ML071770553

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Final Outlines (Folder 3)
ML071770553
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 04/19/2007
From:
AmerGen Energy Co
To: D'Antonio J
Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800145 List:
References
50-289/07-301, ES-401, ES-401-2, NUREG-1021 50-289/07-301
Download: ML071770553 (29)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2

2. 1 3 1 3 0 0 5 2 3 4 2 5 28 2 3 5 Plant 2 0 1 1 2 2 0 0 1 1 2 0 10 0 1 1 2 3 Systems Tier 3 2 4 2 2 5 2 4 5 4 5 38 3 5 8 Totals
3. Generic Knowledge and 1 2 3 10 1 2 3 4 7 Abilities 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 (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 +I 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. Systemslevolutions 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) WAS 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 (IR) 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. 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 WAS that are linked to 10CFR55.43 NUREG-1021

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 015 I Reactor Coolant Pump Malfunctions/ 4 X I AA2.01 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss 027 I Pressurizer Pressure Control System Malfunction I3 029 /Anticipated Transient Without Scram (ATWS) I 1 X t-I I

2.1.32 2.4.50 of RC Flow): Cause of RCP failure Conduct of Operations. Ability to explain and apply all system limits and precautions.

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Emergency Procedures / Plan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual 038 I Steam Generator Tube Rupture / 3 EA2.15 Ability to determine or interpret the followmg as they apply to a SGTR Pressure at which to maintain RCS 4.4 I 79 I

during SIG cooldown Ability to determine and interpret the following as they 054 I Loss of Main Feedwater I 4 apply to the Loss of Main Feedwater (MFW) AFW X AA2.06 adjustments needed to maintain proper T-ave and SIG level

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065 I Loss of Instrument Air i 8 X Conduct of Operations Ability to explain and apply all 2 1.32 svstem limits and mecautions

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007 I Reactor Trip I 1 X Knowledge of the interrelations between a reactor trip EK2.02 and the following: Breakers, relays and disconnects 008 I Pressurizer Vapor Space Accident I 3

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AA2.17 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: Steam dumD valve controller (Dosition) 2.5 I 40 009 I Small Break LOCA I 3 X Conduct of Operations: Knowledge of operator 2.1.2 responsibilities during all modes of plant operation E

Knowledge of the interrelations between the Reactor 015 I Reactor Coolant Pump Malfunctions/ 4 I I 1 x 1 I AK2.07 Coolant Pump Malfunctions (Loss of RC Flow) and the following: RCP seals 022 I Loss of Reactor Coolant Makeup 1 2 x 1 AA2.02 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Charging pump problems 3.2 I 43 325 I Loss of Residual Heat Removal System 1 4 X AA1.01 Ability to operate andlor monitor the following as they apply to the Loss of Residual Heat Removal System:

4 RCSIRHRS cooldown rate Knowledge of the reasons for the following responses 126 I Loss of Component Cooling Water I 8 X as they apply to the Loss of Component Cooling Water:

AK3.03 Guidance actions contained in EOP for Loss of CCWINuclear Service Water VUREG-1021 2

I ES-401 TMI Unit 1 Form ES-401-2 I NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

1) E/APE # / Name Safety Function 1G I K1 I K2 ] K3 I A I I A2 ] Number I WA Topic@)

1 029 I Anticipated Transient Without Scram (ATWS) I 1 EK1.01 Knowledge of the operational implications of the following concepts as they apply to the ATWS: Reactor nucleonics and thermo-hydraulics behavior 2.8 46 Knowledge of the reasons for the following responses 038 I Steam Generator Tube Rupture I 3 EK3.03 as the apply to the SGTR: Automatic actions associated 3.6 47 with high radioactivity in SIG sample lines Knowledge of the reasons for the following responses 054 I Loss of Main Feedwater I 4 AK3.03 as they apply to the Loss of Main Feedwater (MFW): 3.8 48 Manual control of AFW flow control valves Knowledge of the operational implications of the 055 I Station Blackout I 6 E K I .02 following concepts as they apply to the Station 4.1 49 Blackout: Natural Circulation Cooling Knowledge of the operational implications of the following concepts as they apply to Loss of Offsite 056 I Loss of Off-site Power I 6 AK1.04 3.1 50 Power: Definition of saturation conditions, implication for the systems Emergency Procedures I Plan: Ability to recognize abnormal indications for system operating parameters 057 I Loss of Vital AC Electrical Instrument Bus 1 6 2.4.4 4.0 51 which are entry-level conditions for emergency and abnormal operating procedures.

Knowledge of the operational implications of the 058 I Loss of DC Power I6 AK1.01 following concepts as they apply to Loss of DC Power: 2.8 52 Battery charger equipment and instrumentation Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The 062 I Loss of Nuclear Service Water I 4 AK3.02 3.6 53 automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS Knowledge of the interrelations between the (Inadequate Heat Transfer) and the following: Facility's I E04 I Inadequate Heat Transfer 1 4 EK2.2 heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, 4.2 54 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 (Excessive Heat Transfer): Normal, E05 IExcessive Heat Transfer I 4 EK3.2 3.5 55 abnormal and emergency operating procedures associated with (Excessive Heat Transfer).

NUREG-I021 3

I ES-401 TMI Unit 1 Form ES-401-2 1 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function Knowledge of the reasons for the following responses as they apply to the (Post-Trip Stabilization): RO or SRO function within the control room team as E10 / Post-Trip Stabilization I 1 X EK3.4 4.0 56 appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

r(/A Category Point Totals: 213 4 3 6 1 213 Group Point 1816 Total:

NUREG-I 021 4

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Emergency Procedures i Plan: Knowledge of which 037 I Steam Generator Tube Leak / 3 2.4.30 events related to system operationsistatus should be 3.6 82 reported to outside agencies.

Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste: The 060 I Accidental Gaseous RadWaste Release I 9 X EA2.04 3.4 83 effects on the power plant of isolating a given radioactive gas leak Equipment Control: Knowledge of bases in technical 067 I Plant Fire On-site / 8 2.2.25 specifications for limiting conditions for operations and 3.7 84 safety limits.

Ability to determine and interpret the following as they apply to the (Natural Circulation Cooldown):

E09 I Natural Circulation Operations / 4 EA2.2 Adherence to appropriate procedures and operation 4.0 85 within the limitations in the facility's license and amendments.

Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak:

037 I Steam Generator Tube Leak I 3 AK3.02 3.1 57 Comparison of makeup flow and letdown flow for various modes of operation Ability to operate andlor monitor the following as they 051 I Loss of Condenser Vacuum I4 AA1 .04 2,5 58 apply to the Loss of Condenser Vacuum: Rod position Ability to operate and/or monitor the following as they apply to the Pressurizer Level Control Malfunction:

028 I Pressurizer Level Control Malfunction I 2 AA1.08 3.7 59 Selection of an alternate PZR level channel if one has failed.

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068 I Control Room Evacuation I 8

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AK2.07 1 Knowledge of the interrelations between the Control Room Evacuation and the following: EDIG I 3.3 60 Ability to operate and/or monitor the following as they A01 I Plant Runback I 1 AA1.2 apply to the (Plant Runback): Operating behavior 3.2 61 characteristics of the facility.

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Knowledge of the reasons for the following responses as they apply to the (Loss of NNI-Y): Normal, abnormal A03 I LOSSOf NNI-Y I7 AK3.2 3.0 62 and emergency operating procedures associated with (LOSS Of NNI-Y).

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Knowledge of the interrelations between the (Turbine Trip) and the following: Facility's heat removal systems, including primary coolant, emergency A04 I Turbine Trip I 4 AK2.2 3.3 63 coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

NUREG-I021 5

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier IGroup 2 1

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E X P E # / Name Safety Function I G I K1 I K2 I K3 I A I I A2 I Number 1 K/A Topic(s) 1 E03 Ihadequate Subcooling Margin I 4 I

EK2.2 Knowledge of the interrelations between the (Inadequate Subcooling Margin) and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Knowledge of the reasons for the following responses 4.3 as they apply to the (Natural Circulation Cooldown):

EO9 INatural Circulation Operations I 4 EK3.3 Manipulation of controls required to obtain desired 3.8 operating results during abnormal and emergency situations.

WA Category Point Total: I 012 NUREG-I021 6

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 l------

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS, and (b) based on those predictions, use procedures to 010 Pressurizer Pressure Control X A2.02 3.9 86 correct control, or mitigate the consequences of those malfunctions or operations Spray valve failures 012 Reactor Protection 2.1.33 Conduct of Operations: Ability to recognize system operating parameters which are entry-level conditions for technical specifications.

1 1 1 4.0 87 Conduct of Operations Ability to explain and apply 026 Containment Spray 2.1.32 all svstem limits and mecautions Ahlhty t G (a) predict the impacts Of the following malfunctions or operations on the AC distribution system and (h) based on those predictions use 1 062 AC Electrical Distribution X A2.12 procedures to correct, control or mitigate the consequences of those malfunctions or operations 36 89 Restoration of power to a system with a fault on it Conduct of Operations Knowledge of system 103 Containment 2.1.27 29 90 purpose and or function Knowledge of the effect of a loss or malfunction on 003 Reactor Coolant Pump xx K6.04 the following will have on the RCPS: Containment 2.8 1 isolation valves affecting RCP operation Knowledge of the physical connections and/or 004 Chemical and Volume cause-effect relationships between the CVCS and X K1.05 Control the following systems: CRDS operation in automatic mode control Knowledge of the effect of a loss or malfunction on 005 Residual Heat Removal X K6.03 the following will have on the RHRS: RHR heat exchanger 006 Emergency Core Cooling X A4.05 Ability to manually operate andlor monitor in the control room: Transfer of ECCS flow paths prior to recirculation 3.9 I 4 r

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007 Pressurizer RelieflQuench Knowledge of the effect that a loss or malfunction of X K3.01 the PRTS will have on the following: Containment Tank Conduct of Operations: Knowledge of operator 008 Component Cooling Water 2.1.2 3.0 responsibilities during all modes of plant operation.

Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure Control X A2.03 based on those predictions, use procedures to 4.1 correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures NUREG-I 021 7

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems Knowledge of the effect of a loss or malfunction of the following will have on the RPS: Permissive circuits Knowledge of bus power supplies to the following:

ESFASkafeguards equipment control Conduct of Operations: Ability to explain and apply all system limits and precautions.

A b i t y to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation I 4,1 1 1 12 Conduct of Operations: Knowledge of system purpose and or function.

I 2.8 I 1 13

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Ability to manually operate andlor monitor in the control room: CSS controls 1 4.5 I I 14 Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS 3,9 15 Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) 3.0 16 associated with operating the MRSS controls including: Main steam pressure Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to 3.0 17 correct, control, or mitigate the consequences of those malfunctions or operations: Tripping of MFW pump turbine Knowledge of the effect that a loss or malfunction of 3.6 18 the MFW will have on the following: AFW system Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: 1 1 1 2.6 19

':::I Pumps

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Ability to monitor automatic operation of the AC distribution system, including: Vital AC bus amperage Ability to monitor automatic operation of the DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights

ES-401 TMI Unit 1 Form ES-401-2 NRC Written Examination Outline I

Plant Systems - Tier 2 Group 1 I Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)

A I .03 associated with operating the ED/G system controls 3.2 22 including: Operating voltages, currents, and temperatures Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and A2.02 (b) based on those predictions, use procedures to 2.7 23 correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure

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Knowledge of the physical connections andlor cause-effect relationships between the ECCS K1.05 2.8 24 system and the following systems: RCP seal injection and return Conduct of Operations: Knowledge of operator 2.1.2 3.0 25 responsibilities during all modes of plant operation.

Knowledge of the physical connections and/or K1.04 cause-effect relationships between the IAS and the 2.6 26 following systems: Cooling water to compressor Conduct of Operations: Ability to recognize 2.1.33 indications for system operating parameters which 3.4 27 are entry-level conditions for technical specifications.

Ability to monitor automatic operation of the A3.01 containment system, including: Containment 3.9 28 isolation Group Point Total: [ 2815 NUREG-1021 9

ES-401 TMI Unit 1 Form ES-401-2 I NRC Written Examination Outline Plant Systems - Tier 2 Group 2 I I I System #/Name KIA Topics I Imp. I Q# I Conduct of Operations Ability to explain and apply 01 1 Pressurizer Level Control X 2.1.32 9, all system limits and precautions

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Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System and (b) based on those 071 Waste Gas Disposal A2.05 predictions, use procedures to correct, control, or 26 92 mitigate the consequences of those malfunctions or operations Power failure to the ARM and PRM systems Conduct of Operations Ability to perform specific 086 Fire Protection X 2.1.23 system and integrated plant procedures during all 40 93 modes of DIant ooeratton Knowledge of the following operational implications 001 Control Rod Drive K5.33 as they apply to the CRDS: Xenon production and 3.2 29 removal process Knowledge of the operational implications of the 01 1 Pressurizer Level Control K5.12 following concepts as they apply to the PZR LCS: 2.7 30 Criteria and purpose of PZR level program Knowledge of ITM system design feature(s) andlor 017 In-core Temperature Monitor K4.01 interlock(s) which provide for the following: Input to 3.4 31 subcooling monitors 041 Steam Dump System and Knowledge of bus power supplies to the following:

K2.01 ICs, normal and alternate power supply Turbine Bypass Control Knowledge of design feature(s) andlor interlock(s) 329 Containment Purge K4.02 which provide for the following: Negative pressure in containment Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, 333 Spent Fuel Pool Cooling A2.03 use procedures to correct, control, or mitigate the 3.1 34 consequences of those malfunctions or operations:

Abnormal Spent Fuel Pool water level or loss of water level.

Ability to manually operate andlor monitor in the control room: Turbine valve indicators (throttle, 145 Main Turbine Generator A4.01 3.1 35 governor, control, stop, intercept), alarms, and annunciators.

Ability to monitor automatic operation of the Waste 171 Waste Gas Disposal A3.02 Gas Disposal System including: Pressure-regulating 2.8 36 system for the waste gas vent header.

NUREG-I021 10

System #/Name G K1 K2 K3 K4 K5 K6 A I A2 A3 A4 Number KIA Topics Knowledge of the effect that a loss or malfunction of 072 Area Radiation Monitoring X K3 02 the ARM system will have on the following Fuel 31 37 handling operations Ability to manually operate and/or monitor in the 086 Fire Protection A4 o6 32 38 control room Halon system K/A Category Point Totals 012 0 1 1 2 2 0 0 111 1 2 Group Point Total 1013 NUREG-I021 11

Facility: TMI Unit 1 I DateofExam: I 4/22/2007 Category KIA #

Topic Knowledge of conditions and limitations in

+I SRO-Only 3.9 94 the facility license.

Ability to explain and apply all system limits 2'1.32 3.8 95 and precautions.

1. Ability to make accurate, clear and concise Conduct of 2'1 3,5 66 verbal reports.

Operations 2.1.3 Knowledge of shift turnover practices. 3.0 67 Knowledge of new and spent fuel 2'2.28 3.5 96 movement procedures.

2.2.33 Knowledge of control rod programming. 2.9 97 Knowledge of the process for determining 2.2.34 the internal and external effects on core 2.8 68

~ 2Equipment Control reactivity.

Knowledge of refueling administrative 2.2.26 2.5 69 requirements.

Subtotal I 2.3.2 Knowledge of facility ALARA program. I I I 2.9 I 98 Knowledge of 10 CFR: 20 and related 2.3.1 3.0 99 facility radiation control requirements Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible 2.5 70 levels in excess of those authorized.

Ability to perform procedures to reduce 2.3.10 excessive levels of radiation and guard 2.9 71 against personnel exposure.

2.3.11 Ability to control radiation releases. 2.7 72 Subtotal I 1 3 1 I 2 Knowledge of the emergency action level 2.4'41 4.1 100 thresholds and classifications.

Knowledge of general guidelines for EOP 2'4'14 3,0 73 flowchart use.

Knowledge of the RO's responsibilities in 2.4.39 3.3 74 emergency plan implementation.

Procedures / Plan Knowledge of crew roles and 2.4'1 3.3 75 responsibilities during EOP flowchart use.

Subtotal 7 r n I 1 10 I 1 7 NUREG-I021 12

Tier I Randomly Reason for Rejection Group Selected KIA 1 I 025 (32.1.27 I System does not exist at TMI. Reselected system 012.

I I 2I I I Facility does not perform function for the selected topic. Randomly selected AA2.1 ~ ~ 2 . for 0 1same topic.

Excessive overlap with Audit Examination. Impossible to develop significantly 055 EK1 different question. Randomly selected EK2.02 for same topic

' 037 AK3'02 Facility does not have air ejectors, and Off-Gas monitors do not have a reset function. Randomly selected AK3.03 No pneumatic valves in DHR system at facility. Randomly selected K1.05 for 211 Oo4 K1. O topic area Facility does not have Containment Spray Reset switches. Randomly selected 211 026 A4.05 A4.01 Waste Gas system has no rupture discs at facility. Randomly selected A2.08 212 07' A2.03 for the same topic.

No procedural support for Inadequate SDM in SFP. Randomly selected A2.03 212 033 A2.01 for the same topic.

Facility design is such that there is no overlap between WGDS and HRPS.

212 07' A3'01 Randomly selected A3.02 for the same topic.

Meteorological changes are not referenced in facility procedures for the 2 12 071 A2.08 system. Randomly selected an A2 (A2.05) that has facility application and is not RMS-related.

1 211 I 073K1.01 I Many RMS-related questions on this examination. Randomly selected a K1 in a svstem not selected twice in T2/G1: 006 K1.05.

KIA yields very similar question to Question 23. Selected the only other 072 212 072 K3.01 K3 (K3.02).

Facility has no normal IA alignment to the containment. Randomly selected 211 078 K1.03 K,

. .04.

A valid question could not be developed for the facility equivalent fan.

212 027 K2'01 Randomly selected K2 >2.5 from a system not covered in T2G2 (041 K2.01).

KIA ties in to other RMS-related questions. Chief Examiner suggested a KIA 060 AA1'02 change. Randomly selected 028 AA1.08.

Chief Examiner suggested a KIA change due to over-sampling. Randomly 3 2'1'27 selected a 2.1 KIA from those not used on the examination (2.1.3).

A valid SRO-level question could not be developed for this KIA. Chief 211 2'1.30 Examiner suggested a KIA change. Randomly selected 2.1.33.

NUREG-I02 1 13

ES-301 Administrative Topics Outline Form ES-301-1 Facility: TMI Unit 1 Date of Examination: April 2007 Examination Level (circle one): I SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform a batch calculation in accordance with OP Conduct of Operations N 1103-4, SOLUBLE BORON CONCENTRATION CONTROL, Enclosure 1.

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 transient RCS leak rate calculation in Conduct of Operations accordance with OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, ATTACHMENT F.

2.1.1 9 (3.0): Ability to use plant computer to obtain and evaluate parametric information on system or comDonent status.

Perform Shiftly Checks of Decay Heat Removal Equipment Control N, s Capability in accordance with Surveillance Procedure 1301-1, SHIFT AND DAILY CHECKS, Data Sheet 3 -

Section C.2.

2.2.1 2 (3.0): Knowledge of surveillance procedures.

Given a set of conditions, determine and apply the Radiation Control N facility dose limits.

2.3.1 (2.6): Knowledge of 10 CFR: 20 and related facility radiation control requirements.

N/A - not selected for RO 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 5 are required.

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

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

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

(S)i mulator NUREG-1021, Revision 9

ES-301 Admi Sst rative Topics Out1ine Form ES-301-1 THREE MILE ISLAND 2007 NRC RO EXAMINATION CONDUCT OF OPERATIONS (Al-1): Perform a batch calculation in accordance with OP 1103-4, SOLUBLE BORON CONCENTRATION CONTROL, Enclosure 1. Given a situation and conditions, determine the applicable section of 1103-4, Enclosure 1 and utilize the referenced figures and tables to perform a batch calculation. New JPM. RO/SRO Common.

CONDUCT OF OPERATIONS (Al-2): Perform a transient RCS leak rate calculation in accordance with OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, ATTACHMENT F. Given a frozen simulator with an RCS leak in progress, use the plant computer to extract the necessary data and then calculate the leak rate.

The calculation is RO/SRO Common. Modify Bank JPM 11205057 by changing the initial conditions and requiring the applicant to retrieve the data from the plant computer on a frozen simulator.

EQUIPMENT CONTROL (A2):Perform Shiftly Checks of Decay Heat (DH) Removal Capability in accordance with Surveillance Procedure 1301-1, SHIFT AND DAILY CHECKS, Data Sheet 3 - Section C.2. Evaluate DH Pump performance, system alignment and the adequacy of support instrumentation with the simulator in cold shutdown on DH cooling; identifying all (two, or more) errors. RO only. New JPM RADIATION CONTROL (A3): Given an emergency situation and survey maps, determine the area dose rate near a specified plant component and apply the applicable facility limits to determine the stay time for the situation. RO/SRO Common. New JPM.

NUREG-1021, Revision 9

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2 FaciIity: TMI Unit 1 Date of Examination: April 2007 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. Take corrective action for a Control Rod Drive Sequence Fault in M, E, L 1 accordance with (IAW) OP-TM-MAP-GO202.

System: 001

b. Take corrective action for a low pressure injection failure during a large break LOCA IAW OP-TM-211-901.

System: 006

c. Respond to an RCS narrow range pressure instrument failure IAW 3 alarm response procedure MAP G-1-6.

System: 010

d. Respond to an RCP Seal problem IAW AOP-040. 4P System: 003
e. Cross-connect Secondary River Water to Nuclear River Water IAW D 4s EP 1202-38. (RO Only)

System: 076

f. Return RB Emergency Cooling to standby following a manual 5 actuation IAW OP-TM-534-901.

System: 022

g. Energize a Vital AC Bus during a loss of off-site power using the 6 SBO Diesel IAW AOP-020.

System: 062

h. Respond to an alarm on Control Room RMS Channel RM-A1 IAW M 7 MAP C, C-1-1.

System: 073 Implant Systems@(3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Reset the steam-driven EFW Pump overspeed trip IAW EOP-10, P, E 4s GUIDE 16.1.

System: 061 NUREG-1021, Revision 9

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2

j. Initiate emergency boration IAW EOP-020. M, R, E 8 System: APE 068
k. Manually operate RR-V-6, Reactor Building Emergency Cooler D Pressure Control Valve, IAW OP-1104-38.

System: 022 Q 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 I SRO-U (D)irectfrom bank <9/<8/<4 (E)mergency or abnormal in-plant 21I21 I21 (L)ow-Power / Shutdown 2 1 1 2 1 12 1 (N)ew or (M)odifiedfrom bank including 1(A) 22122lr1 (P)revious2 exams 5 3 I I 3 1 5 2 (randomly selected) 21 I21 I21 THREE MILE ISLAND 301-2 JPM

SUMMARY

STATEMENTS

a. Take corrective action for a Control Rod Drive Sequence Fault in accordance with (IAW)

OP-TM-MAP-G0202. Group 7 rods withdraw out-of-sequence when power is being raised from < 5% in preparation for synchronizing the main turbine generator. The applicant will respond IAW OP-TM-G0202, CRD SEQUENCE FAULT, and correct the overlap problem IAW OP-TM-622-412, RECOVERING FROM A SEQUENCE INHIBIT CAUSED BY EXCESSIVE OVERLAP. Modify Bank JPM 11.2.05.1 59 by changing the initial conditions and therefore the procedure path. To be performed by: RO, SROI, SROU. Failure to properly perform the task will result in a violation of technical specifications and operation outside of accident analysis assumptions.

b. Take corrective action for a low pressure injection failure IAW OP-TM-EOP-006.

Applicant will assume the watch with directions to perform EOP-006, LOCA COOLDOWN. DH-P-1B has failed to start, requiring alternative actions. The alternate path is via OP-TM-211-901, EMERGENCY INJECTION. Bank JPM 11.2.05.195. To be performed by: RO, SROI, SROU. Failure to properly perform the task will result in the possibility that all LPI flow is out the break.

NUREG-1021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 C. Respond to an RCS narrow range pressure instrument failure IAW alarm response procedure MAP G-1-6. Shortly after assuming the watch, an RCS narrow range pressure instrument fails HI and SASS fails to block the signal. The applicant will respond IAW the alarm response procedure to place equipment in the proper alignmenVposition. Modified Bank JPM TQ-TM-104-220-JOO1 to prevent the PZR Spray Valve from closing in MANUAL. The alternate path is to close the PZR Spray Valve isolation valve. To be performed by: RO, SROI. Failure to properly perform the task will result in unnecessarily creating saturated conditions in the RCS.

d. Respond to an RCP Seal problem IAW AOP-040. Shortly after assuming the watch, an RCP #1 Seal problem will develop, requiring entry into AOP-040, RCP #1 SEAL FAILURE. The alternate path is a requirement to initiate a reactor trip, stop the affected pump and close the return isolation valve. This JPM is identified as NEW because the JPM was removed from the facility bank prior to 2005 and was not based on AOP-040.

To be performed by: RO, SROI, SROU. Failure to properly perform the task could result in a LOCA caused by catastrophic seal failure.

e. Cross-connect Secondary River (SR) Water to Nuclear River (NR) Water IAW EP 1202-
38. The only available NR Pump will trip shortly after the applicant assumes the watch with the unit shutdown. SR is then cross-connected to NR IAW EP 1202-38, NUCLEAR SERVICES RIVER WATER FAILURE. Bank JPM 11.2.05.1 50. To be performed by:

RO Only. Failure to properly perform the task will result in loss of cooling water to emergency safeguards equipment.

f. Return RB Emergency Cooling to standby IAW OP-TM-534-901, RB EMERGENCY COOLING OPERATIONS, following a manual actuation. The applicant assumes the watch with RB Emergency Cooling in service due to a small steam leak that has been isolated and is directed to restore it to ES Standby alignment. Randomly selected repeat from the 2003 NRC Exam (B.l .f). To be performed by: RO, SROI. Failure to properly perform the task could result in inadequate flow to Reactor Building coolers and possible operation outside of accident analysis assumptions.
9. Energize a Vital AC Bus during a loss of off-site power using the SBO Diesel IAW AOP-020. The applicant assumes the watch after a loss of off-site power and AOP-020, LOSS OF STATION POWER, just entered. The alternate path is to energize ID or 1E Vital Bus IAW OP-TM-864-901, SBO DIESEL GENERATOR (EG-Y-4) OPERATIONS.

Randomly selected repeat from the 2005 NRC Exam (JPM F). The JPM will be modified in that it will begin in AOP-020 vice OP-TM-864-901 and a different bus will be re-energized. To be performed by: RO, SROI. Failure to properly perform the task will result in loss of DC power to the respective bus or a station blackout if power is lost to the available bus.

h. Respond to an alarm for RMS Channel RM-A1, Control Room Monitor, IAW MAP C, C-1-1. Shortly after the applicant assumes the watch, alarm C-1-1 (HI ALARM) will actuate. Failure of the interlock will require alignment of components IAW OP-TM-826-901, CONTROL BUILDING VENTILATION SYSTEM RADIOLOGICAL RESPONSE OPERATIONS. The task is similar to Bank JPM TQ-TM-104-826-J001 but will be modified to start from an alarm condition; with failed interlock actuations. To be performed by: RO, SROI. Failure to properly perform the task will result in possible radiation intrusion into the control room environment.

NUREG-1021, Revision 9

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2

i. Reset the steam-driven EFW Pump overspeed trip IAW OP-TM-EOP-010, Guide 16.1, EFW FAILURE. Randomly selected repeat from the 2003 NRC Exam (B.2.c). To be performed by: RO, SROI. Failure to properly perform the task will result in loss of all feedwater flow when the operating pump fails.
j. Initiate emergency boration IAW EOP-020, COOLDOWN FROM OUTSIDE OF CONTROL ROOM, Step 3.1.1 9. Perform the steps necessary to initiate boration from outside the control room. Modify Bank JPM TQ-TM-105-211-JOO1 to have the applicant perform all sub-steps rather than opening just one manual valve (MU-V-51). To be performed by: RO, SROI, SROU. Failure to properly perform the task will result in inadequate SDM during the cooldown.
k. Manually operate RR-V-6, Reactor Building Emergency Cooler Pressure Control Valve, IAW OP-1104-38. Applicant is directed to raise Reactor Building Emergency Cooling coil pressure with a LOCA in progress. Bank JPM TQ-TM-105-534-J001. To be performed by: RO, SROI, SROU. Failure to properly perform the task could result in an uncontrolled leakage path from the Reactor Building atmosphere to the cooling system to the local environment.

NUREG-1021, Revision 9

ES-301 Ad ministrative Topics Outline Form ES-301-1 Facility: TMI Unit 1 Date of Examination: April 2007 Examination Level (circle one): RO / ml Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform a batch calculation in accordance with Conduct of Operations N OP 1103-4, SOLUBLE BORON CONCENTRATION CONTROL, Enclosure 1.

2.1.25 (2.8/3.1): Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

Perform a transient RCS leak rate calculation in Conduct of Operations accordance with OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, ATTACHMENT F, and apply the Technical Specification/procedural requirements to the calculation.

2.1.12 (4.0): Ability to apply technical specifications for a system.

Evaluate a proposed temporary procedure change.

Equipment Control N 2.2.6 (3.3): Knowledge of the process for making changes in procedures as described in the safety analysis report.

Given a set of conditions, determine and apply the Radiation Control N facility dose limits.

2.3.1 (2.6/3.0): Knowledge of 10 CFR: 20 and related facility radiation control requirements.

Given a set of conditions, determine the Emergency Emergency Plan P/M Action Level (EAL) and make a Protective Action Recommendation (PAR).

2.4.44 (4.0): Knowledge of emergency plan protective action recommendations.

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 ( I 3 for ROs; I for SROs & RO retakes)

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

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

(S)imulator NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 THREE MILE ISLAND 2007 NRC SRO EXAMINATION CONDUCT OF OPERATIONS (Al-1): Perform a batch calculation in accordance with 1103-4, SOLUBLE BORON CONCENTRATION CONTROL, Enclosure 1. Given a situation and conditions, determine the applicable section of OP 1103-4, Enclosure 1 and utilize the referenced figures and tables to perform a batch calculation. New JPM. RO/SRO Common.

CONDUCT OF OPERATIONS (Al-2): Perform a transient RCS leak rate calculation in accordance with OS-24, CONDUCT OF OPERATIONS DURING ABNORMAL AND EMERGENCY EVENTS, ATTACHMENT F,and apply the Technical Specification/proceduraI requirements to the calculation. Given a frozen simulator with an RCS leak in progress, use the plant computer to extract the necessary data and then calculate the leak rate. The calculation is RO/SRO Common. The SRO applicants will apply the Technical Specification/procedural requirements based on their calculations. Modify Bank JPM 11205057 by changing the initial conditions, requiring the applicant to retrieve the data from the plant computer on a frozen simulator and having the SRO applicant determine and apply the facility requirements.

EQUIPMENT CONTROL (A2):Evaluate a proposed temporary procedure change. Apply facility requirements to the review of a temporary procedure change containing two (or more) administrative and/or technical errors. New JPM. SRO only.

RADIATION CONTROL (A3): Given an emergency situation and survey maps, determine the area dose rate near a specified plant component and apply the applicable facility limits to determine the stay time for the situation. RO/SRO Common. New JPM.

EMERGENCY PLAN (A4): Given a set of conditions, determine the Emergency Action Level (EAL) and make a Protective Action Recommendation (PAR). Randomly selected task from one of the previous two NRC examinations. Modify by changing the conditions. SRO only.

NUREG-1021, Revision 9

Appendix D Scenario Outline Form ES-D-1 1 Facility: Three Mile Island Scenario No.: 1 OpTestNo.: NRC Examiners: Operators:

Initial Conditions: 100% power, MOC.

0 EF-P-2B is 00s for bearing replacement.

I 0 DR-P-1A is running for effluent flow Turnover: Maintain 100% power operations.

Critical Tasks: 0 Initiate HPI Cooling (CT-14)

I 0 Initiate HPI (CT-2) 11 Event No.

1 1I Malf.

No.

RW04A II Event Type*

CRS II Event Description Decay Heat River Water Pump DR-P-1A trips (TS) 2 CRS NLO Reports an excessive oil leak from Emergency Feedwater Pump EF-P-1 (TS).

3 MSO1D I CRS Turbine Header Pressure instrument fails high slowly I ARO 4 CC04A C CRS Intermediate Closed Cooling Water Pump IC-P-1A trips and IC-P-1B fails to auto start C URO 5 MSl9A N CRS Steam Leak in the Turbine Building N ARO R URO 6 FW-15A M CRS Feedwater Pump 1A trip FW-15B M URO Feedwater Pump 1B trip TC07B M ARO Turbine stop valve fails open 7 FW17 C CRS Emergency Feedwater Pump EF-P-1 trips on start FW18A CAR0 Emergency Feedwater Pump EF-P-2A does not start.

(CT-14) 8 MU08B CCRS High Pressure Injection Valve (HPI) MU-V-16B fails to open C URO B ESAS Manual Actuation Failure (CT-2)

Appendix D Scenario Outline Form ES-D-1 1 Facility: Three Mile Island Scenario No.: 2 OpTest No.: NRC Examiners: Operators:

~ Initial Conditions: Reactor Startup is in Progress NI-12 is 00s due to a detector failure 1 Turnover: Take the Reactor Critical Critical Tasks: Initiate HPI (CT-2) 0 Trip all RCPs (CT-1)

I Reduce Steaming/lsolateAffected SGs (CT-22)

I Limit Uncontrolled Radiation Release (CT-21)

/j Malf.

No.

Event Type*

Event Description 1 RM0322 CRS Reactor Building Hi Range Radiation Monitor Failure (TS) 2 N CRS Reactor Startup R URO N ARO 3 N137A URO Premature Criticality CRS 4 RDO3A M CRS Continuous Rod Withdrawal M URO M ARO 5 TH15A CRS OTSG Tube Leak in OTSG A (TSI 6 THl6A C CRS OTSG Tube Rupture in A OTSG requiring HPI initiation C URO C ARO 7 MU09 C CRS High Capacity Makeup Flow Valve MU-V-217 Fails to open C URO 1 8 I CC02B I C CRS I Decay Heat Closed Cooling Water Pump Trips on ESAS Actuation C URO TH17A C CRS OTSG Tube Rupture in A OTSG resulting in loss of subcooling C URO margin (CT-1, CT-22)

C ARO I

l lo 11 ESOlA ESOlB NV45A I

I CRS I URO CCRS Both Trains of HPI Fail to Actuate at 1600 psig (CT-2)

Emergency Feedwater Pump Steam Supply Valve MS-V-13A Fails Open. (CT-21)

C ARO 1 * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility: Three Mile Island Scenario No.: 3 OpTestNo.: NRC Examiners: Operators:

Initial Conditions: 0 85% power, MOC 0 Power Escalation Following a trip and maintenance outage MU-P-IBOOS Turnover: Raise Power to 100%.

Critical Tasks: 0 Trip all RCPs (CT-I) 0 Establish FW Flow and Feed SGs (CT-IO)

Event Malf. Event Event No. No. Type* Description 1

2 RD0216 1I C CRS CURO Power Operated Relief Valve (PORV) Block Valve RC-VP Breaker Trips (TS)

Stuck Rod in Group 7 (TS) 3 TH13D NCRS Reactor Coolant Pump RC-P-1D High Vibration R URO N URO 4 C CRS Feedwater Flow Fails to re-ratio after securing RC-P-1D C ARO C URO 5 THO6 M CRS An RCS leak occurs requiring a Reactor Trip M URO M ARO 6

7 RW010B I CCRS CURO Reactor Building Emergency Cooling Pump RR-P-1B does not start on ESAS actuation RC-P-1A does not trip when control switch is rotated to the stop position (CT-1) 8 I CRS Emergency Feedwater Valves to the A OTSG EF-V30A and EF-V-30D do not control in automatic due to a level setpoint failure I ARO (CT-10)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301 Transient and Event Checklist Form ES-301-5 TMI Date of Exam: A~ril2007 ODeratina Test No.: NRC Scenarios 1 2 3 4 T M 0 I CREW CREW CREW CREW T N POSITION POSITION POSITION POSITION A I L M U

M(*)

R I U Rx NOR IIC MAJ TS RX 1 1 1 0 NOR 1 1 1 1 4 4 2 IIC 7 MAJ 2 2 2 1 TS 0 2 2 Rx 1 1 0 NOR 1 1 1 1 IIC MAJ t- -TS Instructions:

Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a l-for-I basis.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-301-5

-TMI E

Date of Exam: April 2007 Scenarios Operating Test No.: NRC v

E 4 N

T I I CREW CREW CREW CREW POSITION POSITION POSITION POSITION T

Y P

E SR016 NOR 1 11 IIC MAJ

- 2 TS 2 RX 1 1 1 0 NOR 1 1 1 1 4 4 2 IIC 4 MAJ 2 2 2 1 TS 0 2 2 RX 1 1 1 0 NOR 1 1 1 1 SROll IIC 9 MAJ 2 TS

- 2 2 2

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (IIC) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
4. SRO Instant and Upgrade candidates TOTALS reflect the ATC and SRO positions only.

NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-30 1-5

- TMI Date of Exam: April 2007 Operating Test No.: NRC E Scenarios v

E 4 N

T CREW CREW CREW CREW POSITION POSITION POSITION POSITION T

Y P

E Rx NOR I/C MAJ TS Rx NOR I/C MAJ 2 2 2 1 TS 0 2 2 Rx 1 1 1 0 NOR 1 1 1 1 4 4 2 I/C 9 MAJ 2 2 2 1 TS 2 0 2 2

=_e ns:

Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (IC) malfunctions and one major transient, in the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021 Revision 9

ES-301 Transient and Event Checklist Form ES-301-5

=acility: TMI Date of Exam: April 2007 ODeratina Test No.: NRC A Scenarios P

P 3 4 L

I CREW CREW C POSITION POSITION POSITION POSITION A

N T

SR014 I I I I I I SR013 Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a I-for-I basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
4. SRO Instant and Upgrade candidates TOTALSreflect the ATC and SRO positions only.

NUREG 1021 Revision 9

ES-301 Competencies Checklist Form ES-301-6 Facility: TMI Date of Examination: 2007 Operating Test No.: NRC APPLICANTS SRO RO (ATC) 1 BOP Competencies I

- 4RIO SCEP I

1 3 4 1 1 2 Interpret/Diagnose 3,5, 12, 12, 1,3 2,3 6,7, 3,5, 5,6 ,4, ,4, Events and 8 7, 6,8 6,7 Conditions 8, 9

23, 12, 1,3 1,3 5, 43 ,4, ,6, 8 7,8

$9 N/A NIA 3,4 1,3 95, ,5, 6,7 6,7

,8 8, 9

ALL ALL ALL 1,3 1,2

>4* ,3, 5,6 4,5

,7, ,6, 8 7,8

,9 ALL ALL NI N/

A A 1,2 1,3 NI NI A A Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

Author:

NRC Reviewer:

NUREG-1021, Revision 9

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