ML082200166

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March 05000400-08-301 Exam Draft ES-401-6 Checklist & Sample Plan
ML082200166
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 08/07/2008
From:
- No Known Affiliation
To:
NRC/RGN-II
References
50-400/08-301
Download: ML082200166 (15)
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Text

Draft Submittal (Pink Paper)

DRAFT Written Exam Quality Checklist (ES-401-6)

& Written Exam Sample Plan IIri£ £/S, ;= X/i-M

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ES-401 Form ES-401-6 Facility: Harris Date of Exam: 3/10/2008 Exam RO/SRO Level:

Initial Item Description a b* C#

1. Questions and answers technically accurate and applicable to facilitv. ~
2. a. NRC KJAs referenced for all questions.
b. Facilitv learninq objectives referenced as available. <J"bc<l
3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 VJ.,{
4. The sampling process was random and systematic. (If more than 4 RO and 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL eJM Proqram Office)
5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

- - - the audit exam was systematically and randomly developed, or

- - - the audit exam was completed before the license exam was started, or OM

- - - the examinations were developed independently, or

~ the licensee certifies that there is no duplication, or other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 31 /9 13/10 31/6 GW{

question distribution(s) at riqht,

7. Between 50 and 60 percent of the question on the Memory CIA RO exam are written at the comprehension!

analysis level; the SRO exam may exceed 60 percent if the randomly selected KJAs support the 33/4 42/21 <JPt4 higher cognitive levels; enter the actual RO / SRO question distributiorus) at riqht

8. References/handouts provided do not give away answers or aid in the elimination of distractors.

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9. Question content conforms with specific KJA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are iustified.

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10. Question psychometric quality and format meet the guidelines in ES Appendix B. WAIf II
11. The exam contains the required number of one-point, multiple choice items; the 1 total is correct and aarees with value on cover sheet. OM I Printed Name / Sig~/) Date
a. Author Joseph G. Arsenault

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b. Facility Reviewer (*)
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor Note:
  • The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
  1. Independent NRC reviewer initial items in Column "c"; chief examiner concurrence reauired.

DRAFT NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2 I~ Facility: Harris 2008 NRC Outline Date of Exam: 3/10/08

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\ RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 2 2 1 1 1 2 9 2 2 4 Plant Evolutions Tier 5 5 4 4 4 5 27 5 5 10 Totals 1 3 1 3 3 3 2 3 2 3 2 3 28 2 3 5

2. Plant Systems 2 1 1 1 0 1 1 0 2 1 1 1 10 0 2 1 3 Tier 4 2 4 3 4 3 3 4 4 3 4 38 4 4 8 Totals
3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 2 2 4 2 2 1 2 Note: 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 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 KAs 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) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the 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; 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 KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10CFR55.43

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NUREG-1021 DD.\D J.

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HARRIS 2008 NRC 401-2 SUBMITTAL

ESA01 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

~ E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) I Imp. [§!J Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal 025 / Loss of Residual Heat Removal System /4 X AA2,02 System: Leakage of reactor coolant from RHR into 3,8 76 closed cooling water system or into reactor building atmosphere Conduct of Operations: Knowledge of system 026 / Loss of Component Cooling Water / 8 X 2.1.27 2.9 77 purpose and or function, Conduct of Operations: Knowledge of system status 038 / Steam Generator Tube Rupture / 3 X 2.1,14 criteria which require the notification of plant 3,3 78 personnel.

Ability to determine and interpret the following as 040 / Steam Line Rupture /4 X AA2.05 they apply to the Steam Line Rupture: When 4,5 79 ESFAS systems may be secured Conduct of Operations: Ability to recognize indications for system operating parameters which E04 / LOCA Outside Containment / 3 X 2.1,33 4.0 80 are entry-level conditions for technical specifications.

Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant E11 / Loss of Emergency Coolant Recirculation /4 X EA2.2 Recirculation): Adherence to appropriate 4.2 81 procedures and operation within the limitations in the facility's license and amendments.

Conduct of Operations: Ability to perform specific 007 / Reactor Trip / 1 X 2.1.23 system and integrated plant procedures during all 3,9 39 modes of plant operation.

Knowledge of the interrelations between the 008/ Pressurizer Vapor Space Accident / 3 X AK2.03 Pressurizer Vapor Space Accident and the 2,5 40 following: Controllers and positioners Knowledge of the interrelations between the small 009 / Small Break LOCA / 3 X EK2.03 3.0 41 break LOCA and the following: S/Gs Ability to operate and monitor the following as they 011 / Large Break LOCA / 3 X EA1,15 apply to a Large Break LOCA: RCS temperature 4.2 42 and pressure Knowledge of the operational implications of the following concepts as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

015/ 17/ Reactor Coolant Pump Malfunctions /4 X AK1.05 2,7 43 Effects of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrant power tilt NUREG-1021 2 HARRIS 2008 NRC 401-2 SUBMITTAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

~ E/APE # I Name Safety Function I G I K1 I K2 I K3 I A 1 I A2 I Number I KIA Topic(s) I Imp. l§!J Conduct of Operations: Knowledge of the purpose 022 / Loss of Reactor Coolant Makeup /2 X 2.1.28 and function of major system components and 3.2 44 controls.

Ability to operate and/or monitor the following as they apply to the Loss of Residual Heat Removal 025 / Loss of Residual Heat Removal System /4 X AA1.20 2.6 45 System: HPI pump control switch, indicators, ammeter running lights, and flow meter Ability to operate and/or monitor the following as 027/ Pressurizer Pressure Control System Malfunction they apply to the Pressurizer Pressure Control X AA1.03 3.6 46

/3 Malfunctions: Pressure control when on a steam bubble Ability to determine or interpret the following as they 029 / Anticipated Transient Without Scram (ATWS) / 1 X EA2.05 apply to a ATWS: System component valve position 3.4 47 indications Knowledge of the operational implications of the 038/ Steam Generator Tube Rupture / 3 X EK1.03 following concepts as they apply to the SGTR: 3,9 48 Natural Circulation Knowledge of the operational implications of the following concepts as they apply to Steam Line 040/ Steam Line Rupture / 4 X AK1.07 3.4 49 Rupture: Effects of feedwater introduction on dry S/G Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

054 / Loss of Main Feedwater / 4 X AA2.04 4.2 50 Proper operation of AFW pumps and regulating valves Conduct of Operations: Knowledge of operator 056 / Loss of Off-site Power / 6 X 2.1,2 3.0 51 responsibilities during all modes of plant operation.

Knowledge of the reasons for the following 058 / Loss of DC Power / 6 X AK3.02 responses as they apply to the Loss of DC Power: 4.0 52 Actions contained in EOP for loss of DC power Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear 062 / Loss of Nuclear Service. Water / 4 X AK3.02 Service Water: The automatic actions (alignments) 3.6 53 within the nuclear service water resulting from the actuation of the ESFAS NUREG-1021 3 HARRIS 2008 NRC 401-2 SUBMITTAL

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! E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) I Imp. I Q# i Knowledge of the interrelations between the (LOCA Outside Containment) and the following: Facility's heat removal systems, including primary coolant, E04 / LOCA Outside Containment / 3 X EK2.2 emergency coolant, the decay heat removal 3.8 54 systems, and relations between the proper operation of these systems to the operation of the facility.

Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary E05 / Loss of Secondary Heat Sink / 4 X EA2.2 Heat Sink): Adherence to appropriate procedures 3.7 55 and operation within the limitations in the facility's license and amendments.

Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency E11 / Loss of Emergency Coolant Recirculation /4 X EK3.3 Coolant Recirculation): Manipulation of controls 3.8 56 required to obtain desired operating results during abnormal and emergency situations.

KIA Category Point Totals: 3/3 3 3 3 3 3/3 Group Point Total: I 18/6 NUREG-1021 4 HARRIS 2008 NRC 401-2 SUBMITTAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

~ E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) I Imp. I Q# i Emergency Procedures/Plan: Ability to verify system 005/ Inoperable/Stuck Control Rod / 1 X 2.4.50 alarm setpoints and operate controls identified in the 3.3 82 alarm response manual.

Ability to determine and interpret the following as 068 / Control Room Evacuation / 8 X AA2.10 they apply to the Control Room Evacuation: Source 4.4 83 range count rate Conduct of Operations: Knowledge of operator E06/ Degraded Core Cooling /4 X 2.1.2 4.0 84 responsibilities during all modes of plant operation.

Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam E10 / Natural Circulation with Steam Void in Vessel X EA2.1 Void in Vessel with/without RVLlS): Facility 3.9 85 with/without RVLlS / 4 conditions and selection of appropriate procedures during abnormal and emergency operations.

Knowledge of the operational implications of the 003 / Dropped Control Rod / 1 X AK1.11 following concepts as they apply to Dropped Control 2.5 57 Rod: Long-range effects of core quadrant power tilt Knowledge of the interrelations between the 024 / Emergency Boration / 1 X AK2.03 Emergency Boration and the following: Controllers 2.6 58 and positioners Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate 033/ Loss of Intermediate Range Nuclear X AK3.02 Range Nuclear Instrumentation: Guidance 3.6 59 Instrumentation /7 contained in EOP for loss of intermediate range instrumentation Ability to determine and interpret the following as 036 / Fuel Handling Incidents / 8 X AA2.01 they apply to the Fuel Handling Incidents: ARM 3.2 60 system indications Emergency Procedures/Plan: Ability to verify system 059 / Accidental Liquid RadWaste Release / 9 X 2.4.50 alarm setpoints and operate controls identified in the 3.3 61 alarm response manual.

Conduct of Operations: Ability to explain and apply 060 / Accidental Gaseous RadWaste Release / 9 X 2.1.32 3.4 62 all system limits and precautions.

Knowledge of the interrelations between the Loss of 069/ Loss of Containment Integrity /5 X AK2.03 Containment Integrity and the following: Personnel 2.8 63 access hatch and emergency access hatch Knowledge of the operational implications of the 074/ Inadequate Core Cooling /4 X EK1.06 following concepts as they apply to the Inadequate 3.0 64 Core Cooling: Definition of superheated steam NUREG-1021 5 HARRIS 2008 NRC 401-2 SUBMITTAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions- Tier 1 Group 2 II E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) I Imp. @!J Ability to operate and/or monitor the following as they apply to the (Natural Circulation with Steam E10/ Natural Circulation with Steam Void in Vessel X EAU Void in Vessel with/without RVLlS): Desired 3.4 65 with/without RVLlS / 4 operating results during abnormal and emergency situations.

KiA Category Point Total: 2/2 2 2 1 1 1/2 Group Point Total: I 9/4 NUREG-1021 6 HARRIS 2008 NRC 401-2 SUBMITTAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1

~ System #/Name [G] K1 I K2 I K3 I K4 I K5 I K6 I A1 I A2 I A3 I A4 I Number I KIA Topics I Imp. I Q# i Conduct of Operations: Ability to recognize indications for system operating parameters which 006 Emergency Core Cooling X 2.1.33 4.0 86 are entry-level conditions for technical specifications.

Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to 012 Reactor Protection X A2.04 3.2 87 correct, control, or mitigate the consequences of those malfunctions or operations: Erratic power supply operation Emergency Procedures/Plan: Knowledge of 026 Containment Spray X 2.4.31 annunciators, alarms and indications, and use of 3.4 88 the response instructions.

Conduct of Operations: Ability to explain and 073 Process Radiation Monitoring X 2.1.32 3.8 89 apply all system limits and precautions.

Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; and (b) based on those predictions, use procedures to 078 Instrument Air X A2.01 2.9 90 correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions.

Knowledge of the operational implications of the following concepts as they apply to the RCPS:

003 Reactor Coolant Pump X K5.03 Effects of RCP shutdown on Tave, including the 3.1 1 reason for the unreliability of Tave in the shutdown loop Knowledge of the operational implications of the 004 Chemical and Volume X K5.19 following concepts as they apply to the CVCS: 3.5 2 Control Concept of SOM Knowledge of the physical connections and/or 005 Residual Heat Removal X K1.11 cause-effect relationships between the RHRS and 3.5 3 the following systems: RWST Knowledge of the effect of a loss or malfunction 005 Residual Heat Removal X K6.03 on the following will have on the RHRS: RHR heat 2.5 4 exchanger Knowledge of the physical connections and/or 006 Emergency Core Cooling X K1.08 cause effect relationships between the ECCS and 3.6 5 the following systems: CVCS Knowledge of ECCS design feature(s) and/or 006 Emergency Core Cooling X K4.05 interlock(s) which provide for the following: Auto 4.3 6 start of HPI/LPI/SIP NUREG-1021 7 HARRIS 2008 NRC 401-2 SUBMITIAL

ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1

! System #/Name I G I K1 I K2 I K3 I K4 , K5 I K6 I A1 I A2 I A3 I A4 I Number I KIA Topics I Imp. I Q# i Knowledge of PRTS design feature(s) and/or 007 Pressurizer Relief/Quench X K4.01 interlock(s) which provide for the following: 2.6 7 Tank Quench tank cooling Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to 008 Component Cooling Water X A2.08 correct, control, or mitigate the consequences of 2.5 8 those malfunctions or operations: Effects of shutting (automatically or otherwise) the isolation valves of the letdown cooler Knowledge of bus power supplies to the following:

010 Pressurizer Pressure Control X K2.01 3.0 9 Pressurizer Heaters Knowledge of the effect of a loss or malfunction of 012 Reactor Protection X K6.03 the following will have on the RPS: Trip logic 3.1 10 circuits Ability to monitor automatic operation of the RPS, 012 Reactor Protection X A3.02 3.6 11 including: Bistables Knowledge of the effect that a loss or malfunction 013 Engineered Safety Features X K3.03 of the ESFAS will have on the following: 4.3 12 Actuation Containment Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 022 Containment Cooling X A1.01 3.6 13 associated with operating the CCS controls including: Containment temperature Knowledge of the physical connections and/or 022 Containment Cooling X K1.01 cause-effect relationships between the CCS and 3.5 14 the following systems: SWS/cooling system Ability to monitor automatic operation of the CSS, 026 Containment Spray X A3.01 including: Pump starts and correct MOV 4.3 15 positioning Equipment Control: Knowledge of limiting 026 Containment Spray X 2.2.22 3.4 16 conditions for operations and safety limits.

Ability to manually operate and/or monitor in the 039 Main and Reheat Steam X A4.01 2.9 17 control room: Main Steam supply valves Ability to monitor automatic operation of the MFW, 059 Main Feedwater X A3.02 2.9 18 including: Programmed levels of the S/G Knowledge of the effect that a loss or malfunction 059 Main Feedwater X K3.03 3.5 19 of the MFW will have on the following: S/GS NUREG-1021 8 HARRIS 2008 NRC 401-2 SUBMITIAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1

!System #/Name I G I K1 I K2 Li§J K4 I K5 I KG I A1 I A2 I A3 I A4 I Number I KIA Topics I Imp. I Q# i 061 Auxiliary/Emergency Equipment Control: Knowledge of limiting X 2.2.22 conditions for operations and safety limits.

3.4 20 Feedwater Knowledge of the operational implications of the 061 Auxiliary/Emergency following concepts as they apply to the AFW:

X K5.01 3.6 21 Feedwater Relationship between AFW flow and RCS heat transfer Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AC distribution 062 AC Electrical Distribution X A1.03 2.5 22 system controls including: Effect on instrumentation and controls of switching power supplies Knowledge of the effect that a loss or malfunction 063 DC Electrical Distribution X K3.02 of the DC electrical system will have on the 3.5 23 following: Components using DC control power Knowledge of ED/G system design feature(s) 064 Emergency Diesel Generator X K4.04 and/or interlock(s) which provide for the following: 3.1 24 Overload ratings Ability to manually operate and/or monitor in the 073 Process Radiation Monitoring X A4.02 control room: Radiation monitoring system control 3.7 25 panel Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) 076 Service Water X A2.01 based on those predictions, use procedures to 3.5 26 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Conduct of Operations: Knowledge of the 078 Instrument Air X 2.1.28 purpose and function of major system 3.3 27 components and controls.

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 103 Containment X A1.01 associated with operating the containment system 3.7 28 controls including: Containment pressure, temperature, and humidity KIA Category Point Totals: 3/3 3 1 3 3 3 2 3 2/2 3 2 Group Point Total:

I 28/5 NUREG-1021 9 HARRIS 2008 NRC 401-2 SUBMITTAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topics Equipment Control: Knowledge of limiting 002 Reactor Coolant X 2.2.22 4.1 91 conditions for operations and safety limits.

Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to 015 Nuclear Instrumentation X A2.02 correct, control, or mitigate the consequences of 3.5 92 those malfunctions or operations: Faulty or erratic operation of detectors or compensating components Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b based on those predictions, use procedures to 016 Non-nuclear Instrumentation X A2.03 3.3 93 correct, control, or mitigate the consequences of those malfunctions or operations: Interruption of transmitted signal Ability to monitor automatic operation of the 001 Control Rod Drive X A3.04 3.5 29 CROS, including: Radial imbalance Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to 002 Reactor Coolant X A2.02 4.2 30 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of coolant pressure Knowledge of bus power supplies to the following:

011 Pressurizer Level Control X K2.02 3.1 31 PZR heaters Knowledge of the effect that a loss or malfunction 016 Non-nuclear Instrumentation X K3.03 3.0 32 of the NNIS will have on the following: SOS Knowledge of the effect of a loss or malfunction of 017 In-core Temperature Monitor X K6.01 the following ITM system components: Sensors 2.7 33 and detectors Knowledge of the physical connections and/or 041 Steam Dump X K1.05 cause-effect relationships between the SOS and 3.5 34 the following systems: RCS Ability to manually operate and/or monitor in the 029 Containment Purge X A4.01 2.5 35 control room: Containment Purge flow rate Conduct of Operations: Knowledge of system 034 Fuel Handling Equipment X 2.1.14 status criteria which require the notification of 2.5 36 plant personnel.

NUREG-1021 10 HARRIS 2008 NRC 401-2 SUBMITIAL

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ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number KIA Topics Imp. Q#

Knowledge of the operational implications of the following concepts as the apply to the MT/G 045 Main Turbine Generator X K5.23 System: Relationship between rod control and 2.7 37 RCS boron concentration during T/G load increases Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use 056 Condensate System X A2.12 procedures to correct, control, or mitigate the 2.8 38 consequences of those malfunctions or operations: Opening of the heater string bypass valve KIA Category Point Totals: 1/1 1 1 1 0 1 1 0 2/2 1 1 Group Point Total: I 10/3 NUREG-1021 11 HARRIS 2008 NRC 401-2 SUBMITTAL

I ES-401 Generic Knowledge and Abilities Outline (Tier3) I Form ES-401-3 I Facility:

I Harris 2008 NRC Outline I Date of Exam:

I 3/10108

( Category KIA # Topic RO SRO-Only IR Q# IR Q#

Ability to maintain primary and secondary plant 2.1.34 2.9 94 chemistry within allowable limits.

2.1.20 Ability to execute procedure steps. 4.2 95 1.

2.1.3 Knowledge of shift turnover practices. 3.0 66 Conduct of Operations Ability to explain and apply all system limits and 2.1.32 3.4 67 precautions.

Subtotal 2 2 Knowledge of the process for conducting tests or 2.2.7 experiments not described in the safety analysis 3.2 96 report.

Knowledge of limiting conditions for operations and*

2.2.22 4.1 97 safety limits.

2.

Equipment Control 2.2.26 Knowledge of refueling administrative requirements. 2.5 68 2.2.12 Knowledge of surveillance procedures. 3.0 69 Subtotal 2 2 Knowledge of the requirements for reviewing and 2.3.6 3.1 98 approvinq release permits.

( Knowledge of radiation exposure limits and

3. 2.3.4 contamination control, including permissible levels in 2.5 70 Radiation Control excess of those authorized.

2.3.2 Knowledge of facility ALARA program. 2.5 71 Subtotal 2 1 Ability to perform without reference to procedures 2.4.49 those actions that require immediate operation of 4.0 99 system components and controls.

Knowledge of the emergency action level thresholds 2.4.41 4.1 100 and classifications.

4. 2.4.10 Knowledge of annunciator response procedures. 3.0 72 Emergency Procedures 2.4.6 Knowledge symptom based EOP mitigation strategies. 3.1 73 1 Plan Ability to interpret control room indications to verify the status and operation of system, and understand how 2.4.48 3.5 74 operator actions and directives affect plant and system conditions.

2.4.29 Knowledge of the emergency plan. 2.6 75 Subtotal 4 2 Tier 3 Point Total 10 7 NUREG-1021 12 HARRIS 2008 NRC 401-2 SUBMITTAL

ES-401 Record of Rejected KlAs Form ES-401-4 Harris NRC 3/10/08 Tier / Randomly

( Group Selected KIA Reason for Rejection 1/1 056 G2.4.30 KIA < 2.5 for RO. Randomly replaced with 056 G2.1.2.

2/2 002 K4.09 Plant design - no loop isolation valves. Randomly replaced with 002 A2.02.

2/1 078 G2.2.22 No TS for this system. Randomly replaced with 078 G2.1.28.

Plant design - no diesel-driven AFW Pump. Randomly replaced with 061 2/1 061 K2.03 K5.01.

No design feature or interlock related to these components. Randomly 2/1 006 K4.22 reselected 006 K4.05 No design limit or procedurally directed action related to containment humidity.

2/1 022 A1.03 Randomly selected 022 A1.01 No relationship between systems at facility. No other 027 K1 topics available.

2/2 027 K1.01 Randomly reselected 041 K1.05 to replace Too difficult to develop an operationally relevant test item for topic, and facility 1/1 038 EK1.04 has no reference material related to topic to support any discussion of the topic. Randomly selected 038 EK1.03 No immediate actions required related to system. Randomly selected 073 2/1 073 G2.4.49 G2.1.32 No physical connection between systems selected. Randomly selected 005 2/1 005 K1.10 K5.11 Facility does not have indicator requiring standard power supply. Randomly 2/1 010 K2.04 selected 010 K2.01

( 2/2 029 A4.04 No relationship between the system and topic selected, whether by interlock or by operator action. Randomly selected 029 A4.01 NUREG-1021 13 HARRIS 2008 NRC 401-2 SUBMITTAL

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