ML103130198

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2010 Prairie Island Nuclear Generating Plant Initial Examination Outline Submittal Revision 1
ML103130198
Person / Time
Site: Prairie Island  
Issue date: 03/15/2010
From: Chuck Zoia
NRC/RGN-III/DRS/OLB
To:
Shared Package
ML093500371 List:
References
Download: ML103130198 (39)
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Text

2010 PRAIRIE ISLAND NUCLEAR GENERATING PLANT INITIAL EXAMINATION 0 UTLl N E S U B M ITTAL REVISION 1

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

Prairie Island Date Of Exam:

March 201 0 I

I RO w A Category Points

3. Generic Knowledge And Abilities Categories
1.
2.
3.
4.
5.
6.

7.*

8.
9.

Printed:

SRO-Only Points A2 I G* I Total 0

I O

I O

0 I

I 0

0 0

0 Note:

Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., 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 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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 WA 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 #1 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 totals (#) on Form ES-401-3.

10 CFR 55.43.

Limit SRO selections to WAS that are linked to 1

Pr Printed PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 Facility:

Prairie Island ES - 401 Form ES-401-2 ctor Trip - Stabilization -

EK2.02 - Breakers, relays and 00062 Loss of Nuclear Svc Water emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility Point 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Facility:

Prairie Island ES - 401 Printed R'

Form ES-401-2 APE # I Name I Safety Function Y

W/El 1 Loss of Emergency Coolant Recirc. / 4 W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 WA Category Totals:

K1 3

41 A2 G KA Topic EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations II

~~~

EK3.1 - Facility oper. characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics Imp.

3.8 3.5 31 3 1 31 Group Point Total:

Point 1

1 18 2

PWR RO Examination Outline Imp.

G KATopic Facility:

Prairie Island Point Printed UAPE # I Name I Safety Function P

000001 Continuous Rod Withdrawal / 1 000005 Inoperable/Stuck Control Rod / 1 000028 Pressurizer Level Malfunction / 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 K1 K2 X

AK3.01 - Manually driving rods into position that existed before start of casualty X

AA1.O1 - CRDS X 2.4.31 - Knowledge of annunciator alarms, indications, or response procedures).

000076 High Reactor Coolant Activity / 9 W/E06 Inad. Core Cooling / 4 000059 Accidental Liquid RadWaste Rel. /

9 X

2.7 2.9 3.5 3.6 3.0 3.0 W/El6 High Containment Radiation / 9 1

1 1

1 1

1 W/ElO Natural Circ.With steam void in vessel with/without RVLIS / 4 b

K3 A1 A2 T

X W/E13 Steam Generator Over-pressure

/ 4 X

4.2 KIA Category Totals: I 1 AKl.01 - Types of radiation, their unit5 of intensity and the location of the sources of radiation in a nuclear power plant 2

7 X

2 1

2 1

Group Point Total:

9 AK3.05 - Corrective actions as a result of high fission-product radioactivity level in the RCS EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 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 facility EK2.1 - Components, and functions oi control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features X

EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 1

PWR RO Examination Outline Printed Facility:

Prairie Island 063 DC Electrical Distribution

r ys/Evol # / Name PWR RO Examination Outline K1 K2 Facility:

Prairie Island 078 Instrument Air 103 Containment WA Category Totals:

ES - 401 I

I 3

2 Plant Systems - Tier 2 / Group 1 41 Printed Form ES-401-2 ressure, temperature, and Group Point 28 I 2 1 31 I

I I

2

K1 X

K2 X

1 1

PWR RO Examination Outline Printed RI Facility:

Prairie Island PI int I ystems - Tier 2 / ( roul 2 Form ES-401-2 ES - 401 ys/Evol # / Name 1 Control Rod Drive K3 K4 A3 X

002 Reactor Coolant 01 5 Nuclear Instrumentation 027 Containment Iodine Removal 029 Containment Purge X

035 Steam Generator 045 Main Turbine Generator X

055 Condenser Air Removal

~~~

068 Liquid Radwaste 086 Fire Protection WA Category Totals:

1 -

1 -

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 2.1.29 Knowledge of how to conduct system lineups, 4.1 2.1.41 Knowledge of the refueling process.

2.8 such as valves, breakers, switches, etc.

Facilitv:

Prairie Island 1

1 Printed:

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

Form ES-401-3 3.1 1

Conduct of Operations 2.3.1 I

Knowledge of radiation or contamination abnormal, or emergency conditions or activities.

hazards that may arise during normal, 3.4 1

Equipment Control Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Knowledge of EOP mitigation strategies.

Knowledge of emergency response facilities.

Radiation Control 4.5 1

3.7 1

2.6 1

KA KA Touic Imp. Points 2.2.6 Knowledge of the process for making changes I 3.0 1 1

to procedures.

2.2.1 4 Knowledge of the process for controlling equipment configuration or status.

I 3.9 I 1

2.2.36 Category Total:

3 I

I I

I I

I 2.3.11 I

3.8 I I

Ability to control radiation releases.

Emergency Procedures/Plan 2.4.2 2.4.6 2.4.42 1

Generic Total:

10

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

Prairie Island Printed:

RI Date Of Exam:

March 201 0 Note:

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 (Le., 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 *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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.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 WA 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 #1 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 totals (#) on Form ES-401-3.

10 CFR 55.43.

Limit SRO selections to WAS that are linked to 1

PWR SRO Examination Outline Imp.

4.8 3.0 4.6 4.1 4.2

4.3 Facility

Prairie Island ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Point 1

1 1

1 1

1 Printed A1 Form ES-401-2 A2 X

X X

0 3

YAPE # I Name I Safety Function G

000009 Small Break LOCA / 3 KATopic 00001 5/000017 RCP Malfunctions / 4 X

000040 Steam Line Rupture - Excessive Heat Transfer / 4 2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

000056 Loss of Off-site Power / 6 3

~

~~

000057 Loss of Vital AC Inst. Bus / 6 Group Point Total:

6 000077 Generator Voltage and Electric Grid Disturbances / 6 KIA Category Totals:

on RCS temperature and pressure, saturated and superheated in RCP air vent flow paths and/or oil cooling 2.4.41 - Knowledge of the emergency action level thresholds and classifications.

2.1.8 - Ability to coordinate personnel activities outside the control room

- Operational status of emergency diesel generators 1

Facility:

Prairie Island ES - 401 KA Topic Imp.

Printed P, (

PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 Point E/APE # I Name I Safety Function 6

K1 000024 Emergency Boration / 1 1 K2 K3 0

0 0

000051 Loss of Condenser Vacuum / 4 000067 Plant Fire On-site / 8 000069 Loss of CTMT Integrity / 5 4A2.02 - Conditions requiring reactor md/or turbine trip WA Category Totals:

4.1 AA2.02 - Verification of automatic and manual means of restoring integrity 4.4 1

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

4.7

~

2.2.40 -Ability to apply Technical Specifications for a system.

1 1

Group Point Total:

4 1

PWR SRO Examination Outline 44 G KATopic Facility:

Prairie Island Plant Systems - Tier 2 / Group 1 ES - 401 I

I I

Imp.

Point ys/Evol # / Name K1 K2 K3 03 Reactor Coolant Pump A2.06 - Failure of RPS 4.7 1

signal to trip the reactor X 2.1.20 - Ability to interpret 4.6 1

and execute procedure steps.

A2.16 - Degraded system 2.9 1

voltages A2.01 - Integrated leak rate 2.V 1

test 0

2 Group Point 5

~

I l

l I 01 2 Reactor Protection System 008 Component Cooling Water I

l l

I 103 Containment WACategory Totals:

0 0

0 B a Printed Form ES-401-2 I 4.3 I I

2.4.45 -Ability to prioritize and interpret the of each annunciator or alarm 1

PWR SRO Examination Outline Facility:

Prairie Island Plant Systems - Tier 2 / Group 2 ES - 401 I

I I

I a

0 -

Printed Form ES-401-2 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline 2.2.35 Facilitv:

Prairie Island Ability to determine Technical Specification 4.5 1

Mode of Operation.

@ Generic Catenorv 2.3.4 KA KA Topic Knowledge of radiation exposure limits under 3.7 1

normal or emergency conditions.

Printed:

2.4.30 Conduct of Operations Knowledge of events related to system operation/status external agencies, such as the State, the NRC, or the transmission system operator.

that must be reported to internal organizations or 4.1 1

2.1.5 2.1.14 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Category Total:

Form ES-401-3 Imp. Points 3.9 3.1 2

1 Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system ooerator.

3.8 1

Radiation Control Category Total:

1 I

I I

I Emergency Procedures/Plan I 2.4.11 Knowledge of abnormal condition procedures. I 4.2 I 1

Generic Total:

7 1

R I

1 ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group 212 s 212 Randomly Reason for Rejection Selected WA 029 K3.02 028 A2.01 Purge system not requiredlused for containment entry. No procedural support. Used K3.01.

Could not support an SRO question Replaced with 01 1 A2.10.

s 212 I071 A2.08 Could not support an SRO question Replaced with 034 A2.01.

S 212 1 075 2.1.27 I Could not support an SRO question Replaced with 041 ntrols associated with fire dampers. Replaced with 086

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

Prairie Island Date Of Exam:

March 201 0 1 2 1 1 Printed:

Totals 0

0 0

0 0

0 0

5 5

10 Evolutions

2.

1 0

0 0

0 0

0 0

0 0

0 0

0 3

2 5

2 0

0 0

0 0

0 0

0 0

0 0

0 0

2 1

3 Plant Systems 0

0 0

0 0

0 0

0 0

0 0

0 5

3 8

Tier Totals 1

2 3

4 1

2 3

4 0

0 0

0 2

2 1

2 0

7

3. Generic Knowledge And Abilities Categories 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 (Le., 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 +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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.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 WA 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 #1 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 totals (#) on Form ES-401-3.

10 CFR 55.43.

Limit SRO selections to WAS that are linked to

PWR SRO Examination Outline Facility:

Prairie Island ES - 401 Printed Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 Form ES-401-2 I WAPE # / Name / Safety Function 000009 Small Break LOCA / 3 00001 5/000017 RCP Malfunctions / 4 000040 Steam Line Rupture - Excessive Heat Transfer / 4

~

000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000077 Generator Voltage and Electric Grid Disturbances / 6 0 -

K2 K3 A1 0

0 0

KA Topic EA2.01 - Actions to be taken, based on RCS temperature and pressure, saturated and superheated

~

~~

~

AA2.02 - Abnormalities in RCP air vent flow paths and/or oil cooling 2.4.41 - Knowledge of the emergency action level thresholds and classifications.

2.1.8 - Ability to coordinate personnel activities outside the control room

~

2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

AA2.09 - Operational status of emergency diesel generators Imp. -

4.8 3.0 -

4.6 -

4.1 4.2 4.3 Point 1

1 1

1 1

1 Group Point Total:

6

Facility:

Prairie Island ES - 401 Printed PWR SRO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 R.

Form ES-401-2 APE # I Name I Safety Function K1 P

000024 Emergency Boration / 1 000051 Loss of Condenser Vacuum / 4 000067 Plant Fire On-site / 8 000069 Loss of CTMT Integrity / 5 KIA Category Totals: I 0

K2 K3 0

0 KA Topic 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4A2.02 - Conditions requiring reactor md/or turbine trip

~

~~

~

~

2.2.40 -Ability to apply Technical Specifications for a system.

AA2.02 - Verification of automatic and manual means of restoring integrity 7

4.7 4.1 4.7

~

4.4 Point 1

1 1

1 Group Point Total:

4 1

PWR SRO Examination Outline KA Topic Imp.

Facility:

Prairie Island Plant Systs ES - 401 Point WACategory Totals: I 0 I 0 I 0 I 0 I 0

~~

2.4.1 - Knowledge of EOP entry conditionsAm. actions.

A2.06 - Failure of RPS signal to trip the reactor 2.1.20 - Ability to interpret and execute procedure steps.

!I 4.8 1

4.7 1

4.6 1

ns - Tier 2 / Group 1 K6 -

0 I

G X -

X 2

Printed R. 1

-ybti6 - Degraded system 1 2.9 I voltages A2.01 - Integrated leak rate 2.V Group Point 5

~

Facility:

Prairie Island Imp.

3.6 4.4 4.0 ES - 401 11 Pressurizer Level Control Point 1

1 1

PWR SRO Examination Outline Printed R Q I

K5 I I 034 Fuel Handling Equipment K6 0

0 041 Steam Dump System X

WACategory Totals: I 0 I 0 2.4.1 8 - Knowledge of the specific bases for EOPs.

Plant Systems - Tier 2 / Group 2 G KATopic A2.10 - Failure of PZR level instrument - high I--

A2.01 - Dropped Fuel Element I

'I Form ES-401-2 Group Point 3

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline 2.2.35 Facilitv:

Prairie Island Ability to determine Technical Specification 4.5 1

Mode of Operation.

e Generic Cateaory Knowledge of radiation exposure limits under normal or emergency conditions.

Conduct of Operations 3.7 1

Equipment Control 2.4.30 KA Knowledge of events related to system operation/status external agencies, such as the State, the NRC, or the transmission system operator.

that must be reported to internal organizations or 4.1 1

KA Topic Printed:

Form ES-401-3 Imp. Points 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Category Total:

3.9 1

2 3.1 1

2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

3.8 I

I I

I I

I Radiation Control 2.3.4 I Category Total:

1 I

I I

I Emergency Procedures/Plan I 2.4.11 Knowledge of abnormal condition procedures. I 4.2 I 1

Generic Total:

7

ES-301 Transient and Event Checklist Form ES-301-5

-acility: Prairie Island Date of Exam:

March 201 0 Operating Test No.: 1 32 nstructions:

2 CREW POSITION 1,3,5 4

1 2, 3 4

Scenarios M

I N

I M

U M(*)

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-1 basis.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021, Revision 9 Supplement 1

ES-301 Transient and Event Checklist Form ES-301-5

-acility: Prairie Island Date of Exam:

March 2010 Operating Test No.: 1 I

A P

P L

I C

A N

T 35 17 istructions:

0 Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO addifionallyserves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

0 Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-1 basis.

0 Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021, Revision 9 Supplement 1

E. I ES-301 Transient and Event Checklist Form ES-301-5 nstructions:

0 Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

0 Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-1 basis.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

NUREG 1021, Revision 9 Supplement 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: -Prairie Island Date of Examination: -March 201 0-Examination Level: RO x SRO u Operating Test Number:

1 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code*

N/A Describe activity to be performed Admin 43, Determine the Time to Boil During Reduced Inventory (2.1.25 3.9/4.2)

Admin 48, RCS / Steam Generator Temperature Verification. (2.1.20 4.6/4.6)

Admin 61, Approve An Equipment Isolation (2.2.13 4.1/4.3)

~

Admin 62, Verification of Radiation Work Permit Limits (2.3.7 3.5/3.6)

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 all 5 are required.

Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

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

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

NUREG 1021, Revision 9 Supplement 1

P c Examination Level: RO Administrative Topic (see Note)

Emergency Procedures/Plan ES-301 SRO X Operating Test Number:

1 Type Code*

Describe activity to be performed Admin 63, Verify Time to Boiling Determination During Reduced Inventory Operations (2.1.25 3.9/4.2)

N, R Admin 64, Verify RCS / Steam Generator Temperature N, R Determination (2.1.20 4.6/4.6)

Admin 61, Approve An Equipment Isolation N, R (2.2.13 4.1/4.3)

Admin 62, Verification of Radiation Work Permit Limits N, R (2.3.7 333.6)

Admin 47, Emergency Classification of a Plant Event N, R (2.4.41 4.6)

Administrative Topics Outline Form ES-301-1 Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

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

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

NUREG 1021, Revision 9 Supplement 1

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title

a. FL-1 OSF-3, Lineup RWST to Charging During ATWS Facility:

Prairie Island Date of Examination:

March 201 0 Exam Level: RO x SRO-I 0 SRO-U 0 Operating Test No.:

1-Type Code*

Safety Function A, p, D, s 1

b. EO-31 SF-1, Perform Attachment L: Containment Isolation Actuation Failure A, D, s 2

11 c. PS-3, Respond to a Pressurizer Level Channel Failing Low I

D,S I

3

e. RC-22SF-1, Lower PRT Level
f. EA-19SF, Restore Power to Bus 15 from Unit 2
g. NI-4SF-1, N35 Failure High With Failure of Reactor to Trip
h. CC-6S, Loss of Component Cooling I

D f S I

d. AF-8S, Restore AFW Flow After AFW Pump Trip on Low ll Pressure A, p, D, s 5

A, N, EN, S 6

A, D, S 7

N, S 8

4 s

i. VC-16, Borate Unit 1 RCS from Outside the Control Room
j. IP-3, Respond to Bypassed instrument Inverter D, E, R 1

D, E, P 6

k. AF-18, Control S/G Water Levels N, E, L 4 s
  • Type Codes II NUREG 1021, Revision 9 Supplement 1 Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (WCA (S)imulator 4-6 14-6 12-3 s g i s a i s 4 51151121 5 1 I 5 1 I 5 1 2 2 / 2 2 / 2 1 I

3 1 s 3 I s 2 (randomly selected) 2 1 / 2 1 121

- I - I 21 (control room system)

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

Prairie Island Exam Level: RO 0 SRO-I x SRO-U 0 Date of Examination:

March 201 0 Operating Test No.:

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

System / JPM Title Type Code*

Safety Function

a. FL-1 OSF-3, Lineup RWST to Charging During ATWS A, P, D, S 1
b. N/A
c. PS-3, Respond to a Pressurizer Level Channel Failing Low I

D, S I

3

d. AF-8S, Restore AFW Flow After AFW Pump Trip on Low D, S 4 s
e. RC-22SF-1, Lower PRT Level A, p, D, s 5
f. EA-19SF, Restore Power to Bus 15 from Unit 2 A, N, EN, S 6

Pressure

g. NI-4SF-1, N35 Failure High With Failure of Reactor to Trip 1

A, D, S I

7

h. CC-6S, Loss of Component Cooling In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. VC-16, Borate Unit 1 RCS from Outside the Control Room D, E, R 1
j. IP-3, Respond to Bypassed Instrument Inverter D, E, P 6
k. AF-18, Control S/G Water Levels N, E, L 4 s Q

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (S)imulator

( W A Criteria for RO I SRO-I I SRO-U 4-6 14-6 12-3 1 9 / 5 8 / 5 4 2 1 I 2 1 I 2 1 2 1 1 2 1 1 2 1 22122121 6 3 I 5 3 1 5 2 (randomly selected) 2 1 l b 1 I 2 1

- I - I 21 (control room system)

NUREG 1021, Revision 9 Supplement 1

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System I JPM Title

a. NIA
b. EO-31 SF-1, Perform Attachment L: Containment Isolation Actuation Failure
c. NIA
d. NIA
e. NIA
f. EA-19SF, Restore Power to Bus 15 from Unit 2
g. NI-4SF-1, N35 Failure High With Failure of Reactor to Trip
h. NIA Facility: -Prairie Island Date of Examination: -March 201 0-Exam Level: RO 0 SRO-I 0 SRO-U X Operating Test No.:

1-Type Code*

Safety Function A, D, S 2

A, N, EN, S 6

A, D, s 7

i. VC-16, Borate Unit 1 RCS from Outside the Control Room 11 j. NIA D, E, R 1

I I

k. AF-18, Control S/G Water Levels N, E, L 4s (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (S)imulator WCA Type Codes

~~

4-6 14-6 12-3 Criteria for RO I SRO-I I SRO-U 1 9 t s a 1 1 4 21 I 2 1/21 11 I 1 1 1 2 1 r 2 / r 2 / 2 1 I

3 I I 3 I s 2 (randomly selected) 1 1 1 2 1 I 2 1

- I - I 11 (control room system)

NUREG 1021, Revision 9 Supplement 1

Appendix D Scenario Outline Form ES-D-1 Malf.

No.

NIA Facility: -Prairie Island Scenario No.:

1 Op-Test No.:

1 Event Type*

Event RX (RO)

N (SR0,BOP)

Description Increase Power to 60%.

Place Second Main Feed pump in service.

Examiners:

Operators:

VC04A Initial Conditions:

50% Power with xenon increasina C (RO) 11 Charging Pump Trips.

Turnover:

No EauiDment 00s RX226 RC14 Event No.

I (SRO, RO)

TS (SRO)

Turbine 1 Stage Pressure (PT-485) Fails High.

T.S. LOC 3.3.1 Condition A and Table 3.3.1 -1 Function 16.b.2.

TS(SR0)

RCS Leak.

T.S. LCO 3.4.1 4 Condition A.

1 RC07A 3

M (All)

Small Break LOCA.

3 T C l l A 4

C(B0P)

Failure of Turbine to Auto Trip.

5

S105A, S105B 6

C (BOP)

SI Pumps fail to auto start.

7 I

I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Revision 9 Supplement 1

Scenario 1 Summary The crew assumes the duty at 50% power with xenon increasing, No equipment 00s. The crew is directed to increase power to 60%. During the power rise a second main feedwater pump will be started.

After the crew has completed the power increase, 11 Charging Pump Trips. The RO will stabilize seal injection flows and/or start 13 charging pump. The crew responds IAW C47 and 1c12.1.

After the plant is stabilized, Turbine First Stage Pressure channel (PT-485) fails high. The RO will take rod control to manual and stabilize charging. The BOP will address the instrument failure and swap steam dumps to Pressure Mode. The SRO will determine T.S. requirements.

After the plant is stabilized, a 20 gpm RCS leak develops. The SRO will determine T.S.

requirements. The crew responds IAW 1 C4 AOPl.

After the crew identifies the T.S requirements for the RCS leak, a Small Break LOCA occurs.

The crew will trip the reactor and enter 1 E-0. Upon the trip, BOP will recognize the turbine fails to auto trip and both SI pumps fail to auto start and perform manual actions to remedy these failures. The crew will transition to 1 E-1 and the scenario will continue until safeguards pumps are stopped in 1 FR-P.l or the first SI pump is stopped in 1 ES-1.l.

Termination Criteria:

Safeguards pumps are stopped in 1 FR-P.l or the first SI pump is stopped in 1 ES-1. I.

Critical Tasks:

E-0 -- H: Manually start at least one safety Injection pump before transition out of E-0.

E TCOA4: Control AFW flow within 38 minutes following a Reactor Trip.

(SW I 0-35 identified Time Critical Operator Action).

E-0 -- Q: Trip turbine before leaving E-0.

E-1 -- C: Trip all Reactor Coolant Pumps so that a severe challenge to Core Cooling does not occur when forced circulation in the RCS stops (Small Break LOCA).

NUREG 1021, Revision 9 Supplement 1

Appendix D Scenario Outline Form ES-D-1 Event No.

1 Facility: -Prairie Island Scenario No.:

2 Examiners:

Operators:

Malf.

Event Type*

Event No.

Description FW13A R ( R 0 )

11 Main Feedwater Pump Trip.

C (SRO, BOP)

Op-Test No.:

1 TS (SRO)

Initial Conditions:

71 % Power and stable T.S. LCO 3.3.1 Condition A and Table 3.3.1-1 Functions 2a, 2b, 3a, 3b, 6, 16b.1, 16c, 16d, 16e.

Turnover :

11 CC PumD 00s 4

MSOlA M (All)

Steam Break I/S Containment on Trip.

2 I N105D I I (SRO, RO) 1 N44 Power Range NI Fails High.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Revision 9 Supplement 1

Scenario 2 Summary The crew assumes the duty at 71 Yo power and stable. 1 1 CC pump is 00s.

After the crew takes the duty, 11 MFW pump will trip. The RO will reduce power to -50% using IAW 1 C1.4 AOPl. BOP will address the ARP for the failure and manipulate control room switches as necessary to facilitate trouble shooting and ensure proper system response.

After the crew has completed the power reduction, N44 Power Range NI Fails High. The BOP will address the failure and remove the affected channel from service IAW C47 and 1 C51. The RO will place rod control to manual and restore Tave to Tref. The SRO will determine T.S.

requirements.

After the NI failure is addressed, Instrument Bus 1 13 loses power. The loss of Bus 1 13 compounded with N44 being 00s causes an automatic reactor trip. The crew will respond IAW 1 E-0 and transition to 1 ES-0.1. The SS will direct performance of 1 C20.8 AOPl to restore power to Instrument Bus 11 3 in conjunction with 1 ES-0.1.

After power is restored to Instrument Bus 113, 11 S/G Main Steam line break in containment.

The crew will transition back to 1 E-0. The BOP will recognize the failure of 11/12 MSIVs to auto close and manually perform the action using 1 E-0 Att. L. The crew will then transition to 1 E-2 to isolate the faulted SG and transition to 1 E-1. The scenario will be terminated when the crew transitions to 1 FR-P.l or upon termination of SI pumps in 1 ES-0.2.

Termination Criteria:

When the crew transitions to 1 FR-P.1 or upon termination of SI pumps in 1 ES-0.2.

Critical Tasks:

E-0 -- P: Manually close MSlVs before transition out of E-0.

E TCOA4: Control AFW flow within 38 minutes following a Reactor Trip.

(SW I 0-35 identified Time Critical Operator Action).

E-2 -- A: Isolate the faulted STEAM GENERATOR before transition out of E-2.

NUREG 1021, Revision 9 Supplement 1

Appendix D Scenario Outline Form ES-D-1 Facility: -Prairie Island Scenario No.:

3 Op-Test No.:

1 Examiners:

Operators:

6 Event Description Increase Power to Point of Adding Heat.

12 Condensate pump will be started to replace 11 for Filter Demin Support.

122 Instrument Air Compressor trips, 123 Instrument Air Compressor fails to auto start.

RP12 C (BOP)

PZR Heater B/U Group 1 B Breaker Trip.

T.S. LCO 3.4.9 Condition B.

PZR pressure channel (PT-431) fails High.

T.S. LCO 3.3.1 Condition A and Table 3.3.1-1 Functions 6, 8a, 8b.

T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 Function Id.

T.S. LCO 3.4.1.a Condition A.

12 S/G Tube Rupture (on trip).

SI signal CL System Fails.

NUREG 1021, Revision 9 Supplement 1

Scenario 3 Summary The crew assumes the duty with power at 1 x l 0-8 amps and stable. 13 Charging Pump is 00s.

The crew is directed to increase power to the POAH. During the power rise the BOP will start 12 Condensate pump and stop 11 Condensate pump.

After the crew has completed the power increase, 122 Air Compressor trips with the 123 A/C failed to auto start. The BOP will recognize that 123 Air Compressor does not automatically start and will manually start 123 Air Compressor. The crew responds IAW C47 and C34 AOP1.

After the plant is stabilized, PZR Heater B/U Group 1 B Breaker will trip. The RO will co-ordinate with the BOP to align the heater group to the alternate power supply and restore the heaters to operation IAW 1 C20.6. The SRO will determine T.S. requirements.

After the plant is stabilized, the controlling pressurizer pressure channel 1 P-431 fails High. The RO will respond to stabilize RCS pressure. The RO and BOP will coordinate to swap the controlling pressurizer channel to another channel IAW C47 and 1 (251.3. The SRO will determine T.S. requirements.

After the plant is stabilized, 12 S/G will suffer a Tube Rupture. The crew will trip the reactor and enter 1 E-0. The BOP will recognize the CL systems fails to respond to the SI signal and will manually align the system IAW 1 E-0 Att L. The crew will transition to 1 E-3. The scenario will be terminated upon securing SI pumps in 1 E-3.

Termination Criteria:

Upon securing SI pumps in 1 E-3.

Critical Tasks:

E TCOA4: Control AFW flow within 38 minutes following a Reactor Trip. (SWI 0-35 identified Time Critical Operator Action).

E-3 -- A: Isolate feedwater flow into and steam flow from the ruptured Steam Generator before a transition to ECA-3.1 occurs.

E B: Establish/maintain an RCS temperature so that transition from E-3 does not occur because of the inability to maintain required subcooling or such that an extreme or severe challenge to the Subcriticality and/or the Integrity CSF occurs.

E-3 -- C: Depressurize RCS to meet SI termination criteria prior to overfilling the ruptured Steam Generator.

E-3 -- D: Terminate SI prior to overfilling the ruptured Steam Generator.

NUREG 1021, Revision 9 Supplement 1

Appendix D Scenario Outline Form ES-D-1 Event Type*

Facility: -Prairie Island Scenario No.:

4 Op-Test No.:

1 Event Description 1

2 3

4 5

6 NIA ED1 7B, DI-46924T RX216 RX05C

TC12, RP07A,
RP07B, Dl-464478, Dl-464471 FW34A R (RO)

(SRol Reduce Power to 90% for 12 Heater Drain Pump brush checks.

At 95% the BOP remove 12 Heater Drain Pump from service.

C (SRO, RO)

TS (SRO)

M (All)

Loss of Safeguards Bus 16.

T.S. LCO 3.8.9 Condition A and T.S. 3.8.4 Condition A.

Turbine Trip with ATWS.

C (BOP)

TS (SRO)

I (SRO, RO)

TS (SRO) 12 S/G Pressure Instrument PT-478 Fails High, causing 12 S/G PORV to open.

T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 Function 1 e.

Tavg Instrument Fails High.

T.S. LCO 3.3.1 Condition A and Table 3.3.1-1 Functions 6, 7.

T.S. LCO 3.3.2 Condition A and Table 3.3.2-1 Function 4d.

NUREG 1021, Revision 9 Supplement 1 C (BOP) 11 TDAFW Fails to Auto start.

Scenario 4 Summary The crew assumes the duty at 100% power and stable. 1 1 MDAFW pump and 13 Heater Drain pump are 00s. The crew will Reduce Power to 90% to remove 12 Heater Drain pump from service for brush inspections.

After the power reduction, Loss of Safeguards Bus 16 occurs. D2 D/G starts and does not auto load. The RO will stabilize RCP seal injection flows. The BOP will restore power to Bus 16 by restoring power from CT-11 IAW 1 C20.5 AOP2. The SRO will determine T.S. requirements.

After Bus 16 is restored, 12 S/G Pressure instrument PT-478 Fails high causing 12 S/G PORV to open. The BOP will recognize the failure and manually close 12 S/G PORV. The SRO will determine T.S. requirements.

After the plant is stabilized, RCS Loop Thot RTD fails high causing Tavg and Delta T channels to indicate high. The RO will take manual control of charging and rod control. The BOP will coordinate with the RO to take the appropriate channel to defeat. The SRO will determine T.S.

requirements.

After the plant is stabilized, a spurious turbine trip signal occurs. The turbine will trip but the reactor does not. The Crew will enter 1 E-0 and transition immediately to 1 FR-S.l. The RO will recognize the ATWS and attempt to manually trip the Reactor, but will be unsuccessful. Rods will be inserted and a boration commenced IAW 1 FR-S.1. The BOP will recognize the 11 TDAFW pump failed to automatically start and will manually start the pump. The scenario will be terminated upon successful tripping of the Reactor per 1 FR-S.l and transitioning back to 1 E-O.

Termination Criteria:

Upon completion of 1 FR-S.l and transition back to 1 E-0.

Critical Tasks:

E F: Establish and maintain 200 gpm AFW flow to the Steam Generator(s) before transition out of E-0, unless the transition is to FR-H.1, in which case the task must be initiated before RCPs are manually tripped in accordance with step 2 of FR-H.l.

FR-S.l - C: Insert negative reactivity into the core by inserting rods or establishing emergency boration flow to the RCS during the performance of FR-S.1.

NUREG 1021, Revision 9 Supplement 1

P-)

ES-401 Record of Rejected WAS Form ES-401-4 s 211 s 211 s3 It I

007 A2.06 007 A2.03 2.2.1 8 No procedural direction. Replaced with 007 A2.03.

Knowledge area covered by another topic. Replaced with 01 2 A2.06.

No SRO actions. Replaces with 2.2.21.

Reason for Rejection not support an SRO question Replaced with 034

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