ML100470400

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Initial Exam 2009-301 Draft Administrative Documents
ML100470400
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/02/2010
From:
NRC/RGN-II
To:
References
Download: ML100470400 (19)
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ES-401 11 Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Catawba Date of Exam: Dec 2009 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 3 2 4 3 3 3 18 3 3 6 Emergency &

2 2 2 2 1 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 6 4 4 4 27 5 5 10 1 2 3 3 2 3 2 3 3 2 3 2 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 1 2 2 2
1. Ensure that at least two topics from every applicable KIA 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 KIA 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 +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 pointspOints 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA 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 KIAs 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 KIA categories.
7. *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be relevant to the applicable evolution or system.
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; iffuel 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. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. selecttopics For Tier 3, select topics from Section 2 ofthe KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 100 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 A1 A2 A3 A4 G TOPIC:

RO SRO 007EG2.4.50 Reactor Trip - Stabilization - Recovery 4.2 4.0 DDDDDDDDDD~ Ability to verify system alarm setpoints and operate 11 controls identified in the alarm response manual.

008AK1.02 Pressurizer Vapor Space Accident 1 3 13 3.1 3.7 ~DDDDDDDDDD Change in leak rate with change in pressure 009EA2.31 Small Break LOCA 1 3 2.5 3.5 D D D D D D D ~ D D D Tech-Spec limits for plant operation with an idle loop 011 EG2.4.35 Large Break LOCA 13 3.8 4.0 D D D D D D D D D D ~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 015AK2.10 RCP Malfunctions 1 4 2.8 2.8 D ~ D D D D D D D D D RCP indicators and controls 025AK1.01 Loss of RHR System 14 3.9 4.3 ~ D D D D D D D D D D Loss of RHRS during all modes of operation 027AK3.03 Pressurizer Pressure Control System 3.7 4.1 D D ~ D D D D D D D D Actions contained in EOP for PZR PCS malfunction Malfunction 1 3 029EK3.10 ATWS 11 ATWS/1 4.1 4.1 D D ~ D D D DDDDD D D D D D Manual rod insertion 054AK3.04 Loss of Main Feedwater 1 4 4.4 4.6 D D .~ D D D D D D D D Actions contained in EOPs for loss of MFW 055EK3.02 Station Blackout 1 6 4.3 4.6 D D ~ D D D D D D D D Actions contained in EOP for loss of offsite and onsite power 056AG2.1.28 Loss of Off-site Power 1 6 4.1 4.1 D D D D D D D D D D ~ Knowledge of the purpose and function of major system components and controls.

Par~ * 'If 2 2/26/2009 7:24 AM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 057AA1.06 OS7 AA 1.06 Loss of Vital AC Inst. Bus 1 6 3.5 3.S 3.5 3.S 0D D 0 0D 0D D0 0D ~ 0D D0 0D D 0 Manual control of components for which automatic control is lost 058AK1.01 OS8AK1.01 Loss of DC Power 1616 2.8 3.1 ~ 0D D0 0D D0 0D D D 0 0D D0 0D Battery charger equipment and instrumentation 062AA1.02 062AA 1.02 Loss of Nuclear Svc Water 1 4 3.2 3.3 D 0 0D 00 D D 0D D 0 ~ D 0 0D 0D D0 Loads on the SWS in the control room 065AA1.03 06SAA 1.03 Loss of Instrument Air 1 8 2.9 3.1 D 0 0D D 0 0D D0 0D ~ D 0 0D D0 0D Restoration of systems served by instrument air when pressure is regained WE04EA2.2 LOCA Outside Containment 1 133 3.6 4.2 0 D 0 D D D D D D ~ D D D oooo~ooo Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

WE05EK2.1 WEOSEK2.1 Inadequate Heat Transfer - Loss of 3.7 3.9 0D ~ 0D D 0 0D 0D D 0 D D 00D0 D Components and functions of control and safety systems, Secondary Heat Sink 14 14 including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE11 EA2.1 14 Loss of Emergency Coolant Recirc. 14 3.4 4.2 0 0D D D 0 0D D 0 0D 0D ~ 0D D 0 0D Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Pao" ') of 2 Pao'" 2/26/2009 7:24 AM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 005AK2.02 Inoperable/Stuck Control Rod / 1 2.5 2.6 D 0 ~ D 0 DD 00 D0 D0 D0DDo D Breakers, relays, disconnects and control room switches 033AG2.1.19 Loss of Intermediate Range NI / 7 3.9 3.9 3.8 3.B 0DDDDDDDDDD~

0 0 0 0 0 0 0 0 0 ~ Ability to use plant computer to evaluate system or component status.

037AK1.01 Steam Generator Tube Leak / 3 2.9 2.9 3.3 3.3 ~ 0 0 0 0 0 0 0 0 0 0

~DDDDDDDDDD Use of steam tables 067AK1.01 Plant Fire On-site / 9 B 8 2.9 2.9 3.9 3.9 ~ 0 0 0 0 0 0 0 0 0 0

~DDDDDDDDDD Fire classifications by type WE03EK2.2 LOCA Cooldown - Depress. / 4 3.7 4.0 0D~DDDDDDDDD

~ 0 0 0 0 0 000 Facility's 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.

WEOBEK3.1 WE08EK3.1 RCS Overcooling - PTS / 4 3.4 3.9 o~oooooo DD~DDDDDDDD o 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.

WE13EK3.1 Steam Generator Over-pressure / 4 2.9 2.9 3.2 3.2 0DD~DDDDDDDD 0 ~ 0 0 0 0 0 0 0 0 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.

WE14EA2.1 Loss of CTMT Integrity / 5 3.3 3.3 3.8 3.B 0DDDDDDD~DDD 0 0 0 0 0 0 ~ 0 0 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

WE15EA 1.2 WE15EA1.2 Containment Flooding /5 /5 2.7 2.9 0 oooo~oooo DDDDDD~DDDD Operating behavior characteristics of the facility.

Pa(1~ < C)f 1 2/26/2009 7:24 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K5 K6 A1 A2 A3 A4 G K1 K2 K3 K4 KS TOPIC:

RO SRO 003K4.04 Reactor Coolant Pump 2.8 2.B 3.1 DDD~DDDDDDD Adequate cooling of RCP motor and seals 004A4.08 004A4.0B Chemical and Volume Control 3.B 3.8 3.4 DDDDDDDDD~D Charging 00SA4.0S 005A4.05 Residual Heat Removal 2.B 2.8 2.B 2.8 DDDDDDDDD~D Position of RWST recirculation valve (locked when not in use, continuously monitored when in use).

00SK1.13 005K1.13 Residual Heat Removal 3.3 3.S 3.5 ~DDDDDDDDDD SIS 006A1.07 Emergency Core Cooling 3.3 3.6 DDDDDD~DDDD Pressure, high and low 006KS.06 006K5.06 Emergency Core Cooling 3.S 3.5 3.9 DDDD~DDDDDD Relationship between ECCS flow and RCS pressure 007KS.02 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 DDDD~DDDDDD Method of forming a steam bubble in the PZR 00BA1.03 008A1.03 Component Cooling Water 2.7 2.9 DDDDDD~DDDD CCW pressure 010K6.01 Pressurizer Pressure Control 2.7 3.1 DDDDD~DDDDD Pressure detection systems 012K6.10 Reactor Protection 3.3 3.S 3.5 DDDDD~DDDDD Permissive circuits 013K5.02 013KS.02 Engineered Safety Features Actuation 2.9 3.3 DDDD~DDDDDD Safety system logic and reliability Page 1 of 3 2/26/2009 7:24 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 022A2.01 Containment Cooling 2.5 2.7 2.7 0 0 0 0 0 0 0 ~

DDDDDDD~DDD o Fan motor over-current 022K3.02 Containment Cooling 3.0 3.3 0 0 ~ 0 0 0 DD~DDDDDDDD 0000 Containment instrumentation readings 025A3.02 Ice Condenser 3.4 3.4 3.4 3.4 0 0 0 0 0 0 0 0 ~ 0 0 DDDDDDDD~DD Isolation valves 026A2.02 Containment Spray 4.2 4.2 4.4 4.4 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Failure of automatic recirculation transfer 039A 1.09 039A1.09 Main and Reheat Steam 2.5 2.7 2.7 0 0 0 0 0 0 ~ 0 0 0 0 DDDDDD~DDDD Main steam line radiation monitors 039G2.2.37 Main and Reheat Steam 3.6 3.6 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

DDDDDDDDDD~ Ability to determine operability and/or availability of safety related equipment 059A4.0B 059A4.08 Main Feedwater 3.0 3.0 2.9 2.9 0 0 0 0 0 0 0 0 0 ~ 0 DDDDDDDDD~D Feed regulating valve controller 061 G2.4.20 061G2.4.20 Auxiliary/Emergency Feedwater 3.8 3.B 4.3 0 0 0 0 DDDDDDDDDD~ ooooo~ Knowledge of operational implications of EOP warnings, cautions and notes.

062A3.01 AC Electrical Distribution 3.0 3.1 0 0 0 0 0 0 0 DDDDDDDD~DD Vital ac bus amperage 062K2.01 AC Electrical Distribution 3.3 3.4 0 ~ 0 0 0 0 D~DDDDDDDDD Major system loads 063K2.01 DC Electrical Distribution 2.9 3.1 0 ~ 0 0 0 D~DDDDDDDDD 0000 Major DC loads Pag p 9 of 3 2/26/2009 7:24 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 063K3.01 DC Electrical Distribution 3.7 4.1 0 0 ~ 0 0 0 0 0 0 0 0 DOD ED/G 064K4.01 Emergency Diesel Generator 3.8 4.1 0 0 0 ~ 0 0 0 0 0 0 0 Trips while loading the ED/G (frequency, voltage, speed) 073A2.01 Process Radiation Monitoring 2.5 2.5 2.9 2.9 0 0 0 0 0 0 0 ~ 0 0 0 DDDD~DDD Erratic or failed power supply 076K2.01 Service Water 2.7 2.7 0 ~ DO 0 0 0 0 00 0 0 0 0 0 0 0 0 0 Service water 078K3.02 Instrument Air 3.4 3.6 0 0 ~ 0 0 0 0 0 0 0 o 0 Systems having pneumatic valves and controls 103K1.01 Containment 3.6 3.9 ~ 0 0 0 0 0 0 0 0 0 0 CCS Page 3 of 3 2/26/2009 7:24 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001K2.01 Control Rod Drive 3.5 3.6 D~DDDDDDDDD One-line diagram of power supply to MIG sets.

002A3.02 Reactor Coolant 2.6 2.8 DDDDDDDD~DD Containment sound-monitoring system 011A2.11 Pressurizer Level Control 3.4 3.6 DDDDDDD~DDD Failure of PZR level instrument - low 016K3.04 Non-nuclear Instrumentation 2.6 2.7 DD~DDDDDDDD MFW system 028K6.01 Hydrogen Recombiner and Purge 2.6 3.1 DDDDD~DDDDD Hydrogen recombiners Control 033K4.04 Spent Fuel Pool Cooling 2.7 2.9 DDD~DDDDDDD Maintenance of spent fuel pool radiation 035A1.02 Steam Generator 3.5 3.8 DDDDDD~DDDD SIG pressure 041A4.07 DumpfTurbine Bypass Control Steam Dumprrurbine 2.9 3.0 DDDDDDDDD~D Remote gagging of stuck open-relief valves 045K5.01 Main Turbine Generator 2.8 3.2 DDDD~DDDDDD Possible presence of explosive mixture in generator if hydrogen purity deteriorates 071 K1.05 071K1.05 Waste Gas Disposal 2.7 2.8 ~DDDDDDDDDD Meteorological tower Page 1 of 1 2/26/2009 7:24 AM 2126/2009

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.3 Conduct of operations 3.7 3.9 DDDD DOD 0 0D 0D D DD 0 0 D 0 0 ~ Knowledge of shift or short term relief turnover practices.

.5 G2.1.5 Conduct of operations 2.9 2.9 3.9 3.9 DD 00 D0 D0 D0 D0 D0DDD D~~ Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.1:7

7 Conduct of operations 4.4 4.7 D 0 0D 0D D0 0DD 0 0 DD DD 0 0 0 ~ Ability to evaluate plant plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument instrurnent interpretation.

G2.2.1 Equipment Control 4.5 4.4 DDDDDDDDDD~ Ability to perforrn perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.25 Equipment Control 3.2 4.2 DDDDDDDDDD~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.3.14 Radiation Control 3.4 3.8 DDDDDDDDDD~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.6 Radiation Control 2.0 3.8 DDDDDDDDDD~ Ability to aprove release permits G2.3.7 Radiation Control 3.5 3.6 requirernents DDDDDDDDDD~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.21 Emergency Em ergency Procedures/Plans 4.0 4.6 DDDDDDDDDD~ Knowledge of the parameters and logic used to assess the status of safety functions G2.4.29 Emergency Procedures/Plans 3.1 4.4 DDDDDDDDDD~ Knowledge of the emergency plan.

Pap p 1 of 1 2/26/2009 7:24 AM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR KS K6 A1 A2 A3 A4 G K1 K2 K3 K4 K5 TOPIC:

RO AO SRO SAO 008AA2.18 Pressurizer Vapor Space Accident 1/ 3 3.0 3.0 D D D D D D D D ~ D D D DDDD~DDD Computer indications for ACS RCS temperature and pressure 011EA2.02 Large Break LOCA 1 /3 3.3 3.7 D D D D D D D ~ D D D Consequences to AHA RHR of not resetting safety injection 026AG2.4.9 Loss of Component Cooling Water 18 /8 3.8 4.2 D D D D D D D D D D ~

DDDDD~ Knowledge of low power 1/ shutdown implications in accident (e.g. LOCA or loss of RHR)

AHA) mitigation strategies.

OS4AG2.1 .30 054AG2.1.30 Loss of Main Feedwater 1

/4 4.4 4.0 D D D D D D D D D D ~ Ability to locate and operate components, including local controls.

077AG2.4.18 Generator Voltage and Electric Grid 3.3 4.0 D D D D D D D D D D ~ Knowledge of the specific bases for EOPs.

Disturbances 1

/6 WEOSEA2.1 WE05EA2.1 Inadequate Heat Transfer - Loss of 3.4 4.4 D D D D D D D ~ D D D Facility conditions and selection of appropriate Secondary Heat Sink 1

/4 procedures during abnormal and emergency operations.

Page 1 of 1 2/26/2009 7:24 AM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO 005AA2.04 00SAA2.04 Inoperable/Stuck Control Rod 1 1 2.3 3.4 D D D D D DD D D D D ~ D D D Interpretation of computer in-core TC map for dropped rod location 032AG2.4.4 Loss of Source Range NI 1 7 17 4.5 4.S 4.7 D D D D D D D D D D ~ Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

033AG2.1.30 Loss of Intermediate Range NI 17 17 4.4 4.0 D D

.D D D D D D D D D D D D D ~ Ability to locate and operate components, including local controls.

067AA2.02 Plant Fire On-site 1 9 8 2.5 2.S 2.9 D DD D D D D D D ~ D D D D D Damper position Pap p Paw' 1 1 of 1 2/26/2009 7:24 AM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003A2.02 Reactor Coolant Pump 3.7 3.9 D D D D D D D ~ D D D Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 008G2.4.9 Component Cooling Water 3.8 3.8 4.2 4.2 D D D D DDDDD D D D D D D ~ Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

039A2.02 Main and Reheat Steam 2.4 2.7 D D D D D D D ~ D D D

~DDD Decrease in turbine load as it relates to steam escaping from relief valves 063G2.2.40 DC Electrical Distribution 3.4 4.7 D D D D D D D D D D ~ Ability to apply technical specifications for a system.

076A2.02 Service Water 2.7 3.1 D D D D D D D ~ D D D Service water header pressure PagE" 1 of 1 2/26/2009 7:24 AM

'.~

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 016A2.02 Non-nuclear Instrumentation 2.9 2.9 3.2 3.2 D D D D D D D ~ D D D DDDDDDD~DDD Loss of power supply 029G2.1.28 Containment Purge 4.1 4.1 4.1 4.1 D D D D D D D D D D ~

DDDDDDDDDD~ Knowledge of the purpose and function of major system components and controls.

033A2.03 Spent Fuel Pool Cooling 3.1 3.1 3.5 D D D D D D D ~ D D D DDDDDDD~DDD Abnormal spent fuel pool water level or loss of water level Pap p 1 of 1 2/26/2009 7:24 AM

--/ ~/

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.26 Conduct of operations 3.4 3.6 D D D D D D D D D D ~ Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

G2.2.41 Equipment Control 3.S 3.9 D D D D D D D D D D ~ Ability to obtain and interpret station electrical and mechanical drawings G2.2.44 Equipment Control 4.2 4.4 D D D D D D D D D D ~ 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 G2.3.4 Radiation Control 3.2 3.7 D D D D D D D D D D ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.S 3.6 D D D D D D D D D D ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.20 Emergency Procedures/Plans 3.8 3.8 4.3 4.3 D D D D D D D D D D ~

DDDDDDD~ Knowledge of operational implications of EOP warnings, cautions and notes.

G2.4.S0 Emergency Procedures/Plans 4.2 4.0 D D D D D D D D D D ~ Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Pa(lp * ()f 1 2/26/2009 7:24 AM

DRAFT ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Exam ination 12/7/2009 Exam Level: ~RO DSRO Operating Test No.:

Administrative Topic Type Describe activity to be performed (see Note) Code*

S R M Calculate Reactor Vessel Head Venting Time Conduct of Operations Conduct of Operations R M Determine the amount of boric acid required to get Control Bank D 0

above the Rod insertion limits Equipment Control S R D P Complete a Unit Vent Flow Manual Calculation per PT/l/A/4450/017 PT/l/A/44S0/017

(

Radiation Protection Emergency Plan R D Activate the Oil Spill Response Team 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

(~3 (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)

(

DRAFT ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Examination Date of Exam ination 12/7/2009 Exam Level: ORO ~SRO Operating Test No.:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations S R M Calculate Reactor Vessel Head Venting TIme Time Conduct of Operations R M Determine the amount of boric acid required to get Control Bank D above the Rod insertion limits Equipment Control S R D P Determine SLC requirements and complete a Unit Vent Flow Manual calculation per PTjljAj44S0j017 Radiation Protection R D Calculate Low Pressure Service Water Discharge Flow for Liquid Radioactive Release Emergency Plan S D Perform RPjOjAjSOOOj007 (Natural Disasters and Earthquake)

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)

DRAFT ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination Exam ination 12/7/2009 Exam Level: ~RO o SRO-I o SRO-U Operating Test No.:

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function

a. Pressurize Cold Leg Accumulator 1A lA D S 2
b. Align the NS System to Cold Leg Recirculation A D EN 5
c. Restore Offsite Power to 6.9 5.9 kV Busses per AP/07 (Loss of Normal Power) , A D P S 6 5

Enclosure 21 (Black Restart Procedure)

d. Verify Adequate Shutdown Margin Following a Reactor Trip A N S 1
e. Place Steam Dumps in Automatic Operation per OPjljA/5100jOOl OP/1/A/6100/001 L N S 4S
f. Transfer Emergency Core Cooling System to Hot Leg Recirculation A M S 3
g. Start Reactor Coolant Pump 1B lB ADS 4P

(

h. Shift Operating RC Pumps A N S 8 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Transfer Control to the Standby Shutdown System D R 8
j. Locally Operate Steam Generator PORVs During a SGTR D E 3
k. Locally Trip the Reactor E M 1

@ 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 rooin

  • Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank ~9/~8l~4

~9/~8/~4 (E)mergency or abnonmal abnormal in-plant  ;::1/;::1/;::1

1/
;:1/:;:1 (EN)gineered safety feature I;::I:;: 1 (control room system)

(L)ow-Power 1 Shutdown  ;::1/;::1/;::1

1/
;:1/:;:1 (N)ew or (M)odified from bank including 1(A)  :;:2/:;:2/:;:1
2/;
:2/;::1 (P)revious 2 exams ~ 3 1 ~ 3 1 ~ 2 (randomly selected)

(R)CA  :;:1/:;:1/:;:1

1/;
:1/;::1 (S)imulator

DRAFT ES-301, Rev. 9 Room/In-Plant Systems Outline Control Roomlln-Plant Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/7/2009 Exam Level: ORO ~ SRO-I o SRO-U Operating Test No.:

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System I/ JPM Title Type Code* Safety Function a.

b. Align the NS System to Cold Leg Recirculation A D EN 5
c. Restore Offsite Power to 6.9 kV Busses per AP/07 AP/O? (Loss of Normal Power) I, A D P S 6 Enclosure 21 (Black Restart Procedure)
d. Verify Adequate Shutdown Margin Following a Reactor Trip A N S 1
e. Place Steam Dumps in Automatic Operation per OP/1/A/61001001 OP/l/A/6100/001 L N S 4S
f. Cooling System to Hot Leg Recirculation Transfer Emergency Core COOling ReCirculation A M S 3
g. Start Reactor Coolant Pump 1B lB ADS 4P

(

h. Shift Operating RC Pumps A N S 8 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Transfer Control to the Standby Shutdown System D R 8
j. Locally Operate Steam Generator PORVs During a SGTR D E 3
k. Locally Trip the Reactor E M 1

@ 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-II SRO-I / SRO-U (A)ltemate (A)lternate path 4-6 I/ 4-6 I/ 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4
=:9/:=:8/:=:4 (E)mergency or abnormal in-plant ~1/~1/~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) ~2/~2/~1 (P)revious 2 exams ~ 3 I/ ~

=: ~ 2 (randomly selected)
=: 3 I/ :=:

(R)CA ~1/~1/~1 (S)imulator

DRAFT ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/7/2009 Exam Level: ORO o SRO-I ~ SRO-U Operating Test No.:

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ES System / JPM Title Type Code* Safety Function a.

b. Align the NS System to Cold Leg Recirculation A D EN 5 c.

d.

e. Place Steam Dumps in Automatic Operation per OP/l/A/61DD/DDl L N S 4S
f. Transfer Emergency Core Cooling System to Hot Leg Recirculation A M MS 3 g.

h.

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

i. Transfer Control to the Standby Shutdown System D R 8 j.
k. Locally Trip the Reactor E MM 1

@ 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 1 / SRO-I 1 / SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4
9/:::8/:::4 (E)mergency or abnormal abnonmal in-plant  ::::1/::::1/::::1

.=::1 I.=::1 I.=::1 (EN)gineered safety feature I::::I.=:: 1 (control room system)

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

.=::1 I.=::1 I.=::1 (N)ew or (M)odified from bank including 1 1(A)

(A) I.=::2 I.=::1

2/::::2/::::1

.=::2 (P)revious 2 exams ~ 3 1 :::

~ 3 1 :::

~ 2 (randomly selected)

(R)CA  ::::1/::::1/::::1

.=::1 I.=::1 I.=::1 (S)imulator

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