ML060860145

Final Outlines (Folder 3)

ML060860145
Person / Time
Site:	Millstone
Issue date:	03/01/2006
From:	Jane Spence Dominion
To:	Johnson G Operations Branch I
Conte R
References
Download: ML060860145 (14)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millsi ne Unit 2 Date of Exam:

II Tier 1.

Emergency

&

Abnormal Plant Totals Evolutions 2.

Plant Systems Totals

3. Generic Knowledge and Abilities Categories Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., 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 41 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 applicable 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.

NUREG 1021, Draft Revision 9

, E/APE#/Name/SafetyFunction K K K A 1 2 3 1 A

2 G WA Topic(s) IR #

000007 (BW/E02&E10; CVE02) Reactor X EK3.2: Knowledge of the reasons for normal, abnormal and 2.8 1 Trip - Stabilization - Recovery / 1 emergency operating procedures associated with Reactor Trip 3.5 Recovery as they apply to the Reactor Trip Recovery.

000008 Pressurizer Vapor Space X AK1.02: Knowledge of the operational implications of the 3.1 1 Accident I 3 following concepts as they apply to a PressurizerVapor Space 3.7 Accident: Change in leak rate with change in pressure 000009 Small Break LOCA / 3 X EK1.02: Knowledge of the operational implications of the 3.5 1 following concepts as they apply to the small break LOCA: 4.2 Use of steam tables 000011 Large Break LOCA I 3 X EA2.03: Ability to determine or interpret the following as they 3.7 1 apply to a Large Break LOCA: Consequences of managing 4.2 LOCA with loss of CCW 000015117 RCP Malfunctions/ 4 X G2.2.23: Ability to track limiting conditions for operations. 2.6 1 3.8 LOIT2K5-ES-401-2.doc NUREG 1021, Draft Revision 9

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

E/APE#/Name/SafetyFunction K K K A A G WA Topic(s) IR #

I K/A Category Totals I 5I 1I 2I 3I 3 I4I Group Point Total:

NUREG 1021, Draft Revision 9

LOIT2K5-ES-401-2.doc NUREG 1021, Draft Revision 9 EYAPE # / Name / Safety Function K K K A A G WA ToDick) IR #

BWIE09; CEIA13; W/E09&E10 Natural Circ. / 4 X AKl.3: Knowledge of the operational implications of 3.1 1 annunciators and conditions indicating signals and 3.4 remedial actions associated with the Natural Circulation Operations as they apply to the Natural Circulation CE/Al 1; WIE08 RCS Overcooling - PTS / 4 X AA2.2: Ability to determine and interpret adherence to 3.0 1 appropriate procedures and operation within the 3.4 limitations in the facility's license and amendments as they apply to the RCS Overcooling.

P - RANDOMLY DESELECTED - Note 4 0

- RANDOMLY DESELECTED - Note 4 0 WA Category Point Totals: 2 2 2 0 2 1 Group Point Total: 9 NUREG 1021, Draft Revision 9

(1 ES-401 PW R ExaminationOutline

roup 1 (I YSRO)

Form ES-401-2 K1 K2 A4 G WA Topic(s) IR #

003 Reactor Coolant K6.04: Knowledge of the effect of a loss or 2.8 1

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malfunction on the following will have on the 3.1 RCPS: Containment isolation valves affecting RCP operation

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& s o Note 3 004 Chemical and Ability to (a) predict the impacts of the 2.7 1 Volume Control following malfunctions or operations on the 2.7 CVCS; and (b) based on those predictions, Note 3 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Excessive letdown flow, pressure, and temperatures on ion exchange resins (also causes) 004 Chemical and A1 .lo: Ability to predict and/or monitor 3.7 1 Volume Control changes in parameters (to prevent exceeding 3.9 design limits) associated with operating the CVCS controls including: Reactor power .I.

005 Residual Heat K5.09: Knowledge of the operational 3.2 1 Removal implications of the following concepts as they 3.4 apply the RHRS: Dilution and boration considerations.

2 5 - 0 24 Note 3 006 Emergency Core Cooling Note 3 x3 I Ability to manually operate and/or monitor in the control room: Valves 4.0 3.8 1

007 Pressurizer K5.02: Knowledge of the operational 3.1 1 Relief/QuenchTank implications of the following concepts as the 3.4 apply to PRTS: Method of forming a steam bubble in the PZR.

008 Component K4.02: Knowledge of CCWS design feature(s) 2.9 1 Cooling Water and/or interlock(s) which provide for the 2.7 following: Operation of the surge tank, including the associated valves and controls.

010 Pressurizer A3.01: Ability to monitor automatic operation 3.0 1 Pressure Control of the PZR PCS, including: PRT temperature 3.2 and pressure during PORV testing.

@K%ea&& s o 44 Note 3 I

u 012 Reactor K3.01: Knowledge of the effect that a loss or 3.9 1 Protection malfunction of the RPS will have on the 4.0 following: CRDS 013 Engineered X K2.01: Knowledge of bus power supplies to 3.6 1 Safety Features the following: ESFASkafeguards equipment 3.8 Actuation control.

022 Containment Al.02: Ability to predict and/or monitor 3.6 1 Cooling changes in parameters (to prevent exceeding 3.8 design limits) associated with operating the CCS controls including: Containment I I pressure.

NUREG 1021, Draft Revision 9

1 ES-401 PWR Exar iination Outline GrouFI 1 (RO/SRO) f x m ES-401-2 I

G I WA Topic@)

I 022 Containment X I G2.3.1: Knowledae of 10 CFR: 20 and related facility radiation control requirements.

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Not applicable to Millston$2 . y

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m zitainment I x K1.01: Knowledgeof the physical connections and/or cause-effect relationships between the CSS and the following systems: ECCS.

4.2 4.2 I K3.02: Knowledgeof the effect that a loss or malfunction of the CSS will have on the following: Recirculation spray system.

K5.08: Knowledge of the operational 4.3 4-2 3.6 I 1 implications of the following concepts as the 3.6 apply to the MRSS: Effect of steam removal K1.03: Knowledge of the physical connections 2.6 1 and/or cause-effect relationships between the 2.6 Condensate system and the following systems: MFW.

,

A1.07: Ability to predict and/or monitor 2.5 1 changes in parameters (to prevent exceeding 2.6 design limits) associated with operating the MFW controls including: Feed Pump speed, including normal control speed for ICs.

K3.02: Knowledge of the effect that a loss or 4.2 1 malfunctionof the AFW will have on the 4.4 K6.02: Knowledge of the effect of a loss or 2.6 1 malfunctionof the following will have on the 2.7 A1.03: Ability to predict and/or monitor 2.5 1 changes in parameters (to prevent exceeding 2.8 design limits) associated with operating the ac distribution system controls including: Effect on instrumentation and controls of switching power supplies.

a 0 34 I

I A1.01: Ability to predict and/or monitor 3.4 1 changes in parameters (to prevent exceeding 3.8 design limits) associated with operating the ac distribution system controls including:

Significance of D/G load limits X K2.01: Knowledge of bus power supplies to 2.9 1 the following: Major DC loads. 3.1 A1.O1: Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battety capacity as it is affected by discharge rate.

A2.05: Ability to (a) predict the impacts of the following malfunctions or operations on the 3.2 ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctionsor operations: Loading the NUREG 1021, Draft Revision 9

ES-401 PWR Examination OL Plant Systems - Tier UGroup 1 (I O/SRO)

System#/Name K1 K2 WA Topic@) IR #

073 Process G2.1.7: "Ability to evaluate plant performance 3.7 1 Radiation Monitoring and make operationaljudgments based on 4.4 operating characteristics, reactor behavior, and instrument interpretation."

076 Service Water A3.02: Ability to monitor automatic operation 3.7 1 of the SWS, including: Emergency heat loads. 3.7 078 InstrumentAir X2+- K1.03: Knowledge of the physical connections 3.3 1 and/or cause-effect relationships between the 3.4 IAS and the following systems: Containment air.

103 Containment Al.01: Ability to predict and/or monitor 3.7 1 changes in parameters (to prevent exceeding 4.1 design limits) associated with operating the containment system controls including:

Containment pressure, temperature, and humidity.

WA Category Point 3 1 3 2 6 2 3 1 2 Group Point Total: 28 NUREG 1021, Draft Revision 9

Form ES-401-2 System # / Name K1 K2 K3 WA Topic(s) IR #

001 Control Rod Drive K5.95: Knowledge of the 3.4 1 following operational 3.7

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implications as they apply to the CRDS: Effect of reactor power changes on RCS temperature.

- RANDOMLY DESELECTED Note 4-0 011 Pressurizer Level Control I l l K6.04: Knowledge of the effect of a loss or 3.1 3.1 1

malfunction on the following will have on the PZR LCS:

Operation of PZR level controllers.

014 Rod Position Indication K4.06: Knowledge of RPlS 3.4 1 design feature@)and/or 3.7 interlock(s) which provide for the following: Individual and group misalignment.

015 Nuclear Instrumentation X K2.01: Knowledge of bus 3.3 1 power supplies to the 3.7 following: NIS channels, components, and interconnections.

- RANDOMLY DESELECTED Note 4-0 I l l - RANDOMLY 0 028 Hydrogen Recombiner and Purge X K1.01: Knowledge of the 2.5 Control physical connections and/or 2.5 cause-effect relationships between the HRPS and the following systems:

Containment annulus ventilation system (including pressure limits).

- RANDOMLY

- ,

0 DESELECTED Note 4 -

I l l - RANDOMLY DESELECTED - Note 4 0

- -

~

RANDOMLY 0 DESELECTED - Note 4 -

- RANDOMLY 1 0 DESELECTED - Note 4 -

041 Steam Dumpnurbine Bypass K5.08: Knowledge of the 2.5 1 Control operational implications of 2.8 the following concepts as the apply to the SDS: Effect of power change on fuel cladding. --

045 Main Turbine Generator X A4.01: Ability to manually 3.1 1 operate and/or monitor in the 2.9 control room: Turbine valve indicators (throttle, governor, control, stop, intercept),

alarms, and annunciators.

NUREG 1021, Draft Revision 9

ES-401 PWR Examination Outline Form ES-401-2 er 2/Group 2 (F System # I Name K6 A1 A2 WA Topic@)

-.

055 Condenser Air Removal K1.06: Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems: PRM system.

- RANDOMLY DESELECTED Note 4-071 Waste Gas Disposal K4.03: Knowledge of design 2.5 1 feature(s) and/or interlock(s) 2.6 which provide for the following: Tank loop seals.

- RANDOMLY 0 DESELECTED Note 4-

- RANDOMLY DESELECTED - Note 4 0

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- RANDOMLY 0 DESELECTED - Note 4 086 Fire Protection X3 A1.05: Ability to predict 2.9 and/or monitor changes in 3.1 parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: FPS lineups. -

WA Category Point Totals: Group Point Total:

Note 1 - Randomly selected to be duplicated to achieve required count for Tier and Group.

Note 2 - Randomly reselected due to no WA with an IR >/= 2.5 existing in the initial category.

Note 3 - Randomly redrawn based on Lead Examiners initial comment of WA not fitting system interrelations of MP2 and to ensure required distribution or WAS.

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Note 4 Randomly deselected to achieve the required item count per the applicable Tier and Group.

NUREG 1021, Draft Revision 9

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

Facility: Mills Category WA # Topic RO SRO-Only IR # IR #

1. 2.1.2 Knowledge of operator responsibilities during all modes of 3.0 1 plant operation.

Conduct of 2.1.3 Knowledge of operator responsibilities during all modes of 3.0 1 Operations plant operation.

2.

, _....

.. , .

.:., Equipment

. . .<... .

-... Control handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated

, from the control room in support of fueling operations, and ,

3.

Radiation Control 4.

Emergency Procedures Plan Note I : Deselected per NRC Examiner initial comments.

Note 2: Randomly reselected, per NRC Examiner, to meet category number requirement.

All WAS were randomly selected using the guidance provided in NUREG 1021, ES-401, Attachment 1 LOIT2K5-ES-40 1-2.d0~ NUREG 1021, Draft Revision 9

ES-401 Record of Rejected WAS Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/ I 2.2.23 000015/17 RCP Malfunctions / 4; Redrawn, with the approval of the Lead Examiner, due to the lack of system concepts that would meet the WA and still distinguish between a competent and non-competent Operator.

Randomly reselected WA AK3.04: Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Sequence of events for manually tripping reactor and RCP as a result of an RCP malfunction 1/ I 2.1.24 000054 (CEIEOG) Loss of Main Feedwater / 4; Redrawn, with the approval of the Lead Examiner, due to the original WA testing a concept that is meant to be evaluated in a JPM (open reference) format.

Randomly reselected WA AAl.02: Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW): Manual startup of electric and steam-driven AFW Dumps.

1/ I EK3.01 000055 Station Blackout / 6 ; Redrawn, with the approval of the Lead Examiner, due to the similarity with the WA drawn for question #50.

Randomly reselected WA EK3.02: Knowledge of the reasons for the following responses as they apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power.

1/2 AA2.14 000028 Pressurizer Level Malfunction / 2; Reselected, with Lead Examiner approval, due to WA concept not existing in a C.E. plant.

Randomly reselected KIA AA2.10: Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions: Whether the automatic mode for PZR level control is functioning improperly, necessity of shift to manual modes.

LOIT2006-ES-401-4 ES401-4,Page 1 of 3

Tier / Randomly Reason for Rejection 3oup Selected WA 1/2 2.1.1 000032 Loss of Source Range NI / 7: Redrawn based on Feedback from Lead Examiner. Original WA did not distinguish between competent and non-competent operator.

Randomly reselected WA AK2.01: Knowledge of the interrelations between the Loss of Source Range Nuclear Instrumentation and the following: Power supplies, including proper switch positions.

2/1 A I .05 004 Chemical and Volume Control: Redrawn based on Lead Examiners initial comment of WA not fitting system interrelations of MP2 and to ensure required distribution or K/As.

Randomly reselected K/A A2.21: Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Excessive letdown flow, pressure, and temperatures on ion exchange resins (also causes) 2/1 2.2.33 006 Emergency Core Cooling; Redrawn based on Lead Examiners initial comment of WA not fitting system interrelations of MP2 and to ensure required distribution or K/As.

Randomly reselected K/A A4.02: Ability to manually operate and/or monitor in the control room: Valves 211 K3.04 012 Reactor Protection; Redrawn based on Lead Examiners initial comment of K/A not fitting system interrelations of MP2 and to ensure required distribution or K/As.

Randomly reselected K/A K3.01: Knowledge of the effect that a loss or malfunction of the RPS will have on the following:

CRDS 2/1 2.3.1 022 Containment Cooling; WA redrawn by instruction from Lead Examiner due to over-sampling of ALARA concept.

Randomly reselected WA 2.4.5: Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions LOIT2006-ES-401-4 ES401-4, Page 1 of 3

iandomly Reason for Rejection Selected WA 2.3.9 162 AC Electrical Distribution; Redrawn based on Lead fxaminers initial comment of WA not fitting system nterrelations of MP2 and to ensure required distribution or

(/As.

3andomly reselected WA A I .01: Ability to predict and/or nonitor changes in parameters (to prevent exceeding design imits) associated with operating the ac distribution system

ontrols including: Significance of D/G load limits K5.06 341 Steam Dump/Turbine Bypass Control; Redrawn based on

-ead Examiner feedback, due to original concept not jistinguishing between a competent and non-competent RO.

3andomly reselected WA K5.02: Knowledge of the operational mplications of the following concepts as they apply to the SDS: Use of steam tables for saturation temperature and Dressure.

K4.03 371 Waste Gas Disposal; Randomly redrawn due to original K/A not fitting system design of MP2.

Randomly reselected WA K4.05: Knowledge of design feature(s) and/or interlock(s) which provide for the following:

Point of Release.

2.2.4 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility. Deselected per NRC Examiner initial comments. (Unit 2 is a CE unit, Unit 3 is a Westinghouse unit)

Randomly reselected K/A 2.3.10: Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

. 2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

Deselected per NRC Examiner initial comments. (Licensed operators are not necessarily qualified as Fire Brigade members.)

Randomly reselected K/A 2.4.50: Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

LOIT2006-ES-401-4 ES401-4,Page 1 of 3