Text

Final Outlines for the Point Beach Initial Examination - September 2003
	ML033030032
Person / Time
Site:	Point Beach
Issue date:	09/29/2003
From:	Short P; Nuclear Management Co
To:	; Office of Nuclear Reactor Regulation
References
	50-266/03-301, 50-301/03-301
	Download: ML033030032 (31)
	v • d • e

FINAL OUTLINE§ FOR THE POINT BEACH INITIAL EXAMINATION SEPT 2003

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Examination Level: RO Operating Test Number: 2003301 I

Administrative Topic Describe activity to be performed:

(see Note)

Conduct a Control Board Walk-down for Shift Turnover Conduct of Operations /

(identify ALL abnormal items using Turnover Checklist, similar to last Shift Turnover NRC exam, with varied items).

Conduct of Operations /

Plant Parameter Perform a Pressurizer Heater Input Test Calculation (new JPM).

Verification Equipment Control /

Review a Tag Series for adequacy (similar to 2000 NRC Exam).

Tagging & Clearances I Radiation t Control

- /

Radiation Exposure Perform a stay-time calculation (new JPM).

Limits Emergency Plan N/A 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.

NUREG- 1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 1Facility: Point Beach Nuclear Plant Date of Examination: 9129-10/3/03 Examination Level: SRO Operating Test Number: 2003301 Administrative Topic Describe activity to be performed:

Conduct a Control Board Walk-down for Shift Turnover Conduct of Operations /

(identify ALL abnormal items using Turnover Checklist, similar to last Shift Turnover NRC exam, with varied items).

Conduct of Operations /

Plant Parameter Perform a Pressurizer Heater Input Test Calculation (new JPM).

Verification

- I Equipment Control /

Review a Tag Series for adequacy (similar to 2000 NRC Exam).

Tagging & Clearances Radiation Control /

Knowledge of Radiation Evaluate an Emergency Dose Extension (new P M ) .

Exposure Limits Emergency Plan /

Emergency Action Make an Emergency Plan Classification (includes PARS, new JPM).

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

NUREG- 1021, Draft Revision 9

ES-301 Control Roodn-Plant Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Exam Level : RO Operating Test No: 2003301 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U) l System / JPM Title Type Code" Safety Function 1 a. Control Rod Drive System / Respond To Uncontrolled Rod Motion.

1 1 b. Chemical & Volume Control System / Manually Makeup To TheVCT.

c. Emergency Core Cooling System / Fill An Accumulator Gas 2

3: '

I/ d. Reactor Coolant Bump System / Start A Reactor Coolant Pump (last NRC exam)

e. Auxiliary Feedwater System I Raise Steam Generator Level 4 Using Auxiliary Feedwater (secondary)

f. Containment Spray System I Secure Containment Spray .' ' 5.

g. Emergency Diesel Generators / Respond To An Emergency

'6 Diesel Generator Failure To Load

h. Nuclear Instrumentation System I Return A Power Range 7

Nuclear Instrument To Service In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 1

i. Pressurizer Level Control System / Locally Operate A Charging 2

j. A.C. Electrical Distribution / Align Alternate AC Power To A 6

Residual Heat Removal Pump.

k. Spent Fuel Pool Cooling I Use The Spent Fuel Pool Cooling 8

System To Re-flood The RHR System Suction.

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (Slimulator, (L)ow-Power, (R)CA NUREG- 1021, Draft Revision 9

ES-301 Control Roodn-Plant Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 9/29-10/3/03 Exam Level : SRO-I Operating Test No: 2003301 11 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Safety System I JPM Title Code" Function

a. Control Rod Drive System I Respond To Uncontrolled Rod Motion. D, s, A 1 1 b. Chemical & Volume Control System I Manually Makeup To TheVCT. I M,S,A 2

c. Emergency Core Cooling System I Fill An Accumulator Gas 3

d. Reactor Coolant Pump System I Start A Reactor Coolant Pump (last NRC exam) D, s, L IL e. Auxiliary Feedwater System I Raise Steam Generator Level Using Auxiliary Feedwater N, S , L, A 4

(secondary) 1I f. Containment Spray System I Secure Containment Spray

g. Emergency Diesel Generators I Respond To An Emergency 5

N,S, L, A 6 Diesel Generator Failure To Load 1 h. N/A 1 NIA NIA 11 In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) , I

i. Pressurizer Level Control System / Locally Operate A Charging I j. A.C. Electrical Distribution I Align Alternate AC Power To A Residual Heat Removal Pump.

I k. Spent Fuel Pool Cooling I Use The Spent Fuel Pool Cooling System To Re-flood The RHR System Suction.

8

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, @)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021,Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: Point Beach Scenario No.: 1 OP-Test No.: 2003301 Examiners: Operators:

Initial Conditions: Unit 1 is at 100%Power, MOL, equilibrium xenon conditions. Unit 2 is at 100% Power.

Turnover: G-02 EDG is out of service for annual maintenance. It was taken 00s 2 days ago, and is expected to be returned to service in 3 days. G-01 EDG is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW 01-35A.

1P-2C Charging Pump is out of service due to a failed motor bearing. The failure occurred 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago and has been tagged out for repair.

1P-15A Safety Injection Pump has iust been tagged out (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago) due to high vibration that was identified during In-service Testing. The pump is not available.

Today is Sunday, present clock time is real time. A normal shift complement is available with exception of the 3"'

SRO. An RP Tech is on-site along with two mechanics who are working on the diesel. A maintenance crew has iust been called in for 1P-15A.

The obiective of the shift is to maintain stable plant conditions.

p____

Event 1 Malf. Event Event Type* Description II -

SRO I - Ro Service Water Pump Trip.

Controlling Pressurizer Pressure channel PT-43 1 fails high.

SRO

- Ro 1P-2A Charging Pump belt failure.

SRO Turbine First Stage Pressure Transmitter PT-485 fails low.

SRO M - All RCS Leak develops to SBLOCA, requiring reactor trip.

- Ro Reactor trip breakers fail to open - (ATWS).

SRO -

'Safety Injection Pump 1P-15B fails to start.

SRO (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

I AppendixD Scenario Outline FormES-D-1 I Facility: Point Beach Scenario No.: 2 OP-Test No.: 2003301 I Examiners: Operators:

Initial Conditions: Unit 1 is at 75% power. Power was reduced approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ago at the request of the Power System Supervisor. Xenon is building in slightly. Unit 2 is at 100% Power.

Turnover: G-02 EDG is out of service for annual maintenance. It was taken 00s 2 days ago, and is expected to be returned to service in 3 days. G-01 EDG is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW 01-35A.

1P-2C Charging Pump is out of service due to a failed motor bearing. The failure occurred 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ago and has been

-a-t

~

scheduled In-service Testing. The pump is not available.

Today is Sunday, present clock time is real time. A normal shift complement is available with exception of the 31d SRO. An RP Tech is on-site along with two mechanics who are working on thediesel. A maintenance crew has i u g been called in for 1P-15A.

The obiective of the shift is to maintain stable plant conditions until the Power System Supervisor requests power be returned to 100%.

Event Event Description Steam Generator Steam Flow Transmitter IFT-474 fails high.

Running CCW pump trips, with failure of standby to start.

Letdown line pressure controller IHC- 135 fails (oscillating in AutoMan).

Steam Generator B Tube Leak develops.

I I R-RO Power reduction initiated due to tube leak.

Tube leak increases to rupture requiring reactor trip.

C - RO 7 Main turbine fails to auto-trip.

SRO I

1 I

8 I I M- ALL Steam Leak develops on Steam Generator B C - BOP 9 Steam Generator B Blowdown Valve fails to isolate.

SRO

(N)ormal, (R)eacr ity, (I)nstrument, (C)omponent, (M)ajor NUREG- 1021, Draft Revision 9

6 1

~

ES-401 PWR Examination Outline , ,. - Form ES-401-2 Facility: Poit t Beach Nuclear Plant Date of Exam: Sep 29,2003 II I RO WA Catc I Points Tier f

Total

1. 7 Emergency

& 5 Abnormal Plant Evolutions Tier 12 Totals 1 (512 4 -

2. 2 Plant Systems 3Totals -___

4 ,

6

3. Generic Knowledge and - 7 Abilities Categories Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.l .c for additional guidance regarding SRO sampling.

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 f l 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the categoryhier.

6.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

Page 1 of 13

ES-401 I

PWR Examination Outline 5 -Tier 11Group 1 (ROISRO)

Form ES-401-2

=

EIAPE # I Name I Safety Function WA Topic(s) #

2.4.31 Knowledge of annunciators 000007 (BW/E02&E10; CE/E02) Reactor alarms and indications, and use of 3.3 Trip - Stabilization - Recovery / 1 the response instructions 008.AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer 000008 Pressurizer Vapor Space Vapor Space Accident (Relief Valve 4.1 Accident (Relief Valve Stuck Open) 1 3 Stuck Open): Actions contained in EOP for PZR vapor space accident I LOCA 009.EA2.34 Ability to determine or interpret the following as they apply to 000009 Small Break LOCA / 3 3.6 3 a small break LOCA: Conditions for throttling or stopping HPI 011.EK2.02 Knowledge of the 000011 Large Break LOCA / 3 interrelations between Large Break 2.6 LOCA and the following: Pumps 015.AK3.02 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant 000015117 RCP Malfunctions1 4 3.0 Pump Malfunctions (Loss of RC Flow): CCW lineup and flow paths to RCP oil coolers 022.AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Reactor 000022 Loss of Rx Coolant Makeup / 2 Coolant Pump Makeup: Actions , 3.5 contained in SOPS and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging .-

025.AK1.01 Knowledge of the operational implications of the following concepts as they apply to 000025 Loss of RHR System I 4 3.9 7 Loss of Residual Heat Removal System: Loss of RHRS during all

'modes of operation 026.AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of 000026 Loss of Component Cooling Component Cooling Water: The 3.6 8 Wate.r 18 automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 827.AK1.01 Knowledge of the operationai implications of the 000027 Pressurizer Pressure Control following concepts as they apply to 3.1 9 System Malfunction 1 3 Pressurizer Pressure Control Malfunctions: Definition of saturation temperature 000029 ATWS I 1 038.EA2.17 Abilitv to determine or 000038 Steam Gen. Tube Rupture / 3 interpret the following as they apply to 3.8 10 a SGTR: RCP restart criteria 040.AA2.05 Ability to determine and 000040 (BWlE05; CUE05; W/E12) interpret the following as they apply to Steam Line Rupture - Excessive Heat 4.1 11 the Steam Line Rupture: When Transfer 1 4 ESFAS systems may be secured - -

Page 2 of 13

I PWR Examination Outline ES-401 Emergency a -Tier 1I&ou~1(ROISRO) = -

Form ES-401-2 WAPE # / Name I Safety Function WA Topic(s) IR #

054.AA2.05 Ability to determine and interpret the following as they apply to 000054 (CE/EO6) Loss of Main 3.5 12 the Loss of Main Feedwater (MFW):

Feedwater 1 4 Status of MFW pumps, regulating and 000055 Station Blackout / 6 monitor the following as they apply to 000056 Loss of Off-site Power I 6 3.3 13 the Loss of Offsite Power: PZR heater group control switches 000057 Loss of Vital AC Inst. Bus 1 6 000058 Loss of DC Power 1 6 2.4.31 Knowledge of annunciators 000062 Loss of Nuclear Svc Water 1 4 alarms and indications, and use of 3.3 14 the response instructions 065.AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of 000065 Loss of Instrument Air I 8 2.9 15 Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air Wk04.EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (LOCA Outside Containment):

W k 0 4 LOCA Outside Containment 1 3 3.5 16 Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Containment)

W/E11 .EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant W/E11 Loss of Emergency Coolant Recirculation): Annunciators and 3.6 17 Recirc. I 4 conditions indicating signals, and '

remedial actions associated with the (Loss of Emergency Coolant Recirculation)

WIE05.EA1.1 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat BW/EO4; W/E05 Inadequate Heat Sink): Components, and functions of Transfer - Loss of Secondary Heat control and safety systems, including 4.1 18 Sink 1 4 instrumentation, signals, interlocks, failure modes, and automatic and manual features -

WA Category Totals: Group Point Total:

Page 3 of 13

-5 +' I *,

PWR Examination Outline ES-401 Form ES-401-2 Emergency and Abnoi ial Plant Evolutio ;-Tier l/Group 2 (RO/SRO)

I I E/APE # I Name / Safety Function WA Topic(s) 001.AK1.08 Knowledge of the I-IR #

operational implications of the 000001 Continuous Rod Withdrawal / 1 following concepts as they apply to 2.9 19 Continuous Rod Withdrawal: Control rod motion on S/G pressure.

interpret they following as they apply 000005 Inoperable/StuckControl Rod / 1 I/ to the Inoperable/StuckControl Rod:

-+-

Required actions if more than one rod is stuck or inoperable.

024.AK2.04 Knowledge of the 3.5 20 000024 Emergency Boration / 1 X interrelations betweenthe Emergency I 2.6 21 system and integrated plant 22 Range NI / 7 procedures during all modes of plant 000051 Loss of Condenser Vacuum 000059 Accidental Liquid Radwaste reasons for the following responses 000069 (W/E14) Loss of Containment as they apply to the Loss of 3.8 23 Integrity / 5 Containment Integrity: Guidance contained in EOP for loss of monitor the following as they apply to 000076 High Reactor Coolant Activity / 9 3.2 24 the High Reactor Coolant Activity:

Failed fuel-monitoring equipment W/E02.EA2.1 Ability to determine and interpret they following as they apply W/EOl & E02 Rediagnosis & SI to the (SI Termination): Facility 3.3 25 Termination / 3 conditions and selection of appropriate procedures during abnormal and emergency operations. I 3 W/El3.EA1.2 Ability to operate W/El3 Steam Generator Over-pressure/ 4 11 M and/or monitor the following as they apply to the (Steam Generator Overpressure): Operating behavior characteristics of the facility -

3.0 26 Page 4 of 13

I PWR Examination Outline .

ES-401 Emergency and A iormal Plant Evolutions - Tier l/droub 2 (RO/SRO) I --

r"ll" EIAPE # I Name I Safety Function K WA Topic@) IR #

1 WlEl5 Containment Flooding I 5 I interpret the following as they apply to the (LOCA Cooldown and BWlE08; WlE03 LOCA Cooldown and Depressurization): Adherence to 3.5 27 Depressurization/ 4 appropriate procedures and operation within the limitations in the facility's license and amendments. -

Page 5 of 13

I PWR E) mination Outline ES-401 I -(RO/SRO)

Form ES-401-2 I_ =

System # / Name KIA Topic(s) IR #

003.K3.01 Knowledge of the effect that a loss or malfunction of the 3.7 28 RCPS will have on the following:

003 Reactor Coolant Pump RCS -

003.A3.01 Ability to monitor automatic operation of the RCPS, 3.3 29 including: Seal injection flow 004.K6.31 Knowledge of the effect of a loss or malfunction on the 004 Chemical and Volume Control following CVCS components: 3.1 30 Seal injection system and limits on flow range 005.K2.01 Knowledge of bus 005 Residual Heat Removal power supplies to the following: 3.0 31 RHR pumps 006.K6.18 Knowledge of the effect of a loss or malfunction on the 32 006 Emergency Core Cooling 3.6 following will have on the ECCS:

Subcooling margin indicators 007.K1.01 Knowledge of the physical connections and/or 007 Pressurizer RelieWQuench cause-effect relationships between 2.9 33 Tank the PRTS and the following

--- systems: Containment system 008.A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 3.1 34 008 Component Cooling Water associated with operating the CCSW controls including: Surge tank level 010.K6.04 Knowledcre " of the effect of a loss or malfunction of the 2.9 35 following will have on the PZR PCS: PRT -

010 Pressurizer Pressure Control 010.A4.03 Ability to manually operate and/or monitor in the 4.0 36 control room: PORV and block

_______ ~~

valves 012.A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS: and (b) based on those predictions, use procedures to 4.4 37 012 Reactor Protection correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of RPS signal to trip the reactor 2.4.4 Ability to recoanize w abnormal indications for system operating 013 Engineered Safety Features parameters which are entry-level 4.0 38 Actuation conditions for emergency and abnormal operating procedures 2.1.27 Knowledge of system 2.8 39 022 Containment Cooling purpose and/or function Page 6 of 13

I PWR Examination Outline ES-401 I

~

Plant (RO/SRO) Form ES-401-2 System # / Name WA Topic(s) IR #

026.A3.01 Ability to monitor 026 Containment Spray automatic operation of the CSS, 4.3 40 including: Pump starts and correct MOV positioning 039.K1.07 Knowledge of the physical connections and/or cause-effect relationships between 3.4 41 the MRSS and the following -

039 Main and Reheat Steam systems: AFW -

039.K3.06 Knowledge of the effect that a loss or malfunction of the 2.8 32 MRSS will have on the following:

SDS 056.K1.03 Knowledge of the physical connections and/or cause-effect relationships between 2.6 43 the Condensate System and the following systems: MFW 056.A2.04 Ability to (a) predict the 356 Condensate impacts of the following malfunctions or operations on the Condensate System: and (b) based on those predictions, use 2.6 44 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of condensate pumps 059.K1.02 Knowledge of the physical connections and/or I59 Main Feedwater cause-effect relationships between 3.3 45 the MFW and the following systems: AFW system 061.K5.02 Knowledge of the operational implications of the following concepts as they apply to 3.2 46 I61 Auxiliary/Emergency the AFW: Decay heat sources

-eedwater and magnitude 2.2.22 Knowledge of limiting conditions for operations and 3.4 47 safety limits 062.A3.01 Ability to monitor 162 AC Electrical Distribution automatic operation of the AC 3.0 48 distribution system, including:

Vital AC bus amperage D63.A3.01 Ability to monitor automatic operation of the DC 163 DC Electrical Distribution electrical system, including: 2.7 49 Meters, annunciators, dials, recorders, and indicating lights 064.K4.02 Knowledge of ED/G system design feature(s) and/or 164 Emergency Diesel Generator interlock(s) which provide for the 3.9 50 iollowing: Trips for ED/G while operating (normal or emergency)

D73.K5.01 Knowledge of the operational implications as they apply to concepts as they apply to 173 Process Radiation Monitoring 2.5 51 the PRM system: Radiation theory, including sources, types, Jnits, and effects Page 7 of 13

ES-401 PWR Examination Outline . I - -_

CRO/S#6\ I Form ES-401-2 System # / Name WA Topic(s) IR #

076.K1.08 Knowledge of the physical connections andlor 076 Service Water cause-effect relationships between 3.5 52 the SWS and the followina -

systems: RHR system 078.K2.01 Knowledge of bus 078 Instrument Air power supplies to the following: 2.7 53 Instrument air compressor 103.K3.01 Knowledge of the effect that a loss or malfunction of the containment system will have on 3.3 54 the following: Loss of containment integrity under shutdown conditions 103.A2.04 Ability to (a) predict the 103 Containment impacts of the followhg.

malfunctions or operations on the containment system and (b) based on those predictions, use 3.5 55 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Containment evacuation (including recognition of the alarm). -

- -~

WA Category Point Totals: Group Point Total: 28

=

Page 8 of 13

i. ' .-

I PWR Examination Outline ES-401 I PIi rsten 2/Gr ! (RO/SRO)

Form ES-401-2

__p System # / Name WA Topic(s) IR #

001 Control Rod Drive 2.4.6 Knowledge of symptom 002 Reactor Coolant 3.1 56 based EOP mitigation strategies 011.A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those 01 1 Pressurizer Level Control predictions, use procedures to 3.0 57 correct, control, or mitigate the consequences of those malfunctions or operations:

Isolation of letdown -

014.K4.03 Knowledge of RPIS' design feature(s) and/or 014 Rod Position Indication 3.2. .58 interlock(s) which provide for the following: Rod bottom lights 015.K2.01 Knowledge of bus power supplies to the following:

015 Nuclear Instrumentation 3.3 59 NIS channels, components, and interconnections 016.A4.02 Ability to manually 016 Non-nuclear lnstrurnentation operate and/or monitor in the 50. ,

017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those 033 Spent Fuel Pool Cooling predictions, use procedures to 61 correct, control, or mitigate the consequences of those malfunctions or Operations:

Abnormal spent fuel pool water 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dumpmurbine Bypass Control impacts of the following' malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures 045 Main Turbine Generator 62 to correct, control, or mitigate the consequences of those malfunctions or operations:

Malfunction of electrohydraulic control Page 9 of 13

I PWR Examination Outline ES-401 Form ES-401-2 Plant ! (stems -Tier 2 D 2 rRo/sRoi

_= -

System # / Name K/A Topic(s) IR #

055 Condenser Air Removal 068 Liquid Radwaste operate and/or monitor in the 3.8 63 control room: Automatic isolation 071.Al.O6 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 071 Waste Gas Disposal associated with Waste Gas 64 Disposal System operating the controls including: Ventilation 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air impacts of the following' malfunctions or operations of the Fire Protection System; and (b) based on those predictions, use 086 Fire Protection 65 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure to actuate the FPS when required, resulting in fire damage

~~~ ~ _ _ _ _ _ _ _ _ _

WA Category Point Totals: Group Point Total:

- 10 Page 10 of 13

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facilitv: Point Beach Nuclear Plant Date of Exam: SeD 29.2003 Category WA # Topic Ability to recognize indications for system

+T SRO-Only 2.1.33 operating parameters which are entry-level 3.4 66 conditions for technical specifications Ability to make accurate, clear and concise 2.1.17 3.5 67 verbal reports 1.

Conduct of Operations Subtotal I 2.2.22 Knowledge of limiting conditions for operations and safety limits 1 1 .-

3.4 68 2.2.33 I Knowledge of control rod programming I 2.5 I 69

2. 2.2.27 Knowledge 04 the refueling process Equipment Control t-- tt-L' 2.3.1 I Knowledge of 10 CFR: 20 and related facility radiation control requirements 2.6 71 Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible

_- levels in excess of those authorized 3.

Radiation 2.3.1 1 Ability to control radiation releases 2.7 Control

- I-Subtotal 3 -+

Page 11 of 13

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Poir

= -

Category WA # Topic RO I SRO-Only IR Knowledge of annunciators alarms and 2.4.31 indications, and use of the response 3.3 instructions Knowledge of low power I shutdown 2.4.9 implications in accident (e.g. LOCA or loss of 3.3

4. RHR) mitigation strategies Emergency Procedures I Plan Subtotal Tier 3,Point Total Page 12 of 13

ES-401 Record of Rejected WAS i. 1.-21 Form ES-401-4 4

Tier I Randomly Group Selected WA Reason for Rejection 000008 I I1 Fundamentals question - Selected AK3.03 AK3.02 111 000011 I K3 No K2s selected for tier 1 - Selected EK2.02 000026 I K1 No K1 statements - Selected AK3.01 AK3.01 NIA to PBNP - Selected AK3.02 111 000062 I K2 No K2 statements - Selected G2.4.31 000001 1 .

I2 SRO level knowledge - Selected AK1.08 AK3.02 1I 2 000024 I K3 No K2s selected for tier 1 - Selected AK2.04 211 022 I K5 WA < 2.5 - Selected G2.1.27 211 056 I A I All WAs < 2.5 - Selected K1.03 211 059 I K5 All WAs < 2.5 - Selected K1.02 211 062 I K6 All WAs < 2.5 - Selected A3.01 211 078 I A2 WA < 2.5 - Selected K2.01 212 014 I K6 All WAS < 2.5 - Selected K4.03 212 0461K6 WA < 2.5 - Selected A4.02 212 045 I K2 All WAs < 2.5 - Selected A2.17 212 068 I A1 All WAs e 2.5 - Selected A4.02 3 2 I 2.2.1 1 SRO level knowledge - Selected 2.2.27 3 . 3 12.3.8 WA < 2.5 - Selected 2.3.1 3 3 I 2.3.5 WA < 2.5 - Selected 2.3.3 2.3.3 WA < 2.5 - Selected 2.3.4 3 3 I 2.3.7 WA < 2.5 - Selected 2.3.1 1 3 4 12.4.37 WA < 2.5 - Selected 2.4.31 3 4 I 2.4.28 WA < 2.5 - Selected 2.4.9 Unable to write question to WA, selected next WA in sequence, 212 01 1 I A2.06 01 1.A2.07 Page 13 of 13

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

=acility: Point Beach Nuclear Plant Date of Exam: Sep 29,2003 I I I I

3. Generic Knowledge and 2 Abilities Categories

- 3 Note: 1. Ensure that at least two topics from everj WA category are sampled within each tier of the RO outline (i.e.] the "Tier Totals" i t 1 each WA category shall not be less than two). Refer to Section D.l .c for additional guidance regarding SRO sampling.

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 F-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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

4. Systemsievolutions within each group are identified on the associated outline. '

5. The shaded areas are not applicable to the categoryher.

6.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401 Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

Page 1 of 11

PWR Examination Outline ES-401 Form ES-401-2 Emergency and 4bnorm: Plant Evolutions -Tier l/Group 1 (SRO)

I E/APE # / Name I Safety Function I: A A G 1 2 WA Topic(s) 2.4.30 Knowledge of which events 000007 (BW/E02&EI 0; CE/E02) Reactor related to system operations/status Trip - Stabilization - Recovery / 1 should be reported to outside 000009 Small Break LOCA / 3 00001 1 Large Break LOCA 1 3 I 000015/17 RCP Malfunctions I 4 I 000022 Loss of Rx Coolant Makeup I 2 I interpret the following as they apply to 000027 Pressurizer Pressure Control the Pressurizer Pressure Control System Malfunction / 3 Malfunctions: PZR heater 000029 ATWS I 1 I 000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 000054 (CEIEO6) Lass of Main Feedwater / 4 interpret the following as they apply to 000055 Station Blackout J 6 a Station Blackout: Actions necessaty 000056 Loss of Off-site Power / 6 000058 Loss of DC Power I 6 -t 000057 LosG of Vital AC lnst. Bus / 6 000062 Loss of Nuclear Svc Water / 4 I interpret the followiig as they apply to the (LOCA Outside Containment):

W/E04 LOCA Outside Containment / 3 4.2 6/8, Adherence to appropriate procedures and operation within the limitations in the facility's license and W l E l l .EA2.2 Ability to W/E11 Loss of Emercjency Coolant Recirc. / 4 interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments I Page 2 of 11

PWR Examination Outline ES-401 Form ES-401-2 Emeraencv and Abnormal Plant Evolutions -Tier l/GrouD 1 ISRO)

WA Topic(s)

Transfer - Loss of Secondary Heat Sink I 4 Group Point Total: 1 7 1 I I .

Page 3 of 11

I PWR Examination Outline ES-401 I Emeraency and A Ivolutio - Tier 11Group 2 (RO/SRO)

Form ES-401-2 4

WAPE # / Name / Safety Function 000001 Continuous Rod Withdrawal / 1 I,K r(rA Topic(s)

I IR 000003 Dropped Control Rod / 1 005.AK1.02 Knowledge of the operational implications of the 000005 Inoperable/Stuck Control Rod / 1 following concepts as they apply to 3.9 8/83 Inoperable/StuckControl Rod: Flux 000024 Emerqency Boration / 1 000028 Pressurizer Level Malfunction 12 interpret the foilowing as they apply to the Pressurizer Level Control Malfunctions: Cause for PZR level .I 3.5 9/84 deviation alarm: controller malfunction or other instrumentation I Accident / 8 000051 Loss0 II Y

reasons for the following responses 000060 Accidental Gaseous Radwaste as they apply to the Accidental 4.2 10185 Rel. 19 Gaseous Radwaste:

000061 ARM Svstem Alarms 17 Evac. I 8 O O O O ~ YW E I ~ ~ L O S S of CTMT Integrity 5i t-000074 (W/E06&E07)

W/El3 Steam Generator interpret the following as they apply to the (High Containment Radiation):

W/El6 High Containment Radiation/ 9 3.3 1 1/86 Adherence to appropriate procedures and operation within the limitations in Page 4 of 11

ES-401 I PWR Examination Outline Emeraencv and Abnormal Plant Evolutions - Tier 11GrouD 2 (ROISRO) I Form ES-401-2 EIAPE # I Name I Safety Function WA Topic(s) I IR #

Depress. / 4 W/E09.EK3.4 Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations): RO or SRO BWIEOS; CEIA 3; W/EOS&EI 0 Natural function within the control room team Circ. 1 4 as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the faciiities license and CE/AI 1; WE08 RCS Overcooling -

.PTS I4.

CE/AI6 Excess RCS Leakage 1 2

- .--G-

-, Liiwl CUE09 Fiinctional Recovery I'--".',

WA Category Point- Totals: Group Point Total: -

Page 5 of 11

PWR Examination Outline ES-401 Form ES-401-2 2/Gr( (RO/SRO)

System # / Name WA Topic(s)

IR I #

003 Reactor Coolant Pump 004.A1.11 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 004 Chemical and Volume Control associated with operating the CVCS controls including: Letdown

- -___ and charging flows -

2.2.25 Knowledge and bases in technical specifications for !imiting 005 Residual Heat Removal conditions for operations and safety limits 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008.A2.02 Abilitv to (a) predict the impacts of the following' (nalfunctions or operations on the CCWS, and (b) based on those 008 Component Cooling Water predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser - .-.

monitor changes in parameters (to prevent exceeding design limits) 026 Containment Spray associated with operating the CSS controls including: Containment 039 Main and Reheat Steam 056 Condensate 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water

---+--

078 Instrument Air I

Page 6 of 11

Form ES-401-2 Plant Svstems -Tier 2/Grouo 1 (RO/SROI

++ System # / Name k

1 103 Containment Page 7 of 11

I PWR Examination Outline ES-401 Form ES-401-2 I I I I I I / I I I I System # / Name 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control I l l l l Ixl l l I / monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR I /

3.3 17/92 0 14 Rod Position Indication 015 Nuclear Instrumentation I 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator 041 Steam DutrpRurbine Bypass Control 1 I 1 I I I 1 I I 1 XI and limitations in thefacility . ' I 3.9 ' 1 18193 045 Main Turbine Generator

~ ~~

055 Condenser Air Removal 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 036 Fire Protection WA Category Point Totals:

Page 8 of 11

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Poi1 Beach Nuclear Plant 1 Date of Exam: Sep 29,2003 RO SRO-Only Category WA # Topic IR # IR #

Ability to locate and use procedures and 2.1.5 directives related to shift staffing and 3.4 19/94 activities.

Ability to direct personnel activities inside the 2-1*9 4.0 20/95 control room 1.

Conduct of Operations Subtotal I I Knowledge of limiting conditions for 2.2'22 4.1 21/96 operations and safety limits.

2.2.24 Ability to analyze the effects of maintenance 3.8 22/97 activities on LCO status.

2.

Equipment Control - - - --

Subtotal 2 Knowledge of the process for performing a 2.3*9 containment purge

3. -

Radiation Control Subtotal 1 Page 9 of 11

ES-401 ~

Form ES-401-3 Facility: Poir Beach Nuclear

- Plant I Date of Exam: Sep 29,2003 Knowledge of general guidelines for EOP 2'4.14 3.9 24/99 flowchart use.

Knowledge of EOP implementation hierarchy 251 2.4.1 6 and coordination with other support 4-0 100

4. procedures Emergency Procedures

/ Plan Subtotal 2 Tier 3 Point Total 7 Page 10 of 11

ES-401 Record of Rejected WAS Form ES-401-4 Randomly Reason fof Rejection Selected WA 000007 I K2 Not SRO only - Selected K1 K1 Not SRO only - Selected G2.4.30 000015/0171 Not SRO only - Selected G2.1.12 K2 000027 / K1 Not SRO only - Selected A1 A1 I Not SRO only - Selected K2 K2 I ~~

Not SRO only - Selected AA2; 0 000038 / A1 I Not SRO only - Selected EK3.09 WlE04 I K1 1 Not SRO only - Selected AI A1 1 Not SRO only - Selected EA2.2 000005 I Previously selected in RO outline, selected AK1.02 AA2.03 000060 I Not SRO only - Selected AK3.01 AK3.04 - --

005 I K5 Not SRO only - Selected K1

- - ~ - -

K1 Not SRO only - Selected 62.2.25 008 I K5 All WAS e 2.5 - Selected K6 K6 All WAS < 2.5 -- Selected A2.09 011 f A3 Not SRO only - Selected K5 K5 Not SRO only - Selected A I .04 3 12.3.4 I Previously selected in RO outline - Selected 2.3.1 2.3.1 4 12.4.2 f 008 I A2.09 Previously selected in RO outline - Selected 2.3.9 Not SRO only - selected 2.4.1 4 Unable to write SRO level question - selected A2.02 Page 11 of 11

ML033030032

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