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 Tier

1.

Emergency Abnormal Plant Evolutions

2.

Plant Systems ne Unit 2 Date of Exam:

II Totals

• Totals

3. Generic Knowledge and Abilities Categories Note:

1.

2.

3.

4.

5.

6.*

7.

8.

9.

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.

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.

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.

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

The shaded areas are not applicable to the categoryhier.

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.

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.

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

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

NUREG 1021, Draft Revision 9

E/APE#/Name/SafetyFunction 000007 (BW/E02&E10; CVE02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA / 3 00001 1 Large Break LOCA I 3 00001 511 7 RCP Malfunctions / 4 LOIT2K5-ES-401-2.doc NUREG 1021, Draft Revision 9 K K K A A G

WA Topic(s)

IR 1

2 3

1 2

X EK3.2: Knowledge of the reasons for normal, abnormal and 2.8 1

emergency operating procedures associated with Reactor Trip Recovery as they apply to the Reactor Trip Recovery.

following concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure following concepts as they apply to the small break LOCA:

Use of steam tables apply to a Large Break LOCA: Consequences of managing LOCA with loss of CCW 3.5 X

AK1.02: Knowledge of the operational implications of the 3.1 1

3.7 X

EK1.02: Knowledge of the operational implications of the 3.5 1

4.2 X

EA2.03: Ability to determine or interpret the following as they 3.7 1

4.2 X

G2.2.23: Ability to track limiting conditions for operations.

2.6 1

3.8

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

IR E/APE#/Name/SafetyFunction K K K A A G

WA Topic(s)

I K/A Category Totals I 5 I 1 I 2 I 3 I 3 I 4 I 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 NUREG 1021, Draft Revision 9 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 P

WA Category Point Totals:

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.

- RANDOMLY DESELECTED - Note 4

- RANDOMLY DESELECTED - Note 4 0

0 2 2 2 0 2 1 Group Point Total:

9

(1 ES-401 IR 2.8 3.1 s

o 2.7 2.7 3.7 3.9 3.2 3.4 2

5 0

24 4.0 3.8 3.1 3.4 2.9 2.7 3.0 3.2 s

o 44 3.9 4.0 3.6 3.8 3.6 3.8 003 Reactor Coolant 1

1 1

1 1

1 1

1 1

1 1

Note 3 K1 004 Chemical and Volume Control Note 3 K2 X

004 Chemical and Volume Control 005 Residual Heat Removal Note 3 006 Emergency Core Cooling Note 3 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control

@K%ea&&

Note 3 012 Reactor Protection 01 3 Engineered Safety Features Actuation 022 Containment Cooling II PW R Examination Outline Form ES-401-2

roup 1 (I A4 G

YSRO)

WA Topic(s)

K6.04: Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: Containment isolation valves affecting RCP operation L

p 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)

A1.lo: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including: Reactor power K5.09: Knowledge of the operational implications of the following concepts as they apply the RHRS: Dilution and boration considerations.

x3 I Ability to manually operate and/or monitor in the control room: Valves I u K5.02: Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.

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

A3.01: Ability to monitor automatic operation of the PZR PCS, including: PRT temperature and pressure during PORV testing.

K3.01: Knowledge of the effect that a loss or malfunction of the RPS will have on the following: CRDS K2.01: Knowledge of bus power supplies to the following: ESFASkafeguards equipment control.

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

.I.

NUREG 1021, Draft Revision 9

11 ES-401 3.6 3.6 2.6 2.6 2.5 2.6 4.2 4.4 2.6 2.7 2.5 2.8 a

0 3 4 3.4 3.8 2.9 3.1 PWR Exar 1

1 1

1 1

1 1

1 022 Containment I x I

z i t a i n m e n t X

iinatio GrouF n Outline f

I 1 (RO/SRO)

I G I WA Topic@)

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

, - - -**,+,

Not applicable to Millston$2

-e

~ y m

~.~

K1.01: Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: ECCS.

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

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

A1.07: Ability to predict and/or monitor changes in parameters (to prevent exceeding 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 malfunction of the AFW will have on the K6.02: Knowledge of the effect of a loss or malfunction of the following will have on the A1.03: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: Effect on instrumentation and controls of switching power supplies.

I I

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

Significance of D/G load limits K2.01: Knowledge of bus power supplies to the following: Major DC loads.

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 ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loading the x m ES-401-2 4.2 4.2 I 4.3 4-2 I 3.2 NUREG 1021, Draft Revision 9

ES-401 System#/Name K1 K2 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air X2+-

103 Containment WA Category Point WA Topic@)

G2.1.7: "Ability to evaluate plant performance operating characteristics, reactor behavior, and instrument interpretation."

A3.02: Ability to monitor automatic operation of the SWS, including: Emergency heat loads.

K1.03: Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Containment air.

changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including:

Containment pressure, temperature, and humidity.

and make operational judgments based on Al.01: Ability to predict and/or monitor PWR Examination OL Plant Systems - Tier UGroup 1 (I 3

1 3

2 6

2 3

1 2

IR 3.7 1

4.4 3.7 1

3.7 3.3 1

3.4 3.7 1

4.1 O/S RO)

Group Point Total:

NUREG 1021, Draft Revision 9 28

System # / Name K1 K2 001 Control Rod Drive -

01 1 Pressurizer Level Control I

l l

K3 014 Rod Position Indication 014 Rod Position Indication 015 Nuclear Instrumentation X

015 Nuclear Instrumentation I

l l

X 028 Hydrogen Recombiner and Purge Control I

l l

X

~ -

041 Steam Dumpnurbine Bypass Control 045 Main Turbine Generator Form ES-401-2 WA Topic(s)

IR K5.95: Knowledge of the 3.4 1

following operational 3.7 implications as they apply to the CRDS: Effect of reactor power changes on RCS temperature.

- RANDOMLY 0

K6.04: Knowledge of the 3.1 1

DESELECTED - Note 4 effect of a loss or malfunction on the following will have on the PZR LCS:

Operation of PZR level controllers.

3.1 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.

K2.01: Knowledge of bus 3.3 1

following: NIS channels, components, and interconnections.

power supplies to the 3.7

- RANDOMLY 0

DESELECTED - Note 4

- RANDOMLY 0

K1.01: Knowledge of the 2.5 physical connections and/or 2.5 cause-eff ect relationships between the HRPS and the following systems:

Containment annulus ventilation system (including pressure limits).

- RANDOMLY DESELECTED - Note 4 DESELECTED - Note 4

- RANDOMLY

- RANDOMLY DESELECTED - Note 4

- RANDOMLY DESELECTED - Note 4 K5.08: Knowledge of the operational implications of the following concepts as the apply to the SDS: Effect of power change on fuel cladding.

operate and/or monitor in the control room: Turbine valve indicators (throttle, governor, control, stop, intercept),

alarms, and annunciators.

X A4.01: Ability to manually 2.5 2.8 3.1 2.9 0

0

0 1 0 1

1 NUREG 1021, Draft Revision 9

ES-401 PWR Examination Outline Form ES-401-2 er 2/Group 2 (F K6 A1 A2 X3 System # I Name 055 Condenser Air Removal WA Topic@)

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 K4.03: Knowledge of design feature(s) and/or interlock(s) which provide for the following: Tank loop seals.

DESELECTED - Note 4 DESELECTED - Note 4 DESELECTED - Note 4

- RANDOMLY

- RANDOMLY

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

071 Waste Gas Disposal 2.5 2.6 1

0 0 -

0 086 Fire Protection 2.9 3.1 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 Note 4 - Randomly deselected to achieve the required item count per the applicable Tier and Group.

interrelations of MP2 and to ensure required distribution or WAS.

NUREG 1021, Draft Revision 9

WA #

2.1.2 2.1.3 ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-:

Topic RO SRO-Only IR IR Knowledge of operator responsibilities during all modes of 3.0 1

plant operation.

Knowledge of operator responsibilities during all modes of 3.0 1

plant operation.

Facility: Mills Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures Plan 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 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-40 1 -4 Tier /

Group 1 / I 1 / I 1 / I 1 /2 Randomly Selected K/A 2.2.23 2.1.24 EK3.01 AA2.14 Reason for Rejection 00001 5/17 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 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.

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.

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 /

3 o u p 1 /2 2/1 2/1 211 2/1 Randomly Selected WA 2.1.1 A I.05 2.2.33 K3.04 2.3.1 LOIT2006-ES-401-4 Reason for Rejection 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.

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) 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 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 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 ES401-4, Page 1 of 3

iandomly Selected WA 2.3.9 K5.06 K4.03 2.2.4 2.4.26 LOIT2006-ES-401-4 Reason for Rejection 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 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.

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.

(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 2.3.1 0: Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

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 mem bers.)

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

ES401-4, Page 1 of 3