Text

Draft Administrative Documents
	ML092850004
Person / Time
Site:	Summer
Issue date:	10/10/2009
From:	; NRC/RGN-II
To:	; South Carolina Electric & Gas Co
References
	50-395/09-301
	Download: ML092850004 (30)
	v • d • e

~s=401, Rev. 9 I

PWR examination Outline Facility: ~ tI M t71/A..

Date of Exam:

1~9 I

I RO KIA Category Points SRO-Only Points I

i Tier Group I

K K

A A

G A2 G*

Total I i

1 2

3 4

5 6

1 2

3 4

Total I

I

1.

1 3

4 3

3 3

2 18 3

3 6

I Emergency &

2 2

1 2

1 1

2 9

2 2

4 Abnormal Plant N/A N/A i

Evolutions Tier Totals 5

5 5

4 4

4 27 5

5 10 I

I 1

2 2

2 3

3 3

2 3

3 2

3 28 2

3 5

I I

2.

2 1

0 1

1 1

10 2

1 3

I I

Plant Systems Tier Totals 3

2 3

4 4

4 3

4 4

3 4

38 4

4 8

I

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

2 3

2 2

1 2

2 I

I i I

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only ouUlnes (I.e., except for one category In Tier 3 of the SRO-only outline, the "Tier Totals" In each KIA category shall not be less than two).

I

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 I

based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 pOints.

I

3.

Systemslevolutions within each group are Identified on the associated outline; systems or evolutions that do i

I I

not apply at the facility should be deleted and justified; operationally important, site-specific systems that are I not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

I

4.

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

I

5.

Absent a plant-specific priority, only those KIAs having an Importance rating (IR) of 2.5 or higher shall be I

selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

i I

6.

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

I

7.

The generic (G) K/As In Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics I

must be relevant to the applicable evolution or system.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topiCS' Importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter I

the group and tier totals for each category In the table above; if fuel handling equipment is sampled In other I

than Category A2 or G* on the SRO-only exam, enter It on the left side of Column A2 for Tier 2, Group 2 (Note

1 does not apply). Use duplicate pages for RO and SRO-only exams.

I

9.

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

I

____________ J QPA~r I E8-401, Rev. 9 PWR examination Outline Fonn E8-401*2 Facility: <;;11 nt." tA...

Date of Exam:

ltfl9 I

RO KIA Category Points SR~1y Points i

Tier Group I

K K

A A

G A2 G*

Total I

1 2

3 4

5

1 2

3 4

Total I

1.

1 3

4,

2 18 3

6 I

Emergency &

2 2, 2 2

2 2

4 Abnonnal Plant NJA NIA I

Evolutlons Tier Totals 5

5 5

4 4

4 Z7 5

5 10 1

2 2

2 3,, 2,, 2,

28 2

5

2.

Plant 2

1 0,,,,,,,,,

10 2

Systems l ief" Totals, 2, 4 4

4, 4 4, 4 "

4 4

8 I

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 1

Categories 2

2 2,

2 2

1.

Ensure that at least two ~cs from every appUca~ KIA category are sampled within each tier of the RO arK! SRO-ooiy ouUlnea (I.e., 8J(cept for one category In Tier 3 of the SRQ-onIy outline. the ' ller Totals" kI ead! KIA categOl'}' ahall not be lua than two).

( ~

2.

The point total for each grnup and tier In the proposed ooUine must match that specified In the table.

The final point total for each group and tler may deviate by t 1 from that specified In the fable boIsed on NRC revision *. Tl1e flnal RO exam must totaL 75 paints and the SRO-ooly eKam must total 25 points.

3.

Systems/evolutions within each group are identified on the assoo::lated outline; systems or evolutions that do not apply at the facility should be deleted and JU3tlfied; operationelly Important, slte-spe<:Uic systems that are not Included on the outline sl'K)uld be added. Refer to E5-401, Attachment 2, for guidance regarding the eliminatJon of Inappropriate KIA statements.

4.

Seleet topics from as many systems and evolutions as possible; sample every system Of" evolution In the group before selecting a second topic ro.- any system or evolution.

5.

Absent a plant-specific Pflorlty, only those KlAs having an Importance raUng (IR) of 2.5 0( higher shall be selected. Use the RO and SRO ratings for the RO and SRQ-on/y portions, respectively.

8.

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

7.

--rhe generic (G) KlAs In TIers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relavant to the applicable evolutlon Of" system.

8.

On the following pages, enter the KIA numbers, a brief descrlptlon of each topic, the topics' Importance ratings (IRs) to( the applicable license level, and the point totals (') for each system and category. Enter the group and tier totals tOf" each category In the table above; If fuel handling equipment Is.ampted In other than Category A2 01"" G* on the SRO-ooly ellam, enter It on the left slOe of Column A2 for TIer 2, Group 2 (Note

, 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

FO( TIer 3, select topiCS from section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (') on Form E5-401*3. Limit SRO selections to KIA. that are linked to 10 CFR 55.43.

(

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 008AA1.06 Pressurizer Vapor Space Accident 1 3 3.6 3.6 0 0 0 0 0 0 ~ 0 0 0 0 011EK3.15 Large Break LOCA 13 015AK2.07 RCP Malfunctions 1 4 015AK2.07 RCP Malfunctions 1 4 022AA2.02 Loss of Rx Coolant Makeup 1 2 025AK1.01 Loss of RHR System 1 4

~

Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51

.45.5) 4.3 4.4 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 2.9 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) 2.9 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) 3.2 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct. control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.9 4.3

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections andlor cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8)

P~f3

"-./

FORM ES-401-2 TOPIC:

Control of PZR level Criteria for shifting to recirculation mode RCP seals RCP seals Charging pump problems Loss of RHRS during all modes of operation 4/3/2008 J

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 1(3 1<4 1(5 1(6 Al A2 A3 A4 G RO SRO 008AA1.06 Pressurizer Vapor Space Accidenlf3 3.6 3.6 0 0 0 0 0 0 ~ 0 0 0 0 0"EK3,15 Large Break LOCA/3 015AK2.01 Rep MalfunctiOns f 4 015AK2.07 Rep Malfunctions 14 022AA2.02 l oss of Rx Coolant Makeup 12 025AK1.01 Loss of RHR System 14 Ability to predict and/Of" monitor changes in pall'lmeters associated with operating the (SYSTEM) controls inciuding:(CFR: 41.5 f 45.5) 4.3 4.4 OO ~ OOOOOOOO Knowledge of the effect that a loss or malfunction of the (SYSTEM) wi" have 00 the folkrMng:(CFR: 41.7145.6) 2.'

2.'

O ~ OOOOOOOOO Kno'NIedge 01 electrical power suppfles to the foliowing:(CFR: 41.7) 2.' 2.'

O ~ OOOOOOOOO Knowledge of electrical power supplies to the foIlO'Ning:(CfR: 41.7) 3.2 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) pt'edict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures 10 COITeCl control, or mitigate the consequences of those abnormal opef3tioo:(CFR: 41.5 / 43.5/45_3 145.13) 3.' 4.3

~ OOOOOOOOOO Knowledge 01 the physical connections and/or cause-effect relationships between (SYSTEM) and the loIlowing:(CFR 41.2 to 41.9/45.11045.8)

P","'3 FORM ES-401*2 TOPIC:

Control of PZR level Criteria for shifting to recirculation mode RCP seats Rep seals Charging pump problems Loss 01 RHRS during an modes 01 operation 41312008

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 026AG2.1.20 Loss of Component Cooling Water / 8 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

027AK2.03 029EK1.02 038EK1.01 054AK3.03 055EA1.01

~

'---./

Pressurizer Pressure Control System Malfunction / 3 ATWS 11 Steam Gen. Tube Rupture 1 3 Loss of Main Feedwater 1 4 Station Blackout / 6 This is a Generic. no stem statement is associated.

2.6 2.8 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to

, the following:(CFR: 41.7) 2.6 2.8

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections andlor cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8) 3.1 3.4

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8) 3.8 4.1 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 3.7 3.9 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5)

,-f3 FORM ES-401-2 TOPIC:

Ability to execute procedure steps.

Controllers and positioners Definition of reactivity Use of steam tables Manual control of AFW flow control valves In-core thermocouple temperatures 4/3/2008

~.

ES-401. REV 9 T1Gl PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 026AG2.1.20 LossofComponentCooliogWater/8 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

027AK2.03 029EK 1.02 038EK1.0 1 Pressurizer Pressure Control System Malfunction I J ATWSf1 Steam Gen. TUbe RuplUfe /3 054AK3.03 Loss 01 Main Feedwaler 14 055EA1.01 Station Blackout { 6 This Is 8 Genenc. no stem statement is aSSOCiated.

2.6 2.8 D ~ DDDDDDDDD Knowledge of electrical power supplies to the followlng:(CFR: 41.7) 2.6 2.8

~ DDDDDDDDDD Knowledge of the physiCal conl'leCtions and/or cause-effecl relationships between (SYSTEM) and the foUowing:(CFR: 41.2 to 41.9145.7 to 45.8) 3.1 3.4 Ii/I 0 0 0 0 0 0 0 0 0 0 Kl'lOYI'Iedge of the physical connections andlor causa-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.1 to 45.8) 3.8 4 1 0 0 ~ 0 0 0 0 0 0 0 0 Koo-Medge of the effect thai a loss or malfunction of the (SYSTEM) win have on the following:(CFR: 41.7145.6) 3.7 3.9 DDDDDD ~ DDDD Ability to predict andfor monitor changes in parameters associated with operating the (SYSTEM) controls includlng:(CfR: 41.5 (

45.5) 1-'3 FORM ES-401-2

TOPIC, Ability to exectJle procedure steps.

CootroliefS and poSitioners Definition of reactivity Use of steam tables Manual control of AFW flow control valves In-core thefTTlocouple temperatures 41312008

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 056AA2.02 Loss of Off-site Power 1 6 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0 0 057AG2.4.B Loss of Vital AC Inst. Bus 16 06SAK3.0B Loss of Instrument Air ( B 077AK2.02 Generator Voltage and Electric Grid Disturbances I 6 WE04EA 1.1 LOCA Outside Containment 1 3 WEOSEA2.1 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.B 4.S 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.7 3.9 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/4S.6) 3.1 3.3 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7}

4.0 4.0 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.SI 4S.S) 3.4 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.S ( 43.S ( 4S.3 14S.13)

~

P.",..f3

"--..-/

\\...J FORM ES-401-2 TOPIC:

ESF load sequencer status lights Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Actions contained in EOP for loss of instrument air Breakers, relays Components and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

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

4/3/200B

~

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

056AA2.02 Loss of Off-site Power /6 057AG2.4.8 loss alVital AC lost Bus 16 065AK3.08 Loss of Instrument Air 18 OnAK2.02 Generator Voltage and Electric GOd DisbJrbances, 6 WE04EA1.1 LOCA Outside Containment 13 WE05EA2.1 InadeQuate Heal Transfer - Loss of Secondary Heal Sink /4 T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRQ 3.53.6 DDDDDDD Ii'l DDD Ability to (a) predict the Impacts of the following on the (SYSTEM) and (b) based on those predictions. use pnx:edures to COITed, control, or mitigate the consequences of those abnormal oplWtion:(CFR: 41.5/43.5/45.3/45.13) 3.645 DDDDDDDDOO Oil This is a Geoe~. no stem statement Is associated.

3.7 3.9 0 0 Ii'l 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss Of malfunctioo of the (SYSTEM) will have on the following:(CFR: 41.7 ' 45.6) 3.1 3.3 O !;;] 0 0 0 0 0 0 0 0 0 Knov.1edge of electriCal power supplies to the foIlowing:(CFR: 41.7) 4.040 0000DD Ii'lD ODD Abnily to predict aod/or monitor changes in parameters associated with operating the (SYSTEM) conlrols includlng:(CFR: 41.5/

45.5) 3.4 4.4 ODOOODO Ii'l ODD Ability 10 (a) predict the impacts 01 the following on !he (SYSTEM) and (b) based on those predictions, use procedlJ'l'8S 10 correct. control. Of mitigate the COll5equences of those abnormal operalio<l:(CFR: 41.5/ <13.5' <15,3/ 45_13)

P""f3 FORM ES-4111-2 TOPIC:

ESF load sequencer status fights KnO'Medge 01 how abnormal opemting procedures are used in conjunction with EOPs.

Actions contained in EQP for Joss ollnstrumeol air Breakers. relays Components and functions 01 control and safety systems, Including instrumentation. signals. interiocks. Failure modes and automatic and mllnual features.

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

4/312008

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

001AK1.16 Continuous Rod Withdrawal I 1 024AK2.01 Emergency Boration ( 1 033AG2.4.11 Loss of Intermediate Range Nil 7 051AA1.04 Loss of Condenser Vacuum ( 4 061AK3.02 ARM System Alarms 1 7 068AA2.02 Control Room Evac. 18

~

\\ ---/

T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3

3.4

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9 (45.7 to 45.8) 2.7 2.7 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7) 4.0 4.2 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

2.5 2.5 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict andlor monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.51 45.5) 3.4 3.6 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 3.7 4.2 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 I 43.5 I 45.3 I 45.13)

P""f2

\\......./

FORM ES-401-2 TOPIC:

Definition and application of power defect Valves Knowledge of abnormal condition procedures.

Rod position Guidance contained in alarm response for ARM system Local boric acid flow 4/3/2008

--J ES401, REV9 KA NAME I SAFETY FUNCTION:

001AK1.16 Continuous Rod Withdrawal I 1 024AK2.01 Emergency Bora60n I 1 033AG2.4.11 Loss of Intermedia!1! Range NI/7 051AA 1.04 Loss of Condenser Vacuum / 4 061AK3.02 ARM System Alarms 17 068AA2.0Z Control Room Evac.I B T1G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 KG A1 A2 A3 A4 G RO SRO

'.4 02J DDDDDDDDDD Kno...... edge of the physical connections and/or cause-effect relationships betweefl (SYSTEM) and thl! following:(CFR: 41.2 to 41.9/45.7 to 45.8) 2.7 27 0 02J 0 0 0 0 0 0 0 0 0 Knowledge of electrteal power suppl1es to the foIlowing:jCFR: 41.7) 4.04.2 DDDDDDDDDD 02J This is a Genetic, no stem statement is associated.

2.52.5 DDDDDDIi'IDDDD Ability to predict andfor monilOt changes in parameters associated with Opel"ating the (SYSTEM) tXIntroiS Including:(CFR: 41.5/

45.5)

'.4,.* DD Ii'I DDDDDDDD Kno\\IAedge of ltIe effect thai a loss or malfunction of the (SYSTEM) win have on

!tie foUowing:(CFR: 41.7/45.6)

'.7 4.2 0 0 0 0 0 0 0 Ii'I 0 0 0 AbIlity to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use proce<lures to correct, control, or mitigate the consequences of those abnormal operation:(CFR 41.5143.51 45.31 45.13)

FORM ES-401-2 TOPIC:

Definition and <lpplication of power defect Knowledge of <lboOl'lTlal condition prOCl:!dures.

Rod poSition Guidance contained in <llann response for ARM system Local boric acid ftow 4/312008

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

074EK3.03 Inad. Core Cooling I 4 WE01EK1.2 Rediagnosis 13 we03EG2.4.21 LOCA Cooldown - Depress. I 4 4

.../

T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.4 3.8 0 0 ~ 0 0 0 0 0 0 0 0 3.4 4

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

~DDDDOODDDD KnoWledge of the physical connections andlor cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

P"~ 2 FORM ES-401-2 TOPIC:

Placing the plant in hot standby status Normal, abnormal and emergency operating procedures

. associated with (Reactor Trip or Safety Injection 1 Rediagnosis ).

Knowledge of the parameters and logic used to assess the status of safety functions 4/3/2008 ES-401, REV 9 KA NAME I SAFETY FUNCTION:

074EK3.03 Inao. Core Coolirtg/4 WE01EK1.2 Rediagnosis / 3 we03EG2.4.21 LOCA Cooldown - Depress. I 4 T1G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 At A2 A3 A4 G RO SRO 3.43.8 DD Ii?I DDDDDDDD 3.4 4

KnoYAedge of the effect !hal a loss Of malfunction of the (SYSTEM) will have on the foiloWing:(CFR: 41.7 145.6)

Ii?I DDDDDDDDDD Kno..... edge ol lhe physical c:.onnections 8OOlor ca.use-effed relationships between (SYSTEM) and Ihe foIlowing:(CFR: 41.2 ID 41.9/45.7 to 45.8) 4.04.6 DDD D DDDDDD I!Il This is a Generic, no stem statement is associated.

P",'2 FORM ES-401-2 TOPIC; Placing the phmt In hot standby status Normal, abnormal and emergency operating pnx;edUfes associated with (Reactor Trip or Safety InJection '

Rediagnosis).

Knowtedge of the parameters and logic used to assess the status of safety fuoctions 41312008

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

003G2.1.7 Reactor Coolant Pump 004A3.15 Chemical and Volume Control T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.4 4.7 0 0 0 [J fJ 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.5 3.6 0 0 0 0 [J 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

FORM ES-401-2 TOPIC:

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

PZR pressure and temperature 004K2.05 Chemical and Volume Control 2.7 2.9 0 ~ 0 0 0 0 0 [l 0 0 0 MOVs 005K5.02 Residual Heat Removal 006A1.09 Emergency Core Cooling

.. _------_... _----_._----...,.-:=---

007A2.03 Pressurizer Relief/Quench Tank

~

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3.4 3.5 Knowledge of electrical power supplies to the foliowing:(CFR: 41.7)

DOD 0 ~ 0 0 0 0 0 0 Need for adequate subcooling Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7) 2.8 3.2 0 0 0 [J 0 0 ~ lJ 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5)

Pump amperage, including start, nonnal and locked 3.6 3.9 0 0 0 0 0 0 0 ~ 0 0 0 Overpressurization of the PZR Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal operation:(CFR: 41.5/43.5/45.3/45_13)

PJII'.5 413/2008...

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ES-401, REV 9 KA NAME I SAFETY FUNCTION:

003G2.1.7 Reactor Coolant Pump 004A3. 15 Chemical and Volume Control T2Gl PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 AI A2 A3 A4 G RO SAO 4.4 4.7 0 0 0 0 0 0 0 0 0 0 621 This is a Generic, no stem statement is associated.

3.53.6 00000000 62100 Ability to mooi(Or automatic operations of the (SYSTEM) inCludiog:(CFA: 41.7 / 45.5)

FORM ESa401-2 TOPIC:

Ability 10 evaluate plant performance and make operational Judgments based on operating characteristics, reaC10f behavior and instrumenl interpretation.

PZR Pf8SSl,II8 and temperature oo.-

K2~05 Ch",",,

=iCalandVolumeConlrol-----O:2.7 2.=-.---:OO~0iI

"'-'O~O=O~"O~O'-"[l

"--'O~O~O=C---CMO=V'C-------------

Knowledge 01 eJeclrical power supplies to the IOllowing:(CFR:..,.7)

OO5K5".",'--'R"',:';"""-","', H'~..

'OR;;: '~

=';;;'-----,3;:

.4'-c3"

.5,---ro;-ro"'o 0 F-lI [J O'O""O"'O""-"O"--'N"'= tor adequate Subcool"

KnoWledge of \\tie opetatlonal lmp/lcations of !he tollOYling concepts as they apply to the (SYSTEM):(CFA: 41.5/45.7) 006Al.09 Emergency Core Cooling 2.8 3.2

==:-:-----

C::=::7.:'~-.

o 0 0 0 0 0 ~ 0 0 0 0 Pump amperage. including slart, Mmlal and locked Ability to predict and/or monitor changes in parameters associated with operating !he (SYSTEM) cootrols incIuding:(CFR: 41.5 /

45.5) 007A2.03'- Dp",,=,,::m",,:::,". Ro.~ill~;:;II;ra"",

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-7 T

,"=k---'3"

.6;--;3.9 0 0 0 0 0 0 0 ~ 0 0 0 Ab~ity 10 (a) predicl the impacts 01 the fo~

on the (SYSTEM) and (b) based on those predictions. use procedures to correct control. Of mitigate the consequences of those abnotma!

operation:(CFR; 41.5/43.5' 45.3' 45.13)

Overpressurizalion 01 the PZR

E$-401, REV 9 KA NAME / SAFETY FUNCTION:

OOSA1.03 Component Cooling Water T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 2.9 ODD 0 0 [] ~ 0 DOD Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.5/

45.5)

FORM ES-401-2 TOPIC:

CCW pressure 010A2.01 Pressurizer Pressure Control 3.3 3.6 0 0 0 0 [J 0 0 ~ LJ 0 0 Heater failures Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 012K4.01 Reactor Protection 3.7 4.0 o 0 0 ~ 0 0 0 0 0 0 0 Trip logic when one channel OOC or in test Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7) 012K6.10 Reactor Protection 3.3 3.5 o 0 [J 0 0 ~ 0 0 0 0 0 Permissive circuits Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)

~--.----.--...

.N _ _ _

013K6.01 Engineered Safety Features Actuation 2.7 3.1 DOODO~ODDOD Sensors and detectors 022K1.02 Containment Cooling

~

./

Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 3.7 3.5

~ [] [J 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.S)

P~5 J

SEC/remote monitoring systems 4/31200S ES-401, REV 9 KA NAME / SAFETY FUNCTION:

OO8AI.03 Component Cooling Water T2G1 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2. A3 A4 G RO SAO 2.7 2.9 0 0 0 0 0 0 Ii1I 0 0 0 0 Ability to Pfedlct and/or monitor changes In parameters associated with operating the (SYSTEM) controls 1nc1uding:(CFR: 41.5 1 45.5)

TOPIC, CCW p!"asstJre OTOA2.01~~PC-fassuriZer Pressure Cont*c-",,~--~3

'"".-3 3.6 0 0 0 0 [J 0 0 !ill 0 "O"'O=;-- Heater failur6S:-------

Abltlly to (a) predict the Impacts of the lollo'hing on the (SYSTEM) and (b) based on those predictions, use procedures to COtrect. control. Of mHigateltte consaqU6f"CeS of those abnormal op!Iration:(CFR: 41.5' 43.5 f 45.3 / 45.13)

FORM ES-401-2

"'"";;;K"4."", --';Rea=ct;:~:OProtection

=---------'3.7 4.",-'o=;-ro;-rO'-;Ii1I"O"O'-;O=;-;OOO'o=;--Trlp logic vmen one Channa. OOC or in I~:;-' ----

Knowtedge of (SYSTEM) tSesign feature(s)

=~- --.

012K6.10 Aeactor Protection and or interlock(s)....nic" provide lor !he foilowing:(CFR: 41.7) 3.33.5 00000 1i1l 00000 Knowledge of the sHect that a loss or malfuoclion of Ihe following win have on the (SYSTEM):(CFA: 41.7 f 45.7)

Permissive circuits 013K6.01 -----0-'--. - -- ---. =

Engineered Safety Features Actuation 2.7 3.1 0 0 0 0 0 ~ 0 0 0 0 0 Sensors and OOtectors 022KI.02 Containment Cooling Knowledge of the effect that a loss Of maitlrlCtion 01 the loIlowing will have on the (SYSTEM):{CFA: 41.7/45.7) 3.73.5 Ii1I OC100000000 Knowledge of !he physical connections and/or cause-effect relationships between (SYSTEM) and the follo'hing:(CFR: 41.210 41.9 /45.71045.8)

SEC/remote monitoring systems

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

022K6.0S Containment Cooling T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 1.9 2.0 0 0 0 0 0 ~ 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7)

FORM ES-401-2 TOPIC:

Heat exchangers and condensers 026A4.05 CootainmentSpray-----.---S.5 3.S--tJ 0 [1 0 0 0 0 0 0

~-O--Coriiainment-sprayresetswitcties------ ----*----

Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.S)

---==----,:- -_. -----_._---------_._------_._---

3.4 3.7

[J [l 0 0 0 0 0 ~ 0 [] [J Malfunctioning steam dump 039A2.04 Main and Reheat Steam Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 039K5.05 Main and Reheat Steam 2.7 3.1

[ J [] 0 Cl ~ [] 0 0 0 [J 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5/45.7)

Bases for RCS cooldown limits 059K4.13 Main Feedwater 2.9 2.9 0 0 0 ~ 0 0 0 0 0 0 0 Feedwater fill for S/G upon loss of RCPs 061K3.01 Auxiliary/Emergency Feedwater 061 KS.05 Auxiliary/Emergency Feedwater 4

--/

Knowledge of (SYSTEM) design feature(s) and or intertock(s) which provide for the foliowing:(CFR: 41.7) 4.4 4.6 0 [] ~ DOD 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 3.6 3.9 0 0 LJ 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.S / 4S.7)

PlI'S V

RCS Relationship between AFW flow and RCS heat transfer 413/2008

'-...-/' -

ES-401. REV 9 KA NAME I SAFElY FUNCTION, 022KB,08 ContaifYlloot Cooling 026A4.05 Containment Spray 039A2.04 Main and Reheat Stearn 039K5.;;05'-M".

"~and Reheat S"I..

mO;--

T2G1 PWR EXAMINATION OUTUNE IR RD SAO K1 K2 K3 K4 KS K6 At A2 A3 A4 G 1.92.0 00000 0il OOOOO Knowledge of !he effecllttat a loss or maltunclion 01 the following will have on the (SYSTEM):(CFR: 41.7 ' 45.7)

FORM ES-401~2 TOPIC:

Heat exchangers and condensers 3.53.5 000000000 0il O

===.. _-_._---

Containment spray reset switches Ability to manually Q9&1'3te and/or monitor in the control room:{CFA: 41.7 145.5 to 45.6)

=-----'. _._._--

3.4 3.7 0 0 0 0 0 0 0 !ill 0 0 [J Malfunctioning steam dump Abilily to (a) predict the Impacts of the following on the (SYSTEM) and (b) based on those predictions, \\JS8 procedures to con9CI. control. or millgale the consequences 01 those abnormal operalion:(CFA: 41.5 / 43.5/45.3/45.13) 2.7 3.1 COO 0 Oil 0 0 0 0 0 0 Knowledge of the operational implications of the following conceptS as they apply to the (SYSTEM):(CfR: 41,5/45.7)

Bases 101 RCS cookIoWn limits

,..:;:-;; :=------.-0,--,-;,.--,=,-;=

059K4.13 Main Feedwater 2,9 2.9 LJ 0 0 blI 0 0 0 0 0 0 0 FeedWater fill fOl" SIG upon bss of RCPs

--_.. --0=.

061K3.Q1 AuxiliarylEmergeocy Feed..... ater

--.--CC7.

061K505 Auxiliary/Emergency Feedwater Knowledge of (SYSTEM) deslg1 feature(s) and or Intel1ock(s) which provide for Ihe foliowing:(CFA: 41.7) 4.4 4.6 OO I!il OOOOOOOO Knowledge of tfte eHeet Ihat a loss or matfu-w::tion of the (SYSTEM) will have on the foliowing:(CFA: 41.7 / 45.6) 3.6 3.9 OO~O Oil OOOOOO Knowledge of !tie operational implications 01 the folloWing concepts as they apply to the (SVSTEM):(CFR: 41.5 145.7)

RCS Relationship betweeo AFW flOW and ACS~hea

=I~"""

="

'I~

41312008

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

062G2.4.46 AC Electrical Distribution 062G2.4.9 AC Electrical Distribution 063A4.01 DC Electrical Distribution 064A3.05 Emergency Diesel Generator 064K4.10 Emergency Diesel Generator T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

3.8 4.2 0 0 0 0 0 0 0 [J 0 0 ~

This is a Generic. no stem statement is associated.

2.8 3.1 0 0 0 LJ 0 0 0 0 Cl ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 2.8 2.9 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

FORM ES-401-2 TOPIC:

Ability to verify that the alarms are consistent with the plant conditions.

Knowledge of low power 1 shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Major breakers and control power fuses Operation of the governor control of frequency and voltage control in parallel operation

---=--=_..

3.5 4.0 0 0 0 ~ 0 0 [J 0 [] 0 0 Automatic load sequencer: blackout Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7) 073K3.01 Process Radiation Monitoring 076K1.16 Service Water

~

'---./

3.6 4.2 0 0 ~ 0 [J [] 0 0 0 [J 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the following:(CFR: 41.7/45.6) 3.6 3.8

~ 0 0 0 [1 0 0 0 0 [] []

Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/45.7 to 45.8)

P~5 Radioactive effluent releases ESF 41312008

~

E5-401, REV 9 KA NAME I SAFETY FUNCTION.

062G2.4.46 AC E1ectncaJ Oistribution 062G2.4,9 AC Electrical Dislribulioo 063A4.01 DC Electrical Dlstribu'!lon

'OC-----

~~--.::=

064A3.05 Emergency Diesel Generator 064K4.10 Eme~y Diesel Generator T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G AO SAO 4.2 42 0000000000 ~

This is a Generic, no stem statement is associated.

3.'

4.2 0000000000 ~

This is a Generic, no slem statement is associated.

2.'

3.1 0 0 0 LJ 0 0 0 0 0 Oil 0 Ability to manually operate andlor monitor In the control room:(CFR: 41.7/45.5 to 45.8) 2.' 2.'

OOOOOOOO ~ Oo Ability to monitor automatic opemtions of the (SVSTEM) including:{CFA: 41.7 / 45.5)

TOPIC.

Ability to verify thai the alarms are consistent with the planl oooditions.

Knowledge 01 loW power I shutdown implications In accident (e.g. l OCA Olloss 01 AHA) mitigation strategies.

Major breakers and control power fuses Operalloo of the goveffiOf control of frequency and voltage control in parallel operation

-=~~-

-~~==~~~,~~.~~~~-

3.5 4.0 0 0 0 ~ 0 0 0 0 0 0 0 Automatic load sequencer: blackout Knowledge 01 (SYSTEM) design faature(s) and Of interk:lcl\\(s) v.tlich prO'Jide 101 the toIlowing:{CFR: 41.1)

=-~ ----~~~~~~~~~~rc 073K3.01 Process Radiation Monitoring 3.6 4.2 0 0 ~ 0 0 0 0 0 0 0 0 Radioactive effluent 'eleas..

~:----

076K1.16 Service Waler Knowledge 01 the effect thai a toss Of mallunctlon 01 the (SYSTEM) will have on the foIiO'Mng:(CFR: 41.7 145.6) 3.. 3.'

~ 0 0 0 0 [l 0 O"O""O"'O;-----;;."S.,--------- ------

Knowledge 01 the physical connections arG'or c3use-effect relationships between (SYSTEM) and the 101i0wing:(CFR: 41.2 to 41.9 145.710 45.8J P1""'5

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

078K2.01 Instrument Air T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.7 2.9 0 ~ 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies to the following:(CFR: 41.7)

. 103A3.01 Containment 3.9 4.2 0 0 0 0 [1 0 DOli'] 0 0

~

\\...J' Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/45.5)

Page 5 of 5 --

FORM ES-401-2 TOPIC:

Instrument air compressor Containment isolation 41312008 2:42 PM

\\..J ES-401, REV 9 KA NAME I SAFETY FUNCTION:

078K2.01 tnslrunenl Air 103A3.01 Coolainm6fl1 T2Gl PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 A1 102 A,3 A4 G RO SRO 2.7 2.9 0., 0 0 0 0 0 0 0 0 0 Knowledge of electrical power supplies 10 the followiog:(CFR: 4 1.7) 3.94.20 0000000 0il 00 Ability to monitor automatiC operations of the (SYSTEM) locIuding:(CFR: 41.7 /45.5)

Page 5 015 FORM ES-401-2 TOPIC:

'nsbunent a ir compreSSOf Containment isolation 41312008 2:42 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION:

00lA2.07 Control Rod Drive 002A4.02 Reactor Coolant 011K6.05 Pressurizer Level Control 016K5.01 Non-nuclear Instrumentation 027G2.4.31 Containment Iodine Removal 02SK3.01 Hydrogen Recombiner and Purge Control

~

\\...J T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct. control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 4.3 4.5 0 0 0 0 0 0 0 0 0 ~ 0 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.S) 3.1 3.7 0 0 0 0 0 ~ 0 0 DOD Knowledge of the effect that a loss or malfunction of the following will have on the (SYSTEM):(CFR: 41.7/45.7) 2.7 2.8 0 0 0 0 ~ 0 0 0 0 0 0 Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.51 45.7) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.3 4.0 0 0 ~ 0 0 0 0 0 0 0 0 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

P~. 2 FORM ES-401-2 TOPIC:

Effect of reactor trip on primary and secondary parameters and systems Indications necessary to verify natural circulation from appropriate level, flow and temperature indications and valve positions upon loss of forced circulation Function of PZR level gauges as postaccident monitors Separation of control and protection circuits Knowledge of annunciators alarms, indications or response procedures Hydrogen concentration in containment 4131200S E5-401, REV 9 KA NAME I SAFETY FUNCTION:

001A2,Q7 Control Rod Orive 002A4.02 Reactor Coolant 011K6.0S Pressurizer Level Control 0161<5.01 Non-nudear InSlrumentation 027G2.4.31 Cootainmeot Iodine Removal 0281(3.01 Hydrogen Recombineraod Purge Coo,",i T2G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.1 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict tna Impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct, COfltrol, Of mitigate the consequences of those abnormal operalion:(CFR: 41.5/ 43.5/45.3 f 45.13) 4~ 4.5 0 0 0 0 0 0 0 0 0 " 0 Ability to manually operate andlOl' monitor in the control room:(CFR: 41.7 /45.5 to 45.S}

3.1 3.7 0 0 0 0 0 " 0 0 0 0 0 Knowledge of the effect that a loss or malfunctlon of the following will have on the (SYSTEM):(CFR: 41.7' 45.7) 2.7 2.8 0 0 0 0 111 0 0 0 0 0 0 Knowtedge of the operational implicatiol'l5 of the following concepts as they apply to tI'IEt (SYSTEM):(CFR 41.5/45.7) 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

This Is a Genenc, no stem statement is associated.

3.3 4.0 00 111 00000000 Knowledge of the effecltOat a loss or malfurldion of the (SYSTEM) will have on the lolfowing;(CFR: 41.7/45.6)

P~2 FORM ES-401*2 TOPIC:

Effect of reactor trip on primary aJ'ld SOOOIldalY parameters and systems Indications necessary to verify natural circulation from appropriate level, !I(JY,I and temperature indications OInd valve positions upon loss of forced circtJlatlon Function of PZR level gauges as postaccident monitors Separation of conltol and protection circuits Knowledge of annunciators alanns. indications 01' response procedures Hydrogen concentration in containment 4I3I2OOa

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

03SA1.01 Steam Generator 072K1.0S Area Radiation Monitoring 07SK4.01 Circulating Water 086A3.01 Fire Protection

~

\\...J T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.6 3.8 0 0 0 0 0 0 ~ 0 0 0 0 Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR: 41.S/

4S.5) 2.8 2.9

~ 0 0 0 0 0 0 0 0 0 0 Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the following:(CFR: 41.2 to 41.9/4S.7 to 4S.8) 2.S 2.8 0 0 0 ~ 0 0 0 0 0 0 0 Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the following:(CFR: 41.7) 2.9 3.3 0 0 0 0 0 0 0 0 ~ 0 0 Ability to monitor automatic operations of the (SYSTEM) including:(CFR: 41.7/4S.5)

P"c2

. FORM ES-401-2 TOPIC:

S/G wide and narrow range level during startup.

shutdown and nonnal operations MRSS Heat sink Starting mechanisms of fire water pumps ES-401. REV 9 KA NAME I SAFElY FUNCTION:

Q35A1.01 Sleam Generator 072Kl.0S Area Radiation Monitoring 075K4.01 Circulating Water 086A3.01 FlreProtectioo T2G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.*

3.6 OOOOOO ~ OOOO Ability to predict and/or monitor changes in parameters associated with operating 1he (SYSTEM) controls lllCludlng:(CFR: 41.5 f 45.5) 2.6 2.9

~ OOOOOOOOOO KnOlliledge of the physical connections and/or eause-effec:l relationships between (SYSTEM) and the foIlowIl"9:(CFR: 41.2 to 41.9/45.7 to 45_8) 2.5 2.'

OOO ~ OOOOOOO KOO'Ntedge of (SYSTEM) design feature(s) and or InleOock(s) which provide for the foIlowing=(CFR: 41.7)

2. 3.3 OOOOOOOO ~ OO Ability to monitor automatic operations of thl! (SYSTEM) induding:(CFR: 41.7 f 45.5)

FORM ES-401*2 TOPIC; SlG wide and narrow range level during startup.

shutdown and normal operations MRSS Heat sink Starting mechaoisms of fire ~ter pUmps 41312008

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.17 Conduct of operations G2.1.18 Conduct of operations G2.1.43 Conduct of operations G2.2.14 Equipment Control G2.2.37 Equipment Control G2.3.11 Radiation Control G2.3.S Radiation Control

~

T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.9 4.0 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

3.6 3.8 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

4.1 4.3 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

2.9 2.9 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no stem statement is associated.

P,.,..2 FORM ES-401-2 TOPIC:

Ability to make accurate. clear and concise verbal reports.

Ability to make accurate. clear and concise logs. records.

status boards and reports.

Ability to use procedures to determine the effects on reactivity of plant changes Knowledge of the process for controlling equipment configuration or status Ability to determine operability and/or availability of safety related equipment Ability to control radiation releases.

Ability to use radiation monitoring systems 4/3/2008 ES401, REV 9 KA NAME I SAFETY FUNCTION:

02.1.11 Conduct of operations G2.1.18 Conduct of opemtions G2.1.43 Cooduct of operations 02.2.14 Equipment Control 02.2.37 Equipment Control Radiation Control G2.3.5 Radiation Control T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 AI A2 A3 A4 G RO SRO 3.9 '.0 0 0 0 0 0 0 0 0 0 0 011 This is a Generic, no slem stalem6flt is assOCiated.

3.63.8 DDDDDDDDDD Ii'I This is II Generic, no stem statement is associated.

,., '.3 0 0 0 0 0 0 0 0 0 0 Ii'I This Is II Generic. no stem statement is associated.

3.9 '.6 DDDDDDDDDD Ii'I This is II Generic. no stem statement is associated.

3.6 '.60 000000000011 This is a Generic. no stern statement is associated.

3.8

<.3 DDDDDDDDDD Ii'I This is a Generic, no stem statement is associated.

2.9 2.9 0 0 0 0 0 0 0 0 0 0 Ii'I This is a Generic, no slem Slalemenl is associaled~

TOPIC:

Ability to make accurate. clear and concise.. erosl reports.

Ability to make accurate. clear and concise logs, records, status boards and repo!1s.

Ability to use procedures 10 detemllne the effects on reactivity of Dlant changes Knowtedge 01 the process for conlrolling eQuipment configuration or status Ability to determine operability and/or availability of safety retated equipment Ability to control radiation releases.

Abltity to use radiation monitoring systems 4131'2008

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.3.7 Radiation Control G2A.30 Emergency Procedures/Plans G2.4.32 Emergency ProceduresIPlans

\\..J T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 KB A1 A2 A3 A4 G RO SRO 3.5 3.B 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

2.7 4.1 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

3.B 4.0 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, no stem statement is associated.

P-.2 FORM ES-401-2 TOPIC:

Ability to comply with radiation work permit requirements during' normal or abnormal conditions Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Knowledge of operator response to loss of all annunciators.

4/3/2008

\\J ES-4ll1, REV 9 KA NAME I SAFETY FUNCTION:

G2.3.7 Radiation Control G2.4.3O Emergency Procedures/Plans G2.4.32 Emergency ProcedureslPlans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A~ G RO SRO 3.53* 00000000001i21 ThiS is a Generic. no stem statement is associated.

2.7 4.1 0 0 0 0 0 0 0 0 0 0 Ii2I This is a Generic, /10 stem statement is associated.

3.64.0 0000000000 1i'J This Is a Genetic, no stem statement is asSOCiated.

FORM ES-4ll1-2 TOPIC:

Ability to comply with radiation woOl penni! requirements during normal or abnormal conditions Knowledge of events related to system operations/status that must be reported to intemal orglnizaHoos or ootside agencies.

Knowledge of operator response 10 loss of all annuncialars.

4/312008

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 008AG2.4.6 Pressurizer Vapor Space Accident! 3 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~

015AA2.10 RCP Malfunctions 1 4 This is a Generic, no stem statement is associated.

3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 026AG2.4.34 Loss of Component Cooling Water 1 8 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

054AA2.04 Loss of Main Feedwater 1 4 062AG2.2.36 Loss of Nuclear Svc Water 1 4 WE04EA2.1 LOCA Outside Containment f 3 This is a Generic. no stem statement is associated.

4.2 4.3 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the follOwing on the (SYSTEM) and (b) based on those predictions. use procedures to correct. control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.1 4.2 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic. no' stem statement is associated.

3.4 4.3 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 J 43.51 45.3 f 45.13)

~

P~1

~

FORM ES-401-2 TOPIC:

Knowfedge symptom based EOP mitigation strategies.

When to secure RCPs on loss of cooling or seal injection Knowfedge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Proper operation of AFW pumps and regulating valves Ability to analyze the effect of maintenance activities.

such as degraded power sources. on the status of limiting conditions of operations Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

4/3/2008 ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE KA NAME I SAFElY FUNCTION:

IR Kl K2 K3 K4 KS K6 Al At. A3 A4 G RO SRO 00SAG2.4.6 Preuurizer Vapor Space Accidentl 3 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~

015AA2.10 Rep Malfunctions I 4 This is a Geoefic, no stem statement Is asSOCiated.

3.7 3.7 0 0 0 0 0 0 0 Ii1I 0 0 0 Abilily to (a) predictltle impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the coosequences of those abnonnal operalioo:(CFR: 41.5 / 43.5 / 45.3 /45. 13) 026AG2.4.34 loss of Component Cooling Water 18 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

This is a Generic, 1'\\0 stem statement is associated.

054A.A2.04 Loss of Main Feedwaler 14 062AGZ.2.36 Loss of Nuclear Svc Water f "

WE04EA2.1 LOCA Outside OJolainment 1 J 4.2 4.3 OOOOOOO ~ OOO Ability 10 (a) predict the impacts 01 the following on !he (SYSTEM) and (b) based on Ihose predictions, use procedl.1l'es to correct. control, or mitigate the consequences ollhose abnormal operation:(CFR: 41.5, 43.5, 45.J /45.13) 3.1 42 0 0 0 0 0 0 0 0 0 0 Ii1I ThiS Is a Generic. no stem statement is associated.

3.4 4.3 OOOODOO ~ OOO Ability to (a) predict the Impacts of the following on tfle (SYSTEM) and (b) based on those predic~ons, use procedures to correct. control. or mitigate the conseQuences of those abnormal operation:(CFR: 41.5 / 4J.5/45.3/45.1J)

FORM ES-401-2 Knowtedge symptom based EOP mitigation strategies.

When to secure Reps on loss of oooIlng or seal injection Knowledge of RO taslFW pumps and regulallng valves Ability to analyze Ihe effect of maintenance activities, such as degraded power sources, on Ihe stalus of limiting conditions of ope!CItions Facility conditions and selection of appropriate procedures during abnormal and emergency opera~OI"Is.

~~4/312008~~

~~ES-401, REV 9 KA NAME I SAFETY FUNCTION:~~

~~001AA2.03 Continuous Rod Withdrawal/1 003AA2.03 Dropped Control Rod 11 037AG2.4.8 Steam Generator Tube Leak 13 we08EG2.2.25 RCS Overcooling - PTS 1 4~~

~

SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.5 4.8 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.6 3.8 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~

~~This is a Generic, no stem statement is associated.~~

~~3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~P~1 FORM ES-401-2 TOPIC:~~

Proper actions to be taken if automatic safety functions have not taken place Dropped rod, using in-core/ex-core instrumentation in-core or loop temperature measurements Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

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

~~4/3/2008 ES-401. REV 9 KA NAME I SAFETY FUNCTION:~~

001AA2.0J Continuous Rod Withdrawal / 1 003AA2.03 Dropped Control Rod 11 037AG2.4.B Steam GaneratorTube Leak 13 weOSEG22.2S RCS Overcooling. PTS 14 SRO T1G2 PWR EXAMINATION OUTliNE IR RO SRO K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G 4.54.8 DDDDDDD Ii[J DDD Ability 10 (3) predict the impacts 01 the following on the (SYSTEM) aod (b) based on those predictions, use procedures to correct, cootrol, or mitigate the consequences of those abnofTTlal operatloo:(CFR: 41.5/43.5 f 45.3/45.13) 3.6 3.8 DDDDDDD ~ DDD Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictiom. use procedures to correct, control, or mitigate the consequences of those abnolmal operatiort:{CFR: 41.5/43.5/45.3/45.13) 3.84.5 0000000000 "

~~This is a Generic. no stem statement is aSSOCiated.~~

~~3.242 0000000000.,~~

~~Thi$1s 8 Generic. no $tam statement 1$~~

~~associaled.~~

~~FORM ES-401-2 TOPIC:~~

Proper actions to be takef1 if automatic safety functions have nol takafl place Dropped rod, using in-core/ex-c:;orQ inslnlrnentation in*

~~core 0( loop temperature measurements KnO\\ldedge of how aboomlal opeIiIting procedUteS are used in conjunction with EOPs.~~

~~Knowledge of the bases in Technical Specifications for limiting conditions fof operations and safety limits.~~

~~ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:~~

~~IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 013G2.2.42 Engineered Safety Features Actuation 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~062G2.4.6 AC Electrical Distribution 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~~~

~~064A2.13 073G2.4.S 07SA2.01~~

~~, ~~~

~~Emergency Diesel Generator Process Radiation Monitoring Instrument Air This is a Generic, no stem statement is associated.~~

2.6 2.S 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:{CFR: 41.5/43.5/45.3 145.13) 3.S 4.5 0 0 0 0 0 0 0 0 0 0 ~

~~This is a Generic, no stem statement is associated.~~

2.4 2.9 0 0 0 0 0 0 0 ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 143.5 1 45.3 145.13)

~~P~1 FORM ES-401-2 TOPIC:~~

~~Ability to recognize system parameters that are entry-level conditions for Technical SpeCifications Knowledge symptom based EOP mitigation strategies.~~

~~Consequences of opening auxiliary feeder bus (ED/G sub supply)~~

~~Knowledge of how abnormal operating procedures are used in conjunction with EOPs.~~

~~Air dryer and filter malfunctions 4/3/200S _.~~

~~ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE KA NAME I SAFE1Y FUNCTION, IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 013G2.2.42 Engineered Safety Features Actuation 3.9 4.6 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, nQ stem statement is associated.~~

~~062G2.4.6 AC Electrical Oisllibution 3.7 4.7 0 0 0 0 0 0 0 0 0 0 ~~~

~~064A2.13 Emergency Diesel Genelator 073G2.4.8 Process Radlatioo Monitoring 078A2.01 Instrument Air This is a Generic, 00 stem statement Is assoclated.~~

2.' 2.8 0000000 0 000 Atrility to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictioos, use proeecIlK8S to correct, control, or mitigate the consequences of those abnormal opera.tJoo:(CFR: 41.5/43.5 /45.3 / 45.13)

~~"4.5 0000000000 0 This is a Generic, no stem statement is associated.~~

2.4 2.9 0 0 0 0 0 0 0 01J 0 0 0 Ability to (a) predict the impacts of the fQl\\Qwing on the (SYSTEM) and (b) based on those predictions, use procedures to c:orrec:t, control, Of mitigate the consequences of those abnormal operation:(CFR: 41.5 / 43.5/45.3/45.13)

~~FORM ES-401*2 TOPIC:~~

~~Abi!ity to recognize system parameten; that al e entry-level coodiUoos fOf Technical Specifications Kna'Madge symPfQm based EOP mitigation strategies.~~

~~Consequences of opening au..aflary feeder bus (ED/G sub supply)~~

~~KnO'Medge of how abnOfTllal operating procedures are used in conjunction with EOPs.~~

~~Air dryer and filter malfunctions 4/312008~~

~~ES-401, REV 9 KA NAME I SAFETY FUNCTION:~~

~~001G2.4.34 Control Rod Drive 034A2.03 Fuel Handling Equipment 068A2.04 Liquid Radwaste~~

~

~~SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.1 0 D DOD 0 DOD 0 ~~~

~~This is a Generic. no stem statement is associated.~~

3.3 4.0 D D D DOD 0 ~ DOD Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct. control. or mitigate the consequences of those abnonnal operation:(CFR: 41.5/43.5/45.3/45.13) 3.3 3.3 0 DOD DOD ~ 0 0 0 Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions. use procedures to correct. control. or mitigate the consequences of those abnonnal operation:(CFR: 41.5/43.5/45.3/45.13)

~~P~. 1 FORM ES-401-2 TOPIC:~~

Knowledge of RO tasks perfonned outside the main control room during an emergency and the resultant operational effects Mispositioned fuel element Failure of automatic isolation 41312008 ES-401, REV 9 KA NAME I SAFETY FUNCTION:

001G2.4.34 Control Rod Drive 034A2.03 Fuel Haodlillg Equipment 068A2.04 Uqukl Radwaste SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.2 4.1 0 0 0 0 0 0 0 0 0 0 RI This is a Generic, no stem statement is aSSOCiated.

3.34.0 DDDDDDD Rl DDD Ability to (a) predIct the Impacts of the following on the (SVSTEM) and (b) based Ofl those predictions, use procedUfes to correct, control, or mitigate the consequences of those abnomlat operation:{CfR: 41.51 43.51 45.3/ 45.13) 3.3 3.3DDDDDDD IiII DDD Ability to (a) predict the impacts 01 the following on the (SYSTEM) and (b) based Ofl those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal opef8tion:(CFR: 41.51 43.5145.3 145.13)

~~FORM ES-40'*2 TOPIC:~~

~~Knowledge of RO tasks performed outside the main CQfllroi room during an emergency and Ihe resullant operaUonal effects Mispositioned fuel element FaHure of automatic Isolation 41312008~~

~~ES-401, REV 9 KA NAME I SAFETY FUNCTION:~~

G2.1.27 Conduct of operations G2.1.34 Conduct of operations G2.2.38 Equipment Control G2.3.13 Radiation Control G2.3.14 Radiation Control G2.4.20 Emergency Procedures/Plans G2.4.41 Emergency Procedures/Plans L"

~~SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4~~

~~oooooooooo~~~

~~This is a Generic, no stem statement is associated.~~

~~2.7 3.5 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~3.6 4.5 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~~~

~~This is a Generic, no stem statement is associated.~~

~~Page 1 of 1~~

~

~~FORM ES-401-2 TOPIC:~~

~~Knowledge of system purpose and or function.~~

~~Knowledge of primary and secondary chemistry limits Knowledge of conditions and limitations in the facility license.~~

Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of operational implications of EOP warnings, cautions and notes.

~~Knowledge of the emergency action level thresholds and classifications.~~

~~~20082i ES-401, REV 9 KA NAME f SAFETY FUNCTION:~~

02.1,27 Conduct of operations G2.1.34 Conduct of operations G2.2.38 Equipment Control G2.3.13 Radiation Control 02.3,14 Radiation Cootrol G2.4.20 Emergency Procedures/Plans G2.4.41 Emergency Proce(lures!Plans SRO T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4 oooooooooo ~

~~This is a Generic. no slem statement is associated.~~

~~'.7 3.5 0 0 0 0 0 0 0 0 0 0 ~~~

~~This Is a Generic, no stem statement is associated.~~

~~3.6 4.5 OOOOOOOOOO~~~

~~This is 8 Generic, 00 stem statement is asSOCiated.~~

~~3.4 3.8 OOOOOOOOOO ~~~

~~This is a Generic, no stem statement is associated.~~

~~3.4 3.8 OOOOOOOOOO~~~

~~This is a Generic, no stem statement is associated.~~

~~3.8 4.3 OOOOOOOOOO ~~~

~~This is a Generic, no stem statement is associated.~~

~~'.9 4.6 OOOOOOOOOO ~~~

~~This is a Generic. 00 stem statement is associated.~~

~~FORM ES-401-2 TOPIC:~~

~~Knowledge of system purpose and or ruoclion,~~

~~Knowledge of primary and secondary chemistry ijmits Kncw.iOOge of conditions and limitations in the facility license.~~

KnO'Nledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation orcootaminaUon hazards that may anse dorirlg nOllTlal, abnormal. or emergency conditions or activities Knowledge of operational implications 01 EOP warnings.

~~cautions and notes.~~

~~Knowledge of the emergency action level thresholds and classifications.~~

~~413121)Oa 'I~~

~~ES-301 Administrative Topics Outline Form ES-301-1~~

~~/J)/iA.t-v~~

(

~~Facility:~~

~~VCSUMMER Date of Examination:~~

~~2009 NRC Examination Level (circle one):~~

~~~/SRO Operating Test Number:~~

~~Administrative Topic Type Describe activity to be performed (see Note)~~

Code*

RO/SRO Common Conduct of Operations P,M Calculate the Maximum Allowable Head Venting Time (A1-1) in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2 G2.1.25 (3.9/4.2): Ability to interpret reference materials, such as graphs, curves, tables, etc.

~~Perform a Shutdown Margin Verification for intended Conduct of Operations M~~

~~plant conditions in accordance with GOP-005, (A1-2)~~

~~REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b.~~

~~G2.1.23 (4.3/4.4): Ability to perform specific system and integrated plant procedures during all modes of plant operation.~~

~~Perform the surveillance test procedure and complete Equipment Control (A2)~~

~~N the associated documentation for the Pressurizer PORV motor operated block valves.~~

(

~~G2.2.12 (3.7/4.1): Knowledge of surveillance procedures.~~

~~RO/SRO Common Radiation Control (A3)~~

~~M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure.~~

~~G2.3.7 (3.5/3.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions..~~

~~Emergency Plan Category not selected for RO NOTE:~~

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

~~NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1~~

~~",rr-(~~

~~Facility:~~

~~VC SUMMER Date of Examination:~~

~~2009 NRC Examination Level (circle one):~~

~~I!!QII SRO Operating Test Number:~~

~~Administrative Topic Type Describe activity to be performed (see Note)~~

Code*

RO/SRO Common Conduct of Operations P, M Calculate the Maximum Allowable Head Venting Time (A1-1) in accordance with EOP-1S.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2 G2.1.25 (3.9/4.2): Ability to interpret reference materials, such as graphs, curves, tables, etc.

~~Perform a Shutdown Margin Verification for intended Conduct of Operations M~~

~~plant conditions in accordance with GOP-DOS, (A 1-2)~~

~~REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b.~~

~~G2.1.23 (4.3/4.4) ; Ability to perform specific system and integrated plant procedures during all modes of plant operation.~~

~~Perform the surveillance test procedure and complete Equipment Control (A2)~~

~~N the associated documentation for the Pressurizer PORV motor operated block valves.~~

(

~~G2.2.12 (3.7/4.1): Knowledge of surveillance procedures.~~

~~RO/SRO Common Radiation Control (A3)~~

~~M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure.~~

~~G2.3.7 (3.513.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions..~~

~~Emergency Plan Category not selected for RO NOTE:~~

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

~~NUREG-1021, Revision 9~~

(

~~ES-301~~

~~Type Codes & Criteria:~~
Administrative Topics Outline Form ES-301-1 (C)ontrol room (D)irect from bank (:s; 3 for ROs; :s; for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (:s; 1; randomly selected)
(S)imulator JPM
~~SUMMARY~~
STATEMENTS CONDUCT OF OPERATIONS (A1-1): Given a set of conditions, calculate the Maximum Allowable Head Venting Time in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2. Modify 2005 NRC JPM A 1-2 by changing the Reactor Building initial conditions. RO/SRO Common JPM.
CONDUCT OF OPERATIONS (A1-2): Perform a Shutdown Margin Verification for intended plant conditions in accordance with GOP-005, REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b. The applicant will be directed from GOP-005 to perform STP-134.001, SHUTDOWN MARGIN VERIFICATION, to determine the required boron concentration for the intended conditions (Mode 5). Modify a Bank JPM by changing core burnup, existing boron concentration, and adding an "untrippable" rod. In addition, STP-134.001 has undergone significant revisions since the Bank JPM being modified was last revised.
EQUIPMENT CONTROL (A2): Perform the surveillance test procedure and complete the associated documentation for the Pressurizer PORV motor operated block valves. The applicant will perform STP-127.001, PRESSURIZER BLOCK VALVE OPERABILITY TEST, on the simulator; stroke testing the three PZR PORV Block Valves with a malfunction placing one valve outside of the specified acceptance criteria. New JPM.
RADIATION CONTROL (A3): Determine the stay time for performance of a task involving whole body exposure to ensure compliance with RWP requirements. Identified as a modified JPM because there are dose rate/dose calculation JPM's in the facility bank (JPA-007).
RO/SRO Common JPM.
NUREG-1021, Revision 9
(
(
ES-301 "Type Codes & Criteria:
Administrative Topics Outline Form ES-301-1 (C)ontrol room (D)irect from bank (oS 3 for ROs;,; for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (s 1; randomly selected)
(S)imulator JPM
~~SUMMARY~~
STATEMENTS CONDUCT OF OPERATIONS (A1*1): Given a set of conditions, calculate the Maximum Allowable Head Venting Time in accordance with EOP*1B.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2. Modify 2005 NRC JPM A1-2 by changing the Reactor Building initial conditions. RO/SRO Common JPM.
CONDUCT OF OPERATIONS (A1*2): Perfonm a Shutdown Margin Verification for intended plant conditions in accordance with GOP*OOS, REACTOR SHUTDOWN FROM STARTUP TO HOT STANDBY (MODE 2 TO MODE 3), Step 3.7.b. The applicant will be directed from GOP*
005 to perfonm STP*134.001, SHUTDOWN MARGIN VERIFICATION, to detenmine the required boron concentration for the intended conditions (Mode 5). Modify a Bank JPM by changing core burnup. existing boron concentration, and adding an ~ untrippable~ rod. In addition, STP-134.001 has undergone significant revisions since the Bank JPM being modified was last revised.
EQUIPMENT CONTROL (A2): Perform the surveillance test procedure and complete the associated documentation for the Pressurizer PORV motor operated block valves. The applicant will perfonm STP-127.001, PRESSURIZER BLOCK VALVE OPERABILITY TEST, on the simulator; stroke testing the three PZR PORV Block Valves with a malfunction placing one valve outside of the specified acceptance criteria. New JPM.
RADIATION CONTROL (A3): Determine the stay time for perfonmance of a task involving whole body exposure to ensure compliance with RWP requirements. Identified as a modified JPM because there are dose rateldose calculation JPM's in the facility bank (JPA*007).
ROISRO Common JPM.
NUREG*1021, Revision 9
ES-301 Administrative Topics Outline Form ES-301-1
(
Facility:
VCSUMMER Date of Examination:
2009 NRC Examination Level (circle one):
RO/~
Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note)
Code*
RO/SRO Common Conduct of Operations P,M Calculate the Maximum Allowable Head Venting Time (A 1-1) in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2 G2.1.25 (3.9/4.2): Ability to interpret reference materials, such as graphs, curves, tables, etc.
Evaluate the impact of a change in the plant electrical Conduct of Operations N
lineup (close AL T Feed BRKR to ESF Bus 1DA or (A1-2) 1 DB) on the TS LCO and complete SAP-205, - REMOVAL AND RESTORATION CHECKSHEET G2.1.18 (3.6/3.8): Ability to make accurate, clear, and concise logs, records, status boards, and reports.
Evaluate the completed surveillance test procedure for Equipment Control (A2)
M a safety related system G2.2.12 (3.7/4.1): Knowledge of surveillance procedures.
(
RO/SRO Common Radiation Control (A3)
M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure.
G2.3.7 (3.5/3.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions..
Given a set of conditions, determine the EAL and Emergency Plan (A4)
M complete the Emergency Notification Form within the required time G2.4.41 (2.9/4.6): 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 5 are required.
~~Type Codes & Criteria:~~
(C)ontrol room (D)irect from bank (:$ 3 for ROs; :$ for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (:$ 1; randomly selected)
(S)imulator
(
NUREG-1021, Revision 9 ES-301 Administrative Topics Outline Form ES-301-1
(
Facility:
VCSUMMER Date of Examination:
2009 NRC Examination Level (circle one):
RO /~
Operating Test Number:
Administrative Topic Type Describe activity to be performed (see Note)
Code*
RO/SRO Common Conduct of Operations P, M Calculate the Maximum Allowable Head Venting Time (A1-1) in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2 G2.1.25 (3.9/4.2): Ability to interpret reference materials, such as araohs, curves, tables, etc.
Evaluate the impact of a change in the plant electrical Conduct of Operations N
lineup (close AL T Feed BRKR to ESF Bus 1 DA or (A1-2) 1 DB) on the TS LCO and complete SAP-205, - REMOVAL AND RESTORATION CHECKSHEET G2.1.18 (3.613.8): Ability to make accurate, dear, and concise loas records status boards and reoorts.
Evaluate the completed surveillance test procedure for Equipment Control (A2)
M a safety related system G2.2.12 (3.7/4.1): Knowledge of surveillance procedures.
(
RO/SRO Common Radiation Control (A3)
M Determine the dose limit and apply the RWP dose limits to calculate stay time for performance of a task involving whole body exposure.
G2.3.7 (3.513.6): Ability to comply with radiation work permit requirements during normal or abnormal conditions..
Given a set of conditions, determine the EAL and Emergency Plan (A4)
M complete the Emergency Notification Form within the required time G2.4.41 (2.9/4.6): 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 5 are required.
-Type Codes & Criteria:
(C)ontrol room (D)irect from bank (5 3 for ROs; 5 for SROs & RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (:5 1; randomly selected)
(S)imulator
(
NUREG-1021, Revision 9
(
(
ES-301 Administrative Topics Outline Form ES-301-1 JPM
~~SUMMARY~~
STATEMENTS CONDUCT OF OPERATIONS (A1-1): Given a set of conditions, calculate the Maximum Allowable Head Venting Time in accordance with EOP-18.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2. Modify 2005 NRC JPM A 1-2 by changing the Reactor Building initial conditions. RO/SRO Common JPM.
CONDUCT OF OPERATIONS (A1-2): Evaluate the impact of a change in the plant electrical lineup (close alternate feed breaker to ESF Bus 1DA or 1 DB in Mode 1) on the Technical Specification LCO and complete SAP-205, STATUS CONTROL AND REMOVAL AND RESTORATION, Attachment 1 - REMOVAL AND RESTORATION CHECKSHEET. The applicant will be required to determine the Technical Specification Action Statements that must be entered and then complete the status tracking document. New JPM.
EQUIPMENT CONTROL (A2): Evaluate the completed surveillance test procedure for a safety related system. The applicant will be directed to review (for approval) a completed STP-205.004, RHR PUMP AND VALVE OPERABILITY TEST, containing three significant errors.
Modify a Bank JPM by changing all errors.
RADIATION CONTROL (A3): Determine the stay time for performance of a task involving whole body exposure to ensure compliance with RWP requirements. Identified as a modified JPM because there are dose rate/dose calculation JPM's in the facility bank (JPA-007).
RO/SRO Common JPM.
EMERGENCY PLAN (A4): Given a set of conditions, determine the EAL and complete the Emergency Notification Form within the required time. The applicant will be given a set of conditions requiring declaration of a GENERAL EMERGENCY for an A TWS Event.
NUREG-1021, Revision 9
(
(
ES-301 Administrative Topics Outline Form ES-301-1 JPM
~~SUMMARY~~
STATEMENTS CONDUCT OF OPERATIONS (A1-1): Given a set of cond"ions, calculate the Maximum Allowable Head Venting Time in accordance with EOP-1S.2, RESPONSE TO VOIDS IN REACTOR VESSEL, Attachment 2. Modify 2005 NRC JPM A1-2 by changing the Reactor Building initial conditions. RO/SRO Common JPM.
CONDUCT OF OPERATIONS (A1-2): Evaluate the impact of a change in the plant electrical lineup (close alternate feed breaker to ESF Bus 1DA or 1 DB in Mode 1) on the Technical Specification LCO and complete SAP-205, STATUS CONTROL AND REMOVAL AND RESTORATION, Attachment 1 - REMOVAL AND RESTORATION CHECKSHEET. The applicant will be required to determine the Technical Specification Action Statements that must be entered and then complete the status tracking document. New JPM.
EQUIPMENT CONTROL (A2): Evaluate the completed surveillance test procedure for a safety related system. The applicant will be directed to review (for approval) a completed STP-205.004, RHR PUMP AND VALVE OPERABILITY TEST, containing three significant errors.
Modify a Bank JPM by changing all errors.
RADIATION CONTROL (A3): Determine the stay time for performance of a task involving whole body exposure to ensure compliance with RWP requirements. Identified as a modified JPM because there are dose rateldose calculation JPM's in the facility bank (JPA-007).
RO/SRO Common JPM.
EMERGENCY PLAN (A4): Given a set of conditions, determine the EAL and complete the Emergency Notification Form within the required time. The applicant will be given a set of conditions requiring declaration of a GENERAL EMERGENCY for an ATWS Event.
NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 0
Facility:
VC Summer Date of Examination:
2009 Exam Level (circle one):
ROI SRO(I)
Operating Test No.:
NRC Control Room Systems@ (8 for RO; 7 for SRO-I)
System / JPM Title Type Code*
Safety Function
a.
APE 001 [JPSF-036]
Respond to Continuous Rod Withdrawal (AOP-403.3)
M,A,S 1
b.
System 006 [JPS-058]
Raise ECCS Accumulator level (SOP-112)
D,S 2
System 010 [JPSF-150]
Depressurize the RCS to Refill the Pressurizer (EOP-2.1)
P, D,A,E,S 3
d.
APE 025 [JPSF-065]
Establish hot leg injection during loss of RHR at mid-loop D,A,S,L 4P conditions (AOP-115.5)
e.
System 045 [JPSF-022B]
Respond to Turbine Trip Failure (EOP-1.0)
M,A,E,S 4S
(
f.
System 026 [JPSF-019A]
Manually Initiate Reactor Building Spray (EOP-1.0)
M,A,E,S 5
g.
System 015 Perform an Intermediate Rcmge NI Analog Channel Operational N,S 7
Test (STP-102.003)
h.
System 078 Establish Instrument Air to Reactor Building (EOP-3.0)
N,A,E,S 8
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
i.
System 001 [JPPF-096]
Locally Trip the Reactor (EOP-13.0)
D,A, E 1
j.
System 061 [JPP-068]
Reset Turbine Driven Emergency Feed Pump (SOP-211)
D,R 4S
k.
System 062 Transfer a Vital 120VAC Power Supply - Return of Alternate N
6 Source (SOP-310)
RO Only NUREG-1021, Revision 9 ES 301 Control Room/ln-PlanR ems Outline Form ES 301 2
/JIUJ, Facility:
VC Summer Date of Examination:
2009 Exam Level (circle one):
RO I SRO(I)
Operating Test No.:
NRC Control Room SystemsC (8 for RO; 7 for SRO-I)
System I JPM TiUe Type Code" Safety Function
a.
APE 001 [JPSF-036]
Respond to Continuous Rod Withdrawal (AOP-403.3)
M, A, S 1
b.
System 006 [JPS-058]
Raise ECCS Accumulator level (SOP-112)
D, S 2
System 010 [JPSF-150]
Depressurize the ReS to Refill the Pressurizer (EOP-2.1)
P,D,A,E, S 3
d.
APE 025 [JPSF-065]
Establish hot leg injection during loss of RHR at mid-loop D, A, S, L 4P conditions (AOP-11S.5)
e.
System 045 [JPSF-022B]
Respond to Turbine Trip Failure (EOP-1.0)
M, A, E, S 4S
(
f.
System 026 [JPSF-019A]
Manually Initiate Reactor Building Spray (EOP-1.0)
M, A, E, S 5
g.
System 015 Perform an Intermediate RaAge NI Analog Channel Operational N, S 7
Test (STP-l02.003)
h.
System 078 Establish Instrument Air to Reactor Building (EOP-3.0)
N, A, E, S 8
In-Plant SystemsC (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
i.
System 001 [JPPF-096]
locally Trip the Reactor (EOP-13.0)
D, A,E 1
j.
System 061 [JPP-068]
Reset Turbine Driven Emergency Feed Pump (SOP-211)
D, R 4S
k.
System 062 Transfer a Vital 120VAC Power Supply - Return of Alternate N
6 Source (SOP-31 0)
ROOnly NUREG-1021, Revision 9
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
(
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
~~Type Codes Criteria for RO / SRO-I (A)lternate path 4-6/4-6~~
[6V [6]
(C)ontrol room (D)irect from bank
9 /

:; 8
[5]/ [4]
(E)mergency or abnormal in-plant
~ 1 / ~ 1
[4]/ [4]
(L)ow-Power
~ 1 / ~ 1
[1]/ [1]
(N)ew or (M)odified from bank including 1 (A)
~ 2 / ~ 2
[6]/ [6]
(P)revious 2 exams
3/

:; 3 (randomly selected) [1]/ [1]
(R)CA
~ 1 / ~ 1
[1]/ [1]
(S)imulator
(
NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 All control room (and in*plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
~~Type Codes Criteria for RO I SRO-I (A)lternate path 4-6 / 4-6~~
[6y [6J (C)ontrol room (O)irect from bank s: 9 f s: B
[5JI [4J (E)mergency or abnormal in-plant
~
1 f "2 1
[4JI [4J (L)ow-Power
~~1f :z. 1~~
[lJI [lJ (N)ew or (M)odified from bank including 1(A)
"2 2/ "2 2
[6JI [6J (P)revious 2 exams
~~s 31 :s 3 (randomly selected) [lJI [lJ (R)CA "2 1 / "2 1~~
[lY[lJ (S)imulator
(
NUREG-l021, Revision 9
(
(
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 VC SUMMER 2009 NRC EXAM JPM
~~SUMMARY~~
a. Respond to continuous rod withdrawal in accordance with AOP-403.3, CONTINUOUS CONTROL ROD MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps for evaluating PZR level response.
b. Raise the level in an ECCS Accumulator in accordance with SOP-112, SAFETY INJECTION SYSTEM. The applicant will restore ECCS Accumulator level to within the technical specification band using the system operating procedure. Bank JPM JPS-058.
c. Depressurize the RCS to refill the Pressurizer using a PORV in accordance with EOP-2.1, POST-LOCA COOLDOWN AND DEPRESSURIZATION, Step 8. The alternate path is that the applicant must use a PZR PORV to depressurize because the spray valve for the running RCP fails to open. After depressurizing, the PZR PORV will fail to close requiring the respective isolation valve to be closed. Randomly selected from 2007 NRC Exam. Bank JPM JPSF-150.
d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115.5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs. Bank JPM JPSF-065.
e. Respond to a turbine trip failure in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION. The alternate path is that the applicant will be required to trip the turbine using diverse means from the MCB and/or locally. After completing the immediate operator actions for the turbine trip, the applicant will respond to degrading plant conditions that require manual initiation of SI. Modify Bank JPM JPSF-022A by adding a simulator malfunction that leads to a requirement for MANUAL SI actuation.
f.
Manually initiate reactor building spray in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray pump suction and header isolation valves. Failure of MVG-3003A, RB Spray Isolation Valve, to open automatically will require the applicant to manually open the valve to establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.
~~g. Perform an Intermediate Range Analog Channel Operational Test for N35 in accordance with STP-102.003. New JPM.~~
h. Establish instrument air to the Reactor Building in accordance with EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, Step 11. Following a complete loss of instrument air the applicant will be required to start an instrument air compressor and then align instrument air to the Reactor Building. The alternate path requires the applicant to start the Supplemental Air Compressor. New JPM.
~~NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 VC SUMMER 2009 NRC EXAM JPM~~
~~SUMMARY~~
a. Respond to continuous rod withdrawal in accordance with AOP-403.3, CONTINUOUS CONTROL ROD MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps for evaluating PZR level response.
b. Raise the level in an ECCS Accumulator in accordance with SOP-112, SAFETY INJECTION SYSTEM. The applicant will restore ECCS Accumulator level to within the technical specification band using the system operating procedure. Bank JPM JPS-058.
c. Depressurize the ReS to refill the Pressurizer using a PORV in accordance with EOP*
2.1, POST-LOCA COOLDOWN AND DEPRESSURIZATION, Step 8. The alternate path is that the applicant must use a PZR PORV to depressurize because the spray valve for the running RCP fails to open. After depressurizing, the PZR PORV will fail to close requiring the respective isolation valve to be closed. Randomly selected from 2007 NRC Exam. Bank JPM JPSF-150.
d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115.5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs. Bank JPM JPSF-065.
e. Respond to a turbine trip failure in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION. The alternate path is that the applicant will be required to trip the turbine using diverse means from the MCB and/or locally. After completing the immediate operator actions for the turbine trip, the applicant will respond to degrading plant conditions that require manual initiation of SI. Modify Bank JPM JPSF-022A by adding a simulator malfunction that leads to a requirement for MANUAL SI actuation.
f.
Manually initiate reactor building spray in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray pump suction and header isolation valves. Failure of MVG-3003A, RB Spray Isolation Valve, to open automatically will require the applicant to manually open the valve to establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.
~~g. Peifonn an Intermediate Range Analog Channel Operational Test for N35 in accordance with STP-102.003. New JPM.~~
h. Establish instrument air to the Reactor Building in accordance with EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, Step 11. Following a complete loss of instrument air the applicant will be required to start an instrument air compressor and then align instrument air to the Reactor Building. The alternate path requires the applicant to start the Supplemental Air Compressor. New JPM.
NUREG-1021, Revision 9
(
(
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
i.
Locally trip the reactor in accordance with EOP-13.0, RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION, ATTACHMENT 1 - TRIPPING THE REACTOR LOCALLY. The alternate path requires the applicant to open the Rod Drive MG Set breakers after attempts to manually open the reactor trip breakers fail. Bank JPM JPPF-096.
j.
~~Reset turbine driven emergency feed pump in accordance with SOP-211, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.~~
k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT -5901 in accordance with procedure section IV.AD. New JPM.
NUREG-1021, Revision 9
(
(
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2
i.
Locally trip the reactor in accordance with EOP-13.0, RESPONSE TO ABNORMAL NUCLEAR POWER GENERATION, ATTACHMENT 1 - TRIPPING THE REACTOR LOCALLY. The alternate path requires the applicant to open the Rod Drive MG Set breakers after attempts to manually open the reactor trip breakers fail. Bank JPM JPPF-096.
j.
~~Reset turbine driven emergency feed pump in accordance with SOP-211, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.~~
k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT -5901 in accordance with procedure section IV.AD. New JPM.
NUREG-1021, Revision 9
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2
/J RIJ r--r Facility:
VC Summer Date of Examination:
2009
(
Exam Level (circle one):
SRO (U)
Operating Test No.:
NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)
System 1 JPM Title Type Code*
Safety Function
a.
APE 001 [JPSF-036]
Respond to Continuous Rod Withdrawal (AOP-403.3)
M,A,S 1
d.
APE 025 [JPSF-065]
Establish hot leg injection during loss of RHR at mid-loop D,A,E,S, L 4P conditions (AOP-115.5)
f.
System 026 (JPSF-019A]
Manually Initiate Reactor Building Spray (EOP-1.0)
M, A, E, EN, 5
S In-Plant Systems@ (3 or 2 for SRO-U)
j.
System 061 [JPP-068]
Reset Turbine Driven Emergency Feed Pump (SOP-211)
D,R 4S
k.
System 062 Transfer a Vital 120VAC Power Supply - Return of Alternate N
6 Source (SOP-310)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
~~Type Codes Criteria for RO 1 SRO-II SRO-U (A)lternate path 4-61 4-6 1 2-3 (C)ontrol room (D)irect from bank~~
~~~9/~8/~4 (E)mergency or abnormal in-plant~~
1/ ;

:: 1/ ;::: 1 (EN)ngineered safety feature 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 1 ~ 31 s 2 (randomly selected)
(R)CA
1/ ;

:: 1/ ;::: 1 (S)imulator NUREG-1021, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 lJ 1<'1.1 t:-7 Facility:
VC Summer Date of Examination:
2009
(
Exam level (circle one):
SRO (U)
Operating Test No.:
NRC Control Room SystemsC (8 for RO; 7 for SRO-I: 2 or 3 for SRO-U)
System I JPM Title Type Code' Safety Function
a.
APE 001 (JPSF-036)
Respond to Continuous Rod Withdrawal (AOP-403.3)
M, A, S 1
d.
APE 025 [JPSF-065)
Establish hot leg injection during Joss of RHR at mid-loop D,A, E, S, L 4P conditions (AOP-11S.S)
f.
System 026 [JPSF-019A)
Manually Initiate Reactor Building Spray (EOP-1.0)
M, A, E, EN, S
S In-Plant Systemsilll (3 or 2 for SRO-U)
j.
System 061 [JPP-068)
Reset Turbine Driven Emergency Feed Pump (SOP-211)
D, R 4S
k.
System 062
(
Transfer a Vital 120VAC Power Supply - Return of Alternate N
6 Source (SOP-310)
All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
.. Type Codes Criteria for RO 1 SRO-II SRO-U (A)ltemate path
' 4-61 4-6 1 2-3 (C)ontror room (D)irect from bank
$ 9/ $ 8/ $ 4 (E)mergency or abnormal in-plant
~ 1/ ~ 1/ ~
1 (EN)ngineered safety feature 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
$ 31 $ 3/ :S" 2 (randomly selected)
(R)CA iSiimutator
~ 1/ ~ 1/ ~
1 NUREG-1021, Revision 9
(
(
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 VC SUMMER 2009 NRC EXAM JPM
~~SUMMARY~~
a. Respond to continuous rod withdrawal in accordance with AOP-403.3, CONTINUOUS CONTROL ROD MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps for evaluating PZR level response.
d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115.5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs. Bank JPM JPSF-065.
f.
Manually initiate reactor building spray in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray pump suction and header isolation valves. Failure of MVG-3003A, RB Spray Isolation Valve, to open automatically will require the applicant to manually open the valve to establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.
j.
~~Reset turbine driven emergency feed pump in accordance with SOP-211, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.~~
k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT5901 in accordance with procedure section IV.AD. New JPM.
NUREG-1021, Revision 9
(
(
ES-301 Control RoomJln-Plant Systems Outline Form ES-301-2 VC SUMMER 2009 NRC EXAM JPM
~~SUMMARY~~
a. Respond to continuous rod withdrawal in accordance with AOP-403.3, CONTINUOUS CONTROL ROD MOTION. The alternate path is that the applicant will respond to a loss of charging flow that will require manual control of FCV-122, Charging Flow Control Valve, to restore PZR level. Modify Bank JPM JPS-036 by adding the procedure steps for evaluating PZR level response.
d. Establish hot leg injection during loss of RHR at mid-loop conditions in accordance with AOP-115.5, LOSS OF RHR WITH THE RCS NOT INTACT (MODES 5 & 6). The alternate path is that the applicant will respond to degrading plant conditions by aligning RHR injection and establishing flow to the RCS hot legs. Bank JPM JPSF-065.
f.
Manually initiate reactor building spray in accordance with EOP-1.0, REACTOR TRIP/SAFETY INJECTION ACTUATION, Step 8. The applicant will implement alternate path actions to actuate RB Spray using Train B switches or by manually aligning spray pump suction and header isolation valves. Failure of MVG-3003A, RB Spray Isolation Valve, to open automatically will require the applicant to manually open the valve to establish Train A Reactor Building Spray flow. Modify Bank JPM JPSF-019 by adding the MVG-3003A failure.
j.
~~Reset turbine driven emergency feed pump in accordance with SOP-211, EMERGENCY FEEDWATER SYSTEM. Bank JPM JPP-068.~~
k. Transfer a vital 120VAC power supply in accordance with SOP-310, 120 VAC INSTRUMENT AND CONTROL SYSTEM. The applicant will complete the steps to restore the alternate source of power to Inverter XIT5901 in accordance with procedure section IV.AD. New JPM.
~~NUREG-1021, Revision 9~~

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