ML041470484

Examination Outline Submittal for Prairie Island Retake Examination - Apr 2004

ML041470484
Person / Time
Site:	Prairie Island
Issue date:	04/23/2004
From:	Kempkes J Nuclear Management Co
To:	NRC/RGN-III
Shared Package
ML041280237	List: ML041470376 ML041470427 ML041470484 ML041470488 ML041470492
References
50-282/04-301, 50-306/04-301
Download: ML041470484 (12)

Text

EXAMINATION OUTLINE SUBMITTAL FOR THE PRAIRIE ISLAND RETAKE EXAMINATION - APR 2004

Outline Submittal Contains the following:

Outline Submittal Letter ES-201-2 Examination Outline Quality Checklist ES-401-2 PWR Examination Outline & Written Sample Plan (includes equivalent of Form ES-401-3)

Admin There were no NRC Comments on licensee submitted test outline

JAN 2 9 2004 L-PI-04-013 NUREG-I021 Regional Administrator U S Nuclear Regulatory Commission Region Ill 801 Warrenville Road Lisle, Illinois 60532-4351 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 AND 50-306 LICENSE NOS. DPR-42 AND DPR-60 EXAMINATION MATERIAL FOR PRAIRIE ISLAND INITIAL LICENSE EXAMINATION, WEEK OF APRIL 19,2004 As a follow-up to our letter dated January 6, 2004, enclosed are the integrated examination outlines for the initial license examinations to be administered at our facility the week of April 19,2004. As discussed in the earlier letter, this class is comprised of students who passed the operating test portion of the exam and thus the information enclosed supports only the written portion of a License Exam. Letters requesting a waiver of the operating portion of the exam for the affected students will be completed as soon as results from the previous exam are finalized.

This information is being provided in accordance with the guideline ES-201 of NUREG 1021, Operating License Examination Standard for Power Reactors, Draft Revision 9.

NUREG 1021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure until after the examination is complete.

Please direct any questions or comments regarding this material to Bill Markham at 651-388-1165, ext. 5277.

This letter contains no new commitments and no revisions to existing commitments.

Site Vice President, Prairie Island Nuclear Generating Plant C: Dell McNeill (NRC lead examiner) w/ attachments 1717 Wakonade Drive East 0 Welch, Minnesota55089-9642 Telephone: 651.388.1121

ES-201 Examination Outline Quality Checklist Form ES-201-2

~

Facilit Date of Examination:

Item Task Description

1. a. Verify that the outline(s) fit@) the appropriate model per ES-401 W

R I

T T c. Assess whether the outline over-emphasizes any systems, evolutioxs, or E E

N d Assess whether the justifications for deselected or rejected WA 2.

S I ojected number a M . schedule withou 3.

W I

T b Verify that (1) the tasks are distributed a (2) one task is conducted in a I MA 4

w a Aut i r b Facility Reviewer (*)

c NRC Chief Examiner (#)

d NRC Supervisor Note: ' Not applicable for NRC-developed examinations.

1. Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.

NUREG-1021, Draft Revision 9 24 of 25

ES-401 PWR fRBExamination Outline Form ES-401-32 and tier in the proposed outline must match that al point total for each group and tier may deviate by +I based on NRC revisions. The final RO exam must s within each group are identified on the associated outline.

following pages, enter the WA numbers, a brief description of each topic, the importance ratings (IR) for the 533applicable license level, . .and

. the point totals for each system and c a t e g 0 r y . v Enter the group and tier totals for each category in the table above: summarize all the SRO-only knowledge and non-A2 ability categories in the colunins labeled 'K" and "A,"Use duplicate pages for RO and SRO-only exams.

8 For Tic. 3 . enter tlic K/A numbers descriptions importance ratings. and point totals on Forrr KS-401-3 9 Refer to ES-401~ Attachment 2, for guidance regarding t h e elimination of itw p p "0p riate K'A sta t e r mnts .

NUREG-1021, Draft Revision 9 22 of 34 i s

Sample Plan Information for the NRC Makeup RO Exam Tier: 1 Group: 1 RO SRO Exam ID KA Imp Imp Full KA Statement RO 007 EA1.05 4.0 4.1 Ability to operate and/or monitor the followine as they apply to a Nuclcar instrunicntation reactor trip:

RO 008 M2.05 3.9 3.9 Ability to determine and interpret the following as they apply to the PORV isolation (block valve switches and indicators)

Pressurizer Vapor Space Accident:

RO 009 EK3.11 4.4 4.5 Knowledge of the reasons for the following responses as thcy apply to Dangers associated with inadequate core cooling the small break LOCA:

RO 011 EA1.04 4.4 4.4 Ability to operate and/or monitor the following as they apply to a Large ESF actuation system in manual Break LOCA:

RO 022 AA1.04 3.3 3.2 Ability to operate and/or monitor the following as they apply to the Loss Speed demand controller and running indicators (positivc of Reactor Coolant Pump Makeup: displacement pump)

RO 025 2.1.2 3.0 4.0 Conduct of Operations Knowledgk of operator responsibilities during all modes of plant operation.

RO 026 AK3.01 3.2 3.5 Knowledge of the reasons for the following responses as they apply to The conditions that will initiate the automatic opening and closing the Loss of Component Cooling Water: of the SWS isolation valves to the CCW/nuclear service water coolers RO 021 2.4.4 4.0 4.3 Emergency ProceduresPlan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergcncy and abnormal operating procedures.

RO 029 EA2.05 3.4 3.4 Ability to determine and interpret the following as they apply to a System component valve position indications ATWS:

RO 038 EK3.06 4.2 4.5 Knowledge of the reasons for the following responses as they apply to Actions contained in EOP for RCS water inventory balance, S/G the SGTR: tube rupture, and plant shutdown procedures RO 040 AK1.05 4.1 4.4 Knowledge of the operational implications of the following concepts as Reactivity effects of cooldown they apply to Steam Line Rupture:

RO 055 EA2.04 3.7 4.1 Ability to determine and interpret the following as they apply to a Instruments and controls operable with only dc battery power Station Blackout: available RO 056 AK1.03 3.1 3.4 Knowledge of the operational implications of the following concepts as Definition of subcooling: use of steam tables to determine it they apply to Loss of Offsite Power:

RO 058 AKl.01 2.8 3.1 Knowledge of the operational implications of the following concepts as Battery charger equipment and instrumentation they apply to Loss of DC Power:

@ RO 062 2.1.28 3.2 3.3 Conduct of Operations Knowledge of the purpose and function of major systcm

% components and controls.

Tuesday, January 20,2004 Page 1 of 5

Sample Plan Information for the NRC Makeup RO Exam RO E04 EK2.2 3.8 4.0 Knowledge of the interrelations between thc LOCA Outside Facility's hcat removal systems, including primary coolant.

Containment and the following: cmcrgcncy coolant, the decay hcat removal systems. and relations between the proper operation of thcsc systems to the operation of the facility RO EO5 EK2.1 3.7 3.9 Knowledge of the interrelations between the Loss of Secondary Heat components, and functions of control and safcty systems, including Sink and the following: instrumcntation, signals, interlocks, Iailure modcs, and automatic and manual features RO El 1 EK2.1 3.6 3.9 Knowledge of the interrelations between the Loss of Emergency Components, and functions of control and safcty systems, including Coolant Recirculation and thc following: instrumentation, signals, interlocks, failure modes, and automatic and manual features Tier: I Group: 2 RO SRO Exam ID KA Imp Imp Full KA Statement RO 001 AA2.04 4.2 4.3 Ability to determine and interpret thc following as they apply to the Reactor power and its trend Continuous Rod Withdrawal:

RO 003 2. I .23 3.9 4.0 Conduct of Operations Ability to perform specific system and integrated plant procedures during all modes of plant operation.

RO 024 AA1.13 3.2 3.0 Ability to operate and/or monitor the following as they apply to the Boric acid flow controller Emergency Boration:

RO 032 2.4.3 1 3.3 3.4 Emergency Procedures/Plan Knowledge of annunciators alarms and indications, and use of the response instructions.

RO 036 AK2.02 3.4 3.9 Knowledge of the interrelations between the Fuel Handling Incidents Radiation monitoring equipment (portable and installed) and the following:

RO 06 1 AA2.06 3.2 4.1 Ability to determine and interpret the following as they apply to the Required actions if alarm channel is out of service Area Radiation Monitoring (ARM) System Alarms:

RO 068 AA1.06 4.1 4.2 Ability to operate andor monitor the following as they apply to the Charging pump Control Room Evacuation:

RO E03 EK3.2 3.4 3.9 Knowledge of the reasons for the following responses as they apply to Normal, abnormal and emergency operating procedures associated the LOCA Cooldown and Depressurization: with LOCA Cooldown and Depressurization RO El5 EK1.3 2.8 3.0 Knowledge of the operational implications of the following concepts as Annunciators and conditions indicating signals, and remedial they apply to the Containment Flooding: actions associated with the Containment Flooding Tier: 2 Group: 1 RO SRO Exam ID KA Imp Imp Full KA Statement

\J3 RO 003 A3.05 2.7 2.6 Ability to monitor automatic opcration of the RCPS, including: RCP lube oil and bearing lift pumps "D

9 Tuesday, January 20,2004 Page 2 of 5

Sample Plan Information for the NRC Makeup RO Exam RO 004 A3.09 3.3 3.2 Ability to monitor automatic operation of thc CVCS, including: VCT level RO 005 K3.01 3.9 4.0 Knowlcdgc of thc cffcct that a loss or malfunction of thc RHRS will RCS have on the following:

RO 006 K5.07 2.7 3.0 Knowledgc of the opcrational implications of thc following concepts as Expected tcmperatiirc levels in various locations of the RCS due to they apply to the ECCS: various plant conditions RO 007 2.1.30 3.9 3.4 Conduct of Operations Ability to locatc and opcrate components, including local controls.

RO 007 A2.02 2.6 3.2 Ability to (a) predict the impacts ofthe following malfunctions or Abnormal pressure i n the PRT operations on the PRTS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

RO 008 K4.09 2.7 2.9 Knowledge of CCWS design feature(s) and/or interlock(s) which The "standby" feature for the CCW pumps provide for the following:

RO 010 K6.04 2.9 3.2 Knowledge of the effect of a loss or malfunction of the following will PRT have on the PZR PCS:

RO 012 K5.02 3.1 3.3 Knowledge of the operational implications of the following concepts as Power density they apply to the RF'S:

RO 013 A1.01 4.0 4.2 Ability to predict and/or monitor changes in parameters (to prevent RCS pressure and temperature exceeding design limits) associated with operating the ESFAS controls including:

RO 022 K1.04 2.9 2.9 Knowledge of the physical connections and/or cause-effect relationships Chilled water between the CCS and the following systems:

RO 026 K2.02 2.7 2.9 Knowledge of bus power supplies to the following: MOVs RO 026 K4.01 4.2 4.3 Knowledge of CSS design feature(s) and/or interlock(s) which provide Source of water for CSS, including recirculation phase after LOCA for the following:

RO 039 A4.0 1 2.9 2.8 Ability to manually operate and/or monitor in the control room: Main steam supply valves RO 056 A2.04 2.6 2.8 Ability to (a) predict the impacts of the following malfunctions or Loss of condensate pumps operations on the Condensate System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

RO 056 K1.03 2.6 2.6 Knowledge of the physical connections and/or cause-effect relationships MFW between the Condensate System and the following systems:

RO 059 A3.03 2.5 2.6 Ability to monitor automatic operation of the MFW System, including: Feedwater pump suction flow pressure RO 061 K6.01 2.5 2.8 Knowledge of the effect of a loss or malfunction of the following will Controllers and positioners have on the AFW System components:

-!= RO 062 2.2.22 3.4 4.1 Equipment Control Knowledge of limiting conditions for operations and safety limits.

rh o% Tuesday, January 20,2004 Page 3 of 5

Sample Plan Information for the NRC Makeup RO Exam RO 063 A4.03 3.0 3.1 Ability to manually operate and/or monitor i n the control room: Battery dischar,oe rate RO 063 K1.02 2.7 3.2 Knowledge ofthe physical connections :ind/or cause-effect relationships AC electrical system between the D.C. Elcctrical System and thc following systems:

RO 064 A I .03 3.2 3.3 Ability to predict and/or monitor changes in parameters (to prevent Operating voltages, currents, and temperatures excecding design limits) associatcd with operating the ED/G Systcni controls including:

RO 073 A4.02 3.7 3.7 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel RO 076 K2.01 2.7 2.7 Knowledge of bus power supplies to the following: Service water RO 078 2.1.28 3.2 3.3 Conduct of Operations Knowledge of the purpose and function of ma.jor system components and controls.

RO 078 K4.01 2.7 2.9 Knowledge of IAS design feature(s) and/or interlock(s) which provide Manual/automatic transfers of control for the following:

RO I03 A2.03 3.5 3.8 Ability to (a) predict the impacts of the following malfunctions or Phase A and B isolation operations on the Containment System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

RO 103 K3.03 3.7 4.1 Knowledge of the effect that a loss or malfunction of the Containment Loss of containment integrity under refueling operations System will have on the following:

Tier: 2 Group: 2 RO SRO Exam ID KA Imp Imp Full KA Statement RO 00 1 A3.06 3.9 3.9 Ability to monitor automatic operation of the CRDS, including: RCS temperature and pressure RO 002 K5.11 4.0 4.2 Knowledge of the operational implications of the following concepts as Relationship between effects of the primary coolant system and the they apply to the RCS: secondary coolant system RO 01 1 K4.06 3.3 3.7 Knowledge of PZR LCS design feature(s) and/or interlock(s) which Letdown isolation provide for the following:

RO 015 K2.0 1 3.3 3.7 Knowledge of bus power supplies to the following: NIS channels, components, and interconnections RO 016 K3.12 3.4 3.6 Knowledge of the effect that a loss or malfunction o f the "IS will S/G have on the following:

RO 034 K1.02 2.5 3.2 Knowledge of the physical connections and/or cause-effect relationships RHRS between the Fuel Handling System and the following systems:

RO 04 1 A1.02 3.1 3.2 Ability to predict and/or monitor changes in parameters (to prevent Steam pressure u

l exceeding design limits) associated with operating the SDS controls including:

w Tuesday, January 20,2004 Page 4 of 5

Sample Plan Information for the NRC Makeup RO Exam RO 072 A2.02 2.8 2.9 Ability to (a) predict the impacts ofthe following malfunctions or Detector failure operations on the ARM system and (b) based on thosc prcdictions. use procedures to corrcct, control. or mitigate thc consequences of thosc malfunctions or opcrations:

RO 079 A4.01 2.1 2.7 Ahtlity to manually operate and/or monitor in thc control room: Cross-tie valves with IAS RO 086 2.4.50 3.3 3.3 Emcrgency ProccduresPlan Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Tier: 3 Group: 1 RO SRO Exam ID KA ImD ImD Full KA Statement RO iENERII 2.1.11 3.0 3.8 Conduct of Operations Knowlcdgc of less than one hour technical specification action statcnients for systems.

RO iENERIi 2.1.25 2.8 3.1 Conduct of Operations Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.

RO iENERIi 2.2.1 3.7 3.6 Equipment Control Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

RO iENERIi 2.2.12 3.0 3.4 Equipment Control Knowledge of surveillance procedures.

RO iENERIl 2.2.2 4.0 3.5 Equipment Control Ability to manipulate the console controls as required to operate the racil ity betwccn shutdown and designatcd power levels.

RO iENERll 2.3.2 2.5 2.9 Radiation Controls Knowledge of facility ALARA program.

RO ENERF 2.3.4 2.5 3.1 Radiation Controls Knowlcdgc of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

RO iENERIl 2.3.9 2.5 3.4 Radiation Controls Knowledge of the process for performing a containment purge.

RO iENERIl 2.4.2 3.9 4.1 Emergency ProceduresPlan Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. Note: The issue of setpoints and automatic safety features is not specifically covered in the systems sections.

RO iENERIi 2.4.6 3.1 4.0 Emergency Procedures/Plan Knowledge symptom based EOP mitigation strategies.

Tuesday, January 20,2004 Page 5 of 5

n Sample Plan Information for the NRC Makeup SRO Exam Tier: 1 Group: 1 RO SRO Exam ID KA ImD ImD Full KA Statement

~

SRO 007 2.1.14 2.5 3.3 Conduct of Operations Knowledge of system status criteria which require the notification of plant personnel.

SRO 008 AA2.01 3.9 4.2 Ability to determine and interpret the following as they apply to the RCS pressure and temperature indicators and alarms Pressurizer Vapor Space Accident:

SRO 011 2.4.4 4.0 4.3 Emergency ProccdureslPlan Ability to recognize abnormal indications for system operating parameters which arc entry-level conditions for emergency and abnormal operating procedures.

SRO 025 AA2.06 3.2 3.4 Ability to determine and interpret the following as they apply to the Existence of proper RHR overpressure protection Loss of Residual Heat Removal System:

SRO 029 2.4.6 3.1 4.0 Emergency Procedures/Plan Knowledge symptom based EOP mitigation strategies.

SRO 038 EA2.13 3.1 3.7 Ability to determine and interpret thc following as they apply to a SGTR: Magnitude of rupture SRO Ell EA2.1 3.4 4.2 Ability to determine and interpret the following as they apply to the Facility conditions and selection of appropriate procedures during Loss of Emergency Coolant Recirculation: abnormal and emergency operations Tier: 1 Group: 2 RO SRO Exam ID KA Imp Imp Full KA Statement SRO 005 AA2.01 3.3 4. I Ability to determine and interpret the following as they apply to the Stuck or inoperable rod from in-core and ex-corc NIS. in-core or Inoperable/Stuck Control Rod: loop temperature measurements SRO 033 2.1.33 3.4 4.0 Conduct of Operations Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

SRO 037 AA2.12 3.3 4.1 Ability to determine and interpret the following as they apply to the Flow rate of leak Steam Generator Tube Leak:

SRO 076 AA2.02 2.8 3.4 Ability to determine and interpret the following as they apply to the Corrective actions required for high fission product activity in RCS High Reactor Coolant Activity:

SRO E02 2.4.4 4.0 4.3 Emergency Procedures/Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Tier: 2 Group: 1 RO SRO 4 Exam ID KA imp Imp Full KA Statement 0

-7) uo Tuesday, January 20,2004 Page 1 o f 2

Sample Plan Information for the NRC Makeup SRO Exam SRO 061 A2.06 2.7 3.0 Ability to (a) predict the impacts of the following malfunctions or Back leakage of MFW operatiom on the AI:W System and (13) based on those predictions, use procedures to correct. control. or mitigate the consequences of thosc malfunctions or operations:

SRO 062 A2.05 2.9 3.3 Ability to (a) predict the impacts of the following malfunctions or Methods for cnergizing a dead bus operations on the A.C. Distribution System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

SRO 073 2.4.4 4.0 4.3 Emergency Procedures/Plan Ability to recognizc abnormal indications for system operating parameters which are entty-lcvcl conditions for emergency and abnormal operating procedures.

SRO 076 2.1.33 3.4 4.0 Conduct of Operations Ability to rccognize indications for system operating parameters which are entry-level conditions for technical specifications.

Tier: 2 Group: 2 RO SRO Exam ID KA Imp Imp Full KA Statement SRO 027 2.4.6 3. I 4.0 Emergency Procedures/Plan Knowledge symptom based EOP mitigation strategies.

SRO 075 2.4.6 3.1 4.0 Emergency ProceduresPlan Knowledge symptom based EOP mitigation strategies.

Tier: 3 Group: 1 RO SRO Exam ID KA Imp Imp Full KA Statement SRO il:NERII 2.1.10 2.7 3.9 Conduct of Operations Knowledge of conditions and limilations in the facility license.

SRO iENERII 2. I .6 2.1 4.3 Conduct of Operations Ability to supervise and assume a management role during plant transients and upset conditions.

SRO iENERIl 2.2. I O 1.9 3.3 Equipment Control Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment.

SRO iENERIl 2.2.25 2.5 3.7 Equipment Control Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

SRO iENERIl 2.3.11 2.7 3.2 Radiation Controls Ability to control radiation releases.

SRO iENERIl 2.4.3 1 3.3 3.4 Emergency Procedures/Plan Knowledge of annunciators alarms and indications, and use of the response instructions.

• Y, SRO iENERIl 2.4.42 2.3 3.7 Emergency Procedures/Plan Knowledge of emergency responsc facilities.

ho Tuesday, January 20,2004 Page 2 of 2