ML090120828

From kanterella
Jump to navigation Jump to search

Final Outlines (Folder 3)
ML090120828
Person / Time
Site: Beaver Valley
Issue date: 11/12/2008
From:
FirstEnergy Nuclear Operating Co
To: David Silk
Operations Branch I
Hansell S
Shared Package
ML081060562 List:
References
TAC U01628
Download: ML090120828 (27)
v • d • e


Text

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

3. Generic Knowledge and Abilities Category Note:
1.
2.
3.
4.
5.
6.

7.*

a.
9.

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 WA category shall not be less than two).

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 +I 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.

SystemsIevolutions within each group are identified on the associated outline; systems or evolutions that do not appl}

at the facility should be deleted and justified; operationally important, site-specific systemsIevolutions that are not included on the outline should be added. Refer to Section D.l.b of ES-401 for guidance regarding the elimination of inappropriate WA statements.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group befort selecting a second topic for any system or evolution.

Absent a plant-specific priority, only those WAS 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.

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

The generic (G) KIAs 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.l.b of ES-401 for the applicable KIAs.

On the following pages, enter the WA numbers, a brief description of each topic, the topics 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 #I does not apply). Use duplicate pages for RO and SRO-only exams.

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

NUREG-1021, Revision 9 Supplement 1 RO Page 1 of 13 Beaver Valley Facsimile Rev. 2

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1IGroup I(R0)

EIAPE # I Name I Safety Function

~00007 (BWIE02&E10; CEIE02) Reactor Trip - Stabilization - Recovery I 1

[Question I]

000008 Pressurizer Vapor Space Accident I 3

[Question 21 000009 Small Break LOCA 13

[Question 31 00001 511 7 RCP Malfunctions I 4

[Question 41 000025 Loss of RHR System I 4

[Question 51 00026 Loss of Component Cooling Water I 8

[Question 61 000029 ATWS I 1

[Question 71 000038 Steam Gen. Tube Rupture I 3

[Question 81 000040 (BWIE05; CEIE05; WIE12) Steam Line Rupture - Excessive Heat Transfer I 4

[Question 91 NUREG-1021, Revision 9 Supplement 1 KIA Topic(s)

I EK2 Knowledge of the interrelations between a reactor trip and the following:

EK2.03 Reactor trip status panel (CFR 41.7 145.7)

AK3 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident:

AK3.04 RCP tripping requirements EA1.I3 ESFAS AK2 Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

AK2.07 RCP seals I (CFR 41.7 145.7)

I (CFR: 41.10143.5145.13) 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

(CFR: 41.10143.5145.13)

EA2 Ability to determine or interpret the following as they apply to a ATWS:

EA2.05 System component valve position indication (CFR 43.5 145.13)

EKI Knowledge of the operational implications of the following concepts as they apply to the SGTR:

EKI.01 Use of steam tables AKI.04 Nil ductility temperature (CFR41.8141.10145.3)

RO Page 2 of 13 IR 3.5 -

4.2 4.4 2.9 4.0 3.8 3.4 3.1 3.2 1

Beaver Valley Facsimile Re\\. 2

PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1IGroup I(R0) Continued EIAPE # I Name I Safety Function 00055 Station Blackout 16 II

[Question 1 I ]

000057 Loss of Vital AC Inst. Bus 16

[Question 121 000058 Loss of DC Power I 6

[Question 131 11 000062 Loss of Nuclear Svc Water 14 000065 Loss of Instrument Air I 8

[Question 151 WIE04 LOCA Outside Containment I 3

[Question 161 WIEI 1 Loss of Emergency Coolant Recirc. I 4

[Question 171 h

NUREG-1021, Revision 9 Supplement 1 EA2.02 RCS core cooling through natural circulation cooling to SIG cooling AA2.88 Necessary SIG water level for natural circulation (CFR: 43.5 145.13)

AAI Ability to operate and I or monitor the following as they apply to the Loss of Vital AC Instrument AA1.01 Manual inverter swapping AK3.02 Actions contained in EOP for loss of DC

~

~

~

~

4 1

5 I 4 1.IO 145.6 145.1)

AK3 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water:

AK3.03 Guidance actions contained in EOP for Loss of nuclear service water AA2.08 Failure modes of air-operated equipment (CFR: 43.5 145.13)

EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 145.13)

EK3 Knowledge of the reasons for the following responses as they apply to the (Loss of Emergency Coolant Recirculation)

EK3.3 Manipulation of controls required to obtain desired operating results during abnormal and emergency situations.

RO Page 3 of 13 IR 4.4 -

4.1 3.7 4.0 4.0 2.9 3.4 3.8 1

1 1

1 1

I__

1 Beaver Valley Facsimile Rev. 2

ES-401 PWR Examination Outline Form ES-401-2 II Emergenc 1

ElAPE # I Name I Safety Function BW/E04; W/E05 Inadequate Heat Transfer -

Loss of Secondary Heat Sink I 4

[Question 181 KIA Category Point Totals:

and Abnormal Plant Evolutions - Tier I/Group I(R0) Continued as they apply to the (Loss of Secondary Heat Sink)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 13 Beaver Valley Facsimile Rev 2

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2(RO)

I/

ElAPE # / Name / Safety Function

,30005 InoperablelStuck Control Rod / 1 000069 (WIE14) Loss of CTMT Integrity / 5

[Question 221 WlE02 SI Termination/3

[Question 231 WlEl3 Steam Generator Over-pressure / 4

[Question 241 W/E15 Containment Flooding / 5

[Question 251 BW/E08; W/E03 LOCA Cooldown -

Depress. / 4

[Question 261 iin NUREG-1021, Revision 9 Supplement 1 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

(CFR: 41.10/43.5/45.3/45.12) ge of less than or equal to one hour Technical Specification action statements for (CFR: 41.7/41.10/43.2/45.13)

AK3 Knowledge of the reasons for the following responses as they apply to the Steam Generator AK3.04 Use of "feed" and "bleed" process.

as they apply to the Loss of Containment Integrity:

AA2.01 Loss of containment integrity (CFR: 43.5 145.13)

EK2 Knowledge of the interrelations between the (SI Termination} and the following:

EK2.2 Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the (CFR: 41.7 / 45.7)

EK2 Knowledge of the interrelations between the (Steam Generator Overpressure) and the following:

EK2.1 Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 I45.7)

EKI Knowledge of the operational implications of the following concepts as they apply to the (Containment Flooding).

EKI.2 Normal, abnormal and emergency operating procedures associated with (Containment Flooding).

(CFR: 41.8 I 4 1. I O / 45.3)

EA2 Ability to determine and interpret the following as they apply to the (LOCA Cooldown and Depressurization)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and RO Page 5 of 13 3.9 2.5 3.7 3.5 3.0 2.7 3.4 1

1 1

Beaver Valley Facsimile Rev 2

ES-401 EIAPE # I Name I Safety Function BWIE09; CElAl3; W/E09&E10 Natural Circ.

14

[Question 271 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2(RO) Continued F

KIA Category Point Totals:

2 NUREG-1021, Revision 9 Supplement 1 EKI Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation Operations)

EKI.3 Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

0 2

2 Group Point Total:

RO Page 6 of 13 Beaver Valley Facsimile Rev. 2

II ES-401 System # I Name

,03 Reactor Coolant Pump

[Question 281 004 Chemical and Volume Control

[Question 291 005 Residual Heat Removal

[Question 301 006 Emergency Core Cooling

[Question 311 06 Emergency Core Cooling

((Question 321 007 Pressurizer ReliefIQuench Tank

[Question 331 008 Component Cooling Water

[Question 341 010 Pressurizer Pressure Control

[Question 351 I

PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2lGroup l(R0)

KIA Topic(s)

K3 Knowledge of the effect that a loss or malfunction of the RCPS will have on the following:

K3.04 RPS (CFR: 41.7 145.6)

K4 Knowledge of CVCS design feature(s) andlor interlock(s) which provide for the following:

K4.11 TemperatureIpressure control in letdown line: prevent boiling, lifting reliefs, hydraulic shock, piping damage, and burst (CFR: 41.7) 3.1 3.9

~

K6 Knowledge of the effect of a loss or malfunction on the following will have on the RHRS:

K6.03 RHR heat exchanger (CFR: 41.7 145.7)

K6 Knowledge of the effect of a loss or malfunction on the following will have on the K6.03 Safety Injection Pumps CFR: 41.7 145.7 A4.05 Transfer of ECCS flowpaths prior to CFR: 41.7 145.5 to 45.8)

(CFR: 41.7 141. I O 143.2 143.3 145.3) 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

1 (CFR: 41.10143.5145.12)

I I

A I Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including:

A I.06 RCS heatup and cooldown effect on pressure (CFR: 41.5 I45.5)

NUREG-1021, Revision 9 Supplement 1 RO Page 7 of 13 Beaver Valley Facsimile Rev. 2

I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2lGroup I ( R 0 ) Continued System f# I Name

%IO Pressurizer Pressure Control

[Question 361 01 2 Reactor Protection

[Question 371 01 2 Reactor Protection

[Question 381 013 Engineered Safety Features Actuation

[Question 391 022 Containment Cooling Question 401 026 Containment Spray

[Question 411 026 Containment Spray

[Question 421 039 Main and Reheat Steam

[Question 431 059 Main Feedwater

[Question 441 NUREG-1021, Revision 9 Supplement 1 I I R I 1 KIA Topic(s)

A3 Ability to monitor automatic operation of the 3.6 1

PZR PCS, including:

A3.02 PZR pressure (CFR: 41.7 145.5)

I 3.2 I K4 Knowledge of RPS design feature(s) andlor interlock(s) which provide for the following:

K4.06 Automatic or manual enableldisable of RPS trips (CFR: 41.7)

A I Ability to predict andlor monitor Changes in parameters (to prevent exceeding design limits) associated with operating the RPS controls including:

A I.01 Trip setpoint adjustment K2.01 ESFASIsafeguards equipment control I

I (CFR:41.7)

A4 Ability to manually operate andlor monitor 3.6 1

in the control room:

A4.01 CCS fans (CFR: 41.7 145.5 to 45.8)

K1 Knowledge of the physical connections 4.2 1

andlor cause-effect relationships between the CSS and the following systems:

(CFR: 41.2 to 41.9 I45.7 to 45.8)

(CFR: 41. I O 143.2 143.5 145.3)

A4 Ability to manually operate andlor monitor 2.8 1

in the control room:

A4.07 Steam dump valves (CFR: 41.7 I45.5 to 45.8)

K4 Knowledge of MFW design feature(s) 2.5 1

andlor interlock(s) which provide for the following:

K4.08 Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch)

(CFR: 41.7)

RO Page 8 of 13 Beaver Valley Facsimile Rev 2

ES-401 I/

System # l Name i i r 059 Main Feedwater

[Question 451 061 AuxiliarylErnergency Feedwater

[Question 461 061 AuxiliarylEmergency Feedwater

[Question 471 062 AC Electrical Distribution

[Question 481 064 Emergency Diesel Generator

[Question 501 073 Process Radiation Monitoring

[Question 511 NUREG-1021, Revision 9 Supplement 1 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2lGroup l(R0) Continued RO Page 9 of 13 3.7 3.9 3.7 2.7 4.2 2.5 1

1 1

1 Beaver Valley Facsimile Rev. 2

(1 ES-401 System # I Name K

,u 1

PWR Examination Outline Form ES-401-2 Plant Svstems

- Tier 2lGroup I(R0) Continued 21311 31 41 31 Grout) PointTotal:

NUREG-1021, Revision 9 Supplement 1 RO Page 10 of 13 Beaver Valley Facsimile REI.

2

ll ES-401 System # / Name 14 Rod Position Indication

[Question 561 01 5 Nuclear Instrumentation

[Question 571 016 Non-nuclear Instrumentation

[Question 581 028 Hydrogen Recombiner and Purge Control

[Question 591 017 In-Core Temperature lonitor System (ITM)

[Question 601 034 Fuel Handling Equipment

[Question 611 041 Steam DumplTurbine Bypass Control

[Question 621 056 Condensate

[Question 631 NUREG-1021, Revision 9 Supplement 1 RO Page 11 of 13 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2lGroup 2(RO)

Beaver Valley Facsimile Rc-v 2

1 ES-401 K/A Category Point Totals:

System ## I Name,

L 075 Circulating Water

[Question 641 086 Fire Protection

[Question 651 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2lGroup 2(RO) Continued 1 1 0 3 0 Group Point Total:

I I I I I NUREG-1021, Revision 9 Supplement 1 RO Page 12 of 13 Beaver Valley Facsimile Rev. 2

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 11 Facility: Beaver Valley Unit 2 RO Date of Exam Weeks of 12/8 & 12/15 200&

11

' KIA# -

2.1 29 2.1.4 2.1.43 Topic b-Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

(CFR: 41.10 I 45.1 145.12) [Question 661 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

(CFR: 41.IO 143.2)

[Question 671 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(CFR: 41.IO 143.6 145.6) [Question 681 4.1 3.3 4.1 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

I 32 I (CFR: 41.5 141.7 143.2) [Question 691 I

2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 41.IO I 45.12 I 45.13) [Question 701 3.5 2.3.1 2 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.2 I

I i (CFR: 41.12 / 45.9 145.10) [Question 711 2.3.1 5 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.I2 I 43.4 I 45.9) [Question 721 2.9 2.4.4 2.4.1 1

2.4.13 lpi 3.

Radiation Control

4.

Emergency Procedures/

Plan Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.IO I 43.2 I 45.6) [Question 731 Knowledge of abnormal condition procedures.

(CFR: 41.10 143.5 145.13) [Question 741 4.5 4.0 i

4'0 Knowledge of crew roles and responsibilities during EOP usage.

(CFR: 41.10 145.12) [Question 751 NUREG-1021, Revision 9 Supplement 1 RO Page 13 of 13 Beaver Valley Facsimile Re. 2

ES-401 PWR Examination Outline Form ES-401-2 I,

Facility:

Tier

1.

Em erg en cy Abnormal Plant Evolutions

2.

Plant Systems Note

1.
2.
3.
4.
5.
6.

7.*

8.
9.

Ensure that at least two topics from every applicable WA 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).

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 *I 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.

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 systemslevolutions that are not included on the outline should be added. Refer to Section D.l.b of ES-401 for guidance regarding the elimination of inappropriate WA statements.

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.

Absent a plant-specific priority, only those WAS 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.

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

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. Refer to Section D.l.b of ES-401 for the applicable WAS.

On the following pages, enter the WA numbers, a brief description of each topic, the topics 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 # I does not apply). Use duplicate pages for RO and SRO-only exams.

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

NUREG-1021, Revision 9 Supplement 1 SRO Page 1 of 6 Beaver Valley Facsimile Rev. 2

/I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1IGroup I(SR0)

EIAPE # I Name I Safety Function

[Question 761 00001 511 7 RCP Malfunctions 14

[Question 771 000027 Pressurizer Pressure Control System Malfunction 13

[Question 781 000038 Steam Generator Tube Rupture (SGTR)

[Question 791

,iestion 801 I

WlE04 LOCA Outside Containment I 3

[Question 811 KIA Category Point Totals:

(CFR: 41.10143.5145.13)

AA2 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

AA2.10 When to secure RCPs on loss of cooling or seal injection AA2.14 RCP injection flow I I I (CFR:41.10/43.1 145.13)

AA2 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

AA2.19 T-cold and T-hot indicators (wide range)

(CFR: 43.5 145.13)

EA2 Ability to determine and interpret the following as they apply to the (LOCA Outside Containment)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

2.9 4.0 4.2 4.3 1

1 I

.- I NUREG-1021, Revision 9 Supplement 1 SRO Page 2 of 6 Beaver Valley Facsimile Re\\ 2

ES-401 PWR Examination Outline Form ES-401-2 ll Emergenc!

r I!

ElAPE # I Name I Safety Function

[Question 821 000059 Accidental Liquid RadWaste Rel. I 9

[Question 831 000067 Plant Fire on-site

[Question 841 000061 ARM System Alarms 17

[Question 851 d KIA Category Point Totals:

NUREG-1021, Revision 9 Supplement 1 and Abnormal Plant Evolutions -Tier l/Group 2(SRO)

AA2 Ability to determine and interpret the following as they apply to the Dropped Control Rod:

AA2.01 Rod position indication to actual rod position (CFR: 43.5 145.13) 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.IO 143.5 145.12) 2.4.27 Knowledge of fire in the plant procedures (CFR: 41.10143.5145.13)

AA2 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM) System Alarms:

AA2.06 Required actions if alarm channel is out of service (CFR: 43.5 145.13) 0 I l l 2

2 Group Point Total:

4.2 3.9 4.1 1

1 SRO Page 3 of 6 Beaver Valley Facsimile Re,. 2

ES-401 System #f I Name 006 Emergency Core Cooling

[Question 861 01 0 Pressurizer Pressure Control

[Question 871 01 2 Reactor Protection System 11 rouestion 891 KIA Category Point Totals:

NUREG-1021, Revision 9 Supplement 1 KI K PWR Examination Outline Form ES-401-2 Plant Systems

- Tier PlGroup I(SR0) in the facility license.

(CFR: 41.7141.10143.1 145.13)

A2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 Spray valve failures FR: 41.5 143.5 I 45.3 I 45.1 3 A2.02 Loss of instrument Power (CFR: 41.5 143.5 145.3 145.5)

Ability to (a) predict the impacts of the owing malfunctions or operations on the DC predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 Loss of ventilation during battery FR: 41.5 143.5 145.3 145.13 n those predictions, use t, control, or mitigate the se malfunctions or A2.01 Air dryer and filter malfunctions 3.9 3.1 2.9 SRO Page 4 of 6 Beaver Valley Facsimile Rev. 2

System # I Name 01 1 Pressurizer Level Control

[Question 911 071 Waste Gas Disposal

[Question 921 086 Fire Protection

[Question 931 NUREG-1021, Revision 9 Supplement 1 K

K K

K 1

2 3

4 PWR Examination Outline Form ES-401-2 Plant Systems

-Tier 2lGroup 2(SRO)

K/A Category Point Totals:

KIA Topic(s) 0 0

0 0

I IR (CFR: 41. I O 143.5 145.2 145.6) 1x1 2.1.20 Ability to interpret and execute procedure I 4.6 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

SRO Page 5 of 6 Beaver Valley Facsimile Rev. 2

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Beaver Valley Unit 2 SRO Date of Exam Weeks of 12/8 & 12/15 20C &

~~

Category

1.

Conduct 3f Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures/

Plan 2.2.21 2.2.37 requirements.

(CFR: 41.IO / 43.2)

[Question 961 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12) 4.6 I

I I

I Subtotal 3.1

~~

2.4.20

. I personnel monitoring equipment, etc.

(CFR: 41.I2 / 43.4 / 45.9)

I I

I cautions, and notes.

(CFR: 41.10 /43.5/45.13)

[Question 991

~-

2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

(CFR: 41.10/43.5/45.13)

Subtotal 1 -

1 1

2 7 -

NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 Beaver Valley Facsimile Rev. 2

ES-401 Randomly Selected KIA 025 059 K4.05 Tier I Reason for Rejection Beaver Valley does NOT have Ice Condensers.

Beaver Valley does NOT have variable speed main feedwater pumps.

roup APE 003 AA2.04 2.1.27 2.4.3 211 Beaver Valley does NOT have any automatic outward rod motion. All automatic outward rod motion has bem defeated.

WA is NOT linked to IOCFR 55.43 and is therefore NOT suitable for SRO exam.

K/A is NOT linked to IOCFR 55.43 and is therefore NOT suitable for SRO exam.

211 WE16 EK 1.1 033 A3.02 061 A1.04 000029 2.4.1 1 /2 At BVPS the response to containment high radiation procedure (FR-Z.3) has no actions for the operations,:rew other than contact the TSC. Any response to high containment radiation will be guided by ERO. This WA therefore has no discriminatory value for a written exam question.

BVPS Unit 2 Does NOT have any automatic controls on spent fuel pool cooling associated with a leaking 0:

ruptured fuel assembly.

BVPS Unit 2 Does Not have any AFW controls on the AFW source tank (FWE*TK210) except a level contr:Jl valve that will provide makeup to the tank as level drops. Unable to construct a discriminatory written quest on to match this WA.

Unable to construct a SRO discriminatory question for this KIA. Knowledge of ATWS EOP entry conditions m d immediate actions are also RO knowledges. (Q 79)

-~

NIA 000060 2.4.21 NIA Unable to construct a SRO discriminatory question for this K/A. Generic KIA is a difficult match to accidenttA gas release. Too much time( 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) spent trying to construct a valid SRO discriminatory question. (Q 84) 211 000029 EA 2.01 007 K3.01 212 Unable to construct a RO discriminatory question for this WA. (Q 7)

Unable to construct a RO discriminatory question for this KIA. (Q 33) 212 112 212 212 1 I1 112 1 I1 211 Record of Rejected WAS Form ES-401-4 022 A2.05 I Unable to construct a SRO discriminatory question for this WA.

1 1

072 A2.01 Balance of exam. This would be the sixth radiation monitor question BVPS Post DBA Hydrogen control equipment and associated procedures have been retired in place. If the.iced arises, Post DBA Hydrogen control equipment and procedures will be directed by the Technical support ceiter with engineering support.

NUREG-1021, Revision 9 Supplement I Beaver Valley Facsimile Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility :

Beaver Valley Unit 2 Date of Examination: Weeks of 12/8 & 12/15 2008 I

" Fxamination Level RO EI Operating Test Number 2LOT6 NRC Exam Type Code*

N, R N/A Describe activity to be performed Plot and Evaluate 1/M Data 2.1.43 4.1 Perform Daily Heat Balance 2.1.7 4.4 Prepare Tagout of 21 B Service Water Pump 2.2.13 3.6 I

(See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Proced u res/P la n topics, when all 5 are required

  • Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs, 5 4 for SROs & RO retakes)

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

1)

(P)revious 2 exams (I 1, randomly selected)

/I--__

Respond to Radiation Monitor Alarm and complete the Radioactive Waste Discharge permit.

2.3.1 1 3.3 N/A NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2

ES-301 Ad mi n istrat ive Topics Ou ti i ne Form ES-301-1 I

7 Facility:

Beaver Valley Unit 2 Date of Examination Weeks of 12/8 & 12/15 2008

'I Txamination Level SRO El I

(See Note)

Conduct of Operations Co nd u ct of 0 pera t ions Equipment Control Rad i a t io n Con t ro I Em erg en cy P roced u res/Pla n Type Code*

M, R Operating Test Number 2LOT6 NRC Exam Describe activity to be performed Plot and Evaluate 1/M Data and make recommendations fot continued Rod Withdrawal 2.1.43 4.3 Prepare Partial OST for Performance (20ST-6.6, PORV Isolation Valve Test and Position Check) 2.1.20 4.6 Review/Approve Completed RHS Pump Surveillance 2.2.37 4.6 Review/Approve LW Discharge Permit 2.3.1 1 4.3 Evaluate EPP and complete the Initial Notification Form.

2.4.41 4.1 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when a 5

'Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (5 1: randomly selected) are required.

NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2

  • Type Codes (A)lternate Path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2 Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3 a

I Sa 1 4 21 I 21 I 21

- I - 12 1 (Control room system 1

,?)revious 2 exams (VCA (S)imulator 131 13 I s2 (randomly selecteo) 21 I 21 I rl 5

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

Beaver Valley Unit 2 Exam Level: RO 0 SRO(I) El SRO(U) 0 Operating Test No.: 2LOT6 NRC Exam Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Date of Examinati0n:Weeks of 12/8 & 12/15 2008=

11 Facility:

Beaver Valley Unit 2 Date of Examinati0n:Weeks of 12/8 & 12/15 2008=

rlRC Exam li Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

S7 JPM 2CR-646 Perform Nuclear IR Channel Functional Test (Mode 2 - 3% RX Power)

S8 JPM 2CR-537 Batch To RWST (Mode 2 - 3% RX Power) h 004 A4.04 3.213.6 (Paired with S7)

I I

II s, M, A, L 2

System I JPM Title I.

01 3 A3.01 3.713.9 I1 g.

01 5 A3.03 3.9/3.9 (Paired with S8)

( N, S. L I 7

D, EN 2

P I JPM 2PL-048 Safeguards test of FWI P2 JPM 2PL-069 Local Shutdown of 2FWE*P22 (IAW 20ST-24.4A)

j.

06 I A2.04 3.413.8 N, R 4s

k.

064 A4.01 4.014.3 1 E, D,A, EN I 6

  • Type Codes

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

(A)lternate Path (C)ontrol room (D)irect from bank (EN)gineered safety feature (E)mergency or abnormal in-plant

-~

Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3 591 1 8 1 1 4 rl I rllrl

- / - / 2 1 (Control room syster 4 )

(L)ow-power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (RKA

'S)imulator rl I rl I rl 221 2 2 1 rl 531 13 I 12 (randomly selected) 21 I 2.1 I rl NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev.2

~-

~~~~~

Appendix D Scenario Outline Form ES-D-1 Facility:

BVPS 2 Scenario No.:

1 Op Test No.:

NRC Examiners:

Candidates:

SRO ATC BOP Event No 1

2 3

Initial Conditions :

BOL, -5% power following Xe free S/U, CB D = 104,2027 PPM IC-165 Equipment 00s Malf. No.

Event Type R(RO)

N(ALL)

NIS07B SRO T.S.

XMT-RCSO 19A I(RO/SRO)

SRO T.S.

[2SAS-C2 lB] Station Air Compressor undergoing a compressor overhaul, will r a t be returned until 3 days from now Continue plant startup IAW 20M-52.4.A.

Turnover:

Critical Tasks:

1. E-0.1 Crew establishes flow from at least one high head ECCS pump before transition out of E-0.
2. E-0.P Crew manually actuates main steam line isolation before a Severe (orange path) challenge develops to either the Sub-criticality or Integnty CSF 3r before transition to ECA-2.1, whichever occurs first.
3. E-2.A Crew isolates the faulted SG and directs operator to close isolation valve(s) operated from outside of the control room before transition out of E-2.

4 5

N(RO/SRO)

CNH-CFW 15B C(BOP/SRO) 6 7

MSSOlC M(ALL)

PMP-CHS002 C(RO/SRO)

PPL07A PPLl OA C(BOP/SRO)

Event Description Crew raises power IAW procedure (Must raise power above 10% before N-36 failure)

~

~~

~

IRNI N-36 Intermediate Range Nuclear Instrument Inst Pwr fuse blows

[2RCS*LT459] Controlling P U R Level Channel fails low, L/D isolates Alternate channel selected and L/D restored Cy BPFRV fails open in auto, manual control required Steam leak inside CNMT slowly progresses to Stear;r line RUPTURE inside CNMT, SI, CIA, CIB

[2CHS*P21B] HHSI Pump trips on SI [2CHS*P21P5]

HHSI pump Fails to AUTO Start, requires manual start on SI AUTO MSLI failure BOTH Trains, requires manual actuation (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2

Appendix D Scenario Outline Form ES-D-1 RCPO 1 A RCP06A PPLO 1 A PPLO 1 B LOA-AFW022 PPL07B Facility:

BVPS 2 Scenario No.:

2 Op Test No.:

NRC Examiners:

Candidates:

SRO ATC BOP C(RO/SRO)

M(ALL)

C(BOP/SRO)

Initial

-~

Conditions :

MOL, 75 % power Equ Xe, CB = 188,1116 PPM IC-166 Equipment 00s N-42 (PRNI) removed from service per AOP 2.2.1C

[2FWE*P23A] AUX Feed Pump Motor ground, repair estimate is 8 - 10 Hrs.

Rods in MANUAL @ request of I & C, Rod control is FULLY functional.

Maintain current plant conditions Turnover:

Critical Tasks:

1. ~ - 1

,c Crew trips all RCPs when RCS to highest SG D/P criteria is exceeded and SI flow verified prior to exiting procedure E-1.

Crew inserts negative reactivity into the core by inserting RCCAs before completing the immediate action steps of FR-S. 1.

Crew starts AFW pumps before WR SG level is less than 10%.

2. FR-S. 1.C
3. FR-S.l.B Event No.

I 2

3 4

5 6

7 8

SRO T.S.

VLV-RCS032A M(ALL)

Event Description

[2MSS*FT485] "B" SG Selected Steam Flow Channel drifts HIGH VCT Level control channel failure LOW

[2RCS*PT455] P U R Pressure Protection Channel fails HIGH Power reduction due to TS 3.0.3 requirement (No TS Action addressing two channels of OTAT being inoperable)

RCP # 1 seal leakoff excessive, vibration increases (requires Rx trip)

ATWS - Failure of auto/manual Rx trip

[2FWE*P22], Turbine driven AFW pump trips during S/U, [2FWE-P23B] Motor Driven AFW Pump requires manual start

~~~

~

PORV [2RCS*PCV455C] sticks open after auto open and its block valve [2RCS*MOV535] cannot be closed from CR ( P U R Vapor space leak)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2

Appendix D Scenario Outline Form ES-D-1 7

8 I

Facility:

BVPS 2 Scenario No.:

4 Op Test No.:

NRC Examiners:

Candidates :

SRO IMFPPLOlB IOR XBlI021T RCS04C VLV-MSS003 VLV-MS S 004 VLV-MSSOOS PPLOSA PPLOSB ATC BOP

-- Initial Conditions:

BOL, 100% power Equ Xe, CB 229,1500 PPM IC-168 Equipment 00s

[2CHS*P21C] HHSI Pump, Motor replacement and will not be returned until nex week Maintain current plant conditions Turnover:

Critical Tasks:

1. E-0.A
2. E-0.D
3. ECA-3.1.B Crew manually trips the reactor fi-om the control room before performin ;

the mitigation strategy of FR-S.l.

Crew manually actuates at least one train of SIS-actuated safeguards before transition to any OW.

Crew initiates cool down of the RCS to cold shutdown conditions at the highest rate achievable but less than 100°F per hour in all RCS cold legs 1

PMP-CHS002 N/A 3

l I XMT-RCS030A VLV-RCS032 6

Event Type*

I(ALL)

SRO T.S.

C (RO/S RO)

SRO T.S.

I(RO/SRO)

C(RO/SRO)

I(RO/SRO)

M(ALL)

C(RO/SRO) tstrument, (C Event Description

[2MSS*PT446] Selected First Stage Pressure Transmitter fails LOW

[2CHS*I)21B] HHSI Pump trips Crew begins power reduction

[2RCS-PT444] P U R Pressure Control Channel fails HIGH

[2RCS*PCV455C] P U R PORV sticks open after lifting, block valve closure required Automatic reactor trip failure Manual RX trip from BB B.

UNSUCCESSFUL, Manual RX trip from BB A SUCCESSFUL 350 GPM SGTR on C SG with all MSIVs stuck open Auto SI failure, both trains, manual actuation required imponent, (M)aj or NUREG-1021, Revision 9 Supplement 1 Beaver Valley Facsimile Rev. 2

Retrieved from "https://kanterella.com/w/index.php?title=ML090120828&oldid=5321496"