ML090780246

Initial Exam 2008-301 Draft Administrative Documents

ML090780246
Person / Time
Site:	Saint Lucie
Issue date:	07/21/2008
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/08-301, 50-389/08-301, ES-401, ES-401-2, NUREG-1021, Rev. 9 50-335/08-301, 50-389/08-301
Download: ML090780246 (18)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: St. Lucie Plant Date of Exam: July 21, 2008 RO KIA CateQorv Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 2 2 5 4 3 2 18 3 3 6 Emergency &

Abnormal Plant 2 2 1 2 N/A 2 1 N/A 1 9 3 1 4 Evolutions Tier Totals 4 3 7 6 4 3 27 6 4 10 1 2 1 3 5 2 1 2 3 3 4 2 28 2 3 5 2.

Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 2 1 3 Systems Tier Totals 3 2 4 6 2 2 3 4 4 5 3 38 4 4 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 2 2 3 3 2 1 1 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topiGs' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) Ilrllp. I Q# ~

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Knowledge of the interrelations between the (Reactor Trip Recovery) and the following: Components, and functions E02 I Reactor Trip Recovery 11 x EK2.1 of control and safety systems, including instrumentation, 3.3 signals, interlocks, failure modes, and automatic and manual features.

Ability to operate and lor monitor the following as they OOBI Pressurizer Vapor Space Accident I 3 x AA1.0B apply to the Pressurizer Vapor Space Accident: PRT level 3.B 2 pressure and temperature.

Knowledge of the reasons for the following responses as 009 I Small Break LOCA I 3 x EK3.21 they apply to the small break LOCA Actions contained in 4.2 3 EOP for small break LOCA I leak.

Knowledge of the operational implications of the following 011 I Large Break LOCA I 3 x EK1.01 concepts as they apply to the Large Break LOCA : 4.1 4 Natural circulation and cooling, including reflux boiling.

Knowledge of the interrelations between the Reactor 015/17 I RCP Malfunctions I 4 x AK2.10 Coolant Pump Malfunctions (Loss of RC Flow) and the 2.B 5 following: RCP indicators and controls.

Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup:

022 I Loss of Rx Coolant Makeup I 2 x AK3.02 Actions contained in SOPs and EOPs for RCPs, loss of 3.5 6 makeup, loss of charging, and abnormal charging.

Ability to determine and interpret the following as they 025 I Loss of RHR System I 4 x AA2.06 apply to the Loss of Residual Heat Removal System: 3.2 7 Existence of proper RHR overpressure protection.

Ability to operate and lor monitor the following as they 026 I Loss of Component Cooling Water I B x AA1.03 apply to the Loss of Component Cooling Water: SWS as 3.6 B a backup to the CCWS.

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) limp. I Q# ~

Ability to determine and interpret the following as they 027 I Pressurizer Pressure Control System Malfunction I x AA2.04 apply to the Pressurizer Pressure Control Malfunctions: 3.7 9 3

Tech Spec limits for RCS Pressure.

Knowledge of the reasons for the following responses as 0381 Steam Gen. Tube Rupture I 3 x EK3.01 they apply to the SGTR: Equalizing pressure on primary 4.1 10 and secondary side of the ruptured S/G.

Ability to operate and lor monitor the following as they CE/E05 I Excess Steam Demand I 4 x EA1.3 apply to the (Excess Steam Demand): Desired operating 3.4 11 results during abnormal and emergency situations.

Ability to determine and interpret the following as they apply to the (Loss of Feedwater): Facility conditions and CE/E06 I Loss of Feedwater I 4 x EA2.1 2.8 12 selection of appropriate procedures during abnormal and emergency operations.

Knowledge of the operational implications of the following 055 I Station Blackout I 6 x EK1.01 concepts as they apply to the Station Blackout: Effects of 3.3 13 battery discharge rates on capacity.

Conduct of Operations I Knowledge of the purpose and 056 I Loss of Off-site Power I 6 x 2.1.28 4.1 14 function of major system components and controls.

Equipment Control I Ability to interpret control room indications to verify the status and operation of a system, 057 I Loss of Vital AC Inst bus x 2.2.44 4.2 15 and understand how operator actions and directives affect plant and system conditions.

Knowledge of the reasons for the following responses as 058 I Loss of DC Power I 6 x AK3.02 they apply to the Loss of DC Power: Actions contained in 4.0 16 EOP for loss of dc power.

Knowledge of the reasons for the following responses as 062 I Loss of Nuclear Svc Water I 4 they apply to the loss of nuclear service water: Guidance x Ak3.03 4.0 17 actions contained in EOP for loss of nuclear service water.

Ability to determine and interpret the following as they 0771 Generator Voltage and Electric Grid Disturbances I 6 x AA2.04 apply to Generator Voltage and Electric Grid 3.5 18 Disturbances: VARs outside the capability curve ..

KIA Category Point Totals:

Group Point 2/3 2 2 5 4 3/3 18/6 Total:

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # I Name Safety Function I G I K1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) Imp. Q#

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Knowledge of the reasons for the following responses as 003 I Dropped Control Rod 11 x AK3.04 they apply to the Dropped Control Rod: Actions contained 3.8 19 in EOP for dropped control rod.

Ability to determine and interpret the following as they 028 I Pressurizer Level Control Malfunction I 2 x AA2.01 apply to the Pressurizer Level Control Malfunctions: PZR 3.4 20 level indicators and alarms.

Equipment Control I Ability to apply Technical 0321 Loss of Source Range NI/7 x 2.2.40 Specifications for a system.

3.4 21 Ability to operate and I or monitor the following as they 037 I Steam Generator Tube Leak I 3 x AA1.13 apply to the Steam Generator Tube Leak: S/G blowdown 3.9 22 radiation monitors.

Ability to operate and I or monitor the following as they 068 I Control Room Evac I 8 x I I AA1.21 apply to the control room evacuation: transfer of controls from the control room to shutdown panel or local control.

3.9 23 Knowledge of the reasons for the following as they apply 076 I High Reactor Coolant Activity I 5 x I AK3.06 to the High Reactor Coolant Activity: Actions contained 3.2 24 in EOP for high reactor coolant activity.

Knowledge of the interrelations between the (Natural Circulation Operations) and the following: Facility*s heat CE/A13I Natural Circulation 14 removal systems, including primary coolant, emergency x AK2.2 3.4 25 coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Knowledge of the operational implications of the following concepts as they apply to the (Excess RCS Leakage):

CE/A 16 I Excessive RCS Leakage I 2 x AK1.3 Annunciators and conditions indicating signals and 3.2 26 remedial action associated with the (Excess RCS Leakage)

ES-'401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # I Name Safety Function IG IK1 I K2 I K3 I A1 I A2 I Number I KIA Topic(s) nl~P.T Q# ~

Knowledge of the operational implications of the following concepts as they apply to the (Functional Recovery):

CE/E091 Functional Recovery x EK1.2 3.2 27 Normal, abnormal and emergency operating procedures associated with Functional Recovery KIA Category Point Total: 111 2 1 2 2 1/3 Group Point Total: I 9/4 10

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 I System #/Name I G I K1 I K2 I K3 InlS4 I ~11S6 I A1 JA2 I A3 I A! I_Number I ________ ._ KIA Topics limp. I Q#

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x a1l o:t6Is~"¥I~Wl3te'r lJ,i lllQ Knowledge of the physical connections and/or cause-003 Reactor Coolant Pump x I K1.03 effect relationships between the RCPS and the following I 3.3 I 28 systems: RCP seal system.

the effec 003 Reactor Coolant Pump x I K6.14 I following-Will have on the RCPS Starting requirements. I 2.6 I 29 I Knowledge of the operational implications of the 004 Chemical and Volume Control x

I K5.16 following concepts as they apply to the CVCS: Source of T-ave and T-ref signals to control and RPS I 3.2 I 30 004 Chemical and Volume Ability to manually operate and / or monitor in the x A4.15 control room: boron concentration 3.6 31 Control Knowledge of the effect that a loss or malfunction of the 005 Residual Heat Removal x K3.01 3.9 32 RHRS will have on the following: RCS.

Conduct of Operations / Ability to explain and apply 005 Residual Heat Removal x I 2.1.32 system limits and precautions 3.8 33 Knowledge of ECCS design feature(s) and/or 006 Emergency Core Cooling I x I K4.08 interlock(s) which provide for the following: 3.2 I 34 Recirculation flowpath of reactor building sump.

I Ability to (a) predict the impacts of the following malfunctions or operations on the P S; and (b) based on 007 Pressurizer Relief/Quench Tank I I x A2.01 those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or 3.9 I 35 operations: Stuck-open PORV or code safety.

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 I System #/Name G I K1 I K211S~J1(41 K5 IK6 I A1 I A2 I A3LJ\4 I Number I KJA Topics limp. I Q#

Knowledge of CCWS design feature(s) and/or 008 Component Cooling Water x K4.01 interlock(s) which provide for the following: Automatic 3.1 36 start of standby pump.

Ability to monitor automatic operation of the CCWS, 008 Component Cooling Water x A3.05 including: Control of the electrically operated, automatic 3.0 37 isolation valves in the CCWS.

Ability to manually operate and/or monitor in the control 010 Pressurizer Pressure Control x A4.01 3.7 38 room: PZR spray valve.

Knowledge of the effect that a loss or malfunction of the 012 Reactor Protection x K3.01 3.9 39 RPS will have on the following: CROS.

Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based 012 Reactor Protection x A2.02 on those predictions, use procedures to correct, control, 3.6 40 or mitigate the consequences of those malfunctions or operations: Loss of instrument power.

013 Engineered Safety Features Ability to monitor automatic operation of the ESFAS x A3.01 including: Input channels and logic. 3.7 41 Actuation Ability to manually operate and/or monitor in the control 022 Containment Cooling x A4.01 3.6 42 room: CCS fans.

Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following: Prevention of path for 026 Containment Spray x K4.09 3.7 43 escape of radioactivity from containment to the outside (interlock on RWST isolation after swapover)

Ability to monitor automatic operation of the MRSS, 039 Main and Reheat Steam x A3.02 3.1 44 including: Isolation of the MRSS.

Knowledge of the effect that a loss or malfunction of the 059 Main Feedwater x K3.04 3.6 45 MFW will have on the following: RCS.

Ability to (a) predict the impacts ofthe following malfunctions or operations on the MFW; and (b) based 059 Main Feedwater x A2.12 on those predictions, use procedures to correct, control, 3.1 46 or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves.

Ability to predict and/or monitor changes in parameters 061 Auxiliary/Emergency (to prevent exceeding design limits) associated with Feedwater x A1.01 3.9 47 operating the AFW controls including: S/G level.

061 Auxiliary/Emergency Knowledge of the operational implications of the Feedwater x K5.01 following concepts as the apply to the AFW: 3.6 48 Relationship between AFW flow and RCS heat transfer.

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 1 I System #/Name I G I K1 I K2 I K3 I K4 I K5 I K6 I A1 I A2 I A3 I A4 I Number I KIA Topics limp. I Q# I Knowledge of ac distribution system design feature(s) I 062 AC Electrical Distribution x K4.05 and/or interlock(s) which provide for the following: 2.7 49 Paralleling of ac sources (synchroscope). ,

Ability to manually operate and/or monitor in the control 063 DC Electrical Distribution x A4.01 2.8 50 room: Major breakers and control power fuses.

i Knowledge of ED/G system design feature(s) and/or 064 Emergency Diesel Generator x K4.02 interlock(s) which provide for the following: Trips for 3.9 51 I ED/G while operating (normal or emergency).

073 Process Radiation Monitoring Ability to predict changes in parameters (to prevent exceeding design 073 Process Radiation Monitoring x A1.01 3.2 52 limits) associated with operating the PRM system controls including: radiation levels.

Knowledge of bus power supplies to the following:

076 Service Water X K2.01 2.7 53  !

Service water Knowledge of the physical connections and/or cause- i 078 Instrument Air x K1.02 effect relationships between the lAS and the following 2.7 54 i systems: Service Air.

Equipment Control I Knowledge of the bases in 103 Containment x 2.2.25 Technical Specifications for limiting conditions for 3.2 55 operations and safety limits. i KIA Category Point Totals:

2/3 2 1 3 5 2 1 2 3/2 3 4 Group Point Total:

I 28/5 !

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 2 I System #/Name I G I K1 I K2 I K3 I K4 I K5 I K6 I A1 I A2 I A3 I A4 I Number I KIA Topics I Imp. I Q# I Ability to predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions use 075 Circulating Water X A2.02 2.5 65 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of circulating water pumps.

KIA Category Point Totals: 1/1 1 1 1 1 0 1 1 1/2 1 1 Group Point Total: I 10/3

ES-401 St. Lucie USNRC License Exam Form ES-401-2 PWR BOTH Written Examination Outline Plant Systems - Tier 2 Group 2 I System #/Name I G I K1 I K2 I K3 I K4 I K5 I K6 I A1 I A2 I A3 I A4 I Number I KIA Topics Imp. Q#

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Knowledge of CRDS design feature(s) and/or 001 / Control Rod Drive I x I K4.03 interfock(s) which provide for the following: Rod 3.5 56 control logic.

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 002 Reactor Coolant I x I A1.04 associated with operating the RCS controls 3.9 57 including: Subcooling Margin.

Knowledge of bus power supplies to the following:

011 Pressurizer Level Control x I K2.02 Pressurizer Heaters.

3.1 58 Knowledge of the effect of a loss or malfunction on 015/ Nuclear Instrumentation I x I K6.01 I the following will have on the NIS: Sensors, 2.9 59 detectors and indicators.

Ability to monitor automatic operation of the 029 / Containment Purge I x I A3.01 Containment Purge System including: CPS 3.8 60 isolation.

041 Steam Dump/Turbine Bypass Ability to manually operate and/or monitor in the control room: Main steam header pressure. 3.1 61 Control Emergency Procedures / Ability to perform without reference to procedures those actions that require 045 / Main Turbine Generator I x I 2.4.49 immediate operation of system components and 4.6 62 controls.

Knowledge of the effect that a loss or malfunction of 055 Condenser Air Removal I x I K3.01 I the CARS will have on the following: Main 2.5 63 condenser.

Knowledge of the physical connections and/or 056 I Condensate I x I K1.03 cause-effect relationships between the Condensate 2.6 64 System and the following systems: MFW.

ES-401 Generic Knowledge and Abilities Outline (Tier3) I Form ES-401-3 I Facility: St. Lucie NRC Exam Date of Exam: 7/2008 RO Category KIA # Topic IR Q#

1.

Conduct of 4.1 66 Operations 3.4 67 4.3 68 Subtotal 3 2.

Equipment Control 3.8 69 2.2.12 Knowledge of surveillance procedures. 3.7 70 Subtotal 2 Knowledge of radiation exposure limits under 2.3.4 3.2 71 normal or conditions.

Knowledge radiological procedures

3. pertaining to licensed operator duties, such as Radiation Control response to radiation monitor alarms, 2.3.13 3.4 72 containment entry requirements, fuel handling responsibilities, access to locked high-radiation etc.

Subtotal 2 ge of crew responsibilities during EOP 4.0 73

4. Knowledge of the bases for prioritizing safety Emergency 2.4.22 functions during abnormal/emergency 3.6 73 Procedures / Plan alarms, indications, or 2.4.31 4.2 75 Subtotal 3 Tier 3 Point Total 10

I ES-401 Record of Rejected KJAs I Form ES-401-4 I Tier 1 Group De-selected KA Reason for Rejection Not applicable to St. Lucie 1/1 (008) AA1.04 Operate 1 Monitor Feedwater Pumps during Pzr. Vapor sp_ace accident Not applicable to St. Lucie 3.02 Knowledge of opening excess letdown isolation valves during 1/1 (009) EK3.02, EK3.27 SBLOCA 3.27 Manual depress, or HPI recirc for sustained high pressure Not applicable to St. Lucie 1/1 (027) AA2.13 PZR PCS malfunction, ability to interpret Seal return flow Not applicable to St. Lucie 1/1 (038) EK3.07 SGTR RCS loop isolation valves Not applicable to St. Lucie AK3.01, AK3.02, 3.01 Dropped CEA when ICS logic has failed 1/2 (003)

Ak3.03 3.02 Dropped CEA reactor runback 3.03 Dropped CEA turbine run back Not applicable to St. Lucie 2.03 Pzr Level control malfunction ability to determine Charging 1/2 (028) AA2.03, AA2.05 subsystem flow indo And controller 2.05 Pzr Level control malfunction ability to determine flow control valve isolation valve indicator Not applicab,le to St. Lucie 1/2 (068) AA1.09, AA1.22 1.09 CR Evacuation, ability to operate 1 monitor synch. Key 1.22 Flow control valve for RCS charging header Not applicable to St. Lucie 1/2 (076) AK3.03 High RCS activity, knowledge of reasons, orifice controls for minimum letdown Not applicable to St. Lucie 2/1 (004) A4.20 CVCS, deborating demin. Selector valve and control switch Not applicable to St. Lucie 2/1 (006) K4.22, K4.29 4.22 ECCS, interlocks between RCP seal flow rate and standby HPI pp 4.29 ECCS, BIT recirculation Not applicable to St. Lucie 2/1 (059) A2.06, A2.07 2.06 MFW, loss of steam flow 2.07 MFW, tripping of MFW pump turbine Not applicable to St. Lucie 2/1 (076) K2.04 SWS, power supply to reactor building closed cooling water Not applicable to St. Lucie 2/2 (041) A4.01 SOS, ICS voltage inverter NUREG-1021 12 RAFT

Sample Plan Development

1. KIA Category selection To ensure equal distribution of KIA categories, the first column on Form ES-401-2 Examination Outline sheets was covered so that the specific subject could not be seen. The total number of questions for each sheet was written on the top of the page. X's were placed in the KIA boxes at random, ensuring that distribution of Knowledge and Ability items was fairly equal and the total number of boxes checked matched the number written on the top of the page. Items not related to CE plants (such as Westinghouse, B&W E/APs, Ice Condenser, Loss of Intermediate Range Nls, etc.) were initially blacked out (prior to concealing the subjects) to prevent them from being selected. On the SRO portion of the exam, all KAs except Generic and A2s were initially blacked out to prevent them from being selected. Generic KIA categories for Tier 1 and 2 were randomly selected using tokens numbered 1,2 and 4. (no generic KIA's for 2.3 .... were chosen as per ES-401 page 4) Generic KlA'categories for Tier 3 were selected using tokens numbered 1 through 4.

2. Individual Topics Once the category selection was completed, individual topics for each Knowledge or Ability were selected using tokens. When selecting topics, KlAs that were <2.5 and any topics that were not applicable to St. Lucie Plant were deselected from the category prior to drawing tokens from the can (See attached matrix). For example, if the category was K1 and there were 15 topics, then tokens 1 through 15 were used. If item K1.06 was less than 2.5, token 6 was not used. If item K1.11 was not plant specific to St. Lucie, token 11 was not used. If a generic KIA was chosen for tiers 1 and 2, then only the specified numbers in ES-401, page 4 of 33 were used. On tier 3, all numbers in the specified generic category were used.

Summary The sample plan was randomly generated and, by using the above described methodology, no KAs that were initially selected had to be deselected.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Date of Examination: July 2008 Examination Level (circle one): RO@ Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine Fuel Preconditioning Guidelines and Conduct of Operations N,R Severity of Reactivity Event KIA 2.1.37 (4.6)

Determine QSPDS Values when Plasma Display is Conduct of Operations N,R Out Of service, Unit 2.

KIA 2.1.25 (3.9/4.2)

Determine SDM criteria.

Equipment Control N,R KIA 2.2.39 (4.5)

Use a survey map, determine Radiological hazards.

Radiation Control N,R KIA 2.3.7 (3.5/3.6)

Evaluate E-Plan Based on Loss of Annunciation c Emergency Plan NOTE:

N,S KIA 2.4.29 (4.4)

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, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ for SROs & RO retakes)

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

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

FT NUREG-1 021, Revision 9

R FT ES-301 Administrative Topics Outline Form ES-301-1 ADMINISTRATIVE JPM

SUMMARY

A 1-1: Determine Fuel Preconditioning Guidelines and Classification of Reactivity Event. The Candidate will be given a set of conditions to determine if Fuel preconditioning guidelines are being met. The guidelines will not be met and due to set of conditions NAP-402 requires the event to be classified as a noteworthy Reactivity event.

A2: Determine QSPDS Values when Plasma Display is Out Of service, Unit 2. Using Appendix B from 2-1150020 Qualified Safety Parameter Display Operation the Operator will calculate the parameters requested from the Que. sheet.

A3-2 Determine Shutdown Margin Criteria. Applicant will calculate SDM lAW 2-NOP-100.04, "Surveillance Requirements for Shutdown Margin; Modes 2,3,4,and 5 (Subcritical)" and determine SDM not met. Direct emergency boration to meet T.S. 3.1.1.1 A4: Using a survey map, determine Radiological Hazards. The Candidate will be given a radiation survey map of the Unit 2 Charging Pump rooms. His stated task will be to determine Radiological hazards in each of the Charging Pump rooms.

A5: Evalaute E-Plan Based on Loss of Annunciation. The Candidate will be given a set of conditions and directed to implement 1-0NP-100.03 Partial or Complete Loss of Annunciators. They will be required to calculate the percentage of annunciators lost and refer to EPIP-01 Classification of Emergencies. The event should be a classified as Unusual event due to >75% of annunciators lost for >15 minutes.

FT NUREG-1021, Revision 9

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

System / JPM Title Type Code* Safety Function S-1 Restore AFW flow to the 2A SG using 2C AFW pump N,A,S,L 45 All S-2 Respond to loss of RCP Controlled Bleed Off and failed RCP E,N,A,S 4p Seals All S-3 Align ECCS for Hot and Cold Leg Injection M, E,A,S 2 All S-4 Establish Alternate Charging flowpath to RCS through 'A' HPSI D,S,E 1 Header.

S-5 Respond to alarms on Spent Fuel Monitors P,E,A,S,D 7 C-6 Place LTOP In Service Unit 1 P,C,D,E 3 S-7 Align 2C CCW pump to supply the 'B' CCW header N,E,S 8 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 Local Operation of Boron Concentration Control Unit - 2 E,N,R 1 All P-2 Align Unit 2 CST to supply the 1C AFW pump D,E 45 P-3 Disconnect 1B Instrument Inverter from Service Unit -1 D 6 All DRAFT NUREG-1 021, Revision 9

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

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ~ 1/ 1/ 1 (L)ow-Power ~1/21/~1 (N)ew or (M)odified from bank including 1(A)  ?'2/~2/~1 (P)revious 2 exams 3/ s 3 / s 2 (randomly selected)

(R)CA ~1/?'1/?'1 (S)imulator JPM

SUMMARY

DESCRIPTION S-1 New. At low power, the Applicant will be required to start and initiate AFW flow from the 2C AFW pump to the 2A SG and remove the 2A AFW pump form service. Upon starting the 2C AFW pump, it will trip on electrical overspeed. The Candidate will be required to reset the overspeed trip and initiate flow to the 2A SG. Alternate path S-2 S-2 New. Respond to loss of RCP Controlled Bleed Off and failed RCP Seals. The Applicant will be directed to respond to loss of RCP controlled seal bleed off at 100% power. Candidate will be required to recognize V2505 is closed and will be required to open V 2507, to the QT. Upon opening V2507 three seals will fail requiring a manual Reactor trip and stopping the RCP post trip. Alternate path.

S-3 Modified Bank #0821158. The Applicant is required to align the 'B' train for Hot and Cold leg Injection. V3523 will not open and the 'A' train will be required for lineup for Hot and Cold leg injection.

S-4 Bank #0821115. Candidate will line-up 2A Charging pump to the 'A' HPSI header for emergency boration post trip.

S-5 Bank # 0821117 A (2004 NRC Exam). Respond to alarms on Spent Fuel Monitors. Spent Fuel Pool radiation monitors go into high alarm during refueling operations. Candidate is required to verify ventilation system. Alternate path.

C-6 Bank #0821021. (2004 NRC exam) Unit 1 Control Room. Unit 1 is experiencing a LOCA. 1-EOP-03 is being implemented. RCS temperature is 290 degrees and pressure is 500 psia. The Applicant is directed to place LTOP in service lAW 1-GOP-305.

S-7 New. Applicant will be required to align the 2C CCW to the 'B' CCW header. Prior to starting the 2C CCW the AB 4.16KV bus is required to be aligned to the B side.

S-8 Bank #0821143. Using 2-EOP-99 Appendix M, Applicant will place Hydrogen Recombiner in service during LOCA with Hydrogen >2.5% in Containment.

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NUREG-1 021, Revision 9

ES-301 Form ES-301-2 P-1 New. A blend is to be performed to the VCT. Proper flow rates cannot be achieved from the control room. The Applicant is required to use Appendix A to locally blend to the VCT with communication to the control room.

P-2 Bank #0821062. During a Unit 1 total loss of feedwater, Applicant will align the Unit 2 Condensate Storage Tank to supply Unit 1 'C' AFW pump.

P-3 Bank #0821067. The 1B 120V Instrument Inverter is to be removed from service for maintenance. The Applicant is instructed to place the bus on maintenance bypass.

NUREG-1 021, Revision 9