ML12356A430

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301 Draft Administrative Documents
ML12356A430
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/17/2012
From:
Division of Reactor Safety II
To:
Duke Energy Corp
References
ES-401, Rev 9, ES-401-2 50-413/12-301, 50-414/12-301
Download: ML12356A430 (19)
v • d • e


Text

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Catawba Date of Exam: September 2012 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

1 1

2 2

1 2

4 4

5 5

4 5

2 2

3 3

3 2

3 2

2 3

3 1

1 1

1 1

0 1

1 1

1 1

3 3

4 4

4 2

4 3

3 4

4 3

2 2

2 3

2 2

1 3

3 6

2 2

5 5

10 2

3 18 27 38 9

28 10 4

3 5

8 3

1 2

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 Breakers, relays and disconnects 007EK2.02 2.6 2.8 Pressurizer Vapor Space Accident / 3 Controllers and positioners 008AK2.03 2.5 2.4 Small Break LOCA / 3 Natural circulation and cooling, including reflux boiling 009EK1.01 4.2 4.7 Large Break LOCA / 3 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

011EG2.4.9 3.8 4.2 RCP Malfunctions / 4 Consequences of an RCPS failure 015AK1.02 3.7 4.1 Loss of Rx Coolant Makeup / 2 Speed demand controller and running indicators (positive displacement pump) 022AA1.04 3.3 3.2 Loss of RHR System / 4 Reactor building sump 025AK2.05 2.6 2.6 ATWS / 1 Verifying a reactor trip; methods 029EK3.01 4.2 4.5 Loss of Main Feedwater / 4 Effects of feedwater introduction on dry S/G 054AK1.02 3.6 4.2 Loss of Off-site Power / 6 ESF bus synchronization select switch to close bus tie breakers 056AA1.02 4

3.9 Loss of Vital AC Inst. Bus / 6 Safety injection tank pressure and level indicators 057AA2.01 3.7 3.8 Page 1 of 2 8:53 AM 10/3/2011

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 The length of time after the loss of SWS flow to a component before that component may be damaged 062AA2.06 2.8 3.1 Loss of Instrument Air / 8 Cross-over to backup air supplies 065AK3.04 3

3.2 Generator Voltage and Electric Grid Disturbances / 6 Ability to verify that the alarms are consistent with the plant conditions.

077AG2.4.46 4.2 4.2 LOCA Outside Containment / 3 Normal, abnormal and emergency operating procedures associated with (LOCA Outside Containment).

WE04EK3.2 3.4 4.0 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Ability to apply technical specifications for a system.

we05EG2.2.4 3.4 4.7 Loss of Emergency Coolant Recirc. / 4 Desired operating results during abnormal and emergency situations.

WE11EA1.3 3.7 4.2 Steam Line Rupture - Excessive Heat Transfer / 4 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

WE12EA2.2 3.4 3.9 Page 2 of 2 8:54 AM 10/3/2011

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 Dropped Control Rod / 1 Controls and components necessary to recover rod 003AA1.02 3.6 3.4 Inoperable/Stuck Control Rod / 1 Breakers, relays, disconnects and control room switches 005AK2.02 2.5 2.6 Emergency Boration / 1 Actions contained in EOP for emergency boration 024AK3.02 4.2 4.4 Loss of Source Range NI / 7 Satisfactory source-range/intermediate-range overlap 032AA2.04 3.1 3.5 Loss of Intermediate Range NI / 7 Termination of startup following loss of intermediate-range instrumentation 033AK3.01 3.2 3.6 ARM System Alarms / 7 Detector limitations 061AK1.01 2.5 2.9 Plant Fire On-site / 8 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 067AG2.4.34 4.2 4.1 High Reactor Coolant Activity / 9 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

076AG2.1.23 4.3 4.4 Natural Circ. / 4 Operating behavior characteristics of the facility.

WE09EA1.2 3.6 3.9 Page 1 of 1 8:57 AM 10/3/2011

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 Adequate cooling of RCP motor and seals 003K4.04 2.8 3.1 Reactor Coolant Pump RCP seals and seal water supply 003K6.02 2.7 3.1 Chemical and Volume Control Interface between HPI flow path and excess letdown flow path 004K1.25 2.7 3.2 Chemical and Volume Control Pressure response in PZR during in-and-out surge 004K5.44 3.2 3.4 Residual Heat Removal Nil ductility transition temperature (brittle fracture) 005K5.01 2.6 2.9 Emergency Core Cooling ESF control panel 006A4.06 4.4 4.4 Pressurizer Relief/Quench Tank Components which discharge to the PRT 007A3.01 2.7 2.9 Pressurizer Pressure Control PRT temperature and pressure during PORV testing 010A3.01 3.0 3.2 Pressurizer Pressure Control PZR heaters 010K2.01 3.0 3.4 Reactor Protection Trip setpoint adjustment 012A1.01 2.9 3.4 Engineered Safety Features Actuation Sensors and detectors 013K6.01 2.7 3.1 Page 1 of 3 8:57 AM 10/3/2011

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 Containment Cooling Containment humidity 022A1.03 3.1 3.4 Containment Cooling Fan motor over-current 022A2.01 2.5 2.7 Containment Spray Containment humidity 026A1.04 3.1 3.3 Containment Spray Prevention of path for escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover) 026K4.09 3.7 4.1 Main and Reheat Steam Malfunctioning steam dump 039A2.04 3.4 3.7 Main Feedwater Ability to execute procedure steps.

059G2.1.20 4.6 4.6 Main Feedwater Ability to apply technical specifications for a system.

059G2.2.40 3.4 4.7 Auxiliary/Emergency Feedwater AFW diesel driven pump 061K2.03 4.0 3.8 Auxiliary/Emergency Feedwater Feed line voiding and water hammer 061K5.05 2.7 3.2 AC Electrical Distribution Ability to verify that the alarms are consistent with the plant conditions.

062G2.4.46 4.2 4.2 DC Electrical Distribution Major breakers and control power fuses 063A4.01 2.8 3.1 Page 2 of 3 8:57 AM 10/3/2011

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 DC Electrical Distribution Battery discharge rate 063A4.03 3.0 3.1 Emergency Diesel Generator D/G cooling water system 064K1.02 3.1 3.6 Process Radiation Monitoring Letdown isolation on high-RCS activity 073K4.02 3.3 3.9 Service Water Closed cooling water 076K3.01 3.4 3.6 Service Water RHR components, controls, sensors, indicators and alarms, including rad monitors 076K3.05 3.0 3.2 Containment Loss of containment integrity under normal operations 103K3.02 3.8 4.2 Page 3 of 3 8:57 AM 10/3/2011

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 Reactor Coolant NIS 002K1.12 3.5 3.6 Nuclear Instrumentation Redundant sources of information on power level 015K4.10 3.2 3.5 Non-nuclear Instrumentation Separation of control and protection circuits 016K5.01 2.7 2.8 Hydrogen Recombiner and Purge Control Hydrogen recombiner power setting, determined by using plant data book 028A2.01 3.4 3.6 Spent Fuel Pool Cooling Radiation monitoring systems 033A1.02 2.8 3.3 Fuel Handling Equipment Radiation levels 034A4.01 3.3 3.7 Liquid Radwaste Automatic isolation 068A3.02 3.6 3.6 Waste Gas Disposal ARM and PRM systems 071K3.05 3.2 3.2 Circulating Water Emergency/essential SWS pumps 075K2.03 2.6 2.7 Station Air Knowledge of limiting conditions for operations and safety limits.

079G2.2.22 4.0 4.7 Page 1 of 1 8:59 AM 10/3/2011

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 interpret reference materials such as graphs, monographs and tables which contain performance data.

G2.1.25 3.9 4.2 Conduct of operations Knowledge of primary and secondary chemistry limits G2.1.34 2.7 3.5 Conduct of operations Knowledge of procedures, guidelines or limitations associated with reactivity management G2.1.37 4.3 4.6 Equipment Control Knowledge of the process for managing maintenance activities during shutdown operations.

G2.2.18 2.6 3.8 Equipment Control 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 G2.2.44 4.2 4.4 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of general guidelines for EOP usage.

G2.4.14 3.8 4.5 Emergency Procedures/Plans Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

G2.4.2 4.5 4.6 Emergency Procedures/Plans Knowledge of the parameters and logic used to assess the status of safety functions G2.4.21 4.0 4.6 Page 1 of 1 8:59 AM 10/3/2011

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 RCP Malfunctions / 4 Ability to verify that the alarms are consistent with the plant conditions.

015AG2.4.46 4.2 4.2 Steam Gen. Tube Rupture / 3 Ability to verify that the alarms are consistent with the plant conditions.

038EG2.4.46 4.2 4.2 Loss of Main Feedwater / 4 Differentiation between loss of all MFW and trip of one MFW pump 054AA2.02 4.1 4.4 Station Blackout / 6 RCS core cooling through natural circulation cooling to S/G cooling 055EA2.02 4.4 4.6 Loss of DC Power / 6 Knowledge of the purpose and function of major system components and controls.

058AG2.1.28 4.1 4.1 Generator Voltage and Electric Grid Disturbances / 6 Operational status of engineered safety features 077AA2.07 3.6 4.0 Page 1 of 1 9:00 AM 10/3/2011

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 Continuous Rod Withdrawal / 1 Reactor power and its trend 001AA2.04 4.2 4.3 Pressurizer Level Malfunction / 2 Ability to locate and operate components, including local controls.

028AG2.1.30 4.4 4.0 Control Room Evac. / 8 Knowledge of the specific bases for EOPs.

068AG2.4.18 3.3 4.0 High Reactor Coolant Activity / 9 CVCS letdown flow rate indication 076AA2.05 2.2 2.5 Page 1 of 1 9:03 AM 10/3/2011

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 Emergency Core Cooling Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

006G2.4.50 4.2 4.0 Engineered Safety Features Actuation Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

013G2.4.2 4.5 4.6 Main Feedwater Feeding a dry S/G 059A2.04 2.9 3.4 Auxiliary/Emergency Feedwater Back leakage of MFW 061A2.06 2.7 3.0 Instrument Air Knowldege of how AOPs are u 078G2.4.8 3.8 4.5 Page 1 of 1 9:04 AM 10/3/2011 sed in conjuction with EOPS

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 Rod Position Indication Loss of LVDT 014A2.06 2.6 3.0 In-core Temperature Monitor Core damage 017A2.02 3.6 4.1 3.9 4

Page 1 of 1 9:04 AM 10/3/2011 034G2.1.27 Fuel Handling Equipment Knowledge of system purpose &/or function.

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 G2.1.

2.5 3.2 Conduct of operations Knowledge of the fuel handling responsibilities of SRO's G2.1.35 2.2 3.9 Equipment Control Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.1 4.5 4.4 Equipment Control Knowledge of the process for making design or operating changes to the facility G2.2.5 2.2 3.2 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Radiation Control Ability to use radiation monitoring systems G2.3.5 2.9 2.9 Emergency Procedures/Plans Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

G2.4.23 3.4 4.4 Page 1 of 1 9:05 AM 10/3/2011 23 Ability to perform specific system &

integrated plant procedures in all modes

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility:

Catawba Nuclear Station Date of Examination: Sept. 2012 Examination Level: RO SRO LI Operating Test Number:

Administrative Topic Tvne

, 5 Describe activity to be performed (See Note) wove Calculate Reactor Vessel Head Venting Time Conduct of Operations DR G2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.9 Determine NCP Start Requirements. (2008 NRC)

Conduct of Operations DR G2.1.32, Ability to explain and apply system limits and precautions. 3.8 Containment Floor and Equipment Sump Input Rate Equipment Control MR Determination G2.2.12, Knowledge of surveillance procedures. 3.7 Determine Radiation Protection Requirements for Work in SFP Demineralizer Room. (2006 NRC)

Radiation Control DR G2.3.7, Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 Emergency Procedures/Plan NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility:

Catawba Nuclear Station Date of Examination: Sept. 2012 Examination Level: RO LI SRO Operating Test Number: 1 Administrative Topic Tvne

Describe activity to be performed (See Note)

Code Determine if Shift Manning Requirements are Met.

Conduct of Operations MR G2. 1.5, Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. 3.9 Determine NCP Start Requirements. (2008 NRC).

Conduct of Operations DR G2. 1.32, Ability to explain and apply system limits and precautions. 4.0 Review the Containment Floor and Equipment Sump Input Rate Determination.

Equipment Control MR G2.2.42, Ability to recognize system parameters that are entry-level conditions for Technical Specifications. 4.6 Determine Radiation Protection Requirements for Work in SFP Demineralizer Room. (2006 NRC)

Radiation Control DR G2.3.7, Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.6 Upgrade an Emergency Classification and Complete an Emergency Notification Form.

Emergency Procedures/Plan DR G2.4.41, Knowledge of the emergency action level thresholds and classifications. 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 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, Page 22 of 27

ES-301 Control Room!ln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO SRO-l [1 SRO-U [1 Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code*

Fn

a. NCP Seal Injection Verification Test N S 2

003A4.O1 Manually operate/monitor in the CR: Seal injection 3.3/3.2

b. Transfer to Hot Leg Recirc.

A D EN L S P 3

EA1.11 Monitor long term cooling of core for LBLOCA 4.2/4.2 c.

RCCA Movement Test wlTwo Dropped Rods A,N,S I

001A4.08 Monitor mode select for CRDS and control panel 3.7/3.4

d. Verify Proper H2 Control Operation A D L S 5

028A4.01 Operate/monitor HRPS controls 4.0/4.0

e. Verify Blackout Buses Energized A N S 6

EPEO55EAI.06 Operate/monitor restoration of power 4.1/4.5 f.

Initiate a VQ Release (Containment Air Release)

D N S 7

029A1.03 Monitor changes in containment pressure 3.0/3.3

g. Control Tavg Using SIG PORVs in Manual A D S 4S 041A4.08 Operate/monitor steam dump valves 3.0/3.1
h. Place Second Train RHR (ND) in Service L N S 4P 005A4.01 Operate/monitor RHR pumps 3.6/3.4 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.

Start lB MG Set D,L,P 001A2.10 Control loss of power to one or more MG sets 3.4/3.9 j.

Break Main Condenser Vacuum Locally - Unit 2 D E 8

045A1.06 Monitor expected response of secondary parameters following TIG trip 3.3/3.7

k. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF)

D L R 5

G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0 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 I SRO-U (A)lternate path 4-6 I 4-6

/ 2-3 (C)ontrol room (D)irectfrom bank

<9/

<8 I <4 (E)mergency or abnormal in-plant 1 I

> 1 I

> I (EN)gineerecl safety feature I

/

1 (L)ow-Power / Shutdown

> I I

> I I

> I (N)ew or (M)odified from bank including 1(A)

> 2 I

> 2

/

> I (P)revious 2 exams

< 3

< 3 I

< 2 (randomly selected)

(R)CA

>1/

>1 /I

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO [1 SRO-l SRO-U El Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System I JPM Title Type Code*

a. NCP Seal Injection Verification Test N S 2

003A4.O1 Manually operate/monitor in the CR: Seal injection 3.3/3.2

b. Transfer to Hot Leg Recirc.

A D EN L S P 3

EA1.11 Monitor long term cooling of core for LBLOCA 4.2/4.2 c.

RCCA Movement Test wlTwo Dropped Rods A,N,S 001A4.08 Monitor mode select for CRDS and control panel 3.7/3.4

d. Verify Proper Ff2 Control Operation A 0 L S 5

028A4.01 Operate/monitor HRPS controls 4.0/4.0

e. Verify Blackout Buses Energized A N S 6

EPEO55EAI.06 Operate/monitor restoration of power 4.1/4.5 f.

NIA

g. Control Tavg Using SIG PORVs in Manual A D S 4S 041A4.08 Operate/monitor steam dump valves 3.0/3.1
h. Place Second Train RHR (ND) in Service L N S 4P 005A4.01 Operate/monitor RHR pumps 3.6/3.4 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.

Start lB MG Set D,L,P 001A2.10 Control loss of power to one or more MG sets 3.4/3.9 j.

Break Main Condenser Vacuum Locally - Unit 2 D E 8

045A1.06 Monitor expected response of secondary parameters following T/G trip 3.3/3.7

k. Operate 2A H2 Igniters from Standby Shutdown Facility (SSF)

D L R 5

G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0 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 I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrom bank

<9/

<8

/ <4 (E)mergency or abnormal in-plant I /

1

/

I (EN)gineered safety feature I

/

I (L)ow-Power / Shutdown

> I I

> 1

/

> I (N)ew or (M)odified from bank including I (A) 2 /

2 I

I (P)revious 2 exams

< 3

< 3 I

< 2 (randomly selected)

(R)CA 1I

?1 I1 (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2012 Exam Level: RO [1 SRO-l [1 SRO-U Operating Test Number: 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*

Fn a.

N/A

b. Transfer to Hot Leg Recirc.

A D EN L S P 3

EAI.11 Monitor long term cooling of core for LBLOCA 4.2/4.2 c.

N/A d.

N/A

e. Verify Blackout Buses Energized A N S 6

EPEO55EA1.06 Operate/monitor restoration of power 4.1/4.5

f.

N/A g.

N/A h.

N/A In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U) i.

StartlBMGSet DLP 001A2.10 Control loss of power to one or more MG sets 3.4/3.9 j.

Break Main Condenser Vacuum Locally - Unit 2 D E 8

045A1.06 Monitor expected response of secondary parameters following T!G trip 3.3/3.7

k. Operate 2A H2 lgniters from Standby Shutdown Facility (SSF)

D L R 5

G2.1.30 Ability to locate/operate components, including local controls. 4.4/4.0

© 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 I SRO-l / SRO-U (A)lternate path 4-6 /

4-6 I 2-3 (C)ontrol room (D)irectfrom bank 9I 8

/ <4 (E)mergency or abnormal in-plant I /

1 I

> I (EN)gineered safety feature I

I ? I (L)ow-Power I Shutdown

> I I

> I I

> 1 (N)ew or (M)odified from bank including 1(A) 2 /

2 I

I (P)revious 2 exams

< 3

< 3 I

< 2 (randomly selected)

(R)CA 1/

?1 1>1 (S)imulator ES-301, Page 23 of 27

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