ML050690372

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01-2005 - Draft Outline
ML050690372
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/27/2005
From: Gody A
Operations Branch IV
To: Forbes J
Entergy Operations
References
50-368/05-301 50-368/05-301
Download: ML050690372 (30)
v • d • e


Text

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

ANO-2 Date of Examination: 01/21/2004 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic (see note)

Type Code*

Describe activity to be performed Conduct of Operations S/N Perform offsite power availability and vital electrical availability checklist to determine operability.

2.1.31; Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Conduct of Operations D

Calculate Volume needed to raise SFP level.

2.1.23; Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Equipment Control M

Review Surveillance.

2.2.12; Knowledge of Surveillance procedures.

Radiation Control D/P Review Emergency RWP and determine stay time limits.

2.3.10; Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure.

Emergency Plan NA NA 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 (D)irect from bank ( 3 for ROs; 4 for SROs)

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

(P)revious ( 1; randomly selected)

(S)imulator ES-301, Page 22 of 27

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

ANO-2 Date of Examination: 01/21/2004 Examination Level (circle one): RO / SRO Operating Test Number: 1 Administrative Topic (see note)

Type Code*

Describe activity to be performed Conduct of Operations N

Perform Supervisor review and analysis of offsite power availability and vital electrical availability checklist to determine operability.

2.1.33; Ability to recognize indication for system operating parameters which are entry-level conditions for technical specifications.

Conduct of Operations D

Review and approve calculation of volume needed to raise SFP level.

2.1.23; Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Equipment Control M

Review and approve as supervisor a completed Surveillance.

2.2.12; Knowledge of Surveillance procedures.

Radiation Control D/P Review Emergency RWP and determine stay time limits.

2.3.10; Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure.

Emergency Plan M/S Determine the proper Emergency Action Level for the given conditions.

2.4.41; Knowledge of the emergency action level thresholds and classifications.

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 (D)irect from bank ( 3 for ROs; 4 for SROs)

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

(P)revious ( 1; randomly selected)

(S)imulator ES-301, Page 22 of 27

E S-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________

Date of Examination: _01/21/2005____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ____1_________

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

System / JPM Title Type Code*

Safety Function

a. ANO-2-JPM-NRC-AOP2 022 A4.04 RO-3.1 SRO-3.2 Reset CIAS and establish cooling water to containment.

L/N/S 5

Containment Integrity

b. ANO-2-JPM-NRC-CVCS010 004 K6.17 RO-4.4 SRO-4.6 Emergency borate using HPSI.

A/L/M/S 1

Reactivity

c. A2JPM-NRC-PZR02 010 A4.01 RO-3.7 SRO-3.5 Equalize RCS and PZR boron.

A/D/S 3

Pressure Control

d. ANO-2-JPM-NRC-SIT05 006 A1.13 RO 3.5 SRO 3.7 Raise SIT nitrogen pressure.

A/D/S 2

Inventory

e. ANO-2-JPM-NRC-EOP03 002 A4.02 RO-4.3 SRO-4.5 Verify natural circ conditions exist.

A/L/N/S 4

Heat Removal

f. ANO-2-JPM-NRC-ELECXT 062 A4.01 RO-3.3 SRO-3.1 Cross connect 2B1 and 2B2.

D/P/S 6

Electrical

g. ANO-2-JPM-NRC-BMSRM 068 A3.02 RO-3.6 SRO-3.6 Ability to monitor automatic operation of the LRS including automatic isolations.

C/D/P 9

Radioactivity Release

h. ANO-2-JPM-NRC-EOP02 016 A2.01 RO 3.0 SRO 3.1 Restore Shutdown cooling following an Instrument Failure.

D/L/P/S 7

Instrumentation In-Plant Systems@ ( 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. A2JPM-NRC-EFWRS 061 A2.04 RO-3.4 SRO-3.8 Reset A EFW pump Over-speed trip device D/R 4

Heat Removal

j. ANO-2-JPM-NRC-IA01 067 AA2.04 RO-3.1 SRO-4.3 Operate vital equipment during severe fire. (AOP) Trip MTG and Isolate IA to MSIVs.

D/E 8

Plant Services

k. A2JPMNRC-XTCEA 001 A2.14 RO-3.7 SRO-3.9 Obtain CEA #01 Upper Gripper Coil Temperature D

1 Reactivity

@ All control room (and in-plant) systems must be different and serve different safety functions;

  • Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator

E S-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________

Date of Examination: _01/21/2005____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ____1_________

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

System / JPM Title Type Code*

Safety Function

a. ANO-2-JPM-NRC-AOP2 022 A4.04 RO-3.1 SRO-3.2 Reset CIAS and establish cooling water to containment.

L/N/S 5

Containment Integrity

b. ANO-2-JPM-NRC-CVCS010 004 K6.17 RO-4.4 SRO-4.6 Emergency borate using HPSI.

A/L/M/S 1

Reactivity

c. A2JPM-NRC-PZR02 010 A4.01 RO-3.7 SRO-3.5 Equalize RCS and PZR boron.

A/D/S 3

Pressure Control

d. ANO-2-JPM-NRC-SIT05 006 A1.13 RO 3.5 SRO 3.7 Raise SIT nitrogen pressure.

A/D/S 2

Inventory

e. ANO-2-JPM-NRC-EOP03 002 A4.02 RO-4.3 SRO-4.5 Verify natural circ conditions exist.

A/L/N/S 4

Heat Removal

f. ANO-2-JPM-NRC-ELECXT 062 A4.01 RO-3.3 SRO-3.1 Cross connect 2B1 and 2B2.

D/P/S 6

Electrical

g. ANO-2-JPM-NRC-BMSRM 068 A3.02 RO-3.6 SRO-3.6 Ability to monitor automatic operation of the LRS including automatic isolations.

C/D/P 9

Radioactivity Release

h.

In-Plant Systems@ ( 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. A2JPM-NRC-EFWRS 061 A2.04 RO-3.4 SRO-3.8 Reset A EFW pump Over-speed trip device.

D/R 4

Heat Removal

j. ANO-2-JPM-NRC-IA01 067 AA2.04 RO-3.1 SRO-4.3 Operate vital equipment during severe fire. (AOP) Trip MTG and Isolate IA to MSIVs.

D/E 8

Plant Services

k. A2JPMNRC-XTCEA 001 A2.14 RO-3.7 SRO-3.9 Obtain CEA #01 Upper Gripper Coil Temperature.

D 1

Reactivity

@ All control room (and in-plant) systems must be different and serve different safety functions;

  • Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator

E S-301 Control Room / in Plant Systems Outline Form ES-301-2 Facility: __ANO UNIT 2__________________

Date of Examination: _01/21/2005____

Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: ____1_________

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

System / JPM Title Type Code*

Safety Function

a. ANO-2-JPM-NRC-AOP2 022 A4.04 RO-3.1 SRO-3.2 Reset CIAS and establish cooling water to containment L/N/S 5

Containment Integrity

b. ANO-2-JPM-NRC-CVCS010 004 K6.17 RO-4.4 SRO-4.6 Emergency borate using HPSI A/L/M/S 1

Reactivity

c. A2JPM-NRC-PZR02 010 A4.01 RO-3.7 SRO-3.5 Equalize RCS and PZR boron A/D/S 3

Pressure Control

d.
e.
f.
g.
h.

In-Plant Systems@ ( 3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. A2JPM-NRC-EFWRS 061 A2.04 RO-3.4 SRO-3.8 Reset A EFW pump Over-speed trip device.

D/R 4

Heat Removal

j. ANO-2-JPM-NRC-IA01 067 AA2.04 RO-3.1 SRO-4.3 Operate vital equipment during severe fire. (AOP) Trip MTG and Isolate air to MSIVs.

D/E 8

Plant Services

k.

@ All control room (and in-plant) systems must be different and serve different safety functions;

  • Type Codes Criteria for RO /SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)direct from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (L)ow-Power 1 / 1 / 1 (N)ew or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 1 Op-Test No.: 2005-1 Page 1 Examiners:

Operators:

Initial Conditions:

56% MOL, All ESF systems in standby. Condenser outer water box is isolated for tube plugging. B circulating water pump is secured. Green Train Maintenance Week.

Turnover:

56%. 250 EFPD. Condenser outer water box is isolated for tube plugging. Estimated time to complete repairs is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. B circulating water pump is secured. EOOS indicates Minimal Risk. Green Train Maintenance Week.

Event No.

Malf. No.

Event Type*

Event Description 1

NIALINEPWR I (CBOT)

Safety channel linear power channel A fails low.

CBOT must bypass points in PPS channel.

2 CVC2P36AFAL C (CBOR)

Running charging pump trips breaker. AOP entry start standby charging pump.

3 SGATUBE R(CBOR)

N(CBOT)

A SG tube leak results in power reduction to take unit off line.

4 SGATUBE 4162A406 2CV50151 BUHTRS M(ALL)

C (CBOT)

C(CBOR)

A SG tube rupture results in reactor trip and RCS cooldown.

B HPSI pump trips breaker on start.

A HPSI train injection MOV fails to open on actuation.

C HPSI must be started. Or 2CV 5015-1 opened to satisfy HPSI injection flow requirement.

BUHTRS fail on due to relay failure and will not shut off when Pressurizer level drops less than setpoint.

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

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 2 Op-Test No.: 2005-1 Page 1 Examiners:

Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. C HPSI pump tagged out for oil bubbler replacement. C HPSI is aligned to green train. Green train maintenance week.

Turnover:

100%. 250 EFPD. C HPSI pump tagged out for oil bubbler replacement. EOOS indicates Minimal Risk. Green train maintenance week.

Event No.

Malf. No.

Event Type*

Event Description 1

XRCCHAPLVL I (CBOR)

Control Channel A Pressurizer Level fails LOW.

2 XSG2PT10411 I (CBOT)

Steam Generator safety channel pressure fails LOW.

3 FWPMPATRP R(CBOR)

N(CBOT)

A MFP trips due to thrust bearing wear and results in a power reduction to less than 90%.

4 FWAFT5A ESCSBPMP ESFCSASFAIL M(ALL)

C (CBOT)

C (CBOR)

Feedwater line break in containment after 2FW5A which results in ESD on A SG.

Fail B CSAS pump to start on CSAS.

Fail CSAS channel 1 to actuate auto.

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

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-2 Scenario No.: 3 Op-Test No.: 2005-1 Page 1 Examiners:

Operators:

Initial Conditions:

100% MOL, All ESF systems in standby. Green Train Maintenance Week.

Turnover:

100%. 250 EFPD. EOOS indicates Minimal Risk. Green Train Maintenance Week.

Event No.

Malf. No.

Event Type*

Event Description 1

XCV2LT4861 I (CBOR)

VCT level instrument fails low resulting in RWT being aligned to CCP suction.

2 XFW2FIS0735 (CBOT)

A MFP suction transmitter fails low. Results in condensate and MFP recircs to condenser opening fully and reducing feedwater to SGs.

3 CNDVACUUM R (CBOR)

N (CBOT)

Air leakage into condenser requiring a power reduction to maintain condenser vacuum.

4 CNDVACUUM M(ALL)

Air leakage into condenser results in loss of condenser vacuum and turbine and reactor trip.

5 SU#3 lockout N (CBOT)

I(CBOR)

Loss of offsite power. Must energize non-vital busses.

Loss of power to PZR controllers must be controlled manually or transfer to automatic.

6 2CV1503-1 fails to open 2CV0340-2 breaker trips C(CBOT)

Results in loss of all feed to SGs.

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

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 2 RO Written Outline Date of Exam: 01/21/2005 RO K/A Category Points SRO - Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

TOTAL 1

3 3

33 3

33 3

18 2

1 2

22 1

22 1

9

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 4

5 55 N/A 4

55 N/A 4

27 1

2 2

3 3

3 2

2 3

2 3

3 28 2

1 1

1 1

1 1

1 1

0 1

1 10

2.

Plant Systems Tier Totals 3

3 4

4 4

3 3

4 2

4 4

38 1

2 3

4

3. Generic Knowledge and Abilities Catergories 3

2 3

2 10 Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO Outline and the SRO only outlines (i.e. except for one category in Tier 3 of the SRO-only outline, 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 RO exam must total 75 points and the SRO -only exam must total 25 points.

3. 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
4.

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

5.

Absent a plant specific priority, only those K/As 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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.*

The generic (G) 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.

8.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A number, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43 NUREG-1021, Revision 9 1 of 9

ES-401 2 Form ES-401-2 NUREG-1021, Revision 9 2 of 9 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group1 (RO /SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 00007 (BW/E02 & E10; CE/E02) Reactor Trip

- Stabilization - Recovery / 1 X

Ek2.1 Knowledge of the interrelations between the (Reactor Trip Recovery) and the following: Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.3 1

00008 Pressurizer Vapor Space Accident / 3 X

Ak2.02 Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Sensors and Detectors.

2.7*

1 000009 Small Break LOCA / 3 X

EA1.11 Ability to operate and/or monitor the following as they apply to a small break LOCA: EFW/MFW.

4.1 1

000011 Large Break LOCA / 3 X

EK1.01 Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA:

Natural Circulation and Cooling, including reflux boiling.

4.1 1

000015/17 RCP Malfunctions / 4 X

AA2.10 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions: When to secure RCPs on loss of cooling or seal injection.

3.7 1

000022 Loss of Rx Coolant Makeup / 2 X

AK1.03 Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump Makeup: Relationship between charging flow and PZR level.

3.0 1

000025 Loss of RHR System / 4 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System:

Isolation of RHR low-pressure piping prior to pressure increase above specified level.

3.3 1

000026 Loss of Component Cooling Water / 8 X

AA1.01 Ability to operate and/or monitor the following as they apply to the Loss of Component Cooling Water: CCW temperature indication.

3.1 1

000027 Pressurizer Pressure Control System Malfunction / 3 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions:

Verification of alternate transmitter and/or plant computer prior to shifting flow chart transmitters.

2.9*

1 000029 ATWS / 1 X

EK2.06 Knowledge of the interrelations between the ATWS and the following: Breakers, relays and disconnects.

2.9*

1 000038 Steam Gen. Tube Rupture / 3 X

EA1.13 Ability to operate and/or monitor the following as they apply to a SGTR: Steam flow indicators.

3.7*

1 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 X

EA2.2 Ability to determine and interpret the following as they apply to the (Excess Steam Demand): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.4 1

000054 (CE/E06) Loss of Main Feedwater / 4 X

EK1.2 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater): Normal, abnormal and emergency operating procedures associated with (Loss of Main Feedwater) 3.2 1

000055 Station Blackout / 6 X

2.2.30 Equipment Control : Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

3.5 1

000056 Loss of Off-site Power / 6 X

2.1.2. Emergency Procedures/Plan: Knowledge of Operator Responsibilities during all modes of plant operation.

3.0 1

ES-401 2 Form ES-401-2 NUREG-1021, Revision 9 3 of 9 000057 Loss of Vital AC Inst. Bus / 6 X

AA2.15 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: That a loss of AC has occurred.

3.8 1

000058 Loss of DC Power / 6 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in the EOP for loss of DC power.

4.0 1

000062 Loss of Nuclear Svc Water / 4 X

2.4.16 Emergency Procedures/Plan: Knowledge of EOP implementation hierarchy and coordination with other support procedures.

3.0 1

000065 Loss of Instrument Air / 8 Not selected W/E04 LOCA Outside Containment / 3 Not applicable to this Unit.

W/E11 Loss of Emergency Coolant Recirc. / 4 Not applicable to this Unit.

BW/E04; W/E05 Inadequate Heat Transfer

- Loss of Secondary Heat Sink / 4 Not applicable to this Unit.

K/A Category Totals:

3 3

3 3

3 3

Group Point Total:

18

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group2 (RO /SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000001 Continuous Rod Withdrawal / 1 X

AK3.01 Knowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal:

Manually driving rods into position that existed before start of casualty.

3.2 1

000003 Dropped Control Rod / 1 Not Selected.

000005 Inoperable/Stuck Control Rod / 1 X

AK1.05 Knowledge of the operational implications of the following concepts as they apply to Inoperable/Stuck Control Rod: Calculation of Minimum shutdown margin.

3.3 1

000024 Emergency Boration / 1 X

AK2.03 Knowledge of the interrelations between the Emergency Boration and the following: Controllers and positioners.

2.6 1

000028 Pressurizer Level Malfunction / 2 Not Selected.

000032 Loss of Source Range NI / 7 Not Selected.

000033 Loss of Intermediate Range NI / 7 Not applicable to this Unit.

000036 (BW/A08) Fuel Handling Accident / 8 Not Selected.

000037 Steam Generator Tube Leak / 3 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Reset and Check of Condensate air ejector exhaust monitor.

3.2 1

000051 Loss of Condenser Vacuum / 4 Not Selected.

000059 Accidental Liquid RadWaste Rel. / 9 Not Selected.

000060 Accidental Gaseous Radwaste Rel. / 9 Not Selected.

000061 ARM System Alarms / 7 X

AK2.01 Knowledge of the interrelations between the Area Radiation Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location.

2.5*

1 000067 Plant Fire On-site / 8 X

AA2.12 Ability to determine and interpret the following as they apply to the Plant Fire on Site: Location of vital equipment within fire zone.

2.9 1

000068 (BW/A06) Control Room Evac. / 8 Not Selected.

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

AA2.02 Ability to determine and interpret the following as they apply to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

3.9 1

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

EA1.01 Ability to operate and/or monitor the following as they apply to an Inadequate Core Cooling: RCS water inventory.

4.2 1

000076 High Reactor Coolant Activity / 9 Not Selected.

W/EO1 & E02 Rediagnosis & SI Termination / 3 Not applicable to this Unit.

W/E13 Steam Generator Over-pressure / 4 Not applicable to this Unit.

W/E15 Containment Flooding / 5 Not applicable to this Unit.

W/E16 High Containment Radiation / 9 Not applicable to this Unit.

BW/A01 Plant Runback / 1 Not applicable to this Unit.

BW/A02&A03 Loss of NNI-X/Y / 7 Not applicable to this Unit.

NUREG-1021, Revision 9 4 of 9

ES-401 3 Form ES-401-2 BW/A04 Turbine Trip / 4 Not applicable to this Unit.

BW/A05 Emergency Diesel Actuation / 6 Not applicable to this Unit.

BW/A07 Flooding / 8 Not applicable to this Unit.

BW/E03 Inadequate Subcooling Margin / 4 Not applicable to this Unit.

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not applicable to this Unit.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not Selected.

BW/E13&E14 EOP Rules and Enclosures Not applicable to this Unit.

CE/A11; W/E08 RCS Overcooling - PTS / 4 Not Selected.

CE/A16 Excess RCS Leakage / 2 X

2.2.2 Equipment Control: Ability to manipulate the console as required to operate the facility between shutdown and designated power levels.

4.0 1

CE/E09 Functional Recovery Not Selected.

K/A Category Point Totals:

1 2

2 1

2 1

9 NUREG-1021, Revision 9 5 of 9

ES-401 4 Form ES-401-2 NUREG-1021, Revision 9 6 of 9 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 003 Reactor Coolant Pump X

K5.05 Knowledge of the operational implications of the following concepts as they apply to the RCPS: The dependency of RCS flow rates upon the number of operating RCPs 2.8*

1 004 Chemical and Volume Control X

K4.05 Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Interrelationships and design basis, including fluid flow splits in branching network (e.g. charging and seal injection flow) 3.3 1

005 Residual Heat Removal X

K2.03 Knowledge of bus power supplies to the following: RCS Pressure boundary motor operated valves.

2.7*

1 006 Emergency Core Cooling X

K2.02 Knowledge of bus power supplies to the following: Valve Operators for accumulators.

2.5*

1 006 Emergency Core Cooling X

2.1.28 Conduct of Operations: Knowledge of the purpose and function of major system components and controls.

3.2 1

007 Pressurizer Relief/ Quench Tank X

K5.02 Knowledge of the operational implications of the following concepts as they apply to the PRTS: Method of forming a steam bubble in the PZR.

3.1 1

007 Pressurizer Relief/ Quench Tank X

2.2.22 Equipment Control: Knowledge of limiting conditions for operations and safety limits.

3.4 1

008 Component Cooling Water X

K3.02 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: CRDS.

2.9 1

010 Pressurizer Pressure Control X

K6.04 Knowledge of the effect of a loss or malfunction of the following will have on the PZR PCS: PRT (Pressurizer Relief Tank).

2.9 1

012 Reactor Protection X

K3.02 Knowledge of the effect that a loss or malfunction of the RPS will have on the following: T/G.

3.2*

1 012 Reactor Protection X

A4.02 Ability to manually operate and/or monitor in the control room: Components for individual channels.

3.3 1

013 Engineered Safety Features Actuation X

K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the ESFAS: Sensors and detectors.

2.7*

1 022 Containment Cooling X

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the CCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload/high-speed operation.

2.6 1

025 Ice Condenser Not applicable to this unit.

026 Containment Spray X

A3.01 Ability to monitor automatic operation of the CSS, including: Pump starts and correct MOV positioning.

4.3 1

039 Main and Reheat Steam X

K5.08 Knowledge of the operational implications of the following concepts as they apply to the MRSS: Effect of steam removal on reactivity.

3.6 1

ES-401 4 Form ES-401-2 NUREG-1021, Revision 9 7 of 9 059 Main Feedwater X

K1.07 Knowledge of the physical connections and/or cause-effect relationships between the MFW System and the following systems: ICS (FWCS) 3.2 1

061 Auxiliary/Emergency Feedwater X

K3.01 Knowledge of the effect that a loss or malfunction of the AFW System will have on the following: RCS 4.4 1

062 AC Electrical Distribution X

K4.05 Knowledge of A.C. Distribution System design feature(s) and/or interlock(s) which provide for the following: Paralleling of ac sources (synchroscope) 2.7*

1 063 DC Electrical Distribution X

A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the D.C.

Electrical System controls including: Battery capacity as it is affected by discharge rate.

2.5 1

063 DC Electrical Distribution X

2.4.29 Emergency Procedures/Plan: Knowledge of the emergency plan.

2.6 1

064 Emergency Diesel Generator X

K4.02 Knowledge of ED/G System design feature(s) and/or interlock(s) which provide for the following: Trips for the ED/G while operating (normal or emergency).

3.9 1

064 Emergency Diesel Generator X

A4.07 Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid.

3.4 1

073 Process Radiation Monitoring X

A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM System controls including: Radiation levels.

3.2 1

076 Service Water X

K1.15 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: FPS (Fire Protection System) 2.5 1

078 Instrument Air X

A3.01 Ability to monitor automatic operation of the IAS, including: Air pressure 3.1 1

078 Instrument Air X

A4.01 Ability to manually operate and/or monitor in the control room: Pressure gages 3.1 1

103 Containment X

A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency Containment Entry 2.9 1

103 Containment X

A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Containment System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Containment evacuation (including recognition of the alarm) 3.5*

1 K/A Category Point Totals:

2 2

3 3

3 2

2 3

2 3

3 Group Point Total:

28

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 001 Control Rod Drive Not selected 002 Reactor Coolant X

K4.03 Knowledge of RCS design feature(s) and/or interlock(s) which provide for the following: Venting the RCS 2.9 1

011 Pressurizer Level Control X

K2.02 Knowledge of bus power supplies to the following: PZR Heaters 3.1 1

014 Rod Position Indication Not selected 015 Nuclear Instrumentation X

K1.04 Knowledge of the physical connections and/or cause-effect relationships between the NIS and the following systems: ESF (Engineered safety Feature) 3.5*

1 016 Non-nuclear Instrumentation Not selected 017 In-core Temperature Monitor X

K6.01 Knowledge of the effect of a loss or malfunction of the following will have on the ITM System components: Sensors and detectors 2.7 1

027 Containment Iodine Removal Not selected 028 Hydrogen Recombiner and Purge Control X

2.4.20 Emergency Procedures/Plan: Knowledge of operational implications of EOP warnings, cautions and notes.

3.3 1

029 Containment Purge Not selected 033 Spent Fuel Pool Cooling Not selected 034 Fuel Handling Equipment X

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Mispositioned fuel element 3.3 1

035 Steam Generator Not selected 041 Steam Dump/Turbine Bypass Control X

K3.04 Knowledge of the effect that a loss or malfunction of the SDS will have on the following:

Reactor Power 3.5 1

045 Main Turbine Generator X

A1.06 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MT/G System controls including: Expected response of secondary plant parameters following T/G trip.

3.2 1

055 Condenser Air Removal Not selected 056 Condensate Not selected 068 Liquid Radwaste Not selected 071 Waste Gas Disposal X

A4.25 Ability to manually operate and/or monitor in the control room: Setting of process radiation monitor alarms, automatic functions, and adjustments of set points.

3.2*

1 072 Area Radiation Monitoring X

K5.01 Knowledge of the operational implications of the following concepts as they apply to the ARM system: Radiation theory, including sources, types, units, and effect.

2.7 1

075 Circulating Water Not selected 079 Station Air Not selected 086 Fire Protection Not selected K/A Category Totals:

1 1

1 1

1 1

1 1

0 1

1 Group Point Total:

10 NUREG-1021, Revision 9 8 of 9

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One Unit 2 RO Written Outline Date of Exam: 01/21/2005 Category K/A #

Topic RO IR 2.1 2.1.9 Ability to direct personnel activities inside the control room 2.5 1

2.1 2.1.17 Ability to make accurate, clear and concise verbal reports 3.5 1

2.1 2.1.28 Knowledge of the purpose and function of major system components and controls.

3.2 1

2.1 2.1 2.1

1.

Conduct of Operations Subtotal 3

2.2 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.

2.6 1

2.2 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

2.5 1

2.2 2.2 2.2

2.

Equipment Control Subtotal 2

2.3 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.5 1

2.3 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

2.9 1

2.3 2.3.11 Ability to control radiation releases.

2.7 1

2.3 2.3 2.3

3.

Radiation Control Subtotal 3

2.4 2.4.15 Knowledge of communications procedures associated with EOP implementation.

3.0 1

2.4 2.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

2.9 1

2.4 2.4 2.4

4.

Emergency Procedures/ Plan Subtotal 2

Tier 3 Point Total 10 NUREG-1021, Revision 9 9 of 9

ES-401 PWR Examination Outline Form ES-401-2 Facility: Arkansas Nuclear One Unit 2 SRO Written Outline Date of Exam: 01/21/2005 RO K/A Category Points SRO - Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

TOTAL 1

4 2

6 2

3 1

4

1.

Emergency &

Abnormal Plant Evolutions Tier Totals N/A N/A 7

3 10 1

3 2

5 2

2 1

3

2.

Plant Systems Tier Totals 5

3 8

1 2

3 4

3. Generic Knowledge and Abilities Catergories 2

1 2

2 7

Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO Outline and the SRO only outlines (i.e. except for one category in Tier 3 of the SRO-only outline, 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 RO exam must total 75 points and the SRO -only exam must total 25 points.

3. 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
4.

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

5.

Absent a plant specific priority, only those K/As 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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.*

The generic (G) 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.

8.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A number, descriptions, importance ratings, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43 NUREG-1021, Revision 9 1 of 7

ES-401 2 Form ES-401-2 NUREG-1021, Revision 9 2 of 7 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group1 (RO /SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 00007 (BW/E02 & E10; CE/E02) Reactor Trip

- Stabilization - Recovery / 1 Not selected 00008 Pressurizer Vapor Space Accident / 3 Not selected 000009 Small Break LOCA / 3 Not selected 000011 Large Break LOCA / 3 X

EA2.03 Ability to determine and interpret the following as they apply to a Large Break LOCA: Consequences of managing LOCA with loss of CCW.

4.2 1

000015/17 RCP Malfunctions / 4 Not selected 000022 Loss of Rx Coolant Makeup / 2 Not selected 000025 Loss of RHR System / 4 Not selected 000026 Loss of Component Cooling Water / 8 Not selected 000027 Pressurizer Pressure Control System Malfunction / 3 Not selected 000029 ATWS / 1 Not selected 000038 Steam Gen. Tube Rupture / 3 Not selected 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 X

AA2.05 - Ability to determine and interpret the following as they apply to the Steam Line Rupture: When ESFAS systems may be secured.

4.5 1

000054 (CE/E06) Loss of Main Feedwater / 4 X

2.4.36 - Emergency plan/ Procedures: Knowledge of chemistry/health physics tasks during emergency operations.

2.8 1

000055 Station Blackout / 6 Not selected 000056 Loss of Off-site Power / 6 X

AA2.19 - Ability to determine and interpret the following as they apply to the Loss of Offsite Power: T-cold and T-hot indicators (wide range).

4.2 1

000057 Loss of Vital AC Inst. Bus / 6 Not selected 000058 Loss of DC Power / 6 X

2.4.9 - Emergency plan/ Procedures: Knowledge of low power/shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

3.9 1

000062 Loss of Nuclear Svc Water / 4 Not selected 000065 Loss of Instrument Air / 8 X

AA2.04 - Ability to determine and interpret the following as they apply to the Loss of Instrument Air: Typical conditions which could cause a compressor trip (e.g.,

high temperature).

2.7 1

W/E04 LOCA Outside Containment / 3 Not applicable to this Unit.

W/E11 Loss of Emergency Coolant Recirc. / 4 Not applicable to this Unit.

BW/E04; W/E05 Inadequate Heat Transfer

- Loss of Secondary Heat Sink / 4 Not applicable to this Unit.

K/A Category Totals:

Group Point Total:

6

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier1 /Group2 (RO /SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000001 Continuous Rod Withdrawal / 1 Not selected 000003 Dropped Control Rod / 1 Not selected 000005 Inoperable/Stuck Control Rod / 1 Not selected 000024 Emergency Boration / 1 Not selected 000028 Pressurizer Level Malfunction / 2 Not selected 000032 Loss of Source Range NI / 7 Not selected 000033 Loss of Intermediate Range NI / 7 Not selected/Not applicable 000036 (BW/A08) Fuel Handling Accident / 8 X

AA2.02 - Ability to determine and interpret the following as they apply to the Fuel Handling Incidents:

Occurrence of a fuel handling incident.

4.1 1

000037 Steam Generator Tube Leak / 3 Not selected 000051 Loss of Condenser Vacuum / 4 Not selected 000059 Accidental Liquid RadWaste Rel. / 9 X

AA2.05 -Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: The occurrence of automatic safety actions as a result of a high PRM system signal.

3.9 1

000060 Accidental Gaseous Radwaste Rel. / 9 Not selected 000061 ARM System Alarms / 7 Not selected 000067 Plant Fire On-site / 8 Not selected 000068 (BW/A06) Control Room Evac. / 8 Not selected 000069 (W/E14) Loss of CTMT Integrity / 5 Not selected 000074 (W/E06&E07) Inad. Core Cooling / 4 Not selected 000076 High Reactor Coolant Activity / 9 Not selected W/EO1 & E02 Rediagnosis & SI Termination / 3 Not applicable to this Unit.

W/E13 Steam Generator Over-pressure / 4 Not applicable to this Unit.

W/E15 Containment Flooding / 5 Not applicable to this Unit.

W/E16 High Containment Radiation / 9 Not applicable to this Unit.

BW/A01 Plant Runback / 1 Not applicable to this Unit.

BW/A02&A03 Loss of NNI-X/Y / 7 Not applicable to this Unit.

BW/A04 Turbine Trip / 4 Not applicable to this Unit.

BW/A05 Emergency Diesel Actuation / 6 Not applicable to this Unit.

BW/A07 Flooding / 8 Not applicable to this Unit.

BW/E03 Inadequate Subcooling Margin / 4 Not applicable to this Unit.

NUREG-1021, Revision 9 3 of 7

ES-401 3 Form ES-401-2 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not applicable to this Unit.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not selected BW/E13&E14 EOP Rules and Enclosures Not applicable to this Unit.

CE/A11; W/E08 RCS Overcooling - PTS / 4 X

2.4.5 - Emergency Plan/Procedures: Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

3.6 1

CE/A16 Excess RCS Leakage / 2 Not selected CE/E09 Functional Recovery X

EA2.2 - Ability to determine and interpret the following as they apply to the (Functional Recover): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

4.0 1

K/A Category Point Totals:

Group Point Total:

4 NUREG-1021, Revision 9 4 of 7

ES-401 4 Form ES-401-2 NUREG-1021, Revision 9 5 of 7 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 1 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 003 Reactor Coolant Pump Not selected 004 Chemical and Volume Control X

A2.16 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: T-ave.

and T-ref. deviations.

3.6 1

005 Residual Heat Removal X

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Pressure transient protection during cold shutdown.

3.7 1

006 Emergency Core Cooling Not selected 007 Pressurizer Relief/ Quench Tank Not selected 008 Component Cooling Water Not selected 010 Pressurizer Pressure Control Not selected 012 Reactor Protection Not selected 013 Engineered Safety Features Actuation Not selected 022 Containment Cooling X

A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS Pump.

3.2 1

025 Ice Condenser Not selected/Not applicable 026 Containment Spray Not selected 039 Main and Reheat Steam X

2.2.19 - Equipment Control: Knowledge of Maintenance Work Order Requirements.

3.1 1

059 Main Feedwater Not selected 061 Auxiliary/Emergency Feedwater Not selected 062 AC Electrical Distribution Not selected 063 DC Electrical Distribution Not selected 064 Emergency Diesel Generator Not selected 073 Process Radiation Monitoring Not selected 076 Service Water X

2.2.5 - Equipment Control: Knowledge of the process for making changes in the facility as described in the safety analysis report.

2.7 1

078 Instrument Air Not selected 103 Containment Not selected K/A Category Point Totals:

Group Point Total:

5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant systems - Tier 2/Group 2 (RO / SRO)

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 001 Control Rod Drive Not selected 002 Reactor Coolant Not selected 011 Pressurizer Level Control Not selected 014 Rod Position Indication Not selected 015 Nuclear Instrumentation Not selected 016 Non-nuclear Instrumentation Not selected 017 In-core Temperature Monitor Not selected 027 Containment Iodine Removal X

2.4.4 - Emergency Procedures/Plan Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.3 1

028 Hydrogen Recombiner and Purge Control Not selected 029 Containment Purge X

A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Maintenance or other activity taking place inside containment.

3.6 1

033 Spent Fuel Pool Cooling Not selected 034 Fuel Handling Equipment Not selected 035 Steam Generator X

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the S/GS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Reactor trip/turbine trip.

4.4 1

041 Steam Dump/Turbine Bypass Control Not selected 045 Main Turbine Generator Not selected 055 Condenser Air Removal Not selected 056 Condensate Not selected 068 Liquid Radwaste Not selected 071 Waste Gas Disposal Not selected 072 Area Radiation Monitoring Not selected 075 Circulating Water Not selected 079 Station Air Not selected 086 Fire Protection Not selected K/A Category Totals:

Group Point Total:

3 NUREG-1021, Revision 9 6 of 7

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Arkansas Nuclear One Unit 2 SRO Written Outline Date of Exam: 01/21/2005 Category K/A #

Topic SRO-Only IR 2.1 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.

2.9 1

2.1 2.1.14 Knowledge of system status criteria which require the notification of plant personnel.

3.3 1

2.1 2.1 2.1 2.1

1.

Conduct of Operations Subtotal 2

2.2 2.2.26 Knowledge of refueling administrative requirements.

3.7 1

2.2 2.2 2.2 2.2 2.2

2.

Equipment Control Subtotal 1

2.3 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

3.0 1

2.3 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.

3.2 1

2.3 2.3 2.3 2.3

3.

Radiation Control Subtotal 2

2.4 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.

3.6 1

2.4 2.4.41 Knowledge of the emergency action level thresholds and classifications.

4.1 1

2.4 2.4 2.4 2.4

4.

Emergency Procedures/ Plan Subtotal 2

Tier 3 Point Total 7

NUREG-1021, Revision 9 7 of 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection RO Exam Tier 1 Group 1 Generic EOP 007 EK1.02 Reactor Trip This K&A was selected using the Random Generation Program provided by Westinghouse. This program also selected a CE specific K&A for Reactor Trip CE/E02 EK2.1. This caused a duplicate evolution to be selected prior to all evolutions in this tier being selected in accordance with Note 4 on the written outline cover sheet.

The K&As for both selected Reactor Trip evolutions were placed in a container, and this K&A was randomly selected for deletion. The three remaining evolutions in Tier 1 Group 1 that were not selected, Large Break LOCA, Loss of Offsite Power, and Loss of IA, were placed in a container and the Large Break LOCA EOP was randomly selected.

To maintain the balance of the K&A categories a like for like K1 to K1 in the Large Break LOCA section of the K&A catalog was selected. This resulted in K&A 011 EK1.01 being selected.

RO Exam Tier 1 Group 1 Generic AOP 022 AK1.04 Loss of Reactor Coolant Makeup This K&A requires knowledge of the charging flow valve controller associated with centrifugal charging pumps.

ANO Unit 2 has positive displacement charging pumps only and therefore we have no associated flow valve controller to adjust charging flow. This K& A was replaced with 022 AK1.03, Relationship between charging flow and PZR level. This K&A was randomly selected from the other K1 K&As for this topic to maintain the same sample plan K&A balance.

RO Exam Tier 1 Group 1 Generic EOP 054 2.2.2 Loss of Main Feedwater This K&A was selected using the Random Generation Program provided by Westinghouse. This program also selected a CE specific K&A for Reactor Trip CE/E06 EK1.2. This caused a duplicate evolution to be selected prior to all evolutions in this tier being selected in accordance with Note 4 on the written outline cover sheet.

The K&As for both selected Loss of Main Feedwater evolutions were placed in a container, and this K&A was randomly selected for deletion. The Loss of Offsite Power evolution was selected over the Loss of IA evolution due to the selection of the IA system twice in RO outline Tier 2 Group 1. This will prevent an over-emphasis of a system/evolution in accordance with the Exam Outline Quality Checklist assessment. To maintain the balance of the K&A categories a like for like Generic to Generic was randomly selected in the Loss of Offsite Power section of

the K&A catalog was selected. This resulted in K&A 2.1.2 being selected for Loss of Offsite Power.

RO Exam Tier 3 Conduct of Operations Generic K&A 2.1.17 Based on Feedback from the NRC, this originally selected K&A was replaced due to the nature of this K&A. It is more designed to test the candidates ability to communicate properly during activities that would be best evaluated in the simulator. This K&A was replaced with randomly selected K&A 2.1.32 out of all the other 2.1 Generic K&As.

SRO Exam Tier 1 Group 1 Loss of Instrument Air 065 AA2.04 This K&A was rejected based on NRC feedback due to the specific wording of the K&A not SRO only knowledge.

Since there are already 2 Loss of IA questions on the combined RO/SRO exam, we placed all the systems in this tier/group that had not been selected already and randomly selected another system. We then used the same K&A number to keep the same balance on the sample plan. This resulted in selection of Loss of Residual Heat Removal System K&A 025 AA2.04 SRO Exam Tier 2 Group 1 Chemical and Volume Control System 004 A2.16 This K&A was rejected based on NRC feedback that a question on T-ave and T-ref deviation would always have a dilution/boration which is an RO Task. Therefore to develop a SRO only question, a new K&A was randomly selected for this system. K&A 004 A2.15 was selected.

SRO Exam Tier 2 Group 1 Containment Cooling System 022 A2.03 After a review of the sample plans, this K&A was found to be a duplicate of the randomly selected Tier 2 Group 1 RO sample plan outline. Since the SRO candidates will also take the 75 question RO exam and since this K&A is specific to Containment Cooling Fan failures, we did not feel we should generate two very similar questions on the same topic. This K&A was replaced with 022 A2.06, Loss of CCS Pump. This K&A was randomly selected from the other A2 K&As for this topic to maintain the same sample plan K&A balance.

NUREG-1021, Revision 9

Suppressed K/As Facility: Arkansas Nuclear One Basis for Suppression IMPORTANCE RO / SRO 001 Continuous Rod Withdrawal K1 Knowledge of the operational implications of the following concepts as they apply to Continuous Rod Withdrawal:

AK1.14 Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS Not Applicable to ANO Unit 2 3.4*/3.7 003 Dropped Control Rod K1 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:

AK1.13 Interaction of ICS control stations as well as purpose, function, and modes of operation of ICS Not Applicable to ANO Unit 2 3.2*/3.6 AK1.18 Voids coefficient Not Applicable to ANO Unit 2 2.1/2.2 AK2.03 Metroscope Not Applicable to ANO Unit 2 3.1*/3.2*

AK3.01 When ICS logic has failed on a dropped rod, the load must be reduced until flux is within specified target bank Not Applicable to ANO Unit 2 3.5*/3.9*

005 Inoperable/Stuck Control Rod K2 Knowledge of the interrelations between the Inoperable/Stuck Control Rod and the following:

AK2.03 Metroscope Not Applicable to ANO Unit 2 3.1*/3.3*

AA1.03 Metroscope Not Applicable to ANO Unit 2 3.4*/3.4*

008 Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open)

A2 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:

AA2.05 PORV isolation (block valve switches and indicators)

Not Applicable to ANO Unit 2 3.9/3.9 033 Loss of Intermediate Range Nuclear Instrumentation

K1 Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:

AK1.01 Effects of voltage changes on performance Not Applicable to ANO Unit 2 2.7/3.0 AK2.01 Power supplies, including proper switch position Not Applicable to ANO Unit 2 2.4/2.9 AK2.02 Sensors and detectors Not Applicable to ANO Unit 2 2.3/2.6 AK3.01 Termination of startup following loss of intermediate-range instrumentation Not Applicable to ANO Unit 2 3.2/3.6 AK3.02 Guidance contained in EOP for loss of intermediate-range instrumentation Not Applicable to ANO Unit 2 3.6/3.9 AA1.01 Power-available indicators in cabinets or equipment drawers Not Applicable to ANO Unit 2 2.9/3.1 AA1.02 Level trip bypass Not Applicable to ANO Unit 2 3.0/3.1 AA1.03 Manual restoration of power Not Applicable to ANO Unit 2 3.0*/3.2*

AA2.01 Equivalency between source-range, intermediate-range, and power-range channel readings Not Applicable to ANO Unit 2 3.0/3.5 AA2.02 Indications of unreliable intermediate-range channel operation Not Applicable to ANO Unit 2 3.3/3.6 AA2.03 Indication of blown fuse Not Applicable to ANO Unit 2 2.8/3.1 AA2.04 Satisfactory overlap between source-range, intermediate-range and power-range instrumentation Not Applicable to ANO Unit 2 3.2/3.6 AA2.05 Nature of abnormality, from rapid survey of control room data Not Applicable to ANO Unit 2 3.0*/3.1?

AA2.06 Cause of failure of an intermediate-range channel Not Applicable to ANO Unit 2 2.3/2.8*

AA2.07 Confirmation of reactor trip Not Applicable to ANO Unit 2 3.9/4.2 AA2.08 Intermediate range channel operability Not Applicable to ANO Unit 2 3.3/3.4 AA2.09 Conditions which allow bypass of an intermediate-range level trip switch Not Applicable to ANO Unit 2 3.4*/3.7*

AA2.10 Tech-Spec limits if both intermediate-range channels have failed Not Applicable to ANO Unit 2 3.1/3.8 AA2.11 Loss of compensating voltage Not Applicable to ANO Unit 2 3.1/3.4

AA2.12 Maximum allowable channel disagreement Not Applicable to ANO Unit 2 2.5*/3.1*

AA2.13 Testing required if power lost, then restored Not Applicable to ANO Unit 2 2.2*/2.8*

025 Ice Condenser System K1 Knowledge of the physical connections and/or cause-effect relationships between the Ice Condenser System and the following systems:

K1.01 Containment ventilation Not Applicable to ANO Unit 2 2.7*/2.7*

K1.02 Refrigerant systems Not Applicable to ANO Unit 2 2.7*/2.7*

K1.03 Containment sump system Not Applicable to ANO Unit 2 3.2*/3.0*

K2.01 Containment ventilation fans and dampers Not Applicable to ANO Unit 2 2.2*/2.7*

K2.02 Refrigerant systems Not Applicable to ANO Unit 2 2.0*/2.5*

K2.03 Isolation valves Not Applicable to ANO Unit 2 2.0*/2.2*

K3.01 Containment Not Applicable to ANO Unit 2 3.8*/3.8*

K4.01 Glycol expansion tank levels and ice condenser system containment isolation valves Not Applicable to ANO Unit 2 2.2*/2.5*

K4.02 System control Not Applicable to ANO Unit 2 2.8*/3.0*

K5.01 Relationships between pressure and temperature Not Applicable to ANO Unit 2 3.0*/3.4*

K5.02 Heat transfer Not Applicable to ANO Unit 2 2.6*/2.8*

K5.03 Gas laws Not Applicable to ANO Unit 2 2.4*/2.8*

K6.01 Upper and lower doors of the ice condenser Not Applicable to ANO Unit 2 3.4*/3.6*

A1.01 Temperature chart recorders Not Applicable to ANO Unit 2 3.0*/3.0*

A1.02 Glycol expansion tank level Not Applicable to ANO Unit 2 2.5*/2.2*

A1.03 Glycol flow to ice condenser air handling units Not Applicable to ANO Unit 2 2.5*/2.5*

A2.01 Trip of glycol circulation pumps Not Applicable to ANO Unit 2 2.2*/2.7*

A2.02 High/low floor cooling temperature Not Applicable to ANO Unit 2 2.7*/2.5*

A2.03 Opening of ice condenser doors Not Applicable to ANO Unit 2 3.0*/3.2*

A2.04 Containment isolation Not Applicable to ANO Unit 2 3.0*/3.2*

A2.05 Abnormal glycol expansion tank level Not Applicable to ANO Unit 2 2.5*/2.7*

A2.06 Decreasing ice condenser temperature Not Applicable to ANO Unit 2 2.5*/2.7*

A3.01 Refrigerant system Not Applicable to ANO Unit 2 3.0*/3.0*

A3.02 Isolation valves Not Applicable to ANO Unit 2 3.4*/3.4*

A4.01 Ice condenser isolation valves Not Applicable to ANO Unit 2 3.0*/2.7*

A4.02 Containment vent fans Not Applicable to ANO Unit 2 2.7*/2.5*

A4.03 Glycol circulation pumps Not Applicable to ANO Unit 2 2.2*/2.2*

103 Containment System K1 Knowledge of the physical connections and/or cause-effect relationships between the Containment System and the following systems:

K1.03 Shield building vent system Not Applicable to ANO Unit 2 3.1*/3.5*

K1.06 Subsurface drain system Not Applicable to ANO Unit 2 2.4*/2.7*

K1.07 Containment vacuum system Not Applicable to ANO Unit 2 3.5*/3.7*

K4.01 Vacuum breaker protection Not Applicable to ANO Unit 2 3.0*/3.7*

A4.05 PDP speed controller Not Applicable to ANO Unit 2 2.4*/2.2*

A4.09 Containment vacuum system Not Applicable to ANO Unit 2 3.1*/3.7*

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