ML092940703

Initial Exam 2008-301 Draft Administrative Documents

ML092940703
Person / Time
Site:	Catawba
Issue date:	10/20/2009
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-413/08-301, 50-414/08-301
Download: ML092940703 (27)

Text

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Catawba Date of Examination: 12/01/2008 Initials Item Task Description a b* ci cti 1.

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a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

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b. Assess whether the outline was systematically and randomly prepared in accordance with I~

R I Section 0.1 of ES-401 and whether all KiA categories are appropriately sampled.

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c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

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d. Assess whether the justifications for deselected or rejected KiA statements are appropriate.

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2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major S transients.

I M b. Assess whether there are enough scenario sets (and spares) to test the projected number and U mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using at A least one new or significantly modified scenario, that no scenarios are duplicated from the T applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

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c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and R

quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W among the safety functions as specified on the form

/ (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

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c. Ensure that KiA importance ratings (except for plant-specific priorities) are at least 2.5.

E R d. Check for duplication and overlap among exam sections.

A L e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO).

Date

a. Author n

b. Facility Reviewer (*)

c. NRC

c. NRC Chief Chief Examiner (#)

Examiner (#) G.,~ -yJ. 1..~k:A ~~.AjJY4j(~Jlf

d. NRC Supervisor

~CUAr.W~ I/;M...,;r IK;K'-

l I If Note: # Independent NRC reviewer initial items in Columil"C";

Columri"d'; chief examiner concurrence required.

ES-401 & Rev. 9 PWR Examination Outline Form ES-401-2 Facility: CAffllJ/JA Date of Exam: 12/1/

12/1 / ZI>>f; 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 3 3 3 3 3 18 3 3 6 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 2 1

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 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 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. For Tier 3, select topics from Section 2 of the 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 10 CFR 55.43.

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

RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 D~DDDDDDDDD Reactor trip status panel

/1 Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 009EA2.10 Small Break LOCA / 3 3.1 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Airborne activity Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13) 011 EG2.4.30 Large Break LOCA / 3 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside This is a Generic, no stem statement is agencies.

associated.

022AK1.02 Loss of Rx Coolant Makeup / 2 2.7 3.1 ~ 0 0 0 0 0 0 0 0 0 0 Relationship of charging flow to pressure differential between charging and RCS Knowledge* of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 025AG2.4.30 Loss of RHR System /4 2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside This is a Generic, no stem statement is agencies.

associated.

026AA2.03 Loss of Component Cooling Water /8 2.6 2.9 0 0 0 0 0 0 0 ~ 0 0 0 The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the Ability to determine and interpret the abnormal condition following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13)

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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 027AA1.04 Pressurizer Pressure Control System 3.9 3.6 0 0 0 0 0 0 ~ 0 0 0 0 Pressure recovery, using emergency-only heaters Malfunction 1 3 Ability to operate and 1 or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.51 45.6) 029EG2.4.34 ATWS 11 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of RO tasks performed outside the main control room during an emergency and the resultant This is a Generic, no stem statement is operational effects associated.

03BEK1.02 Steam Gen. Tube Rupture 13 3.2 3.5 ~ 0 0 0 0 0 0 0 0 0 0 Leak rate vs. pressure drop Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.B to 41.10/45.3) 057AA2.13 Loss of Vital AC Inst. Bus 1 6 3 3.4 0 0 0 0 0 0 0 ~ 0 0 0 VCT level and pressure indicators and recorders Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.51 45.13) 05BAA1.02 Loss of DC Power 1 6 3.1 3.1 0 0 0 0 0 0 ~ 0 0 0 0 Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector Ability to operate and lor monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.51 45.6) 062AK3.03 Loss of Nuclear Svc Water 1 4 4 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Guidance actions contained in EOP for Loss of nuclear service water Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13)

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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 065AK3.03 Loss of Instrument Air / 8 2.9 3.4 D D ~ D D D D D D D D Knowing effects on plant operation of isolating certain equipment from instrument air Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/

45.6 / 45.13) 077AA1.01 Generator Voltage and Electric Grid 3.6 3.7 D D D D D D ~ D D D D Grid frequency and voltage Disturbances / 6 Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6)

WE04EK2.2 LOCA Outside Containment / 3 3.8 4.0 D ~ D D D D D D D D D Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal Knowledge of the interrelations between systems and relations between the proper operation of (EMERGENCY PLANT EVOLUTION) and these systems to the operation of the facility.

the foliowing:(CFR: 41.7/45.7/45.8)

WE05EK3.1 Inadequate Heat Transfer - Loss of 3.4 3.8 D D ~ D D D D D D D D Facility operating characteristics during transient Secondary Heat Sink / 4 conditions, including coolant chemistry and the effects of Knowledge of the reasons for the following temperature, pressure and reactivity changes and responses as they apply to operating limitations and reasons for these operating (EMERGENCY PLANT characteristics.

EVOLUTION):(CFR: 41.5/41.10/45.6/

45.13)

WE11 EK2.1 Loss of Emergency Coolant Recirc. / 4 3.6 3.9 D ~ D D D D D D D D D Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure Knowledge of the interrelations between modes and automatic and manual features.

(EMERGENCY PLANT EVOLUTION) and

. the foliowing:(CFR: 41.7/45.7/45.8)

WE12EK1.3 Steam Line Rupture - Excessive Heat 3.4 3.7 ~ D D D D D D D D D D Annunciators and conditions indicating signals, and Transfer / 4 remedial actions associated with the (Uncontrolled Knowledge of the operational implications Depressurization of all Steam Generators).

of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3)

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

RO SRO 001AA1.06 Continuous Rod Withdrawal / 1 3 2.9 0 0 0 0 0 0 ~ 0 0 0 0 Rod transfer switches Ability to operate and / or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 005AG2.4.6 Inoperable/Stuck Control Rod / 1 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge symptom based EOP mitigation strategies.

This is a Generic, no stem statement is associated.

024AK1.04 Emergency Boration / 1 2.8 3.6 ~ 0 0 0 0 0 0 0 0 0 0 Low temperature limits for boron concentration Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 / 45.3) 033AK1.01

.01 Loss of Intermediate Range NI / 7 2.7 3 ~DDDDDDDDDD Effects of voltage changes on performance Knowledge of the operational implications of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10/45.3) 037AA2.03 Steam Generator Tube Leak / 3 3.4 3.9 0 0 0 0 0 0 0 ~ 0 0 0 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13) 074EA1.01 Inad. Core Cooling / 4 4.2 4.4 0 0 0 0 0 0 ~ 0 0 0 0 RCS water inventory Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6)

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ES-401, REV 9 T1 G2 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 076AK3.06 High Reactor Coolant Activity 1 9 3.2 3.8 0 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOP for high reactor coolant activity Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.101 45.6/45.13)

WE03EK2.1 LOCA Cooldown - Depress. 1 4 3.6 4.0 0 ~ 0 0 0 0 0 0 0 0 0 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure Knowledge of the interrelations between modes and automatic and manual features.

(EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)

WE09EK3.3 Natural Circ. 1 4 3.5 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Manipulation of controls required to obtain desired operating results during abnormal and emergency Knowledge of the reasons for the following situations.

responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.61 45.13)

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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 003A2.02 Reactor Coolant Pump 3.7 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 004A1.01 Chemical and Volume Control 2.9 3.8 0 0 0 0 0 0 ~ 0 0 0 0 Activity levels in primary system Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5) 004K1.34

.34 Chemical and Volume Control 2.7 2.9 ~ 0 0 0 0 0 0 0 0 0 0 Interface between CVCS and reactor coolant drain tank; and PZR PCS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 005K4.11 Residual Heat Removal 3.5 3.9 0 0 0 ~ 0 0 0 0 0 0 0 Lineup for low head recirculation mode (external and internal)

Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 006A1.05 Emergency Core Cooling 2.9 3.3 0 0 0 0 0 0 ~ 0 0 0 0 CCW flow (establish flow to RHR heat exchanger prior to placing in service Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5) 007G2.4.6 Pressurizer Relief/Quench Tank 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge symptom based EOP mitigation strategies.

This is a Generic, no stem statement is associated.

Page 1 of 5 4/1/2008 4:22 PM

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 00BK3.03 Component Cooling Water 4.1 4.2 D D ~ D D D D D D D D RCP Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 00BK4.07 Component Cooling Water 2.6 2.7 D D D ~ D D D D D D D Operation of the CCW swing-bus power supply and its associated breakers and controls Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 010G2.1.25 Pressurizer Pressure Control 3.9 4.2 D D D D D D D D D D ~ Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

This is a Generic, no stem statement is associated.

012A2.02 Reactor Protection 3.6 3.9 D D D D D D D ~ D D D Loss of instrument power Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 012K5.01 Reactor Protection 3.3 3.B D D D D ~ D D D D D D DNB Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 013K6.01 Engineered Safety Features Actuation 2.7 3.1 D D D D D ~ D D D D D Sensors and detectors Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 022K2.02 Containment Cooling 2.5 2.4 D ~ D D D D D D D D D Chillers Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)

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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 025A4.01 Ice Condenser 3.0 2.7 D D D D D D D D D ~ D Ice condenser isolation valves Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 026A1.03 Containment Spray 3.5 3.5 D D D D D D ~ D D D D Containment sump level Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5) 026K1.01 Containment Spray 4.2 4.2 ~ D D D D D D D D D D ECCS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 039K5.01 Main and Reheat Steam 2.9 3.1 D D D D ~ D D D D D D Definition and causes of steam/water hammer Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 059A4.11 Main Feedwater 3.1 3.3 D D D D D D D D D ~ D Recovery from automatic feedwater isolation Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 061A3.04 Auxiliary/Emergency Feedwater 3.9 3.9 D D D D D D D D ~ D D AFW S/G level control on automatic start Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 062A3.01 AC Electrical Distribution 3.0 3.1 D D D D D D D D ~ D D Vital ac bus amperage Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

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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 063K2.01 DC Electrical Distribution 2.9 3.1 D~ DDDDDDDDD Major DC loads Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 063K3.01 DC Electrical Distribution 3.7 4.1 DD~DDDDDDDD ED/G Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 064A3.07 Emergency Diesel Generator 3.6 3.7 DDDDDDDD~DD Load sequencing Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5) 064K6.07 Emergency Diesel Generator 2.7 2.9 DDDDD~DDDDD Air receivers Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 073A2.02 Process Radiation Monitoring 2.7 3.2 DDDDDDD~DDD Detector failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 076K2.01 Service Water 2.7 2.7 D~DDDDDDDDD Service water Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 078K3.02 Instrument Air 3.4 3.6 DD~DDDDDDDD Systems having pneumatic valves and controls Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

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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 103K1.07 Containment 3.5 3.7 ~ 0 0 0 0 0 0 0 0 0 0 Containment vacuum system Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8)

Page 5 of 5 4/1/2008 4:22 PM

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 001K2.02 Control Rod Drive 3.6 3.7 D ~ D D D D D D D D D One-line diagram of power supply to trip breakers Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 011A1.02 Pressurizer Level Control 3.3 3.5 D D D D D D ~ D D D D Charging and letdown flows Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 016K1.12

.12 Non-nuclear Instrumentation 3.5 3.5 ~ D D D D D D D D D D S/G Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 017K3.01 In-core Temperature Monitor 3.5 3.7 D D ~ D D D D D D D D Natural circulation indications Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 027K5.01 Containment Iodine Removal 3.1 3.4 D D D D ~ D D D D D D Purpose of charcoal filters Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 035G2.2.40 Steam Generator 3.4 4.7 D D D D D D D D D D ~ Ability to apply technical specifications for a system.

This is a Generic, no stem statement is associated.

045A3.05 Main Turbine Generator 2.6 2.9 D D D D D D D D ~ D D Electrohydraulic control Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

Page 1 of 2 4/1/2008 4:15 PM

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 071K4.01 Waste Gas Disposal 2.6 3.0 0 0 0 ~ 0 0 0 0 0 0 0 Pressure capability of the waste gas decay tank Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7) 079A4.01 Station Air 2.7 2.7 0 0 0 0 0 0 0 0 0 ~ 0 Cross-tie valves with lAS Ability to manually operate andlor monitor in the control room:(CFR: 41.7/45.5 to 45.8) 086K6.04 Fire Protection 2.6 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Fire, smoke and heat detectors Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)

Page 2 of 2 4/1/2008 4:15 PM

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 G2.1.45 Conduct of operations 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to identify and interpret diverse indications to validate the response of another indication G2.1.B Conduct of operations 3.4 4.1 0 0 0 0 0 0 0 0 0 0 ~ Ability to coordinate personnel activities outside the control room.

G2.2.2 Equipment Control 4.6 4.1 0 0 0 0 0 0 0 0 0 0 ~ Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

G2.2.39 Equipment Control 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification action statements for systems.

G2.3.11 Radiation Control 3.B 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to control radiation releases.

G2.3.4 Radiation Control 3.2 3.7 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions Page 1 of 2 4/1/200B 4:15 PM

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 G2.4.13 Emergency Procedures/Plans 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of crew roles and responsibilities during EOP usage.

G2.4.22 Emergency Procedures/Plans 3.6 4.4 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

G2.4.42 Emergency Procedures/Plans 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of emergency response facilities.

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

RO SRO 009EG2.2.25 Small Break LOCA / 3 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

This is a Generic, no stem statement is associated.

011 EG2.2.36 Large Break LOCA /3 3.1 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of This is a Generic, no stem statement is limiting conditions of operations associated.

026AA2.05 Loss of Component Cooling Water /8 2.4 2.5 0 0 0 0 0 0 0 ~ 0 0 0 The normal values for CCW-header flow rate and the flow rates to the components cooled by the CCWS Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13) 057AG2.4.21 Loss of Vital AC Inst. Bus / 6 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the parameters and logic used to assess the status of safety functions This is a Generic, no stem statement is associated.

058AA2.03 Loss of DC Power / 6 3.5 3.9 0 0 0 0 0 0 0 ~ 0 0 0 DC loads lost; impact on ability to operate and monitor plant systems Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13) 077AA2.04 Generator Voltage and Electric Grid 3.6 3.6 0 0 0 0 0 0 0 ~ 0 0 0 VARs outside the capability curve Disturbances / 6 Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.5/

45.13)

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ES-401, REV 9 SRO 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 024AG2.2.39 Emergency Boration 1 1 3.9 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of less than one hour technical specification action statements for systems.

This is a Generic, no stem statement is associated.

068AG2.4.21 Control Room Evac. 18 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the parameters and logic used to assess the status of safety functions This is a Generic, no stem statement is associated.

069AA2.02 Loss of CTMT Integrity 1 5 3.9 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Verification of automatic and manual means of restoring integrity Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10/43.51 45.13)

WE16EA2.1 High Containment Radiation 1 9 2.9 3.3 0 0 0 0 0 0 0 ~ 0 0 0 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.51 45.13)

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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 003A2.01 Reactor Coolant Pump 3.5 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Problems with RCP seals, especially rates of seal leak-off Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 026G2.4.47 Containment Spray 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room This is a Generic, no stem statement is reference material.

associated.

039A2.02 Main and Reheat Steam 2.4 2.7 0 0 0 0 0 0 0 ~ 0 0 0 Decrease in turbine load as it relates to steam escaping from relief valves Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 062G2.1.20

.20 AC Electrical Distribution 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to execute procedure steps.

This is a Generic, no stem statement is associated.

076A2.02 Service Water 2.7 3.1 0 0 0 0 0 0 0 ~ 0 0 0 Service water header pressure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

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ES-401, REV 9 SRO 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 033G2.2.22 Spent Fuel Pool Cooling 4.0 4.7 D D D D D D D D D D ~ Knowledge of limiting conditions for operations and safety limits.

This is a Generic, no stem statement is associated.

072A2.02 Area Radiation Monitoring 2.8 2.9 D D D D D D D ~ D D D Detector failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 086A2.01 Fire Protection 2.9 3.1 D D D D D D D ~ D D D Manual shu1down of the FPS Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13)

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ES-401, REV 9 SRO 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 G2.1.14 Conduct of operations 3.1 3.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1.36 Conduct of operations 3.0 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of procedures and limitations involved in core alterations G2.2.15 Equipment Control 3.9 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to determine the expected plant configuration using design and configuration control documentaion G2.2.3 Equipment Control 3.8 3.9 0 0 0 0 0 0 0 0 0 0 ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.3.13 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.3 Emergency Procedures/Plans 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~ Ability to identify post-accident instrumentation.

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ES-401, Rev. 9 Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KA 1/2 APE076 AK3.06 (Q25) There is a question that was used on the 2006R (exam bank #148) which would meet this but within 2 years. It deals with demineralizers which is the only real action in AP/18. Replaced with KIA APE036 AK3.03 2/1 SYS008 K4.07 Q(35) No such component at eNS. KIA replacements originally provided 4.04 and 4.08 are not high enough value (2.1 and 2.3) Replaced with KIA SYS008 K4.09 1/0 APE077 AA2.04 Q(81) Duplicate KA of RO exam #14. Replaced with KIA APE077 AA2.09 1/2 APE069 AA2.02 Q(84) Cannot write an SRO question. Replaced with KIA APE069 AA2.01

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ~RO DSRO Operating Test No.:

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

R N Using Data Book Figure 9 (Permissible Successive Attempts to Start Conduct of Operations Motors) determine the allowed starting time for NCP.

Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Calculate Unit Vent flow manually per PTjljAj44S0j017 (Unit Vent Flow Manual Calculation).

Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits Emergency 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 all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ~ 3 for ROs;.:5. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.:5. 1; randomly selected)

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 Exam Level ORO ~SRO Operating Test No.:

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

R M Determine if a work hours extension is required and if so, which limits Conduct of Operations are exceeded.

Conduct of Operations R M Perform a manual shutdown margin calculation (Unit at Power) per OPjOjAj6100j006 (Reactivity Balance Calculation) with untrippable rods Equipment Control S M Determine SLC requirements and complete a Unit Vent Flow Manual Calculation per PTjljAj4450j017 Radiation Protection R M Calculate the Maximum Permissible Stay Time Within Duke Power ALERT Administrative Dose Limits Emergency Plan R D Upgrade an Emergency Classification and Complete an Emergency Notification Form 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)

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 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 E System / JPM Title Type Code* Safety Function

a. Perform a Manual Makeup to the vcr D S 1

b. Respond to NC System Leakage A D S 2

c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D S 3 a SGTR

d. Cooldown the PRT Using NCDT Heat Exchanger D S 5

e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D S  ?

Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S

h. Perform the Immediate Actions of AP/1/A/5500/004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump)

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

i. Locally Break Vacuum on a Loss of Feedwater D E 4S

j. Align Seal Injection to the Unit 2 NC Pumps D E 2

k. Alternate Cooling to 1A NV Pump D E R 8

@ 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 (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnormal in-plant .=::1 I.=::1 I.=::1 (EN)gineered safety feature - 1 - I.=:: 1 (control room system)

(L)ow-Power 1 Shutdown .=::1 I.=::1 I.=::1 (N)ew or (M)odified from bank including 1 (A) .=::2 I.=::2 I.=::1 (P)revious 2 exams ~ 3 1 ~ 3 1 ~ 2 (randomly selected)

(R)CA .=::1 I.=::1 I.=::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 12/1/2008 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 E System / JPM Title Type Code* Safety Function a.

b. Respond to NC System Leakage A D 5 2

c. Depressurize the NC System to Minimize Primary to Secondary Leakage during A D 5 3 a SGTR

d. Cooldown the PRT Using NCDT Heat Exchanger D 5 5

e. Restore Offsite Power to 6.9 kV Busses per AP/O? (Loss of Normal Power) A N 5 6 Enclosure 21 (Black Restart Procedure)

f. Perform the Immediate Actions of AP/1/A/5500/16, (Malfunction of Nuclear D 5  ?

Instrumentation System), Case 4, (P/R Malfunction)

g. Manually Operate the Steam Dump Valves from the Control Room D L 5 45

h. Perform the Immediate Actions of AP/1jA/5500/004, (Loss of Reactor Coolant A EN M 5 4P Pump) for Loss of One NC Pump)

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

i. Locally Break Vacuum on a Loss of Feedwater D E 45

j. Align Seal Injection to the Unit 2 NC Pumps D E 2

k. Alternate Cooling to 1A NV Pump D E R 8

@ 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-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnonmal in-plant ~1/~1/~1 (EN)gineered safety feature - I - I ~ 1 (control room system)

(L)ow-Power I Shutdown  :=:1 I:=:1 I:=:1 (N)ew or (M)odified from bank including 1(A) ~2/:=:2/~1 (P)revious 2 exams ~3 I ~ 3 I ~ 2 (randomly selected)

(R)CA  :=:1/:=:1/~1 (S)imulator

ES-301, Rev. 9 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Catawba Nuclear Station Date of Examination 12/1/2008 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 E System / JPM Title Type Code* Safety Function a.

b.

c.

d.

e. Restore Offsite Power to 6.9 kV Busses per APjO? (Loss of Normal Power) A N S 6 Enclosure 21 (Black Restart Procedure) f.

g. Manually Operate the Steam Dump Valves from the Control Room D L S 4S

h. Perform the Immediate Actions of APj1jAj5500j004, (Loss of Reactor Coolant A EN M S 4P Pump) for Loss of One NC Pump)

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

j. Align Seal Injection to the Unit 2 NC Pumps D E 2

k. Alternate Cooling to 1A NV Pump D E R 8

@ 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 (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature - / - / ~ 1 (control room system)

(L)ow-Power / Shutdown ~1/~1/~1 (N)ew or (M)odifjed from bank including 1(A) ~2/~2/~1 (P)revious 2 exams ~ 3 / ~ 3 / ~ 2 (randomly selected)

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