ML041470484
| 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: |
| 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 Admin PWR Examination Outline & Written Sample Plan (includes equivalent of Form ES-401-3)
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::L-PI-04-007, Withdrawal of License Amendment Request (LAR) Dated October 31, 2003 Changes to Technical Specifications to Implement NEI 97-06, Steam Generator Program Guidelines, and Inspection Requirements Associated with the Unit 1 Replacement SGs|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 651-388-1 165, 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, Minnesota 55089-9642 Telephone: 651.388.1 121
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facilit Item
~
- 1.
W R
I T
T E
N
- 2.
S I
M
- 3.
W I
T 4
a Aut Date of Examination:
Task Description
- a. Verify that the outline(s) fit@) the appropriate model per ES-401
- c. Assess whether the outline over-emphasizes any systems, evolutioxs, or E d Assess whether the justifications for deselected or rejected WA ojected number a
. schedule withou b Verify that (1) the tasks are distributed a (2) one task is conducted in a I w
i r b Facility Reviewer (*)
c NRC Chief Examiner (#)
d NRC Supervisor MA Note:
' Not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.
NUREG-1021, Draft Revision 9 24 of 25
ES-40 1 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.
For Tic. 3. enter tlic K/A numbers descriptions importance ratings. and point totals on Forrr KS-401-3 Refer to ES-401~, for guidance regarding the elimination of i tw p p "0 p ria te K'A sta term nts.
8 9
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 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)
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 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 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 reactor trip:
Pressurizer Vapor Space Accident:
the small break LOCA:
Break LOCA:
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 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:
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:
ATWS:
tube rupture, and plant shutdown procedures 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 instrumcntation, signals, interlocks, Iailure modcs, and automatic and manual features 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:
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 RO 003 RO 024 RO 032 RO 036 RO 06 1 RO 068 RO E03 RO El5 AA2.04
- 2. I.23 AA1.13 2.4.3 1 AK2.02 AA2.06 AA1.06 EK3.2 EK1.3 4.2 4.3 3.9 4.0 3.2 3.0 3.3 3.4 3.4 3.9 3.2 4.1 4.1 4.2 3.4 3.9 2.8 3.0 Ability to determine and interpret thc following as they apply to the Continuous Rod Withdrawal:
Conduct of Operations Ability to operate and/or monitor the following as they apply to the Emergency Boration:
Emergency Procedures/Plan Knowledge of the interrelations between the Fuel Handling Incidents and the following:
Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms:
Ability to operate andor monitor the following as they apply to the Control Room Evacuation:
Knowledge of the reasons for the following responses as they apply to the LOCA Cooldown and Depressurization:
Knowledge of the operational implications of the following concepts as they apply to the Containment Flooding:
Reactor power and its trend Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Boric acid flow controller Knowledge of annunciators alarms and indications, and use of the response instructions.
Radiation monitoring equipment (portable and installed)
Required actions if alarm channel is out of service Charging pump Normal, abnormal and emergency operating procedures associated with LOCA Cooldown and Depressurization Annunciators and conditions indicating signals, and remedial 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 RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO RO
-!=
RO rh 004 005 006 007 007 008 010 012 013 022 026 026 039 056 056 059 061 062 A3.09 K3.01 K5.07 2.1.30 A2.02 K4.09 K6.04 K5.02 A1.01 K1.04 K2.02 K4.01 A4.0 1 A2.04 K1.03 A3.03 K6.01 2.2.22 NRC Makeup RO Exam 3.3 3.9 2.7 3.9 2.6 2.7 2.9 3.1 4.0 2.9 2.7 4.2 2.9 2.6 2.6 2.5 2.5 3.4 3.2 4.0 3.0 3.4 3.2 2.9 3.2 3.3 4.2 2.9 2.9 4.3 2.8 2.8 2.6 2.6 2.8 4.1 Ability to monitor automatic operation of thc CVCS, including:
Knowlcdgc of thc cffcct that a loss or malfunction of thc RHRS will have on the following:
Knowledgc of the opcrational implications of thc following concepts as they apply to the ECCS:
Conduct of Operations Ability to (a) predict the impacts ofthe following malfunctions or operations on the PRTS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Knowledge of CCWS design feature(s) and/or interlock(s) which provide for the following:
Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS:
Knowledge of the operational implications of the following concepts as they apply to the RF'S:
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including:
Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:
Knowledge of bus power supplies to the following:
Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
Ability to manually operate and/or monitor in the control room:
Ability to (a) predict the impacts of the following malfunctions or 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:
Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems:
Ability to monitor automatic operation of the MFW System, including:
Knowledge of the effect of a loss or malfunction of the following will have on the AFW System components:
Equipment Control VCT level RCS Expected tcmperatiirc levels in various locations of the RCS due to various plant conditions Ability to locatc and opcrate components, including local controls.
Abnormal pressure in the PRT The "standby" feature for the CCW pumps PRT Power density RCS pressure and temperature Chilled water MOVs Source of water for CSS, including recirculation phase after LOCA Main steam supply valves Loss of condensate pumps MFW Feedwater pump suction flow pressure Controllers and positioners Knowledge of limiting conditions for operations and safety limits.
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 in 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 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 RO I03 A2.03 3.5 3.8 Ability to (a) predict the impacts of the following malfunctions or Phase A and B isolation components and controls.
for the following:
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:
System will have on the following:
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 Tier: 2 Group: 2 RO SRO Exam ID KA Imp Imp Full KA Statement RO 00 1 A3.06 RO 002 K5.11 RO 01 1 K4.06 RO 015 K2.0 1 RO 016 K3.12 RO 034 K1.02 RO 04 1 A1.02 ul w
Tuesday, January 20,2004 3.9 3.9 Ability to monitor automatic operation of the CRDS, including:
RCS temperature and pressure 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 provide for the following:
3.3 3.7 Knowledge of PZR LCS design feature(s) and/or interlock(s) which Letdown isolation 3.3 3.7 Knowledge of bus power supplies to the following:
NIS channels, components, and interconnections 3.4 3.6 Knowledge of the effect that a loss or malfunction of the "IS will have on the following:
Knowledge of the physical connections and/or cause-effect relationships RHRS between the Fuel Handling System and the following systems:
exceeding design limits) associated with operating the SDS controls including:
S/G 2.5 3.2 3.1 3.2 Ability to predict and/or monitor changes in parameters (to prevent Steam pressure Page 4 of 5
Sample Plan Information for the NRC Makeup RO Exam 2.9 Ability to (a) predict the impacts ofthe following malfunctions or 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:
Detector failure RO 072 A2.02 2.8 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.
RO SRO Tier: 3 Group: 1 Exam ID KA ImD ImD Full KA Statement RO RO RO RO RO RO RO RO RO RO iENERII iENERIi iENERIi iENERIi iENERIl iENERll ENERF iENERIl iENERIl iENERIi 2.1.11 2.1.25 2.2.1 2.2.12 2.2.2 2.3.2 2.3.4 2.3.9 2.4.2 2.4.6 3.0 3.8 2.8 3.1 3.7 3.6 3.0 3.4 4.0 3.5 2.5 2.9 2.5 3.1 2.5 3.4 3.9 4.1 3.1 4.0 Conduct of Operations Conduct of Operations Equipment Control Equipment Control Equipment Control Radiation Controls Radiation Controls Radiation Controls Emergency ProceduresPlan Emergency Procedures/Plan Knowlcdgc of less than one hour technical specification action statcnients for systems.
Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
Knowledge of surveillance procedures.
Ability to manipulate the console controls as required to operate the racil ity betwccn shutdown and designatcd power levels.
Knowledge of facility ALARA program.
Knowlcdgc of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
Knowledge of the process for performing a containment purge.
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.
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 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 Residual Heat Removal System:
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 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 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.
Steam Generator Tube Leak:
High Reactor Coolant Activity:
Exam ID KA imp Imp Full KA Statement 0
-7) uo Tuesday, January 20,2004 Page 1 of2
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:
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 062 A2.05 2.9 3.3 Ability to (a) predict the impacts of the following malfunctions or Methods for cnergizing a dead bus 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 SRO iENERII SRO iENERIl SRO iENERIl SRO iENERIl SRO iENERIl SRO iENERIl ho Y,
2.1.10
- 2. I.6 2.2. IO 2.2.25 2.3.11 2.4.3 1 2.4.42 2.7 3.9 2.1 4.3 1.9 3.3 2.5 3.7 2.7 3.2 3.3 3.4 2.3 3.7 Conduct of Operations Conduct of Operations Equipment Control Equipment Control Radiation Controls Emergency Procedures/Plan Emergency Procedures/Plan Knowledge of conditions and limilations in the facility license.
Ability to supervise and assume a management role during plant transients and upset conditions.
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.
Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
Ability to control radiation releases.
Knowledge of annunciators alarms and indications, and use of the response instructions.
Knowledge of emergency responsc facilities.
Tuesday, January 20,2004 Page 2 of 2