ML13336A395

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301 Draft Administrative Documents
ML13336A395
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 11/26/2013
From:
Duke Energy Carolinas
To:
NRC/RGN-II
References
50-413/13-301, 50-414/13-301
Download: ML13336A395 (19)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: CATAWBA Date of Exam: SEPTEMBER 2013 SRO-Only_Points Tier Group K K K KK KAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 3 3 3 3 3 v z 6

18 3 Emergency & /

Abnormal 2 j N/A 1 2 N/A j 9 2 2 4 an /

7 - /

5 ,

Evolutions Tier Totals 4 5 4 5 4 27 5 10

/ v V 1 32323332322 28 3- 2 5

2. , --

Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 0 2 1 3 Systems Tier Totals 4 3 4 3 4 4 4 3 4 3 2 38 5 3 8

3. Generic Knowledge and Abilities Categories 1

V 2

1I 4

]I 10 1 2 3 3 2L_2 3 -j-_____ 2 2 V 2-Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RD 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 RD 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 RD and SRO ratings for the RD 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 RD 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 I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

PC SRO 007EK1 .03 - -

Reactor Trip Stabilization Recovery 3.7 4 Reasons for closing the main turbine governor valve and I1 D

the main turbine stop valve after a reactor trip 008AK1 .01 Pressurizer Vapor Space Accident / 3 3.2 3.7 Thermodynamics and flow characteristics of open or leak- ing valves 009EG2.l .25 Small Break LOCA / 3 3.9 4.2 Ability to interpret reference materials such as graphs,

- monographs and tables which contain performance data.

O11EA1.14 Large Break LOCAI3 3.9 4.1 Subcooling margin monitors O15AA1.23 RCPMalfunctions/4 3.1 3.2 RCPvibration 022AA2.03 Loss of Rx Coolant Makeup / 2 3.1 3.6 Failures of flow control valve or controller 025AK1 .01 Loss of RHR System /4 3.9 4.3 Loss of RHRS during all modes of operation 026AK3.02 Loss of Component Cooling Water / 8 3.6 3.9 The automatic actions (alignments) within the CCWS V resulting from the actuation of the ESFAS 029EK3.1 1 ATWS / 1 4.2 4.3 Initiating emergency boration 040AK2.02 Steam Line Rupture Excessive Heat 2.6 2.6 Sensors and detectors Transferl4 054AG2.4.9 Loss of Main Feedwater / 4 3.8 4.2 Knowledge of low power / shutdown implications in Li Li Li Li Li Li Li Li Li Li accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 2 10/9/2012 8:06PM

ES-401, REV 9 T1G1 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:

RO SRO 056AA1 .25 Loss of Off-site Power! 6 2.9 2.9 Main steam supply valve control switch 062AG2.4.21 Loss of Nuclear Svc Water! 4 4.0 4.6 [ Knowledge of the parameters and logic used to assess the status of safety functions 065AA2.05 Loss of Instrument Air? 8 3.4 4.1 When to commence plant shutdown if instrument air pressure is decreasing 077AK3.02 Generator Voltage and Electric Grid 3.6 3.9 Actions contained in abnormal operating procedures for Disturbances? 6 voltage and grid disturbances WE04EK2.2 LOCA Outside Containment! 3 3.8 4.0 Facilitys heat removal systems, including primary

- coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WEO5EK2.1 -

Inadequate Heat Transfer Loss of 3.7 3,9 Components and functions of control and safety systems, Secondary Heat Sink? 4 . including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE1 1 EA2.2 Loss of Emergency Coolant Recirc. ! 4 4 4.2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Page 2 of 2 10?9?2012 8:06PM

ES-401, REV 9 T1G2 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 001 AK2.08 Continuous Rod Withdrawal! 1 31 3 Individual rod display lights and indications 036AK1 .02 Fuel Handling Accident! 8 3.4 3.8 SDM 037AA1 .02 Steam Generator Tube Leak / 3 3.1 2.9 Condensate exhaust system 051 AK3.0l Loss of Condenser Vacuum / 4 2.8 3.1 Loss of steam dump capability upon loss of condenser

- vacuum 059AA2.02 Accidental Liquid RadWaste Rel. / 9 2.9 3.9 The permit for liquid radioactive-waste release 069AK3.0l Loss of CTMT Integrity! 5 3.8 4.2 Guidance contained in EOP for loss of containment

. integrity WEO3EK2.l LOCA Cooldown - Depress. / 4 3.6 4.0 Components and functions of control and safety systems,

... including instrumentation, signals, interlocks, failure modes and automatic and manual features.

weO6EG2.4.20 Degraded Core Cooling / 4 3.8 4.3 Knowledge of operational implications of EOP warnings, V cautions and notes.

WE15EA2.1 Containment Flooding! 5 2.7 3.2 Facility conditions and selection of appropriate V procedures during abnormal and emergency operations.

Page 1 of 1 10!9!2012 8:06 PM

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 003K4.02 Reactor Coolant Pump 5 2.7 Prevention of cold water accidents or transients 004A4.04 Chemical and Volume Control 3.2 3.6 Calculation of boron concentration changes 004K5.30 Chemical and Volume Control 3.8 4.2 Relationship between temperature and pressure in CVCS

-. components during solid plant operation 005A2.03 Residual Heat Removal 2.9 3.1 RHR pump/motor malfunction 006K6.05 Emergency Core Cooling 3.0 3.5 Lj HPI/LPI cooling water

/

007A3.0l Pressurizer Relief/Quench Tank 2.7 2.9 Components which discharge to the PRT 007K3.0l Pressurizer Relief/Quench Tank 3.3 3.6 Containment 008K1.0l ComponentCooling Water 3.1 3.1 SWS 01 0A2.0l Pressurizer Pressure Control 3.3 3.6 Heater failures 010K6.02 Pressurizer Pressure Control 32 3.5 PZR 012K5.0l Reactor Protection 3.3 3.8 LI LI LI LI DNB Page 1 of 3 10/9/2012 8:06 PM

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 013G2.2.39 Engineered Safety Features Actuation 3.9 4.5 Knowledge of less than one hour technical specification

- action statements for systems.

022G2.4.l 1 Containment Cooling 4.0 4.2 Knowledge of abnormal condition procedures.

025K6.01 Ice Condenser 3.4 3.6 Upper and lower doors of the ice condenser 026K1 .01 Containment Spray 42 4.2 ECCS 026K2.02 Containment Spray 21 2.9 MOV5 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 039K3.05 Main and Reheat Steam 3.6 3.7 RCS 059K1.03 Main Feedwater 3.1 3.3 S/GS V

061 K5.0l Auxiliary/Emergency Feedwater 3.6 3.9 Relationship between AFW flow and RCS heat transfer 062A4.0l AC Electrical Distribution 3.3 3.1 All breakers (including available switchyard) 063A1 .01 DC Electrical Distribution 2.5 3.3 Battery capacity as it is affected by discharge rate

/

Page 2 of 3 10/9/2012 8:06 PM

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 063K4.04 DC Electrical Distribution 2.6 2.9 Trips 064K2.03 Emergency Diesel Generator 3.2 3.6 EJ Control power 073K3.0l Process Radiation Monitoring 3.6 4.2 U U U U U U U U U U Radioactive effluent releases 076A1 .02 Service Water 2.6 2.6 U U U U U U U U U U Reactor and turbine building closed cooling water temperatures.

078A3.0l InstrumentAir 3.1 3.2 U U U U U U U U U U Airpressure 103A1.0l Containment 3.7 4.1 U U U U U U U U U U Containment pressure, temperature and humidity Page3of3 10/9/2012 8:06PM

ES-401, REV 9 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:

RO SRO 002K5. 16 Reactor Coolant 3.5 4.0 Reason for automatic features of the Feedwater control system during total loss of reactor coolant flow Ol5Al.03 Nuclear Instrumentation 3.7 3.7 NIS power indication 016A3.01 Non-nuclear Instrumentation 2.9 2.9 Automatic selection of NNIS inputs to control systems 027K2.01 Containment Iodine Removal 3.1 3.4 Fans 033A2.03 Spent Fuel Pool Cooling 3.1 3.5 Abnormal spent fuel pool water level or loss of water level 034K6.02 Fuel Handling Equipment 2.6 3.3 Radiation monitoring systems 071 K3.05 Waste Gas Disposal 3.2 3.2 ARM and PRM systems 072A4.02 Area Radiation Monitoring 2.5 2.5 Major components 079K4.0l Station Air 2 3.2 Cross-connect with lAS 086K1 .02 Fire Protection 2.7 3.2 Raw service water V

Page 1 of 1 10/9/2012 8:06PM

ES-401, REV 9 T3 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 G2.1.15 Conduct of operations 2.7 3.4 Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

G2.1 .29 Conduct of operations 4.1 4.0 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.44 Conduct of operations 3.9 3.8 Knowledge of RO duties in the control room during fuel handling.

G2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

G2.2.43 Equipment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms G2.3.1 1 Radiation Control 3.8 4.3 Ability to control radiation releases.

G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.22 Emergency Procedures/Plans 3.6 4.4 LI LI LI LI LI LI LI Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

G2.4.29 Emergency Procedures/Plans 3.1 4.4 LI LI LI LI LI LI LI LI LI LI Knowledge of the emergency plan.

G2.4.3 Emergency Procedures/Plans 3.7 3.9 LI LI LI LI LI LI LI LI LI LI Ability to identify post-accident instrumentation.

Page 1 of 1 10/9/2012 8:06PM

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:

RO SRO 008AA2.28 Pressurizer Vapor Space Accident / 3 3.3 3 DDDDDDDDDD Safety parameter display system indications 011 EG2.4.41 Large Break LOCA /3 2.9 4 Knowledge of the emergency action level thresholds and classifications.

025AG2.4.34 Loss of RHR System /4 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 056AA2.88 Loss of Off-site Power / 6 4.1 4.2 Necessary S/G water level for natural circulation 065AG2.4.8 Loss of Instrument Air/B 3.8 4.5 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

WEO4EA2.l LOCA Outside Containment / 3 3.4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Page 1 of 1 10/9/2012 8:06PM

ES-401, REV 9 SRO T1G2 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 028AG2.2.25 Pressurizer Level Malfunction /2 3.2 4.2 Knowledge of the bases in Technical Specifications for

. limiting conditions for operations and safety limits.

076AG2.2.40 High Reactor Coolant Activity! 9 3.4 4.7 Ability to apply technical specifications for a system.

WEO3EA2.l LOCA Cooldown - Depress. / 4 3.4 4.2 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE1 OEA2.2 Natural Circ. With Seam Void! 4 3.439 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Page 1 of 1 10/9/2012 8:06 PM

ES-401, REV 9 SRO 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 005G2.2.36 Residual Heat Removal 3.1 4.2 j Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations 008A2.08 Component Cooling Water 2.5 2.7 Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler 026A2.09 Containment Spray 2.5 2.9 Radiation hazard potential of BWST 062G2.1 .30 AC Electrical Distribution 4.4 4.0 Ability to locate and operate components, including local L controls.

063A2.02 DC Electrical Distribution 2.3 3.1 Loss of ventilation during battery charging Page 1 of 1 10/9/2012 8:06 PM

ES-401, REV 9 SRO T2G2 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 001G2.2.44 Control Rod Drive 4.2 4.4 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 01 1A2.12 Pressurizer Level Control 3.3 3.3 Operation of auxiliary spray 028A2.0l Hydrogen Recombiner and Purge 3.4 3 DDDDDDDDDD Hydrogen recombiner power setting, determined by using Control plant data book Page 1 of 1 10/9/2012 8:06PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNC11ON: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .2 Conduct of operations 4.1 Knowledge of operator responsibilities during all modes of plant operation.

G2.l .5 Conduct of operations 2.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.14 Equipment Control 3.9 4. Knowledge of the process for controlling equipment DDDDDDDDDD configuration or status G2.2.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and V emergency conditions G2.4.25 Emergency Procedures/Plans 3.3 3.7 Knowledge of fire protection procedures.

G2.4.38 Emergency Procedures/Plans 2.4 4 DDDDDDDDDD Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator.

Page 1 of 1 10/9/2012 8:06PM

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2013 Examination Level: RO SRO Operating Test Number: 2013301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine boric acid required from RHT for Makeup to the FWST.

Conduct of Operations R,N G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Complete a Unit Vent Flow Calculation Conduct of Operations S,D G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Classify a DG start and complete log entry.

Equipment Control R,D G2.2.12 Knowledge of surveillance procedures.

Calculate Low Pressure Service Water Discharge Flow Radiation Control M,R for Radioactive Release G2.3.11 Ability to control radiation releases.

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

Facility: Catawba Nuclear Station Date of Examination: Sept. 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 2013301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Establish NC System Feed and Bleed A,D,L,P,S 4P 002A2.04 Control/mitigate loss of heat sink. 4.3/4.6
b. Restore power to 1ETA from offsite power A,D,L,P,S 6 062A4.01 Operate/monitor breakers (including switchyard). 3.3/3.1
c. Emergency Boration per FR-S.1 A,D,S 1 004A1.14 Control Emergency Boration. 3.8/3.9
d. Secure ND Pump due to miniflow valve failure A,N,EN,L,S 3 006A2.02 For ECCS, mitigate loss of flow path. 3.9/4.3
e. Increase 1A CLA pressure D,EN,S 2 006A1.03 Operate ECCS controls for accumulator. 3.5/3.7
f. Shift operating RC Pumps A,D,S 8 075A2.02 Mitigate/control loss of circulating water pumps. 2.5/2.7
g. Align the NS System for Cold Leg Recirculation M,L,S 5 026A4.01 Operate/monitor CSS controls 4.5/4.3
h. Main Turbine Weekly Trip Test A,N,S 7 012A2.06 Mitigate failure of RPS signal to trip the reactor 4.4/4.7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Unit 2 Spent Fuel Pool makeup from RN M,R 8 033A2.03 Control/mitigate abnormal SFP water level. 3.1/3.5
j. Establish NC Pump Seal Injection from the SSF M,E 4P 015/017AA1.07 Operate RCP seal water injection system. 3.5/3.4
k. Shifting Main Transformer Auxiliaries M 6 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9

@ 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 / SRO-U 4-6 / 4-6 / 2-3 (A)lternate path (C)ontrol room

<9 / <8 / <4 (D)irect from bank

>1 / >1 / >1 (E)mergency or abnormal in-plant

- / - / >1 (EN)gineered safety feature

>1 / >1 / >1 (L)ow-Power / Shutdown

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

<3 <3 / < 2 (randomly (P)revious 2 exams selected)

(R)CA

>1 / >1 / >1 (S)imulator Page 12 of 19

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: Sept. 2013 Examination Level: RO SRO Operating Test Number: 2013301 Administrative Topic Type Describe activity to be performed (See Note) Code*

Quantify steam leak size Conduct of Operations S,D G2.1.20 Ability to interpret and execute procedure steps.

Complete a Unit Vent Flow Calculation Conduct of Operations S,D G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Classify a DG start and complete log entry.

Equipment Control R,D G2.2.12 Knowledge of surveillance procedures.

Calculate Low Pressure Service Water Discharge Flow Radiation Control M,R for Radioactive Release G2.3.11 Ability to control radiation releases.

Classify an Emergency and Make Initial Notifications Emergency Procedures/Plan R,D G2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

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

Facility: Catawba Nuclear Station Date of Examination: Sept. 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 2013301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Establish NC System Feed and Bleed A,D,L,P,S 4P 002A2.04 Control/mitigate loss of heat sink. 4.3/4.6
b. Restore power to 1ETA from offsite power A,D,L,P,S 6 062A4.01 Operate/monitor breakers (including switchyard). 3.3/3.1
c. Emergency Boration per FR-S.1 A,D,S 1 004A1.14 Control Emergency Boration. 3.8/3.9
d. Secure ND Pump due to miniflow valve failure A,N,EN,L,S 3 006A2.02 For ECCS, mitigate loss of flow path. 3.9/4.3
e. Increase 1A CLA pressure D,EN,S 2 006A1.03 Operate ECCS controls for accumulator. 3.5/3.7
f. Shift operating RC Pumps A,D,S 8 075A2.02 Mitigate/control loss of circulating water pumps. 2.5/2.7
g. N/A
h. Main Turbine Weekly Trip Test A,N,S 7 012A2.06 Mitigate failure of RPS signal to trip the reactor 4.4/4.7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Unit 2 Spent Fuel Pool makeup from RN M,R 8 033A2.03 Control/mitigate abnormal SFP water level. 3.1/3.5
j. Establish NC Pump Seal Injection from the SSF M,E 4P 015/017AA1.07 Operate RCP seal water injection system. 3.5/3.4
k. Shifting Main Transformer Auxiliaries M 6 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9

@ 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 / SRO-U ES-301, Page 23 of 27 Page 13 of 19

Facility: Catawba Nuclear Station Date of Examination: Sept. 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 2013301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Type Safety System / JPM Title Code* Function

a. N/A
b. N/A
c. Emergency Boration per FR-S.1 A,D,S 1 004A1.14 Control Emergency Boration. 3.8/3.9
d. Secure ND Pump due to miniflow valve failure A,N,EN,L,S 3 006A2.02 For ECCS, mitigate loss of flow path. 3.9/4.3
e. N/A
f. N/A
g. Align the NS System for Cold Leg Recirculation M,L,S 5 026A4.01 Operate/monitor CSS controls 4.5/4.3
h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Unit 2 Spent Fuel Pool makeup from RN M,R 8 033A2.03 Control/mitigate abnormal SFP water level. 3.1/3.5
j. Establish NC Pump Seal Injection from the SSF M,E 4P 015/017AA1.07 Operate RCP seal water injection system. 3.5/3.4
k. N/A

@ 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.

ES-301, Page 23 of 27 Page 14 of 19

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