ML082200233

March 05000400-08-301 Exam Final Outlines

ML082200233
Person / Time
Site:	Harris
Issue date:	08/07/2008
From:	- No Known Affiliation
To:	NRC/RGN-II
References
50-400/08-301
Download: ML082200233 (19)

Text

Final Submittal (Blue Paper) l-!Ae.R")S ZaB-30\

Of res\ 3/10- slrs/ltJ.J8 WI ;-<<~V\ A:!>,uIA)I~~ 3/Z//2eKJ o FINAL OUTLINES

ES-301 Administrative Topics Outline Form ES-301-1 Facility: HARRIS Date of Examination: March, 2008 Examination Level (circle one): ~/SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine the cold, xenon free boron concentration Conduct of Operations M requirement prior to commencing a natural circulation cooldown. (EPP-005/0ST-1036)

G2.1 .25 (2.8/3.1) - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Estimate Primary to Secondary Leak Rate. (AOP-016, Conduct of Operations M Curve Book) 2.1.25 (2.8) - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Perform a Quadrant Power Tilt Ratio (QPTR)

Equipment Control M calculation with a control rod misaligned. (OST-1039) 2.2.12 (3.0) - Knowledge of surveillance procedures.

Given an emergency situation, determine the Radiation Control M applicable dose limit and the number of people that will be required to perform the task, with no one exceeding the limit.

2.3.4 (2.5/3.1) - Knowledge of radiation exposure limits and contamination control, including permissible limits in excess of those authorized.

Emergency Plan NOT SELECTED FOR RO NOTE: All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room (D)irect from bank (~ 3 for ROs; s for SROs & RO retakes)

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

(P)revious 2 exams (~ 1; randomly selected)

(S)imulator NUREG-1021 , Revision 9 HARRIS 2008 NRC RO 301-1, Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: HARRIS Date of Examination: March,2008 Examination Level (circle one): RO/lsRq Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine the cold, xenon free RCS boron Conduct of Operations M concentration requirement prior to commencing a natural circulation cooldown. (EPP-005/0ST-1036)

G2.1.25 (2.8/3.1) - Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Perform a Control Room Supervisor review of the Conduct of Operations P,M control board readings log. (OST-1021, Attachment 4)

G2.1.18 (3.0) - Ability to make accurate, clear and concise logs, records, status boards, and reports .

Review the completed surveillance for Motor Driven Equipment Control N AFW Pump "A". (OST-1211) 2.2.12 (3.4) - Knowledge of surveillance procedures.

'Given an emergency situation, determine the Radiation Control M applicable dose limit and the number of people that will be required to perform the task, with no one exceeding the limit.

2.3.4 (2.5/3 .1) - Knowledge of radiation exposure limits and contamination control, including permissible limits in excess of those authorized.

Evaluate a change in conditions with an EAL in effect Emergency Plan M and take the required actions.

2.2.41 (4.1) - Knowledge of the emergency action level thresholds and classifications.

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

• Type Codes & Criteria: (C)ontrol room (D)irect from bank (~3 for ROs; s for SROs & RO retakes)

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

(P)revious 2 exams (~ 1; randomly selected)

(S)imulator NUREG-1021, Revision 9 HARRIS 2008 NRC SRO 301-1, Revision 2

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: HARRIS Date of Examination: 3/2008 Exam Level (circle one): RO / SRO(I) / SRO (U) Operating Test No.: NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Initiate Emergency Boration following a reactor trip (AOP-002) M,A,S 1 System: 004/Bank JPM CR-037

b. Align ECCS for long-term recirculation (EPP-010) M,A,S 3 System: EPE011/Bank JPM CR-031

c. Initiate RCS Feed and Bleed (FRP-H.1) P,D,A,S 4P System: E05/2007 NRC Exam JPM d

d. Respond to a loss of Normal Service Water (AOP-022) N,A,S 4S System: 076

e. Place the Containment Hydrogen Purge System in operation (OP- D,C 5 125)

RO Only System: 028/Bank JPM CR-021

f. Transfer an Emergency Bus to an EDG due to a degraded grid N,A,S 6 condition (AOP-028, Attachment 2)

System: 062

g. Respond to a Fuel Handling Building RMS alarm (AOP-005, OP-170) N,L,S 7 System: 072

h. Align CCW to support RHR Initiation (OP-145) D,L,S 8 System: 008/Bank JPM CR-085 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Perform the local actions for a dropped rod recovery (AOP-001) D,E 1 System: 001/Bank JPM IP-153 NUREG-1021 , Revision 9 HARRIS 2008 NRC 301-2, Revision 2

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2

j. Isolate the ECCS Accumulators after a control room evacuation N,E 8' (AOP-004, Step 38)

System: APE068

k. Terminate a Waste Gas Release (OP-120.07) P,O,R 9 System: 071/2007 NRC JPM k

@ 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 12-3 (C)ontrol room (D)irect from bank ~ 9/ s 8 / s 4 (E)mergency or abnormal in-plant  :::: 1 /:::: 1 /:::: 1 (L)ow-Power 1 Shutdown :2 1 /? 1 /~ 1 (N)ew or (M)odified from bank including 1(A) "2 2 /:::. 2 /?:. 1 (P)revious 2 exams  ::; 3 1:; 3 1::: 2 (randomly selected)

(R)CA 2: 1 / ?:. 1 / ~ 1

{S)imulator HARRIS 2008 NRC 301-2 JPM

SUMMARY

STATEMENTS

a. Initiate Emergency Boration in accordance with AOP-002, EMERGENCY BORATION, following a reactor trip. The alternate path is to take corrective action for two or more stuck rods as determined in EPP-004, REACTOR TRIP. Modified from Bank JPM CR-037 by failing first boration path driving candidate to use secondary means .

b. Transfer to Cold Leg Recirculation in accordance with EPP-010, TRANSFER TO COLD LEG RECIRCULATION, following a LBLOCA. The alternate paths are corrective actions for alignment failures in two different ftowpaths. Modify Bank JPM CR-031 by changing the misaligned valve in one RNO step and the running pump combination.

c. Initiate RCS Feed and Bleed lAW FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. The alternate path is to establish an adequate vent path using RV Head Vents following failure of one PORV to open. Randomly selected repeat from 2007 NRC Exam (JPM d) not in the facility bank.

d. Respond to a loss of the only available Normal Service Water Pump in accordance with AOP-022, LOSS OF SERVICE WATER. The alternate path is to start one Essential Service Water Pump and to trip the Main Turbine with power less than P-10. New JPM.

e. Place the Containment Hydrogen Purge System in operation in accordance with OP-125, POST ACCIDENT HYDROGEN SYSTEM . Bank JPM CR-021. This JPM will be simulated in the Main Control Room (using cues) because some equipment important to the task is not simulated.

NUREG-1021, Revision 9 HARRIS 2008 NRC 301-2, Revision 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

f. With a degraded grid condition, transfer an emergency bus to an EDG in accordance with AOP-028, GRID INSTABILITY - Attachment 2, ENERGIZING EMERGENCY BUSES FROM EDGS, by purposely de-energizing a bus. The alternate path is starting an EDG following evaluation of Voltage/Frequency on an emergency bus and manually resetting the Load Sequencer after the cycle is complete. New JPM.

g. Respond to a Fuel Handling Building RMS alarm in accordance with AOP-005, RADIATION MONITORING SYSTEM, and OP-170, FUEL HANDLING BUILDING HVAC. A FHB monitor alarms and FHB HVAC components fail to align properly. New JPM.

h. Align CCW to support RHR Initiation in accordance with OP-145, COMPONENT COOLING WATER. Bank JPM CR-085 .

i. Perform the local actions for a dropped rod recovery in accordance with AOP-001, MALFUNCTION OF ROD CONTROL AND INDICATION SYSTEM. Bank JPM-IP-153.

j. Isolate the ECCS Accumulators after a control room evacuation in accordance with AOP-004, REMOTE SHUTDOWN, Step 38. New JPM.

k. Terminate a Waste Gas Release in accordance with OP-120.07, WASTE GAS PROCESSING. Randomly selected repeat from 2007 NRC Exam (JPM k).

NUREG-1021 , Revision 9 HARRIS 2008 NRC 301-2, Revision 2

FI~AL..

ES-401 PWR Examination Outline Form ES-401-2 Facility: Harris 2008 NRC Outline Date of Exam: 3/10108 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 (Le., 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 categor ies.

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 NUREG-1021 1

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

~ E/APE # / Name Safety Function ~ Number I KIA Topic(s) l imp. ~

Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal 025 I Loss of Residual Heat Removal System I 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: Ability to evaluate plant performance and make operational judgments 057 I Loss of Vital AC Instrument Bus I 8 X 2.1.7 4.4 77 based on operating characteristics, reactor behavior, and instrument interpretation.

Conduct of Operations: Knowledge of system status 038 I Steam Generator Tube Rupture I 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 I Steam Line Rupture I 4 X AA2.05 they apply to the Steam Line Rupture: When 4.5 79 ESFAS systems may be secured Ability to operate and I or monitor the following as they apply to LOCA Outside Containment: Desired E04 I LOCA Outside Containment I 3 X EA1.3 4.0 80 operating results during abnormal and emergency situations.

Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant E11 I Loss of Emergency Coolant Recirculation 14 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 I Reactor Trip 11 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 I Pressurizer Vapor Space Accident I 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 I Small Break LOCA I 3 X EK2.03 3.0 41 break LOCA and the following: S/Gs Ability to operate and monitor the following as they 011 I Large Break LOCA I 3 X EA1.15 apply to a Large Break LOCA: RCS temperature 4.2 42 and pressure NUREG-1021 2

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 @IK1IK2IK3IA1I A2 I Number I KIA Topic(s) I Imp. I Q# ~

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 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 follow ing 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: HPJ 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 Trans ient 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 Rupture : Effects of feedwater introduction on dry 3.4 49 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 Proper operation of AFW pumps and regulating 4.2 50 valves Conduct of Operations: Knowledge of operator 056/ Loss of Off-site Power / 6 X 2.1 .2 responsibilities during all modes of plant operation .

3.0 51 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 NUREG-1021 3

ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 II *E/APE # / Name Safety Function ~ Number I KIA Topic(s) l imp. @!J 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 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 ~mergency 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

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 [K3] A1 I A2 I Number I KIA Topic(s) I Imp. ~

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 respons ibilities 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 determ ine 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/lnadequate 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

ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 I E/APE # I Name Safety Function IG ~ K3 I A1 I A2 I Number I KIA Topic(s) I Imp. I Q# ~

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 EA1.3 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

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

~ System #/Name """N

-u-m- b-e-r....1~~====KI=A=T=o~P=ic=s====~"'I-lm -p-*--"1=Q=#='~

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 008 Component Cooling Water X A2.01 correct , control, or mitigate the consequences of 3.6 90 those malfunctions or operat ions: Loss of CCW Pump 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 SDM Knowledge of the physical connect ions 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 HPIILPI/SIP NUREG-1021 7

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

~ System #/Name Number I KIA Topics I Imp. ~

Knowledg~ 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 061 Auxiliary/Emergency Equipment Control: Knowledge of limiting X 2.2.22 3.4 20 Feedwater conditions for operations and safety limits.

NUREG-1021 8

ES-401 Harris 2008 NRC Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1 II System #/Name Number I KIA Topics I Imp. L:9!J Knowledge of the operational implications of the 061 Auxiliary/Emergency following concepts as they apply to the AFW:

Feedwater X K5.01 3.6 21 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

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

! ~~m m~me ~~K-1~I-K-2~I-K-3~~

K

4~K=5~=K=69=A=1~~~ N u-m-b=e=r~l~~~~~=~-A~ Th=p=~=s~~~~~1 Imp. ~

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 CRDS, including: Radial imbalance Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predict ions, use procedures to 002 Reactor Coolant X A2.02 correct, control, or mitigate the consequences of 4.2 30 those malfunctions or operations: Loss of coolant pressure Knowledge of bus power supplies to the following:

011 Pressurizer Level Control X K2.01 Charging Pumps 3.1 31 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 follow ing: SDS 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 SDS and 3.5 34 the following systems: RCS Ability to manually operate and/or monitor In the 029 Containment Purge X A4.04 control room: Containment Evacuation Signal 3.5 35 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

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 operat ional 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 1013 NUREG -1021 11

I ES-401 Generic Knowledge and Abilities Outline (Tier3)

Facility:

I Harris 2008 NRC Outline I Date of Exam:

I 3/10108 RO SRO-Only Category KIA # Topic 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 new and spent fuel movement 2.2.28 3.5 96 procedures.

Knowledge of limiting conditions for operations and

' 2.2.22 4.1 97 safe ty 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 requiremen ts for reviewing and 2.3.6 3.1 98 approving 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 com ponents 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 strateg ies. 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

ES-401 Record of Rejected KlAs Form ES-401-4 Harris NRC 3/10/08 Tier/ Randomly Reason for Rejection Group Selected KIA 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 A 1.01 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 2/2 011 K2.02 Duplicate topic with 010 K2.01. Randomly selected 011 K2.01.

No operational validity at facility. E04 EA1.3 randomly selected by CE as 1/1 E04 G2.1.33 replacement.

Unable to write SRO -Level question to this KA. Requested new KA. 008 2/1 078 A2.01 A2.01 randomly selected by CE as replacement.

Too difficult to develop operationally relevant test item, facility requested new 3 G2.2.7 KA. G2.2.28 randomly selected by CE as reolacement.

Topic resulted in questions too similar to KA 008 A2.01, requested new KA.

1/1 026 G2.1.27 057 G2.1.7 randornlv selected bv CE as reolacement.

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