Text

Outline for the Prairie Island Initial Examination - August 2002
	ML023030539
Person / Time
Site:	Prairie Island
Issue date:	08/12/2002
From:	Hironori Peterson; NRC/RGN-III/DRS/OLB
To:	;
References
	-nr
	Download: ML023030539 (51)
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OUTLINE FOR THE PRAIRIE ISLAND INITIAL EXAMINATION - AUGUST 2002

Examination Outline Quality Checklist Form ES-201-2 (R8,S1)

Faciliy Date of Examination:

Initals Item Task Description a

b" Ci

1.

a. Verify that the ouline(s) ft(s) the appropriate model per ES-401.

W R

b. Assess whether the outline was systemnatically and randomly prepared in accordance with Section D. 1 of 1

I ES-401 and whether all WA categories we appro~

ilyped.

T T

c. Assess whether the oulne over-emphasizes any systems, evolutions, or generic topics.

E N

d. Assess whether thejustificaton for deselected or rejected KJA statements re appropriate.

k-(

"2.

a. Using Form ES-301 -5. verify that the proposed scenario sets cover the required number of normal evolutions. instrumnent and component failures, and major tranisienft.

S I

b. Assem whether there ae enough scenario sets (and spares) to test the projected number and mix of M

applicants in accordance with the expected crew conpqsiton and rotation schedule without compromitsing exam integrity-enaure each applicant can be tested using at leat one new or significantly modified scenaio, that no scenarios are duplicated from the applk

's audit test(s)*, and scenarios will not be repeated over success"vedays.

c To the extent possible, assess whether the oL(.s) conform(s) wi th qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks.

W (2) no more than 30% of the test material is repeated from the last NRC examination,

/ (3)* no tasks are duplicated from the applicat'saudit test(s), and T

(4) no more than 80% of any operating test Is taken directly from the licensee's exam banks.

b. Verify that:

(1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task Is conducted in a law-power or shutdown condition, (3) 40% of the tasks require the applicant to Imrplemrent an alternate path procedure, (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and.

(5) the in-plant wallk-hroug requires the applicant to enter the RCA.

c. Verify that the required administrative topics are covered, with emphasis on performance-based activities.

64_

d. Determine if there ae enough different outlines to test the proieced number and mix of applicants and ensure that no Iems are duplicated on successive days.

4

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate examn secr.tion E

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

N E

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

A

d. Check for duplication and overlap among exam sections.

e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job levl (RO or SRO).

6e a Printed Name / Signature Date a Authors (LET)

Nicholas Valos & Charles PhftS / Xq/

10 b Examiner of Record Bruce Palai" c NRC Chief Examiner (#)

Hironori Peterson

?3 0 d NRC Supervisor David Hills/

Note:

Not applicable for NRC-developed examinations. LET - licensing examiner trainee 1 Independent NRC review* initial Iems in Column "c;" chief examiner concurrence required ES-201 I

I

ES-401 PWR RO Examination Outline Form ES-401 -4 (R8, Si)

Facility: Prairie Island Date of Exam: 08/12/02 Exam Level:

RO K/A Category Points Tier Group Point K

K K

K KI K A

A A

A G

Total 1

2 3

4 5

6 1

2 3

4

1.

1 2

1 3

3 4

3 16 Emergency &

Abnormal 2

3 3

2 3

17 Plant 3

1 1

0 0

0 1

3 Evolutions Tier

[

7 36 Totals 1

2 2

3 2

2 2

1 23

2.

Plant 2

3 1

2 3

1 1

1 3

2 1

2 20 Systems 3

1 0

1 1

1 0

1 1

1 8

Tier 6

3 5

6 5

3 5

5 5

4 4

51 Totals I II

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 1_

1__ 1 13 3

3 3

4 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

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

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

PWR RO Examination Outline Form ES-401-4 (R8, S1)

ES-401

ES-401 PWR RO Examination Outline Form ES-401-4 (R8. Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function KI K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000005 Inoperable/Stuck Control Rod / I X

AA1.04 Reactor and turbine power 3.9/3.9 1

000015/17 RCP Malfunctions / 4 X

AA2.10 When to secure RCPs on loss of cooling or seal injection 3.7/3.7 1

BW/E09; CE/A13; W/EO9&E10 Natural Circ. / 4 X

2.4.7 Knowledge of event based EOP mitigation strategies 3.1/3.8 1

000024 Emergency Boration / 1 X

AK1.04 Low temperature limits for boron concentration 2.8/3.6 1

000026 Loss of Component Cooling Water / 8 X

AA2.02 The cause of possible CCW loss 2.9/3.6 1

000027 Pressurizer Pressure Control System X

AK3.03 Actions contained in EOP for PZR PCS malfunction 3.7/4.1 1

Malfunction / 3 000040 (BW/E05; CE/E05; W/E12) Steam Line X

EA1.3 Desired operating results during abnormal and emergency 3.4/3.9 1

Rupture - Excessive Heat transfer / 4 conditions CE/Al 1; W/E08 RCS Overcooling - PTS / 4 X

EA2.1 Facility conditions and selection of appropriate procedures 3.4/4.2 1

during abnormal and emergency operations I

000051 Loss of Condenser Vacuum / 4 X

2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 1

000055 Station Blackout / 6 X

EK1.02 Natural circulation cooling 4.1/4.4 1

000057 Loss of Vital AC Elec. Inst. Bus / 6 X

AK3.01 Actions contained in EOP for loss of vital ac electrical 4.1/4.4 1

instrument bus 000062 Loss of Nuclear Service Water / 4 X

AK3.02 The automatic actions (alignments) within the nuclear service 3.6/3.9 1

water resulting from the actuation of the ESFAS 000067 Plant Fire On-site / 9 X

AA1.07 Fire alarm reset panel 2.9/3.0 1

000069 (W/E14) Loss of CTMT Integrity / 5 X

EA2.2 Adherence to appropriate procedures and operation within the 3.3/3.8 1

limitations in the facility's license and amendments 000074 (W/E06&E07) Inad. Core Cooling / 4 X

2.4.6 Knowlege of symptom based EOP mitigation strategies 3.1/4.0 1

000076 High Reactor Coolant Activity / 9 X

AK2.01 Process radiation monitors 2.6/3.0 1

3K/A CategoryTotals:

121113 314 3 1 Group Point Total:

I 16

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 IK2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000001 Continuous Rod Withdrawal / 1 X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

pIarameters whiich are entry-level conditions for emergency and abnormal operating procedures 0o003 Dropped Control Rod / 1 x

AK1.16 MTC 2.9/3.2 1

000008 Pressurizer Vapor Space Accident / 3 x

AK2.02 Sensors and detectors 2.7/2.7 1

000009 Small Break LOCA / 3 X

EK3.28 Manual ESFAS initiation requirements 4.5/4.5 1

W/E04 LOCA Outside Containment / 3 X

EA1.3 Desired operating results during abnormal and emergency 3.8/4.0 1

situations BW/E08; W/E03 LOCA CooldowritDepress. / 4 X

EA2.2 Adherence to,apropnate procedures and operation within the 3.5/4.1 1

limitations in the faci is license and amendments W/E 11 Loss of Emergency Coolant Recirc. /4 X

2.1.2 Knowledge of operator responsibilities duunng all modes of plant 3.0/4.0 1

operation 000022 Loss of Reactor Coolant Makeup /2 X

AK1.01 Consequences of thermal shock to RCP seals 2.8/3.2 1

000025 Loss of RHR System / 4 X

AK2.01 RHR heat exchangers 2.9/2.9 1

000033 Loss of Intermediate Range NI / 7 X

AK3.01 Termination of startup following loss of intermediate rannge 3.2/3.6 1

instrumentation 000037 Steam Generator Tube Leak / 3 X

AA1. 11 PZR level indicator 3.4/3.3 1

000038 Steam Generator Tube Rupture / 3 x

EA2.13 Magnitude of rupture 3.1/3.7 1

BW/E04; W/E05 Inadequate Heat Transfer - Loss X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

of Secondary Heat Sink / 4 parameters wlich are entry-level conditions for emergency and abrnormal operating procedures 000059 Accidental Liquid RadWaste Rel. / 9 X

AK1.01 Types of radiation, their units of intensity and the location of 2.7/3.1 1

the sourcbs of radiation in a nuclear power plant 000060 Accidental Gaseous Radwaste Rel. / 9 X

AK2.02 Auxiliary building ventilation system 2.7/3.1 1

000061 ARM System Alarms / 7 X

AK3.02 Guidance contained in alarm response for ARM system 3.4/3.6 1

W/E16 High Containment Radiation / 9 X

EA1.3 Desired operating results during abnormal and emergency 2.9/3.3 1

situations K/ACategory PointTotals:

J3

[3 1I I3 32 13 ( GroupPointTotal:

17

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier I/Group 3 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000065 Loss of Instrument Air / 8 X

2.4.2 Knowledge of system set points. interlocks and automatic 3.9/4.1 1

actions associated with EOP entry conditions W/E13 Steam Generator Over-pressure /4 X

EK1.2 Normal abnormal and emergency operating procedures 3.0/3.3 1

associated with (Steam Generator Overpressure)

W/E15 Containment Flooding / 5 X

EK2.1 Components, and functions of control and safety systems.

2.8/2.9 1

including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4-4-l--4-4-4 I

t-t-I-I-t-+-t 4

i-4-A-i-4-+-4 II 4

I I

L K/A Category Point Totals:

I 1 I 0

1 lo J0 J0 1 Group Point Total:

1 3

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Si)

Plant Sytems - Tier /Group 1 System # / Name KI K2 K3 K4 K5 K6 A1 A2 A3 A4 G

K/A Topic(s)

Im Points 001 Control Rod Drive X

X K104 RCS 3.3/3.4 2

K4.07 Rod stops 3.7/3.8 003 Reactor Coolant Pump X

X K2.02 CCW pumps 2.5/2.6 2

K5.04 Effects of RCP shutdown on 3.2/3.5 secondary parameters, such as steam pressure, steam flow, and feed flow 004 Chemical and Volume Control X

X K3.08 RCP seal injection 3.6/3.8 2

K6.13 Purpose and function of the 3.1/3.3 borationldilution batch controller 013 Engineered Safety Features Actuation X

X K4,13 MFW isolation/reset 3,7/3.9 2

A1.06 RWST level 3:6/3:9:]

015 Nuclear Instrumentation X

X K2.01 NIS channels, components, and 3.3/3.7 2

interconnections K5.02 Discrimination/compensation 2.7/2.9 operation 017 In-core Temperature Monitor X

K6.01 Sensors and detectors 2.7/3.0 1

022 Containment Cooling X

A1.01 Containment temperature 3.6/3.7 1

056 Condensate X

A2.04 Loss of condensate pumps 2.6/2.8 1

059 Main Feedwater X

X A1.03 Power level restrictions for operation 2.7/2.9 2

of MFW pum ps and valves A3.06 Feedwater isolation 3.2/3.3 061 Auxiliary/Emergency Feedwater X

X K4.07 Turbine tnp. including overspeed 3.1/3.3 2

A2.05 Automatic control malfunction 3.1/3.4 068 Liquid Radwaste X

X K.02 Waste Gas Vent Header 2.5/2.6 2

A3.02 Automatic isolation 3.6/3.6

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Sl)

Plant Systems - Tier 2/Group 1 System #/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topics)

Imp.

Points 071 Waste Gas Disposal X

X K5.04 Relationship of hydrogenVoxygen 2.5/3.1 2

concentrations to flammiabilil A4.30 Water drainage from the WGDS decay 2.9/2.6 tanks 072 Area Radiation Monitoring X

X K3.02 Fuel handling operations 3.1/35 2

2.4.4 Ability to recognize abnormal 4.0/4-3 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating I procedures K/AACategory PointTotals:

12 2

2 2 13 I2 3

12

[2 2

i1 GroupPointTotal:

_23

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Si)

Plant Systems - Tier 2-/Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 002 Reactor Coolant X

K1.07 Reactor vessel level indication 3.5/3.7 1

system 006 Emergency Core Cooling X

K2.01 ECCS pumps 3.6/3.9 1

010 Pressurizer Pressure Control X

K3.01 RCS 3.9/3.9 1

011 Pressurizer Level Control X

K4.02 PZR level controller 3.3/3.4 1

012 Reactor Protection X

K5.01 DNB 3.3/3.8 1

014 Rod Position Indication X

K4.06 Individual and group 3.4/3.7 1

misalignment 016 Non-nuclear Instrumentation X

A2.02 Loss of power supply 2.9/3.2 1

026 Containment Spray x

A2.05 Failure of chemical addition 3.7/4.1 1

tanks to inject 029 Containment Purge A3.01 CPS isolation 3.8/4.1 1

033 Spent Fuel Pool Cooling X

2.1.27 Knowledge of system purpose 2.8/2.9 1

and or function 035 Steam Generator X

A4.05 Level control to enhance natural 3.8/4.0 1

circulation 039 Main and Reheat Steam X

K1.02 Atmospheric relief dump valves 3.3/3.3 1

055 Condenser Air Removal X

K1.06 PRM system 2.6/2.6 1

062 AC Electrical Distribution X

K3.03 DC system 3.7/3.9 1

063 DC Electrical Distribution X

K4.04 Trips 2.6/2.9 1

064 Emergency Diesel Generator X

K6.07 Air receivers 2.7/2.9 1

073 Process Radiation Monitoring X

A1.01 Radiation levels 3.2/3.5 1

075 Circulating Water X

2.4.31 Knowledge of annunciator 3.3/3.4 1

alarms and indications, and use of the response instructions 079 Station Air X

I A2.01 Cross-connection with IAS 2-9/3.2 1

086 Fire Protection X

A3.01 Starting mechanisms of fire 2.9/3 3 1

water pumps

____CategoryPointTotals:

3 11 213 1

[1 3

2 1i 2

Group Point Total:J 20

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S)

Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 005 Residual Heat Removal X

A4.02 Heat exchanger bypass flow control 3.4/3.1 1

027 Containment Iodine Removal x

2.1.32 Ability to explain and apply all 3.4/3.8 1

system limits and precautions 028 Hydrogen Recombiner and Purge Control X

K5.03 Sources of hydrogen within 2.9/36 1

containment 034 Fuel Handling Equipment X

A1.02 Water level in the refueling canal 2.9/3.7 1

041 Steam Dump/Turbine Bypass Control X

K3.02 RCS 3.8/3.9 1

076 Service Water K4.02 Automatic start features associated 2.9/3.2 1

with SWS pump controls 078 Instrument Air X

A3.01 Air pressure 3.1/3.2 1

103 Containment X

K1.03 Shield building vent system 3.1/3.5 1

K/A Category Point Totals:

110 1

o1 1

0 11 0.1 1I1 I 1 Group Point Total:

8 Plant-Specific Priorities System / Topic Recommended Replacement for...

Reason Points Plant-Specific Priority Total: (limit 10) 1

Facility: Prairie Island Date of Exam: 08/12/02 Exam Level:

RO I Category K/A #

Topic Imp.

Points 2.1.1 Knowledge of conduct of operations 3.7/3.8 1

requirements Conduct of 2.1.3 Knowledge of shift turnover practices 3.0/3.4 1

Operations 2.1.29 Knowledge of how to conduct and verify valve 3.4/3.3 1

lineups Total 3

2.2.12 Knowledge of surveillance procedures 3.0/3.4 1

2.2.13 Knowledge of tagging and clearance 3.6/3.8 1

procedures Equipment 2.2.30 Knowledge of RO duties in the control room 3.5/3.3 1

Control during fuel handling such as alarm from fuel handling area, communication with fuel storage facility, systems operated from the control board in support of fueling operations, and supporting instrumentation Total 3

2.3.1 Knowledge of 10CFR: 20 and related facility 2.6/3.0 1

radiation control 2.3.2 Knowledge of facility ALARA program 2.5/2.9 1

Radiation 2.3.11 Ability to control radiation releases 2.7/3.2 1

Control Total 3

2.4.2 Knowledge of system set points, interlocks 4.3/4.6 1

and automatic actions associated with EOP entry conditions Emergency 2.4.6 Knowledge of symptom based EOP mitigation 3.1/4.0 1

Procedures/

strateges Plan 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 1

2.4.20 Knowledge of operational implications of EOP 3.3/4.0 1

warnings, cautions, and notes Total 4

Tier 3 Point Total (RO/SRO) 13 Form ES-401-5 (R8, S1)

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

Facility:

Date of Exam:

Exam Level:

-C-)

K/A Category Points Tier Group Point K

K K

K A

A2 A

A G

Total 1

2 3

4 5

6 1

3 4

Abnormal 2

2 32

.'-; ::'*: ~2 4

3 16 Plant 3

0 0

1 4

1 1

0,3 Plan 0

0 1

10 3.*'

Evolutions Tier 5

6 7

7 11 7

43 Totals 1

2 2

1 2

2 2

22 1

19

2.

Plant 2

2 1

2 221 1

17 Systems 3

0 0

0 1

1 1

1 0

0 4

Tier 4

3 3

4 5

5 5

3 2

40 Totals I

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 17 4

4 4

5 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

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

5.

The shaded areas are not applicable to the category/tier.

6.

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8. S11)

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, S1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function Ki K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000001 Continuous Rod Withdrawal / 1 X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

parameters which are entry-level conditions for emergency and abnormal operating procedures 41.10, 43.2 000003 Dropped Control Rod / 1X AK 1.16 MTC 41.8, 41.10 2.9/3.2 1

000005 Inoperable/Stuck Control Rod / 1 X

AA1.04 Reactor and turbine power 41.7 3.9/3.9 1

000011 Large Break LOCA / 3 EA2.06 That fan is in slow speed and dampers are in accident mode 3.7/4.0 1

durng LOCA 43.5 W/E04 LOCA Outside Containment / 3 X

EAl.3 Desired operating results during abnormal and emergency 3.8/4.0 1

situations 41.7 W/EO1 & E02 Rediagnosis & SI Termination / 3

/

EK2.2 Facilitys heat removal systems, including primary coolant.

3.5/3.8 1

emergency coolant, the decay heat removal systems, and relations between te proper operation of these systems to the operation of the facility. 41.7 000015/17 RCP Malfunctions / 4 X

AA2.10 When to secure RCPs on loss of cooling or seal injection 43.5 3.7/3.7 1

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X

2.4.7 Knowledge of event based EOP mitigation strategies 43.5 3.1/3.8 1

000024 Emergency Boration / 1 X

AK1.04 Low temperature limits for boron concentration 41.8 41.10 2.8/3.6 1

000026 Loss of Component Cooling Water / 8 X

AA2.02 The cause of possible CCW loss 43.5 2.9/3.6 1

000029 Anticipated Transient w/o Scram / 1

/

EK3.12 Actions contained in EOP for ATWS 3.1/3.1 1

000040 (BW/E05; CE/E05 W/E12) Steam Line X

EA1.3 Desired operating results dunng abnormal and emergency 3.4/3.9 1

Rupture - Excessive Heat transfer/ 4 conditions 41.3 CE/Al1l; W/E08 RCS Overcooling - PTS / 4 X

EA2.1 Facility conditions and selection of appropnate procedures during 3.4/4.2 1

abnormal and emergency operations 43.5 000051 Loss of Condenser Vacuum / 4 X

2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 1

000055 Station Blackout / 6 X

EK1.02 Natural circulation cooling 4.1/4.4 1

000057 Loss of Vital AC Elec. Inst. Bus / 6 X

AK3.01 Actions contained in EOP for loss of vital ac electncal instrument 4.1/4.4 1

bus 000059 Accidental Liquid RadWaste Rel. / 9

/

AK2.02 Radioactive Gas Monitors 3.6/3.9 1

000062 Loss of Nuclear Service Water / 4 X

/

AK3.02 The automatic actions (alignments) within the nuclear service 3.6/3.9 1

water resulting from the actuation of the ESFAS AA2.04 The normal values an upper limits for the tempertures of the 2.5/2.9 1

components cooled by SWS 000067 Plant Fire On-site / 9 X

AA1.07 Fire alarm reset panel 2.9/3.0 1

000068 (BWIA06) Control Room Evac. /8

,/

AK3.08 Trip of the MFW and necessary Condensate pumps 2.4/2.7 1

000069 (W/E 14) Loss of CTMT Integnty / 5 X

EA2.2 Adherence to appropnate procedures and operation within the 3.3/3.8 1

limitations in the facility s license and amendments

000074 (W/EO6&E07) Inad. Core Cooling / 4 X

2.4.6 Knowlege of symptom based EOP mitigation strategies 3.1/4.0 1

BW/E03 Inadequate Subcooling Margin / 4 N/A 000076 High Reactor Coolant Activity / 9 x

AK2.01 Process radiation monitors 2.6/3.0 1

BW/A02&A03 Loss of NNI-XJ'Y / 7 N/A K/A CateoryTotals:

13

[3 J4 14 J6 14 [ Group Point Total:

I 24

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8. S1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 A

A2 G

K/A Topic(s)

Imp.

Points 1

1 000007 (BW/E02&Et10: CE/E02) Reactor Trip -

EA2.06 Occurrence of a reactor trip 4.3/4.5 1

Stabilization - Recovery / 1 1_____________________________

BW/A01 Plant Runback / 1 N/A BW/A04 Turbine Trip / 4 N/A 000008 Pressurizer Vapor Space Accident / 3 X

AK2.02 Sensors and detectors 2.7/2.7 1

000009 Small Break LOCA / 3 X

EK3.28 Manual ESFAS initiation requirements 4.5/4.5 1

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X

EA2.2 Adherence to appropriate procedures and operation within the 3.5/4.1 1

limitations in the facility s license and amendments W/E1 1 Loss of Emergency Coolant Recirc. / 4 X

2.1.2 Knowledge of operator responsibilities during all modes of plant 3.0/4.0 1

operation 000022 Loss of Reactor Coolant Makeup / 2 X

AK.01 Consequences of thermal shock to RCP seals 2.8/3.2 1

000025 Loss of RHR System / 4 X

AK2.01 RHR heat exchangers 2.9/2.9 1

000027 Pressurizer Pressure Control System Randomly deleted to acquire the correct number of questions Malfunction / 3 000032 Loss of Source Range NI / 7

/

AA2.06 Confirmation of reactor trip 3.9/4.1 1

000033 Loss of Intermediate Range NI / 7 X

AK3.01 Termination of startup following loss of intermediate range 3.2/3.6 1

instrumentation 000037 Steam Generator Tube Leak / 3 X

AAI. 11 PZR level indicator 3.4/3.3 1

000038 Steam Generator Tube Rupture / 3 X

EA2.13 Magnitude of rupture 3.1/3.7 1

000054 (CEJEO6) Loss of Main Feedwater / 4

/

AA1.01 AFW Controls, including the use of alternate AFW sources 3.2/3.1 1

BW/E04; W/E05 Inadequate Heat Transfer - Loss X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

of Secondary Heat Sink / 4 parameters which are entry-level conditions for emergency and abnormal operating procedures 000058 Loss of DC Power / 6 AK1.01 Battery charger equipment and instrumentation 2.8/3.1 1

000060 Accidental Gaseous Radwaste Rel. / 9 X

AK2.02 Auxiliary building ventilation system 2.7/3.1 1

000061 ARM System Alarms / 7 Randomly deleted to acquire the correct number of questions W/E 16 High Containment Radiation / 9 Randomly deleted to acquire the correct number of questions 000065 Loss of Instrument Air / 8 X

2.4.2 Knowledge of system set points, interlocks and automatic actions 3.9/4.1 1

associated with EOP entry conditions CE/E09 Functional Recovery N/A K/A Category Point Totals:

12 3 12 2

4 13 I Group Point Total:

16

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000028 Pressurizer Level Malfunction / 2

/

AA2.11 Leak in PZR 3.2/3.6 1

000036 (BW/A08) Fuel Handling Accident / 8/

AA1.02 ARM system 3.1/3.5 1

000056 Loss of Off-site Power / 6

/

K3.02 actions contained in EOP for Loss of offsite power 4.4/4.7 1

BW/E13&E14 EOP Rules and Enclosures N/A BW/A05 Emergency Diesel Actuation / 6 N/A BW/A07 Flooding / 8 N/A CE/A16 Excess RCS Leakage/2 N/A W/E 13 Steam Generator Over-pressure / 4 Randomly deleted to acquire the correct number of questions W/E 15 Containment Flooding / 5 Randomly deleted to acquire the correct number of questions l-t-t-f-t-4-+

I I

I tt-t--l-I-t I

I I

I t-t-t-f-t-+-+

I I

i i

i iI I

K/ACategoryPointTotals:

1 1

I1 I

Group Point Total:

3

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, SI)

Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 Al A

A3 A4 G

K/A Topic(s)

Imp Points 2

001 Control Rod Drive X

K1.04 RCS 3.3/3.4 1

003 Reactor Coolant Pump X

K2.02 CCW pumps 2.5/2.6 1

004 Chemical and Volume Control X

X K3.08 RCP seal injection 3.6/3.8 1

K6.13 Purpose and function of the 3.1/3.3 1

boratioridilution batch controller 013 Engineered Safety Features Actuation X

A1.06 RWST level 3.6/3.9 1

014 Rod Position Indication X

K4.06 Individual and group misalignment 3.4/3.7 1

015 Nuclear Instrumentation X

X K2.01 NIS channels, components, and 3.3/3.7 1

interconnections K5.02 Discrimination/compensation operation 2.7/2.9 1

017 In-core Temperature Monitor x

K6.01 Sensors and detectors 2.7/3.0 1

022 Containment Cooling X

A.01 Containment temperature 3.6/3.7 1

025 Ice Condenser N/A 026 Containment Spray X

A2.05 Failure of chemical addition tanks to 3.7/4.1 1

inject 056 Condensate X

A2.04 Loss of condensate pumps 2.6/2.8 1

059 Main Feedwater X

A3.06 Feedwater isolation 2.7/2.9 1

061 Auxiliary/Emergency Feedwater X

A2.05 Automatic control malfunction 3.1/3.3 1

063 DC Electrical Distribution X

K4.04 Trips 2.6/2.9 1

068 Liquid Radwaste X

X K1.02 Waste Gas Vent Header 2.5/2.6 1

A3.02 Automatic isolation 3.6/3.6 1

071 Waste Gas Disposal X

A4.30 Water drainage from the WGDS decay 2.9/2.6 1

tanks 072 Area Radiation Monitoring X

2.4.4 Ability To recognize abnormal 3.1/3.5 1

indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures KA Category PointTotals:

I2 12 I1 I2 I12 12 1212 12 I1 I Group Point Total:

19

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, $1)

Plant Systems - Tier 2/Group 2 System 0 / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 002 Reactor Coolant X

K1.07 Reactor vessel level indication system 3.5/3.7 1

006 Emergency Core Cooling X

K2.01 ECCS pumps 3.6/3.9 1

010 Pressurizer Pressure Control X

K3.01 RCS 3.8/3.9 1

011 Pressunzer Level Control X

K4.02 PZR level controller 3.3/3.4 1

012 Reactor Protection X

K5.01 DNB 3.3/3.8 1

016 Non-nuclear Instrumentation X

A2.02 Loss of power supply 2.9/3.2 1

027 Containment Iodine Removal X

2.1.32 Ability to explain and apply all system 3.4/3.8 1

limits and precautions 028 Hydrogen Recombiner and Purge Control X

K5.03 Sources of hydrogen within 2-9/3.6 1

containment 029 Containment Purge X

A3.01 CPS isolation 3.8/4.1 1

033 Spent Fuel Pool Cooling Randomly deleted to acquire the correct number of questions 034 Fuel Handling Equipment X

A1.02 Water level in the refueling canal 2.9/3.7 1

035 Steam Generator X

A4.05 Level control to enhance natural 3.8/4.0 1

circulation 039 Main and Reheat Steam X

K1.02 Atmosphenc relief dump valves 3.3/3.3 1

055 Condenser Air Removal Randomly deleted to acquire the correct number of questions 062 AC Electrical Distribution X

K3.03 DC system 3.7/3.9 1

064 Emergency Diesel Generator X

K6.07 Air receivers 2.7/2.9 1

073 Process Radiation Monitoring X

A1.01 Radiation levels 3.2/3.5 1

075 Circulating Water Randomly deleted to acquire the correct number of questions 079 Station Air X

A2.01 Cross-connection with IAS 2.9/3.2 1

086 Fire Protection X

A3.01 Starting mechanisms of fire water 2.9/3.3 1

pumps 103 Containment Randomly deleted to acquire the correct number of questions K/ACategory PointTotals:

12 I

1 2 1 1 2 11 12 12 12 V 11 1 Group Point Total:

I 17

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8. Si)

Plant Systems - Tier 2/Group 3 System N / Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 005 Residual Heat Removal Randomly deleted to acquire the correct number of questions 007 Pressurizer Relief/Quench Tank

/

K5.02 Method of forming a steam bubble in 3.1/3.4 1

the PZR 008 Component Cooling Water A/

Al.02 CCW temperature 2.9/3.1 1

041 Steam DumprTurbine Bypass Control Randomly deleted to acquire the correct number of questions 045 Main Turbine Generator A2.17 Malfunction of electrohydraulic 2.7/2.9 1

control 076 Service Water Randomly deleted to acquire the correct number of questions 078 Instrument Air X

_A3.01 Air pressure 3.1/3.2 1

K/A Category Point Totals:

1 1

Group Point Total T 4 Plant-Specific Pnorities System /Topic Recommended Replacement for...

Reason Points

1.

.1 1

4.

J.

+

4 4

4

+

4

+

4 4

4.

t

+

4

4.

+

4.

I I.

I__

J.

Plant-Specific Priority Total: (limit 10)

.L

Facility: Prairie Island Date of Exam: 08/12/02 Exam Level:

RO Category K/A #

Topic Imp.

Points 2.1.6 Ability to supervise and assume a 2.1/4.3 1

management role during plant transients and upset conditions Conduct of 2.1.10 Knowledge of conditions an limitations in the 2.7/3.9 1

Operations facility license 2.1.22 Ability to determine Mode of Operations 2.8/3.3 1

2.1.33 Ability to recognize indications for system 3.4/4.0 1

operating parameters which are entry-level conditions for technical specifications Total 4

2.2.6 Knowledge of the process for making 2.3/3.3 1

changes in procedures as described in the safety analysis report 2.2.22 Knowledge of limiting conditions for 3.4/4.1 1

Equipment operations and safety limit Control 2.2.28 Knowledge of new and spent fuel movement 3.5/3.3 1

procedures 2.2.26 Knowledge of refueling administrative 2.5/3.7 1

requirements Total 4

2.3.1 Knowledge of 10CFR: 20 and related facility 2.6/3.0 1

radiation control 2.3.4 Knowledge radiation exposure limits and 2.5/3.1 1

Radiation contamination control, ihcluding permissible Control levels in excess of those authorized 2.3.11 Ability to control radiation releases 2.7/3.2 1

2.3.6 Knowledge of the requirements for reviewing 2.1/3.1 1

and approving release permits Total 4

2.4.1 Knowledge of EOP entry conditions and 4.3/4.6 1

immediate action steps Emergency 2.4.22 Knowledge of the bases for prioritizing safety 3.0/4.0 1

Procedures/

functions during abnormal/emergency Plan operations 2.4.41 Knowledge of emergency action level 2.3/4.1 1

thresholds and classifications 2.4.44 Knowledge of emergency plan protective 2.1/4.0 1

action recommendations 2.4.28 Knowledge of procedures relating to 2.3/4.3 1

emergency response to sabotage Total 5

Tier 3 Point Total (RO/SRO) 17 U'-

Record of Rejected K/As (for RO exam)

Form ES-401-10 (R8. S1)

Tier / Group Randomly Selected K/A Reason for Rejection 1 / 1 W/E08 EA2.1 K/A was at the SRO level instead of at the RO level. Randomly selected another K/A, which was K/A W/E08 EA1.3 2 / 3 034 A1.02 Reactor Operators do NOT have any involvement with refueling operations. Randomly selected another K/A, which was K/A 007 K1.03 I

t I

I

¶ I

I ES-401

Facility:

Prairie Island Date of Examination:

8/12/02 Examination Level (circle one): RO / SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Conduct of Determine Maximum RCS vent time due to voids in RCS (JPM Admin 10) (K/A 2.1.23)

Operations

[DIRECT, SIMULATOR]

Conduct of Conduct CpntrQc Board Walkdown for Shift Turnover Operations

[ ldentify,8&bof,,8rrors on the Main Control Board]

[K/A 2.1.3] [3.0/3.4]

,4,tj,,I, 7

[NEW, SIMULATOR]

/

A.2 Equipment Review an Isolation for 11 TDAFW Pump and determine what if Control any TS LCO's will result from isolation of the equipment

[K/A 2.2.13, 2.1.24 ]

[ 3.1/3.3, 2.8/3.1 1

[NEW, CLASSROOM ]

-c /,A-,'1--

4i A.3 Radiation Give candidate initial condtons 1orn emncy on(ainment Control entry and have candidate identify what actions are necessary.

[K/A 2.3.10] [2.9/3.3]

[New, CLASSROOM]

A.4 Emergency Given specific initial conditions candidate must make emergency Action Levels classifications, PARS recommendations, and Fill out forms and PINGP 577 and PINGP 666 Classifications

[NEW, CLASSROOM ]

ES-301 Administrative Topics Outline Form ES-301-1 (R8, S1)

Facility:

Prairie Island Date of Examination:

Examination Level (circle one): RO / SRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Conduct of Conduct Control Board Walkdown for Shift Turnover Ope s

[Identify oferrors on the Main Control Board ][ K/A 2.1.3]

Oprtos

[3.0/3.4 ]-

6A

-J/

ev4

/

[NEW, SIMULATOR]

l Conduct of Perform alternate calorimetric (JPM RC-20, SP005B)

Operations

[K/A 2.1.23]

[ 3.9/4.0]

[DIRECT, SIMULATOR]

A.2 Equipment Prepare an Isolation for 11 TDAFW Pump Control

[K/A 2.2.13, 2.1.24 ]

[ 3.1/3.3, 2.8/3.1]

[NEW, CLASSROOM ]

A.3 Radiation Determine preparation requirements for emergency containment Control entry

[K/A 2.3.10]

[2.9/3.3]

[NEW, CLASSROOM ]

A.4 Emergency Phone in an Emergency Call to The NRC. The Red Phone will Plan not work, the operator must use another phone and call the NRC commercial number.

[K/A 2.4.12] [3.4/3/9]

[NEW, SIMULATOR ]

ES-301 Administrative Topics Outline Form ES-301-1 (R8. S1)

Control Room Systems and Facility Walk-Throuqh Test Outline Form ES-301-2 (R8, S1)

Facility:

Prairie Island Date of Examination:

Exam Level (circle one): RO / SRO(I) / SRO(U)

Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

Transfer SI to Recirculation with Failure of One D,A,L,S 2

Safeguard Train [ JPM B.1.d] [ K/A 006A4.02] [4.0/ 3.8]

b.

Raise #12 Accumulator Level D,S 3

[ JPM SI-2S, Rev 1 ] [ K/A 006A1.13 ][3.5/3.7 ]

c.

Lineup RHR and Commence Phase II Cooldown using D,L,S 4P RHR Pump [ JPM RH-5S ] [ K/A 005A4.01

[ 3.6/3.4 ]

d.

Perform "Quarterly Turbine Stop, Governor, and Intercept N,S 4S Valve Test" per SP 1054

[ K/A 045A4.01, 045A4.06 ] [3.1/2.9, 2.8/2.7]

e.

Manually Start D1 from the Control Room and Load onto D,S 6

Bus 15 [ JPM EG-4&5S [ K/A 064A4.06] [ 3.9/ 3.9 ]

f.

Perform NIS Power Range Daily Calibration with Thermal N,A,S 7

Power greater than Instrument Power per SP 1005

[ K/A 015A1.01 ][ 3.5, 3.8 ]

g.

Respond to an Abnormal Radiation Level During Waste D,A,S 9

Gas Release [ JPM WG-1SF ]

[ K/A 071A2.02, 071 A3.03] [3.3/3.6, 3.6/3.8]

B.2 Facility Walk-Through

a.

Manually Borate the RCS from Outside the Control Room D,A,R 1

[ JPM VC-19F-1 ] [ K/A 004A2.14 ] [ 3.8/3.9 ]

b.

Transfer Unit 1 Auxiliary Feedwater Pump Suction from N,L 4S the CST to Cooling Water per C28.1 AOP2

[ K/A 061K4.01 ] [ 4.1/4.2 ]

c.

Cross-Connect U2 to U1 CC System per 1C14 AOP3 N,R 8

[K/A 008A2.01 ][ 3.3, 3.6]

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA ES-301

Control Room Systems and Facility Walk-Throuqh Test Outline Form ES-301-2 (R8, S1)

Facility:

Prairie Island Date of Examination:

Exam Level (circle one): RO / SRO(l) / SRO(U)

Operating Test No.: 2002301 B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

b.

Raise #12 Accumulator Level D,S 3

[JPM SI-2S, Rev 1] [K/A 006A1.13] [3.5/3.7]

f.

Perform NIS Power Range Daily Calibration withThermal N,A,S 7

Power greater than Instrument Power per SP 1005

[ K/A 015A1.01 ] [ 3.5, 3.8]

B.2 Facility Walk-Through

a.

Manually Borate the RCS from Outside the Control Room D,A,R 1

[ JPM VC-19F-1 ] [ K/A 004A2.14 ] [ 3.8/3.9 ]

b.

Transfer Unit 1 Auxiliary Feedwater Pump Suction from N,L 4S the CST to Cooling Water per C28.1 AOP2

[K/A 061K4.01 ] [4.1/4.2]

c.

Cross-Connect U2 to Ul CC System per 1C14 AOP3 N,R 8

[ K/A 008A2.01 ] [ 3.3, 3.6 ]

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA ES-301

Apedi SearoOtln Fr E--

(R' 51 Facility: -Prairie Island Scenario No.:

1 Examiners:

Op-Test No.: 2001301 Operators:

Initial Conditions: BOL. recovery from reactor scram 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago, currently 15% power, D2 0OS, 12 AFW OOS. Place Steam Dump in Stm. Pressure mode Instrument maintenance is peforming troubleshooting on the Steam Dump Tave control mode Turnover: Recovery from Trip 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ago. Raise power to 100% at maximum rate, MSRs are already in service.

Event Malf.

Event Event No.

No.

Type*

Description 1

R (RO)

Raise reactor power 5-10%.

N RO will adjust reactivity by controlling boron concentration (BOP)

BOP will increase power by increasing turbine load, Lineup 13 Feedwater Heater drains for normal operation, Start one heater drain pump per 1C28.4, Heater Drains, and Shutdown the Condenser Spray System per 1C28.5.

2 I (RO)

PT 431 (PZR press) fails high - take manual control of (BOP) pressure and trip bistables (Simulator file number 97-03) 3 C (RO)

Charging pump trip-start another charging pump (Simulator file number 97-02) 4 I (BOP)

PT-484 failure high - Manual control to shut steam dumps (Simulator file 99-05) 5 C

11 Condensate pump motor stator HI temp - start a different (BOP) condensate pump 6

M (All)

Uncontrolled depressurization of both S/G's - steam leak on A steam header results in manual reactor trip (if not already tripped) and stuck open S/G PORV on B S/G - Gets to ECA 2.1 (Simulator file 97-03) 7 C

SI pump fails to start on SI signal-manually start SI pump (BOP)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 (R8, $1)

". (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

ApedxD cnro uln Fr SD1*

(8 Si Facility: -Prairie Island Scenario No.:

2 Examiners:

Op-Test No.:

Operators:

Initial Conditions:

Unit 1 is at 77% power. Load increase per C1.4 is in progress. Unit power was reduced to replace a bearing on 12 MFP. Equip OOS: 1 1TD AFW Pump, 12 EH oil pump, D5 Diesel Generator, 13 condensate pump to be used in an emergency only.

Turnover: _Commence load increase per C1.4 Event Malf.

Event Event No.

No.

Type*

Description 1

R (RO)

Load increase per C1.4 File 99-04 N

RO will adjust reactivity by controlling boron concentration (BOP)

BOP will increase power by increasing turbine load.

2 I

Diagnose a hotwell level transmitter failure and perform actions lAW C47009 (BOP) 0601 level goes to -7" BOP must open MV-32041 ATT023 3

I (RO)

N42 Power range failure high. Crew will respond per 1C51.2 RO must put rods in manual File ATT023 4

C (RO)

Loss of Instrument Air to containment C34 AOP1 RO must control charging and letdown, and manually control pressure to prevent cycling of PORV's. File 99-04 5

C 11 Component Cooling Water pump trip, 12 CCW pump fails to start (BOP) automatically. BOP must recognize the failure of the standby pump to auto start and manually start it.

6 M

Loss of MFW, 11 MFW is manually tripped on loss of lube oil File 12 MFW (ALL) pump trips for unknown reason. File 99-04 7

C(RO)

AFW starts and then trips - loss of heat sink - RO must stop RCPs and (BOP) depressurize RCS - BOP must depressurize SG's and feed with condensate File 99-04 1*

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 (R8, S1)

I(N)ormal, (R)eactivity,

Apedi SearoOtln Fr E--

(8 51 Facility:

Prairie Island Scenario No.:

3 Examiners:

Op-Test No.:

Operators:

Initial Conditions:

Unit 1: 100% Power, End of Cycle, Equilibrium Xenon, Breaker 16-10 (Bus 16/Bus 26 Bustie) is OOS.

Steam Generator tube leakage of 4 GPD in 11 SG.

Unit 2: 100% Dower steady state operation the HD Pumos to nerform any renuirnd ac~tinn.* diirinr, the niimn s*wnn Turnover: The 11 and 12 Heater Drain (HD) Pumps are presently running. Want to start the 13 HD Pump and shutdown the 12 HD Pump so that preventive maintenance can be performed on the 12 HD Pump. Steps 5.3.1 and 5.3.2 have been completed in Section 5.3 of 1C28.4, "Unit 1 Heater Drains" for swapping HD Pumps. A local operator is available by Event Malf.

Event Event No.

No.

Type*

Description 1

N(BOP)

Start the 13 HD Pump and shutdown the 12 HD Pump 2

I (RO)

Loop B Tcold transmitter failure high (Rods step in and Charging Pump in "AUTO" increases to maximum speed; must place rod control in "MANUAL")

3 C(RO)

Pressurizer PORV (CV-31232) leaking (requires isolation) 4 R (RO)

High stator temperature on 11 Main Feedwater Pump (requires turbine load decrease to 330 MWe, since will need to shutdown pump within 30 minutes) 5 C (BOP) 12 SG FW Reg Valve controller fails "as is" in AUTO (will need to control 12 SG level in "MANUAL")

6 C(BOP) 11 Main Feedwater Pump trip (will need to rapidly reduce turbine load) 7 M(ALL)

Feedwater line break on 11 SG inside containment.

Requires entry into E-0 and then E-2.

8 C(BOP)

Failure of turbine to AUTO trip on Reactor Trip (will require MANUAL turbine trip) 9 C(BOP)

Failure of Phase A to AUTO actuate on Sl (will require MANUAL actuation of Phase A) 10 M(ALL)

SGTR on 11 SG when SG is fully depressurized.

Requires entry into E-3 and then ECA-3.1.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-11 (R8. $1)

Appedix Scnari OutineForm ES-D-1 (R8. 51)

Facility:

Prairie Island Scenario No.:

4 Op-Test No.:

Examiners:

Operators:

Initial Conditions: Unit 1: 50% power, Middle of Cycle. Equilibrium Xenon, 11 Sl Pumo is OOS (on hour 16 of a 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months clock, expected back in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ),

12 Charging Pump is OOS for overhaul. Breaker 16-10 (Bus 16/Bus 26 Bustie) is OOS.

Steam Generator tube leakaae of 4 GPD in 11 SG.

Unit 2: 100% power steady state operations Turnover:

Perform power increase on Unit 1 to 100%.

Are presently at Step 5.21.E of 1C1.4, "Unit 1 Power Operation" at the step to start the second feedwater pump per 1C28.2, "Unit 1 Feedwater System". Steps 5.5.1 through 5.5.8 of Section 5.5 of 1C28.2 have been completed.

Event Malf.

Event Event No.

No.

Type*

Description 1

N(BOP)

Start 12 Main Feedwater Pump 2

R(RO)

Reactor power increase 3

I(RO)

Turbine 1It stage pressure channel 1 PT-485 failure high (rods step out, must place rod control in "MANUAL")

4 I(BOP) 11 SG pressure channel 1 PT-468 failure high (11 SG PORV opens, must manually close PORV) 5 I(RO)

Pressurizer level channel 1 L-428 failure low (letdown isolates, PRZR heaters deenergize, and Charging Pump in "AUTO" increases to maximum speed) 6 C(RO)

RCS leak (30 gpm). Requires entry into 1C4 AOP1.

7 M(ALL)

Small break LOCA. Requires use of E-0, E-1, and ES-1.1.

8 C(BOP)

Bus 16 deenergizes due to breaker failure from CT-11 transformer, with a concurrent sequencer failure. Diesel Generator D2 trips during start. Will need to reenergize Bus 16 from 1 RY transformer per 1 C20.5 AOP2.

(if do not reenergize Bus 16, will need to go to FR-C.2 for degraded core cooling due to no high head Sl flow, since have no SI Pumps or PD Charging Pumps) 9 C(BOP) 12 RHR pump does not AUTO start on Sl (will require manual start of pump)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline

40ý L7 t2o O-aLq 0

ýWI44ý19:A-

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, Si)

Facility: Prairie Island Date of Exam: 08/12/02 Exam Level:

RO K/A Category Points Tier Group I

AlA Point K

K K

K A

A A

AG Total 1 2 1 3

4 5

6 1

2 3

4 1

Emergency &

Abnormal 2

3 3

2-3 17 Plant3 1

1 0

0 0

1 3

Evolutions

-a i~

tos Tier 6

5 6]7 5

u 7

36 Totals 1

2 2

3 2

2 2 1

23

2.

Plant 2

3 1

2 3

1 1

1 32 1

2 20 Systems 3

2 0

1 1

1 0

0 0

1 1

8 Tier 7

3 5

6 5

3 4

5 5

4 4

51 Totals I

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 3

3 3

4 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

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

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

Form ES40-(RS1 ES-401 PWR RO Examination Outline

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

ES-401E Emerency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function KI K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000005 Inoperable/Stuck Control Rod / 1 X

AA1.04 Reactor and turbine power 3.9/3.9 1

000015/17 RCP Malfunctions / 4 X

AA2.10 When to secure RCPs on loss of cooling or seal injection 3.7/3.7 1

BW/E09; CE/A13; W/EO9&E10 Natural Circ. / 4 X

2.4.7 Knowledge of event based EOP mitigation strategies 3.1/3.8 1

000024 Emergency Boration / 1 X

AK1.04 Low temperature limits for boron concentration 2.8/3.6 1

000026 Loss of Component Cooling Water / 8 X

AA2.02 The cause of possible CCW loss 2.9/3.6 1

000027 Pressurizer Pressure Control System X

AK3.03 Actions contained in EOP for PZR PCS malfunction 3.7/4.1 1

Malfunction / 3 000040 (BW/E05; CE/E05 W/E12) Steam Line X

EA1.3 Desired operating results during abnormal and emergency 3.4/3.9 1

Rupture - Excessive Heat transfer / 4 situations CE/Al1; W/E08 RCS Overcooling - PTS / 4 X

EA1.3 Desired operating results during abnormal and emergency 3.6/4.0 1

situations 000051 Loss of Condenser Vacuum / 4 X

2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 1

000055 Station Blackout / 6 X

EK1.02 Natural circulation cooling 4.1/4.4 1

000057 Loss of Vital AC Elec. Inst. Bus / 6 X

AK3.01 Actions contained in EOP for loss of vital ac electrical 4.1/4.4 1

instrument bus 000062 Loss of Nuclear Service Water / 4 x

AK3.02 The automatic actions (alignments) within the nuclear service 3.6/3.9 1

water resulting from the actuation of the ESFAS 000067 Plant Fire On-site / 9 X

AAtI.07 Fire alarm reset panel 2.9/3.0 1

000069 (W/E 14) Loss of CTMT Integrity / 5 X

EA2.2 Adherence to appropriate procedures and operation within the 3.3/3.8 1

limitations in the facility s license and amendments 1_

000074 (W/E06&E07) Inad. Core Cooling / 4 X

2.4.6 Knowlege of symptom based EOP mitigation strategies 3.1/4.0 1

000076 High Reactor Coolant Activity /9 X

AK2.01 Process radiation monitors 2.6/3.0 1

IK/A Category Totals:

i2iL1.L 3..

4.3LJ3 Group Point Total:

16 1

ES-401 PWR RO Examination Outline Form ES-401-4 (R8. S1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000001 Continuous Rod Withdrawal / 1 X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

parameters whnich are en #-level conditions for emergency and abnormal operating prcceoures 000003 Dropped Control Rod / 1 X

AK1.16 MTC 2.9/3.2 1

000008 Pressurizer Vapor Space Accident / 3 X

AK2.02 Sensors and detectors 2.7/2.7 1

000009 Small Break LOCA / 3 X

EK3.28 Manual ESFAS Initiation requirements 4.5/4.5 1

W/E04 LOCA Outside Containment / 3 X

EA1.3 Desired operating results during abnormal and emergency 3.8/4.0 1

situations BW/E08; W/E03 LOCA Cooldown/Depress. / 4 X

EA2.2 Adherence to appopriate procedures and operation within the 3.5/4.1 1

limitations in the facilitys license and amendments W/E1 1 Loss of Emergency Coolant Recirc. / 4 X

2.1.2 Knowledge of operator responsibilities during all modes of plant 3.0/4.0 1

1__

1operation 000022 Loss of Reactor Coolant Makeup / 2 X

AKI.01 Consequences of thermal shock to RCP seals 2.8/3.2 1

000025 Loss of RHR System / 4 X

AK2.01 RHR heat exchangers 2.9/2.9 1

000033 Loss of Intermediate Range NI / 7 X

AK3.01 Termination of startup following loss of intermediate rannge 3.2/3.6 1

instrumentation 000037 Steam Generator Tube Leak / 3 X

AA1. 11 PZR level indicator 3.4/3.3 1

000038 Steam Generator Tube Rupture / 3 X

EA2.13 Magnitude of rupture 3.1/3.7 1

BW/E04; W/E05 Inadequate Heat Transfer - Loss X

2.4.4 Ability torecognize abnormal indications for system operating 4.0/4.3 1

of Secondary Heat Sink / 4 parameters which are entry-level conditions for emergency and abnormal operating proceoures 000059 Accidental Liquid RadWaste Rel. / 9 X

AK1.01 Types of radiation, their units of intensity and the location of 2.7/3.1 1

1__

the sourcesof radiation in a nuclear power plant 000060 Accidental Gaseous Radwaste Rel. / 9 X

AK2.02 Auxiliary building ventilation system 2.7/3.1 1

000061 ARM System Alarms / 7 X

AK3.02 Guidance contained In alarm response for ARM system 3.4/3.6 1

W/E16 High Containment Radiation / 9 X

EAI.3Dered operating results during abnormal and emergency 2.9/3.3 1

K/A Category Point Totals:

131313 312131Group Point Total:

[ 1

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

Emeruency and Abnormal Plant Evolutions - Tier 1l/Group 3 E/APE # Name / Safety Function KI K2 K3 Al A2 G

K/A Topc(s)

Imp.

Points 000065 Loss of Instrument Air / 8 X

2.4.2 Knowledge of system set points, interlocks and automatic 3.9/4.1 1

actions associated with EOP entry conditions WIE13 Steam Generator Over-pressure /4 X

EK1.2 Nor.,al abnormal and emergency operating procedures 3.0/3.3 1

1 associated wth (Steam Generator Overpressure)

W/E 15 Containment Flooding / 5 X

EK2.1 Components, and functions of control and safety systems, 2.8/2.9 1

including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Point Totals:

1 1 : :0 0 :0 Group Point Total:

7 3

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, $1)

Plant Systems - Tler 2/Group 1 System 8/ Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.I Points 001 Control Rod Drive X

X K1.04 RCS 3.3/3.4 2

I K4.07 Rod stops 37/3.8 003 Reactor Coolant Pump X

X K2.02 CCW pumps

?.5/2.6 2

K5.04 Effects of RCP shutdown on 2/3.5 secondary parameters, such as steam pressure, steam flow, and feed flow 004 Chemical and Volume Control X

X K3.08 RCP seal injection 3.6/3.8 2

K6.13 Purpose and function of the 3.1/3.3 boration/dilution batch controller 013 Engineered Safety Features Actuation X

X K4.13 MFW isolation/reset 3.7/3.9 2

A1.06 RWST level 3.6/3.9 015 Nuclear Instrumentation X

X K2.01 NIS channels, components, and 3.3/3.7 2

interconnections K5.02 Discrimination/compensation

.7/2.9 I

I I

operation 017 In-core Temperature Monitor I

X K6.01 Sensors and detectors 2.7/3.0 1

022 Containment Cooling X

A1.01 Containment temperature 3.6/3.7 1

056 Condensate X

A2.04 Loss of condensate pumps 2.6/2.8 1

059 Main Feedwater X

X A1.03 Power level restrictions for operation 2.7/2.9 2

of MFW pumps and valves A3.06 Feedwater isolation 3.2/3.3 061 Auxiliary/Emergency Feedwater X

X K4.07 Turbine trip, including overspeed 3.1/3.3 2

A2.05 Automatic control malfunction 3.1/3.4 068 Liquid Radwaste X

X K1.02 Waste Gas Vent Header

?.5/2.6 2

A3.02 Automatic isolation 3.6/3.6

ES401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

Plant Systems - Tier 2/Group S

System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 071 Waste Gas Disposal X

X K5.04 Relationshi of hydrogen/oxygen 2.5/3.1 2

concentrations to lam5mab3i.1 A4.30 Water drainage from the WGDS decay 2.9/2.6 tanks 072 Area Radiation Monitoring X

X K3.02 Fuel handling operations

.1/3.5 2

2.4.4 Ability to recognize abnormal 4.0/4.3 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating I -

I I procedures K/A Category Point Totals:

12 2

1 122 3

2

[2

.1 Group Point Total:

23

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

Plat Systems -

ier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 002 Reactor Coolant X

K1.07 Reactor vessel level indication 3.5/3.7 1

system 006 Emergency Core Cooling x

K2.01 ECCS pumps 3.6/3.9 1

010 Pressurizer Pressure Control K3.01 RCS 3.9/3.9 1

011 Pressurizer Level Control K4.02 PZR level controller 3.3/3.4 1

012 Reactor Protection K5.01 DNB 3.3/3.8 1

014 Rod Position Indication K4.06 Individual and group 3.4/3.7 1

misalignment 016 Non-nuclear Instrumentation X

A2.02 Loss of power supply 2.9/3.2 1

026 Containment Spray X

A2.05 Failure of chemical addition 3.7/4.1 1

tanks to inject 029 Containment Purge X

A3.01 CPS isolation 3.8/4.1 1

033 Spent Fuel Pool Cooling X

2.1.27 Knowledge of system purpose 2.8/2.9 1

and or function 035 Steam Generator x

A4.05 Level control to enhance natural 3.8/4.0 1

I circulation 039 Main and Reheat Steam X

K1.02 Atmospheric relief dump valves 3.3/3.3 1

055 Condenser Air Removal X

K1.06 PRM system 2.6/2.6 1

062 AC Electrical Distribution X

K3.03 DC system 3.7/3.9 1

063 DC Electrical Distribution X

K4.04 Trips 2.6/2.9 1

064 Emergency Diesel Generator x

K6.07 Air receivers 2.7/2.9 1

073 Process Radiation Monitoring--

X A1.01 Radiation levels 3.2/3.5 1

075 Circulating Water X

2.4.31 Knowledge of annunciator 3.3/3.4 1

alarms and indications, and use of the I-response instructions 079 Station Air X

A2.01 Cross-connection with IAS 2.9/3.2 1

086 Fire Protection X

A3.01 Starting mechanisms of fire 2.9/3.3 1

A wateroupT

ES-401 PWR RO Examination Outline Form ES-401-4 (R8, S1)

Plant Systems - Tier Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 005 Residual Heat Removal X

A4.02 Heat exchanger bypass flow control 3.4/3.1 1

027 Containment Iodine Removal X

2.1.32 Ability to explain and apply all 3.4/3.8 1

system limits and precautions 028 Hydrogen Recombiner and Purge Control K5.03 Sources of hydrogen within 2.9/3.6 1

containment 007 Pressurizer Relief Tank / Quench Tank X

K1.03 RCS 3.0/3.2 1

System 041 Steam Dump/Turbine Bypass Control X

K3.02 RCS 3.8/3.9 1

076 Service Water x

K4.02 Automatic start features associated 2.9/3.2 1

with SWS pump controls 078 Instrument Air X

A3.01 Air pressure 3.1/3.2 1

103 Containment X

K1.03 Shield building vent system 3.1/3.5 1

K/A Category Point Totals:

2 0

1 II

[0 0

01o 1

1 Group Point Total:

8 Plant-Specific Priorities System Topic Recommended Replacement for...

Reason Points Plant-Specific Priority Total: (limit 10) 1

Facility: Prairie Island Date of Exam: 08/12/02 Exam Level:

RO Category K/A #

Topic Imp.

Points 2.1.1 Knowledge of conduct of operations 3.7/3.8 1

requirements Conduct of 2.1.3 Knowledge of shift turnover practices 3.0/3.4 1

Operations 2.1.29 Knowledge of how to conduct and verify valve 3.4/3.3 1

lineups Total 3

2.2.12 Knowledge of surveillance procedures 3.0/3.4 1

2.2.13 Knowledge of tagging and clearance 3.6/3.8 1

procedures Equipment 2.2.30 Knowledge of RO duties in the control room 3.5/3.3 1

Control during fuel handling such as alarm from fuel handling area, communication with fuel storage facility, systems operated from the control board in support of fueling operations, and supporting instrumentation Total 3

2.3.1 Knowledge of 10CFR: 20 and related facility 2.6/3.0 1

radiation control 2.3.2 Knowledge of facility ALARA program 2.5/2.9 1

Radiation 2.3.11 Ability to control radiation releases 2.7/3.2 1

Control Total 3

2.4.2 Knowledge of system set points, interlocks 4.3/4.6 1

and automatic actions associated with EOP entry conditions Emergency 2.4.6 Knowledge of symptom based EOP mitigation 3.1/4.0 1

Procedures/

strategies Plan 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 1

2.4.20 Knowledge of operational implications of EOP 3.3/4.0 1

warnings, cautions, and notes Total 4

Tier 3 Point Total (RO/SRO) 13 Form ES-401-5 (R8, S11)

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

Record of Reiected K/As ('for Re exam*

Form FS-401 -10 ('RR S1~

Tier / Group Randomly Selected K/A Reason for Rejection 1 / 1 W/E08 EA2.1 K/A was at the SRO level instead of at the RO level. Randomly selected another K/A, which was K/A W/E08 EA1.3 2 / 3 034 Al.02 Reactor Operators do NOT have any involvement with refueling operations. Randomly selected another K/A, which was 4

4K/A 007 K1.03 t

I t

I 7

9 t

I t

I 1'

I 7

I 1

I t

I 1-I t

I 7

t ES-401 Record of Reiected K/As (for RO exam)

I Form ES-401

-10 IR8 R1

~~QAA1 ~~~PwR SRO Examination Outline Fr S413(8 1 Facility: Prairie Island Date of Exam: 8/16/2002 Exam Level: SRO K/A Category Points Tier Group Point K

K K

K A

A2 A

A G

Total 1

2 3

4 5

6 4

1.

1 3

3 4

4 6

4 24 Emergency &

Abnormal 2

2 3

2 2

4 3

16 Plant 3

0 0

1 1

1 0

3 Evolutions Tier 5

6 7

711 7

43 Totals 1

2 2

1 2

2 22 2

1 19

2.

Plant 2

2 1

2 2

2 1

1 17 Systems 3

0 0 1 0

0 1

1 1

1 0

0 4

Tier 4

3 3

4 5

5 5

3 2

40 Totals I__

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 17 4

4 4

5 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

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

5.

The shaded areas are not applicable to the category/tier.

6.V The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

CC AnI Form ES-401-3 (R8, S11)

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, S)

ES-401 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE N / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 000001 Continuous Rod Withdrawal / 1 X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

parameters which are entry-level conditions for emergency and abnormal operating procedures 41.10, 43.2 000003 Dropped Control Rod / 1 x

AK1.16 MTC 41.8, 41.10 2.9/3.2 1

000005 Inoperable/Stuck Control Rod / 1 X

AA1.04 Reactor and turbine power 41.7 3.9/3.9 1

000011 Large Break LOCA / 3

/

EA2.06 That fan is in slow speed and dampers are in accident mode 3.7/4.0 1

durinn LOCA 43.5 W/E04 LOCA Outside Containment / 3 X

EA1.3 Desired operating results during abnormal and emergency 3.8/4.0 1

situations 41.7 W/EO1 & E02 Rediagnosis & SI Termination /3

/

EK2.2 Facilitys heat removal systems, including primary coolant, 3.5/3.8 1

emergency coolant, the decay heat removal systems. and relations between the proper operation of these systems to the operation of the facility. 41.7 000015/17 RCP Malfunctions / 4 X

AA2.10 When to secure RCPs on loss of cooling or seal injection 43.5 3.7/3.7 1

BW/E09: CE/A13; W/E09&E10 Natural Circ. / 4 X

2.4.7 Knowledge of event based EOP mitigation strategies 43.5 3.1/3.8 1

000024 Emergency Boration / 1 X

AK1.04 Low temperature limits for boron concentration 41.8 41.10 2.8/3.6 1

000026 Loss of Component Cooling Water / 8 X

AA2.02 The cause of possible CCW loss 43.5 2.9/3.6 1

000029 Anticipated Transient w/o Scram / 1 EK3.12 Actions contained in EOP for ATWS 3.1/3.1 1

000040 (BW/E05; CF/EO5-WIE12) Steam Line X

EA1.3 Desired operating results during abnormal and emergency 3.4/3.9 1

Rupture - Excessive Heat transfer / 4 conditions 41.3 CE/Al 1; W/E08 RCS Overcooling - PTS / 4 X

EA2.1 Facility conditions and selection of appropriate procedures during 3.4/4.2 1

abnormal and emergency operations 43.5 1_

000051 Loss of Condenser Vacuum / 4 X

2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 1

000055 Station Blackout / 6 x

EK1.02 Natural circulation cooling 4.1/4.4 1

000057 Loss of Vital AC Elec. Inst. Bus / 6 X

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument 4.1/4.4 1

bus 000059 Accidental Liquid RadWaste Rel. / 9

/

AK2.02 Radioactive Gas Monitors 3.6/3.9 1

000062 Loss of Nuclear Service Water / 4 x/

AK3.02 The automatic actions (alignments) within the nuclear service 3.6/3.9 1

water resulting from the actuation of the ESFAS I

I AA2.04 The normal values an upper limits for the tempertures of the 2.5/2.9 1

components cooled by SWS 000067 Plant Fire On-site / 9 X

AA1.07 Fire alarm reset panel 2.9/3.0 1

000068 (BW/A06) Control Room Evac. /8

,/

AK3.08 Trip of the MFW and necessary Condensate pumps 2.4/2.7 1

000069 (W/E14) Loss of CTMT Integrity / 5 X

EA2.2 Adherence to appropriate procedures and operation within the 3.3/3.8 1

limitations in the facilit s license and amendments

000074 (W/E06&E07) Inad. Core Cooling / 4 X

2.4.6 Knowlege of symptom based EOP mitigation strategies 3.1/4.0 1

BW/E03 Inadequate Subcooling Margin / 4 N/A 000076 High Reactor Coolant Activity / 9 X

AK2.01 Process radiation monitors 2.6/3.0 1

BW/A02&A03 Loss of NNI-X/Y / 7 N/A K/ACategoryTotals:

1 3 3

4 4

6 4

Group Point Total:

24

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, S1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 A

A2 G

K/A Topic(s)

Imp.

Points I

1_

1 _1 000007 (BW/E02&E10; CEIE02) Reactor Trip -

/

EA2.06 Occurrence of a reactor trip 4.3/4.5 1

Stabilization - Recovery / 1 I

I I

BW/AOl Plant Runback / I N/A BW/A04 Turbine Trip / 4 N/A 000008 Pressurizer Vapor Space Accident / 3 X

AK2.02 Sensors and detectors 2.7/2.7 1

000009 Small Break LOCA / 3 X

EK3.28 Manual ESFAS initiation requirements 4.5/4.5 1

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X

EA2.2 Adherence to appropriate procedures and operation within the 3.5/4.1 1

limitations in the facility s license and amendments W/E 1I Loss of Emergency Coolant Recirc. / 4 X

2.1.2 Knowledge of operator responsibilities during all modes of plant 3.0/4.0 1

operation 000022 Loss of Reactor Coolant Makeup / 2 X

AK.01 Consequences of thermal shock to RCP seals 2.8/3.2 1

000025 Loss of RHR System / 4 X

AK2.01 RHR heat exchangers 2.9/2.9 1

000027 Pressurizer Pressure Control System Randomly deleted to acquire the correct number of questions Malfunction / 3 000032 Loss of Source Range NI / 7

/

AA2.06 Confirmation of reactor trip 3.9/4.1 1

000033 Loss of Intermediate Range NI / 7 X

AK3.01 Termination of startup following loss of intermediate range 3.2/3.6 1

I I instrumentation 000037 Steam Generator Tube Leak / 3 X

A1.11 PZR level indicator 3.4/3.3 1

000038 Steam Generator Tube Rupture / 3 X

EA2.13 Magnitude of rupture 3.1/3.7 1

000054 (CE/E06) Loss of Main Feedwater / 4 AA1.01 AFW Controls, including the use of alternate AFW sources 3.2/3.1 1

BW/E04; W/E05 Inadequate Heat Transfer - Loss X

2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1

of Secondary Heat Sink / 4 parameters which are entry-level conditions for emergency and abnormal operating procedures 000058 Loss of DC Power / 6 AK1.01 Battery charger equipment and instrumentation 2.8/3.1 1

000060 Accidental Gaseous Radwaste Rel. / 9 X

AK2.02 Auxiliary building ventilation system 2.7/3.1 1

000061 ARM System Alarms / 7 Randomly deleted to acquire the correct number of questions W/E 16 High Containment Radiation / 9 Randomly deleted to acquire the correct number of questions 000065 Loss of Instrument Air / 8 X

2.4.2 Knowledge of system set points, interlocks and automatic actions 3.9/4.1 1

I associated with EOP entry conditions CE/EO9 Functional Recovery N/A K/A Category Point Totals:

2 3

.2 2

24 3

1 Group Point Total:

I 16

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)

ES-401-Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE N / Name / Safety Function K1 K2 K3 At A2 G

K/A Topic(s)

Imp.

Points 000028 Pressurizer Level Malfunction / 2

/

AA2.11 Leak in PZR 3.2/3.6 1

000036 (BW/A08) Fuel Handling Accident / 8 AAt.02 ARM system 3.1/3.5 1

000056 Loss of Off-site Power / 6 K3.02 actions contained in EOP for Loss of offsite power 4.4/4.7 1

BW/E13&E14 EOP Rules and Enclosures N/A BW/A05 Emergency Diesel Actuation / 6 N/A BW/A07 Flooding / 8 N/A CEIAI6 Excess RCS Leakage/2 N/A W/E 13 Steam Generator Over-pressure / 4 Randomly deleted to acquire the correct number of questions W/E 15 Containment Flooding / 5 Randomly deleted to acquire the correct number of questions 4-4-l-l-4-+-4 LI

.I

?t1ttt-1 1

4-4-l-1-4-4--l

.I I

?t11t-t-1 4

4 4-4-1-1-4-4-I

.4

.4 1'-1-f-I-t-t-l 4

+

t-1-t-1-t-4-I

.4

.4 i-4-1-4-4-4i

.4 I

K/A Category Point Totals:

1 l1lIl I

Group Point Total:

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Sl)

Plant Systems - Tier 2/Group 1 11 System # / Name K1 K2 K3 K4 K5 K6 Al A

A3 A4 G

K/A Topic(s)

Imp.

Points 2

001 Control Rod Drive X

K1.04 RCS 3.3/3.4 1

003 Reactor Coolant Pump X

K2.02 CCW pumps 2.5/2.6 1

004 Chemical and Volume Control X

X K3.08 RCP seal injection 3.6/3.8 1

K6.13 Purpose and function of the 3.1/3.3 1

boration/dilution batch controller 013 Engineered Safety Features Actuation X

A1.06 RWST level 3.6/3.9 1

014 Rod Position Indication X

K4.06 Individual and group misalignment 3.4/3.7 1

015 Nuclear Instrumentation X

X K2.01 NIS channels, components, and 3.3/3.7 1

interconnections K5.02 Discrimination/compensation operation 2.7/2.9 1

017 In-core Temperature Monitor X

K6.01 Sensors and detectors 2.7/3.0 1

022 Containment Cooling X

A1.01 Containment temperature 3.6/3.7 1

025 Ice Condenser N/A 026 Containment Spray X

A2.05 Failure of chemical addition tanks to 3.7/4.1 1

inject 056 Condensate X

A2.04 Loss of condensate pumps 2.6/2.8 1

059 Main Feedwater X

A3.06 Feedwater isolation 2.7/2.9 1

061 Auxiliary/Emergency Feedwater X

A2.05 Automatic control malfunction 3.1/3.3 1

063 DC Electrical Distribution X

K4.04 Trips 2.6/2.9 1

068 Liquid Radwaste X

X K1.02 Waste Gas Vent Header 2.5/2.6 1

A3.02 Automatic isolation 3.6/3.6 1

071 Waste Gas Disposal X

A4.30 Water drainage from the WGDS decay 2.9/2.6 1

tanks 072 Area Radiation Monitoring x

2.4.4 Ability To recognize abnormal 3.1/3.5 1

indications for system operatingtparameters which are entry-level conditions or emergency and abnormal operating procedures

[K/ACategoryPoint Totals:

2 2 I2 12 1 2 12 I2 12 12 11 1 GroupPont Total:

119

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)

Plant Systems - Tier./Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 002 Reactor Coolant X

K1.07 Reactor vessel level indication system 3.5/3.7 1

006 Emergency Core Cooling X

K2.01 ECCS pumps 3.6/3.9 1

010 Pressurizer Pressure Control X

K3.01 RCS 3.8/3.9 1

011 Pressurizer Level Control X

K4.02 PZR level controller 3.3/3.4 1

012 Reactor Protection X

K5.01 DNB 3.3/3.8 1

016 Non-nuclear Instrumentation X

A2.02 Loss of power supply 2.9/3.2 1

027 Containment Iodine Removal X

2.1.32 Ability to explain and apply all system 3.4/3.8 1

limits and precautions 028 Hydrogen Recombiner and Purge Control X

K5.03 Sources of hydrogen within 2.9/3.6 1

containment 029 Containment Purge-X A3.01 CPS isolation 3.8/4.1 1

033 Spent Fuel Pool Cooling Randomly deleted to acquire the correct number of questions 034 Fuel Handling Equipment X

Al.02 Water level in the refueling canal 2.9/3.7 1

035 Steam Generator X

A4.05 Level control to enhance natural 3.8/4.0 1

circulation 039 Main and Reheat Steam X

K1.02 Atmospheric relief dump valves 3.3/3.3 1

055 Condenser Air Removal Randomly deleted to acquire the correct number of questions 062 AC Electrical Distribution X

K3.03 DC system 3.7/3.9 1

064 Emergency Diesel Generator X

K6.07 Air receivers 2.7/2.9 1

073 Process Radiation Monitoring X

A1.01 Radiation levels 3.2/3.5 1

075 Circulating Water Randomly deleted to acquire the correct number of questions 079 Station Air X

A2.01 Cross-connection with IAS 2.9/3.2 1

086 Fire Protection X

A3.01 Starting mechanisms of fire water 2.9/3.3 1

pumps 103 Containment Randomly deleted to acquire the correct L

number of questions K/ACategoryPointTotals:

F 2 I1 2 I1 12 11 12 1

2 I1 I 1 GroupPointTotal:

17

ES-401 PWR SRO Examination Outline Form ES-401-3 (R8, Si)

Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 005 Residual Heat Removal Randomly deleted to acquire the correct number of questions 007 Pressurizer Relief/Quench Tank

/

K5.02 Method of forming a steam bubble in 3.1/3.4 1

the PZR 008 Component Cooling Water A1.02 CCW temperature 2.9/3.1 1

041 Steam Dump/Turbine Bypass Control Randomly deleted to acquire the correct number of questions 045 Main Turbine Generator

/

A2.17 Malfunction of electrohydraulic 2.7/2.9 1

control 076 Service Water Randomly deleted to acquire the correct I number of questions 078 Instrument Air X

A3.01 Air pressure 3.1/3.2 1

K/A Category Point Totals:

I I I[I I,1,1,1 I

Group Point Total:

4 Plant-Specific Porities System / Topic Recommended Replacement for...

Reason Points Plant-Specific Priority Total: (limit 10)

I S-40u IGeneric Ksnowleage ana Ablilties Outline (Tier 3)

Form ES-401-5 (R8, Sl)

I-

Category K/A #

Topic Imp.

Points 2.1.6 Ability to supervise and assume a 2.1/4.3 1

management role during plant transients and upset conditions Conduct of 2.1.10 Knowledge of conditions an limitations in the 2.7/3.9 1

Operations facility license 2.1.22 Ability to determine Mode of Operations 2.8/3.3 1

2.1.33 Ability to recognize indications for system 3.4/4.0 1

operating parameters which are entry-level conditions for technical specifications Total 4

2.2.6 Knowledge of the process for making 2.3/3.3 1

changes in procedures as described in the safety analysis report 2.2.22 Knowledge of limiting conditions for 3.4/4.1 1

Equipment operations and safety limit Control 2.2.28 Knowledge of new and spent fuel movement 3.5/3.3 1

procedures 2.2.26 Knowledge of refueling administrative 2.5/3.7 1

requirements Total 4

2.3.1 Knowledge of 10CFR: 20 and related facility 2.6/3.0 1

radiation control 2.3.4 Knowledge radiation exposure limits and 2.5/3.1 1

contamination control, ihcluding permissible Raition levels in excess of those authorized Control 2.3.11 Ability to control radiation releases 2.7/3.2 1

2.3.6 Knowledge of the requirements for reviewing 2.1/3.1 1

Total__

and approving release permits 4

Total 4

2.4.1 Knowledge of EOP entry conditions and 4.3/4.6 1

immediate action steps Emergency 2.4.22 Knowledge of the bases for prioritizing safety 3.0/4.0 1

Procedures/

functions during abnormal/emergency Plan operations 2.4.41 Knowledge of emergency action level 2.3/4.1 1

thresholds and classifications 2.4.44 Knowledge of emergency plan protective 2.1/4.0 1

action recommendations 2.4.28 Knowledge of procedures relating to 2.3/4.3 1

emergency response to sabotage Total 5

Tier 3 Point Total (RO/SRO) 17 I=xRm LAvAI" *R*

SFacility: Prairie Island

ML023030539

Text

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