC values 017A4.01 RO-3.8 SRO-4.1 D, S, P RO ONLY 7

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

SO-344:Start up an Instrumentation Inverter 062A2.03 RO-2.9 SRO-3.4 057AA1.01 RO-3.7 SRO-3.7 D

6

j.

SO-New: Start a DDFP and MDFP Manually 086A4.01 RO-3.3 SRO-3.3 E, N 8

k.

SO-386: (Modified) Conduct a Waste Gas Release 071A2.02 RO-3.3 SRO-3.6 071A4.09 RO-3.3 SRO-3.5 071A4.26 RO-3.1 SRO-3.9 A, E, M, R 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 (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 (6/6)

(0/0) 9 / 8 (7/6) 1 / 1 (2/2)

- / -

1 / 1 (7/7) 2 / 2 (4/4) 3 / 3 (randomly selected) (1/0) 1 / 1 (1/1)

(8/7)