ML101600061

301 Written Quality Checklist (Section 1)

ML101600061
Person / Time
Site:	Summer
Issue date:	03/28/2010
From:	NRC/RGN-II
To:
References
ES-401-6
Download: ML101600061 (16)

Text

Draft Submittal (Pink Paper) ec d7 o

DRAFT Written Exam Quality Checklist (ES-401-6)

& Written Exam Sample Plan

ES-401 ES-401 Written Written Examination Examination Quality Quality Checklist Checklist Form Form ES-401-6 ES-401-6 Facility: VC Summer C Summer Date of Date of Exam:

Exam: 6/4/2007 6/4/2007 Exam Exam RO/SRO RO/SRO Leve!:

Level:

Initial Initial Item Description Item Description aa b* C#

c#

1.

1. Questions and Questions and answers answers technically technically accurate accurate and and applicable applicable toto facility.

facility. CI64 CJ1 <~

2. a. NRC KlAs K/As referenced referenced for for all all questions.

questions.

2. a. NRC -(y---

b.

b. Facility_learning_objectives_referenced_as_available.

Facility learning objectives referenced as available. ~

3.

3. SRO questions SRO questions are appropriate in are appropriate in accordance accordance with with Section Section D.2.d D.2.d of ES-401 of ES-401 ~ ~

4. The sampling The sampling process process was random random and and systematic.

systematic. (If (If more more than than 4 RO RO and and 22 SRO SRO t questions were repeated Program Office)

Program Office) repeated from from the the last last 2 NRC NRC licensing licensing exams, exams, consult consult the the NRR NRR OL OL CM ~

5. duplication from the license Question duplication license screening/audit exam exam was controlled \

5. Question controlled as indicated below indicated (check the item below (check item that applies) and appears appropriate:

the audit exam was systematically and randomly developed, or

~

f-the audit exam was completed before the license exam was started, or the examinations were developed independently, or

~ XX the licensee certifies that there is no duplication, or other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest 7.

new or modified); enter the actual RO I/ SRO-only question_distribution(s)_at_right.

question distribution(s) at right.

Between 50 and 60 percent of the question on the 41 I 13 41/13 6 / 1 6/1 28/11 ~

t-Memo ty Memory CIA comprehension/

RO exam are written at the comprehensionl analysis level; the SRO exam may exceed 60 percent iff the randomly selected KlAs question_distribution(s)_at_right question distribution(s) at right K/As support the higher cognitive levels; enter the actual RO / SRO 30 I 3 45 /22 45/22 \{ZO\

F--

8. References/handouts provided do not give away answers or aid in the elimination of Q?(A ~

ddistractors.

istractors.

I

9. Question content conforms with specific KIA K/A statements in the previously approved

~

~

examination outline and is appropriate for the tier to which they are assigned; deviations are justified.

10.

10. Question psychometric quality and format meet the guidelines in ES Appendix B.

~ ~

11.

11. The exam contains the required number of one-point, multiple choice items; the total is is correct_and_agrees_with_value_on_cover_sheet.

correct and agrees with value on cover sheet. ~ 117 ~~

prU/~~

Print d Name / Signytur Date a.

a. Author Joseph Joseph G. G. Arsenault ., 4/1212007 4/12007

"--'II ,

b.

b. Facility Reviewer (*)

Facility Reviewer (*) /;J, 1/, {l ~ f( rx 1/ /Jc l/~JJJA~' ~i~1A '1 f'fh{J()7

c. NRC NRC ChiefChief Examiner (#)

d.

d. NRC Regional Supervisor NRC Supervisor Note:

Note:

• The facility reviewers The facility reviewer's initials/signature initials/signature are are not not applicable applicable for for NRC-developed NRC-developed examinations.

examinations.

1. 1. Independent Independent NRC NRC reviewer reviewer initial initial items items inin Column Column c; "c"; chief chief examiner concurrence required.

examiner concurrence required.

DRAFT R FT NUREG-1021, NUREG-1021, Revision Revision 99

Written Examination Quality Checklist Form ES-401-6 Form ES-401-6 ES-401 ES-40 1 Writte n Exami nation Qualit y Check list IFacility:

Facility: VC VCSummSummer er DateofofExam:

Date Exam: 6/4/20 07 6/4/2007 Exam Exam ROISRO RO/SRO Level:

Level:

Initial Initial aa b* c#

ItemDescription Item Description b* c#

p-1.i. Questions Questions and answerand answers s technically technically accurate accura te andandapplica ble totofacility.

applicable facility. ~

Sj7S ",......

2.2. a.a. NRCK/As KlAsreferen referenced forallallquestio questions.

ns.

~.

NRC ced for

@\)

b.b. Facility Facility_lear learning objectives ning_objectiv referenced es_reference as available.

d_as_availab le.

3.3. SRO questions are appropriate SRO questions are appropriate in accordance with in accordance with Sectio Section D.2.dofofES-401 n D.2.d ES-401 _GJA I~

4.4. Thesampling The sampling proces process wasrandom s was randomand and system systematic. morethan (Ifmore atic. (If than44RO ROand and22SROSRO I questions questio were repeate ns were repeated fromthe d from thelastlast22 NRC licensingexams NRClicensing exams, consultthe

, consult NRROL the NRR OL Vbb Program Program Office) Office) (£~

5.5. Question Questi duplicationfrom on duplication fromthe thelicense license screen ing/audit exam screening/audit examwas controlled as was controlled as I indicated below (check indicated below (check the item the item that that applies) applies ) and and appears appear s appropriate:

appropriate:

the audit audit exam exam was was system systematically atically and randomly develo and randomly developed,ped, or or

- - the

~

~

the the audit audit exam exam was was completed compl eted before before the the license license exam exam was was started started,, or or

-- the examin the examinations ations were were develo developed independently, ped independentl y, oror XX the license the licensee certifies that e certifies that there there isis no no duplication, duplication, or or

- XX -

other (explain) other (explain) 6.

6. Bank use Bank use meets meets limits limits (no(no more more than than 75 75 percen percentt Bank Bank Modified Modified New New from thethe bank bank at at least least 10 10 percen percentt new, new, andand the the rest rest (jtI4 rf from new or new or modified);

modified); enter enter the actual RO I1SRO-only the actual 55/

55/52 52 88/4/ 4 37/44 37/44

....9.uestion distribution(s) at question_distribution(s)_at_right._(IN_%) right.llN  %)

7.

7. Between 50 Between 50 andand 60 60 percen percentt of of the questio question n on the Memo Memory CIA CIA RO exam RO exam are written at are written at the the compr comprehension/

ehension?

~

f-analYSis level; the analysis level; the SRO exam SRO exam may may exceed exceed 60 60/88 40 / 12 40/12 60/88 percent percent ifif thethe randomly randomly selected selected KlAs K/As support support the higher higher cognitive cognitive levels; levels; enter enter thethe actual actual RO / SRO

....9.uestion question_dis distribution(s) at right{IN %)

tribution(s)_at_right_(IN_  %)

8.

8. References/handouts References/handouts provided do not not give away answers answers or aid in the elimination of 9.

distractors.

distractors.

Question approved

\iU4 ~ I

9. Question contentcontent conforms conforms with with specific specific KIA K/A statements statements in in the the previously previously approved ed; GM

~.

examination examin ation outline outline and and is is appropriate approp riate for for the the tier tier to to which which they they are are assigned; assign deviations deviations are are justified.

justified.

10.

10. Question Question psychometric psychometric quality quality and and format format meet meet the the guidelines guidelines in in ES ES Appendix Appendix B. B.

~ ~

11.

11. The The exam exam contains contains the the required required number number of of one-point, one-point multiple multiple choice choice items; items; the the total total isis correct correct and and agrees agrees with with value value on on cover cover sheet.

sheet. <W\ ~

Name ~

Printed Name Pc;nted / Sig t Date Date a.a. Author Author Joseph G.

Joseph Arsenault G. Arsenault L~ ,J.~ ~ 4/1212007 4/1212007 J(/,; {(QJI~k V£0~h :l ::J~.b

~V:(/IU'~

b.b. Facility Reviewer(*)

FacilityReviewer (*)

v y/t-r(J 007 c, NRC

c. NRC ChiefChiefExaminer Examiner(#) (#)

d.d. NRC NRCRegional RegionalSupervisor Supervisor Note:

Note: ** The Thefacility facilityreviewer'S initials/signatureare reviewersinitials/signature arenot notapplicable applicablefor examinations.

NRC-developedexaminations.

forNRC-developed

1. 1. IndependentNRC Independent NRCreviewer reviewerinitial itemsininColumn initialitems Column"c"; c;chief examinerconcurrence chiefexaminer required.

concurrencerequired.

b15!R (8 (JTl(JY/

/;J DRAFT NUREG-1021, NUREG.-1021,Revision Revision99 pECJ7 PEeC8J/

ES-401 PWR Examination I Form ES-401-2 Facility: VC Summer Date of Exam: 6/4/2007 RD KIA RO K/A Category Points SROOnly_Points SRO-Only Points Tier Group G*

K K K K K K A A A A G Total A2 G* Total 11 234561 2 3 4 5 6 1 234*

2 3 4

• 1

1. 11 55434 3 113 3 2 18 3 3 6 Emergency

& 2 00121 2 222 2 2 9 2 2 4 Abnormal Plant Tier 5 5 5 3 5 4 27 5 5 10 Evolutions Totals 11 554321021433 4 3 2. 1 0 2 1 4 3 3 28 3 2 5 2

2.

Plant 2 0 0 1 2 2 2 1 2 0 0 0 10 0 11 2 3 Systems Tier 554443233433 4 4 4 3 2 3 3 4 3 3 38 4 4 8 Totals

3. Generic Knowledge and 11 2 3 4 1 1 2 3 4 10 7 Abilities Categories 3 2 2 3 2 2 11 2 Note: 1. Ensure that at least two topics from every applicable KIA K/A category are sampled within each tier of the RORD and SRO-only SRD-only outlines (i.e., except for one category in Tier 3 of the SRD-only outline, the "Tier SRO-only Tier Totals" Totals in each KIA 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 RD exam must total 75 points SRD-only exam must total 25 points.

and the SRO-only

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 elimination of inappropriate KIAK/A statements.

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.

5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RD RO and SRO ratings for the RD RO and SRD-only SRO-only portions, respectively.

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

7*

7.* KlAs in Tiers 1 The generic (G) K/As 1 and 2 shall be selected from Section 2 of the K/AKIA Catalog, but the topics must be relevant to the applicable evolution or system.

8. Dn On the following pages, enter the K/A KIA numbers, aa brief description of each topic, the topics 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 RD RO and SRD-only SRO-only exams.

9. For Tier 3, select topics from Section 22 of the K/A KIA Catalog, and enter the K/A KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRD SRO selections to K/As KlAs that are linked to 110CFR55.43 OCFR55.43 NUREG-1021 11 DRAFTR FT

ES401 ES-401 VC VC Summer Summer Form ES-401-2 Form ES-401-2 NRC Written Examination Outline NRC Written Examination Outline Emergency and Emergency Abnormal Plant and Abnormal Plant Evolutions Evolutions - Tier Tier 11 Group Group 11 E!APE ## I/ Name E/APE Name Safety Safety Function Function G Ki K2 K3 Al A2 Number Number KIA K/A Topic(s)

Topic(s) Imp. Q#

I

Ability Ability to to determine determine and and interpret interpret the the following following asas they they 022 // Loss 022 Loss of of Reactor Reactor Coolant Makeup /I 22 Coolant Makeup X X AA2.02 AA2.02 apply apply to to the the Loss Loss ofof Reactor Reactor Coolant Coolant PumpPump Makeup: 3.7 76 Makeup: 3.7 76 Charging Charging pump pump problems problems Ability Ability to to determine determine or or interpret interpret thethe following following asas they they 029 I Anticipated 029/ Anticipated Transient Transient Without Without Scram Scram (ATWS)

(ATWS) /I 1I X X EA2.07 EA2.07 apply apply toto aa ATWS:

ATWS: Reactor Reactor triptrip breaker breaker indicating indicating 4.3 77 4.3 77 lights lights Emergency Emergency Procedures Procedures /I Plan Knowledge of Plan Knowledge of 038!j Steam Steam Generator Generator Tube Tube Rupture!

Rupture! 33 X 2.4.31 2.4.31 annunciators annunciators alarms alarms andand indications, indications, and and use use of 038 X of the the 3.4 3.4 78 78 response instructions.

instructions.

Emergency Emergency Procedures Procedures /I PlanPlan Ability to to verify system system 040 !/ Steam 040 Steam Line Line Rupture Rupture /I 44 X 2.4.50 alarm setpoints and operate controls identified identified in in the the 3.3 79 3.3 79 alarm response manual.

Ability to determine or interpret the following following asas they they 055 // Station 055 Station Blackout Blackout!/ 66 X EA2.02 apply to a Station Blackout: RCS core core cooling cooling 4.6 80 4.6 80 through natural circulation cooling to to S/G SIG cooling cooling 056!I Loss of Off-site Loss of Off-site Power Power!/ 66 X Emergency Procedures / Plan Knowledge symptom symptom 056 X 2.4.6 4.0 4.0 81 based EOP mitigation mitigation_s strategies.

trategies.

Knowledge of the reasons for the following followlng asas the the 007! Reactor 007/ Reactor Trip Trip!/ 11 X EK3.01 apply to a reactor trip: Actions contained in EOP EOP for 4.0 39 4.0 39 reactor trip Knowledge of the interrelations between the the 008 I/ Pressurizer 008 Pressurizer Vapor Space Accident!

Vapor Space Accident / 33 X X AK2.01 Pressurizer Vapor Pressurizer Vapor Space Accident and the followlng: following: 2.7 2.7 40 40 Valves Knowledge of of the operational implications of of the the 009 009 I/ Small Small Break Break LOCA LOCA !/ 33 XX EK1 EK1.02

.02 concepts as following concepts as they they apply apply to to the the small small break break 3.5 41 3.5 41 LOCA: Use LOCA: Use ofof steam steam tables tables 011 Knowledge of Knowledge of the the interrelations interrelations between between the the and and the the 011 !/ Large Large Break Break LOCA!

LOCA / 33 XX EK2.02 EK2.02 2.6 2.6 42 42 following Large following Large Break Break LOCA:

LOCA: PumpsPumps Knowledge of Knowledge of the the interrelations interrelations between between the the Reactor Reactor 015!

015/ 17!

17/ Reactor Reactor Coolant Coolant Pump Pump Malfunctions Malfunctions!/ 44 XX AK2.08 AK2.08 Coolant Pump Coolant Pump Malfunctions Malfunctions (Loss(Loss of of RC RC Flow)

Flow) and and 2.6 2.6 43 43 the following:

the following: CCWS CCWS Knowledge of Knowledge of the the operational operational implications implications of of the the 022 following concepts following concepts as as they they apply apply toto Loss of Reactor Loss of Reactor Loss of 022 !/ Loss of Reactor Reactor Coolant Coolant Makeup Makeup I/22 XX AK1 .02 AK1.02 2.7 2.7 44 44 Coolant Pump Coolant Pump Makeup:

Makeup: Relationship Relationship of of charging charging flow flow to pressure to pressure differential differential between between charging charging andand RCS RCS Knowledge of Knowledge of the the reasons reasons for for the the following following responses responses 027!

027 / Pressurizer Pressurizer Pressure Pressure Control Control System System Malfunction Malfunction as they as they apply apply toto the the Pressurizer Pressurizer Pressure Pressure Control Control 3

//3 X AK3.01 AK3.01 3.5 45 45 Malfunctions:

Malfunctions Isolation of

Isolation of PZR PZR spray spray following following loss loss ofof PZR PZR heaters heaters NUREG-102 NUREG-1021 1 22

ES401 ES-401 Form Form ES-401-2 VC Summer VC Summer ES-401-2 NRC Written Examination NRC Written Examination Outline Outline Emergency and Emergency and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier Tier 11 Group Group 11 L

E/APE ## II Name E/APE Name SafetySafety Function Function GG Ki K1 K2 K2 K3 K3 I A1 Al I A2A2 I Number Number KIA K/A Topic(s)

Topic(s) limp.

Imp. I Q# II Knowledge Knowl edge of of the the interrelations interrelations between between the the and and the the 029 / Anticipated Anticipated Transient Transient Without Without Scram Scram (ATWS)

(ATWS) /1 /1 xX EK2.06 following following an an ATWS:

ATWS: Breakers, 029/ EK2.06 Breakers, relays, relays, andand 2.9 2.9 46 46 disconnects disconnects 038 / Steam 038/ Steam Generator Generator Tube Tube Rupture Rupture // 33 XX 2.2.22 2.2.22 Equipment Equipment Control Knowledge of control Knowledge of limiting limiting conditions conditions 3.4 47 for for operations operations and and safety safety limits.

limits. 3.4 47 Knowledge of Knowledge of the the operational operational implications implications of of the the 054 // Loss Loss of of Main Main Feedwater Feedwater // 44 X following following concepts concepts as as they they apply apply to to Loss Loss of of Main Main 054 X AK1 .01 AK1.01 4.1 4.1 48 48 Feedwater Feedwater (MFW):

(MFW): MFW MFW lineline break break depressurizes depressurizes the S/G S/G (similar (similar to aa steam steam lineline break) break)

Ability to Ability to operate operate and and monitor monitor the the following following as as they they 055 // Station Station Blackout Blackout // 66 X EA1 .07 EA1.07 apply to a Station Blackout: Restoration 055 Restoration of of power power 4.3 4.3 49 49 from offsite Ability to determine and interpret the the following following as as they they 056 // Loss Loss of of Off-site Off-site Power Power // 66 apply to the Loss of Offsite Power: Power: That That load load andand 056 X AA2.50 2.8 2.8 50 50 VAR limits, alarm setpoints, frequency frequency and and voltage voltage limits for ED/Gs are not being being exceeded exceeded Ability to determine and interpret the the following following as as they they 057 apply to the Loss of Vital AC Instrument Instrument Bus: Bus: The The 057// Loss of Vital Loss of AC Electrical Vital AC Electrical Instrument Instrument Bus Bus // 66 X AA2.19 4.0 4.0 51 51 plant automatic actions that will will occur occur on on the the loss of aa loss of vital ac electrical instrument bus bus determine and Ability to determine and interpret interpret the the following following as as they they 058/

058 / Loss Loss of of DC DC Power!

Power / 66 X X AA202 AA2 02 apply to the Loss of of DC Power:

Power: 125V 125V dc dc bus bus voltage, voltage, 3.3 52 3.3 52 low, alarm low/critical low, alarm Knowledge of Knowledge of the the reasons reasons for for the the following follOwing responses responses 065 065// Loss of Instrument Loss of Instrument Air? 8 Air /8 XX AK3.04 AK3.04 as they as they apply apply toto the the Loss Loss of of Instrument Instrument Air: Air: Cross-Cross- 3.0 53 3.0 53 over to over to backup backup air air supplies supplies Knowledge of Knowledge of the the operational operational implications implications of of the the following concepts following concepts as as they they apply apply to to the the (LOCA (LOCA E04// LOCA E04 LOCA Outside Outside Containment Containment // 33 XX EK1 .2 EK1.2 Outside Containment Outside Containment) Normal, abnormal

) Normal, abnormal and and 3.5 3.5 54 54 emergency operating emergency operating procedures procedures associated associated with with (LOCA Outside (LOCA Outside Containment Containment). ).

Knowledge of Knowledge of the the operational operational implications implications of of the the Eli following concepts following concepts as as they they apply apply to to the the (Loss (Loss of of E11 // Loss of Emergency Loss of Emergency Coolant Coolant Recirculation Recirculation //4 4 XX EK1.1 EK1.1 Emergency Coolant Coolant Recirculation Recirculation) Components, 3.7 3.7 55 55 Emergency ) Components ,

capacity, and capacity, and function function of of emergency emergency systems. systems.

El2 / Uncontrolled EquipmentControl Equipment Control Knowledge Knowledge of ofbases bases inin technical technical E12/ Uncontrolled Depressuriza tion of Depressurization ofall all Steam Steam Generators X 2.2.25 2.2.25 specifications specification for limiting s for limiting conditions conditions for foroperations operations 2.5 56 Generators // 44 and safety safety limits.

limits.

2.5 56 and NUREG-l NUREG-1021 021 33

ES4O1 ES-401 Form Form ES-401-2 VC Summer VC Summer ES-401-2 NRC Written Examination Outline NRC Written Examination Outline Emergency and Emergency Abnormal Plant and Abnormal Plant Evolutions Evolutions - Tier Tier 11 Group Group 1I E/APE ## II Name E/APE Name Safety Safety Function Function I GG I K1 KI K2 I K3 I K2 K3 I AAl1 I A2 A2 Number I I Number KIA K/A Topic(s)

Topic(s) Imp. I Q#

Imp. Q# II K/A Category KJA Category Point Point Totals:

Totals: Group GroUP Point Point 5 5 4 3 1 6 24 Total:

NUREG-l NUREG-1021 021 44

ES-401 ES-401 Form Form ES-401-2 VC Summer VC Summer ES-401-2 NRC Written NRC Written Examination Examination Outline Outline Emergency and Emergency and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier Tier 11 Group Group 22 E/APE ## I/ Name E/APE Name Safety Safety Function Function G Kl K2 K3 Al A2 Number Number KIA K/A Topic(s)

Topic(s) Imp. Q#

Ability Ability to to determine determine and and interpret interpret the the following following as as Continuous Rod 001 !/ Continuous Withdrawal / 11 Rod Withdrawal; they they apply apply to to thethe Continuous Continuous Rod Rod Withdrawal:

Withdrawal:

001 XX AA2.05 AA2.05 4.6 4.6 82 82 Uncontrolled Uncontrolled rod rod withdrawal, withdrawal, from from available available indications indications Ability Ability to to determine determine and and interpret interpret the the following following as as they apply to they apply to the the (Saturated (Saturated Core Core Cooling)

Cooling)

E07 !/ Saturated E07 Saturated Core Core Cooling!

Cooling / 44 X X EA2.2 EA2.2 Adherence to to appropriate appropriate procedures procedures and and operation operation 3.9 3.9 83 83 within within the the limitations limitations in in the the facility's facilitys license license and and amendments.

amendments.

E08 / Pressurized Pressurized Thelmal Thermal Shock!

Shock I 44 X Equipment Control Knowledge of of limiting conditions conditions E08; 2.2.22 4.1 41 84 84 for operations and safety limits.

Conduct of Operations: Knowledge of of system system status status El155 ;I Containment E Containment Flooding Flooding // 55 X X 2.1.14 criteria which require the notification of of plant plant 3.3 3.3 85 85 personnel.

Ability to determine and interpret the the following following as as 001 ;/ Continuous 001 Continuous Rod Withdrawal / 11 Rod Withdrawal! X X AA2.04 they apply to the Continuous Rod Withdrawal: 4.2 57 Withdrawal: 4.2 57 Reactor power and its trend Knowledge of the reasons for the following following responses as they apply to the Pressurizer Level Level 028 ;/ Pressurizer 028 Pressurizer Level Level Control Control Malfunction Malfunction!/ 22 X X AK3.03 Malfunctions:: False indication Control Malfunctions indication of of PZR PZR level level 3.5 3.5 58 58 when PORV PORV or spray valve is is open open and and RCS RCS saturated Ability to to operate operate and and!/ oror monitor monitor the following following as as 036!/ Fuel 036 Fuel Handling Handling Incidents Incidents!/ 88 X X Ml AA1.01

.01 they apply they apply to to thethe Fuel Fuel Handling Handling Incidents:

Incidents: Reactor Reactor 3.3 3.3 59 59 Building Containment Building Containment Purge Purge Ventilation Ventilation System System Knowledge Knowl edge of of the the reasons reasons for for the the following following 051 responses as responses as they they apply apply to to the the Loss Loss of of Condenser Condenser 051 /; Loss Loss of of Condenser Condenser Vacuum Vacuum!/ 44 X AK3.01 AK3.01 2.8 2.8 60 60 Vacuum: Loss Vacuum: Loss of of steam steam dump dump capability capability uponupon loss loss of condenser of condenser vacuum vacuum Conduct of Conduct of Operations:

Operations: Ability Ability to to recognize recognize indications for indications for system system operating operating parameters parameters which which E03 I! LOCA E03 LOCA Cooldown and Depressuriza Cooldown and tion /44 Depressurization! XX 2.1.33 2.1.33 3.4 3.4 61 61 are entry-level are entry-level conditions conditions for for technical technical specifications.

specification s.

Knowledge of Knowledge of the the interrelations interrelations between between the the (Degraded Core (Degraded Core Cooling)

Cooling) and and the the following:

following:

Facility's heat Facilitys heat removal removal systems, systems, including including primary primary E06 E06 I! Degraded Degraded Core Core Cooling Cooling! I 44 XX EK2.2 EK2.2 coolant, emergency coolant, emergency coolant,coolant, the the decay decay heatheat removal removal 3.8 62 3.8 62 systems, and systems, and relations relations between between the the proper proper operation of operation of these these systems systems to to the the operation operation of of the the facility.

facility.

NUREG-102 NUREG-1021 1 55

ES-401 ES-401 VC VC Summer Summer Form Form ES-401-2 ES-401-2 NRC Written Examination NRC Written Examination OutlineOutline Emergency and Emergency and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier Tier 1I Group Group 22 E/APE ## II Name E/APE Name Safety Safety Function Function G Ki K2 K3 Al A2 Number Number KIA K/A Topic(s)

Topic(s) Imp. Q#

Ability to Ability to operate operate andand // or or monitor monitor the the following following as as they they apply apply toto the the (Pressurized (Pressurized Thermal Thermal Shock)

Shock)

E08/ Pressurized Thermal E08 / Pressurized Shock //4 Thermal Shock 4 XX EA2.1 EA2.1 Facility Facility conditions conditions andand selection selection of of appropriate appropriate 3.4 3.4 63 63 procedures during procedures during abnormal abnormal andand emergency emergency operations.

operations.

ElO / Natural Natural Circulation Circulation with with Steam Void in Steam Void in Vessel Vessel conduct of Conduct of Operations: Ability to perform perform specific specific E10/

with/without RVLlS RVLIS // 44 X 2.1.23 system and integrated plant procedures during all all 3.9 3.9 64 64 with/without modes modes of of plant plant operation.

operation.

Ability to operate and / or monitor the following following asas E16/ High High Containment Containment Radiation Radiation/9 they apply to the (High Containment Radiation)Radiation)

E16/ /9 X EA1.3 2.9 2.9 65 65 Desired operating results during abnormal and and emergency situations.

K/A Category KJA Category Point Point Total:

Total: 4 4 0 1 1 2 2 4 Group Point Total: I 13 13 NUREG-102 NUREG-1021 1 66

ES-401 ES-401 Form Form ES-401-2 ES-401-2 VC Summer VC Summer NRC Written NRC Written Examination Examination Outline Outline Plant Systems Plant Systems - Tier Tier 22 Group Group 11 System #/Name System #/Name G Ki K2 K3 K4 K5 K6 Al A2 A3 A4 Number KIA K/A Topics Topics Imp. Q#

Ability Ability toto (a)

(a) predict predict thethe impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the CVCS; CVCS: and and (b)(b) 004 Chemical and 004 Chemical Volume and Volume based based on on those those predictions, predictions, use procedures to use procedures XX A2.15 A2.15 to 3.7 86 Control Control correct, correct, control, control, or or mitigate mitigate thethe consequences consequences of 3.7 86 of those those malfunctions malfunctions or or operations:

operations: High High or or low low PZR PZR level level Ability to Ability to (a)

(a) predict predict thethe impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on the the PZR PZR PCS; PCS: and and 010 Pressurizer Pressurizer Pressure Pressure Control Control (b)

(b) based based on those predictions, predictions, use use procedures procedures to to 010 X A2.02 A2.02 3.9 3.9 87 87 correct, correct, control, control, or or mitigate mitigate thethe consequences consequences of of those malfunctions or operations: Spray Spray valvevalve failures Emergency Procedures! Knowledge of Procedures / Plan Knowledge of 022 Containment 022 Containment Cooling Cooling X X 2.4.30 which events related to system operations/status operations/status 3.6 88 3.6 88 should be reported to outside agencies.

Ability to (a) predict the impacts of of the the following following mal-functions mal-functions or operations on on the the MRSS; MRSS: and and (b)

(b) based on predictions, use procedures to to correct, correct, 039 Main 039 Main and and Reheat Reheat Steam Steam X A2.05 consequences of control, or mitigate the ccnsequences of those those 3.6 89 3.6 89 malfunctions or operations: Increasing steam steam demand, its relationship to increases in in reactor reactor power 076 Emergency Procedures Procedures / Plan Knowledge Knowledge 076 Service Service Water Water X X 2.4.6 2.4.6 mitigation strategies.

strategies.

4.0 4.0 90 90 symptom based EOP mitigation 003 manually operate Ability to manually operate and/or and/or monitor in in the the 003 Reactor Reactor Coolant Coolant Pump Pump X< A4.08 room: RCPRCP cooling cooling water supplies supplies 3.2 3.2 1 control room:

004 Chemical 004 Chemical and and Volume Volume XX A3.05 A3.05 Ability to Ability to monitor monitor automatic operation operation of of the 3.9 Control Control CVCS, including:

CVCS, including: RCS RCS pressure pressure and and temperature temperature 3.9 22 Knowledge of Knowledge of the the effect effect that that aa loss loss or or malfunction malfunction 005 Residual 005 Residual Heat Heat Removal Removal XX K3.07 K3.07 of the of the RHRS RHRS will will have have onon the the following:

following: Refueling Refueling 3.2 3.2 33 operations operations Knowledge of Knowledge of bus bus power power supplies supplies to to the the following:

following:

006 Emergency 006 Emergency Core Core Cooling Cooling XX K2.01 K2.01 ECCS pumpspumps 3.6 3.6 44 ECCS Ability to Ability to monitor monitor automatic automatic operation operation of of the the 006 Emergency 006 Emergency Core Core Cooling Cooling XX A3.07 A3.07 ECCS, including:

including: RHR RHR pumps pumps 3.6 3.6 55 ECCS, 007 Pressurizer 007 Pressurizer Relief/Quenc Relief/Quenchh XX A4.04 A4.04 Ability to Ability to manually manually operate operate and/or and/or monitor monitor inin the the 2.6 Tank Tank control room:

control room: PZRPZR vent vent valve valve 2.6 66 Knowledge of Knowledge of the the physical physical connections connections and/or and/or 008 Component 008 Component Cooling Cooling Water Water XX K1.03 Kl.03 cause-effect relationships cause-effect relationships between between the the CCWS CCWS and and 2.8 2.8 77 the following the following systems:

systems: PRMSPRMS NUREG-1 NUREG-1021 021 77

ES-401 ES-401 VC VC Summer Summer Form Form ES-401-2 ES-401 -2 NRC Written Examination Outline NRC Written Examination Outline Plant Plant Systems Systems - Tier Tier 2 2 Group Group 11 System #/Name GG Kl K2 I K3 I K4 K5 K6 Al A2 KIA II System #/Name Ki K2 K3 K4 K5 K6 Ai A2 A3 A3 A4 A4 Number Number K/ATopics Topics Imp.

Imp. Q#

Q#

Ability Ability toto monitor monitorautomatic automatic operation operation of of the the PZR PZR 010 Pressurizer Pressurizer Pressure Pressure Control Control XX A3.01 PCS, PCS, including:

including: PRT PRT temperature temperature and 010 A3.0l and pressure pressure 3.0 3.0 88 during during PORVPORV testing testing Knowledge Knowledge of of the the physical physical connections connections and/or and/or 012 Reactor Reactor Protection Protection XX K1.07 cause effect relationships relationships between between the 012 K1.07 cause effect the RPS RPS andand 2.9 2.9 99 the the following following systems:

systems: SDS SDS 012 Reactor Reactor Protection Protection Knowledge Knowledge of of bus bus power power supplies supplies to to the the following:

following:

012 X K2.01

[<2.01 RPS 3.3 3.3 10 10 RPS channels, channels, components, components, and and interconnections interconnections Engineered Safety 013 Engineered Safety Features Features Knowledge of Knowledge of the the physical physical connections connections and/or and/or 013 XX K1.06 cause Actuation K1.06 effect relationships cause effect relationships between between the the ESFAS ESFAS 4.2 4.2 11 11 Actuation and and the the following following systems:

systems: ECCSECCS 013 Engineered Engineered Safety Safety Features Features Knowledge of Knowledge of the effect that the effect that aa loss loss oror malfunction malfunction 013 X X K3.03 of the ESFAS will have on Actuation on the the following:

following: 4.3 4.3 12 12 Actuation Containment Emergency Procedures // Plan Plan Ability Ability to to verify verify that that 022 Containment 022 Containment Cooling Cooling X X 2.4.46 the alarms are consistent with with the the plant plant 3.5 13 3.5 13 conditions.

026 Containment Containment Spray Spray X Knowledge of bus power supplies supplies to to the the following:

following:

026 X K2.02 MOVs 2.7 2.7 14 14 Knowledge of CSS design feature(s) and/or and/or 026 interlock(s) which provide for for the the following:

following:

026 Containment Containment Spray Spray X K4.07 Adequate level level inin containment sump sump for for suction suction 3.8 3.8 15 15 (interlock)

Knowledge of Knowledge of MRSS MRSS design design feature(s) feature(s) and/orand/or 039 039 Main and Reheat Main and Reheat Steam Steam X X K4.06 interlock(s) which provide for interlock(s) for the the following:

following: 3.3 16 3.3 16 Prevent reverse Prevent reverse steam steam flow flow on on steam steam line line break break Emergency Procedures Emergency Procedures // PlanPlan Ability Ability to to verify verify 059 Main Feedwater 059 Main Feedwater XX 2.4.50 2.4.50 system alarm system alarm setpoints setpoints andand operate operate controls controls 3.3 17 3.3 17 identified in identified in the the alarm alarm response response manual.

manual.

Knowledge of Knowledge of the the operational operational implications implications of of the the 061 AuxilIary/Em 061 ergency Auxiliary/Emergency XX K5.02 K5.02 following concepts following concepts as as the the apply apply to to the the AFW:

AFW: 3.2 18 Feedwater Feedwater 3.2 18 Decay heat Decay heat sources sources and and magnitude magnitude Ability to Ability to predict predict and/or and/or monitor monitor changes changes inin parameters (to parameters (to prevent prevent exceeding exceeding design design limits) limits) 062 associated with associated with operating operating thethe acac distribution distribution 062 AC AC Electrical Electrical Distribution Distribution XX A1.03 Al .03 system controls controls including:

including: Effect Effect onon 2.5 2.5 19 19 system instrumentation instrumentati on andand controls controls of ofswitching switching power power supplies supplies NUREG-1 NUREG-1021 021 88

ES-401 ES4O1 VC VC Summer Summer Form Form ES-401-2 ES-401-2 NRC Written NRC Written Examination Examination Outline Outline Plant Systems - Tier Plant Systems Tier 22 Group Group 1 1

• System System #/Name

1. /Name G Kl K2 K3 K4 K5 K6 Al KIA A2 A3 A4 Number K/A Topics Topics Imp. Q#

Ability Ability to to monitor monitor automatic automatic operation operation of of the the acac 062 AC 062 Electrical Distribution AC Electrical Distribution XX A3.04 A3.04 distribution distribution system, system, including: Operation of including: Operation of 2.7 2.7 20 20 inverter inverter (e.g.,

(e.g., precharging precharging synchronizing synchronizing light, light, static static transfer) transfer)

Emergency Emergency Procedures Procedures // Plan Plan Ability Ability to to recognize recognize DC Electrical 063 DC Electrical Distribution Distribution X abnormal abnormal indications indications for for system system operating operating 063 X 2.4.4 2.4.4 4.0 4.0 21 21 parameters parameters whichwhich are are entry-level entry-level conditions conditions for for emergency and and abnormal abnormal operating operating procedures.

procedures.

Ability toto predict predict and/or and/or monitor changes in monitor changes in Emergency Diesel 064 Emergency Diesel Generator Generator parameters parameters (to (to prevent prevent exceeding exceeding design design limits) limits) 064 X A1.05 Al .05 2.5 2.5 22 22 associated with operating the ED/G ED/G system system controls including: D/G room temperature temperature Knowledge of the physical connections connections and/or and/or 064 Emergency Emergency Diesel Diesel Generator Generator X cause-effect relationships between the the ED/G ED/G 064 X K1.01 Kl .01 4.1 4.1 23 23 system and the following systems: AC distribution distribution system 073 Process Process Radiation Radiation Monitoring Monitoring Ability to manually operate and/or monitor monitor in in the the 073 X< A4.01 3.9 3.9 24 24 control room Effluent release Knowledge of the physical connections and/or and/or 073 cause-effect relationships between the the PRM PRM 073 Process Process Radiation Radiation Monitoring Monitoring X X K1.01 1<1 .01 3.6 3.6 25 25 system and the following systems: Those Those systems systems served by PRMs Knowledge of of the effect that aa lossloss oror malfunction malfunction of the SWS of SWS will have have on on the following:

following: RHRRHR 076 Service 076 Service Water Water X K3.05 K3.05 3.0 3.0 26 26 components, controls, components, controls, sensors, sensors, indicators, indicators, and and alarms, including alarms, including radrad monitors monitors 078 Knowledge of Knowledge of bus bus power power supplies supplies to to the the following following 078 Instrument Instrument Air Air X K2.02 K2.02 3.3 3.3 27 27 Emergency air Emergency air compressor compressor Ability to Ability to (a)

(a) predict predict the the impacts impacts of of the the following following malfunctions or malfunctions or operations operations on on the the containment containment system-and (b) system-and (b) based based on on those those predictions, predictions, use use 103 103 Containment Containment XX A204 A2 04 procedures to procedures to correct, correct, control, control, or or mitigate mitigate the the 3.5 28 3.5 28 consequences consequence of those s of those malfunctions malfunctions or or operations operations Containment evacuation Containment evacuation (including (including recognition recognition of of the alarm) thealarm)

K/A KIA Category Category Point Point Totals:

Totals: 55 55 44 33 22 11 00 22 44 44 33 Group Point Group Point Total:

Total: I 33 33 NUREG-102 NUREG-1021 1 99

ES-401 ES-401 VC VC Summer Summer Form Form ES-401-2 ES-401-2 NRC Written NRC Written Examination Examination Outline Outline Plant Plant Systems Systems - Tier 2 Group Tier 2 Group 2 2

1. /Name System #/Name G KI K2 K3 System K4 K5 K6 j Al A2 A3 A4 Number KIA K/A Topics Topics Imp. Q#

Conduct Conduct of of Operations:

Operations: Ability Ability to to perform perform specific specific Control Rod 001 Control Drive Rod Drive XX 2.1.23 2.1.23 system system andand integrated integrated plantplant procedures procedures during 001 during allall 4.0 4.0 91 91 modes modes of of plant plant operation.

operation.

029 Containment Containment Purge Purge X Emergency Emergency Procedures Procedures // Plan Plan Ability Ability to to explain explain 029 X 2.1.32 2.1.32 3.8 3.8 92 92 and and apply apply allall system system limits limits and and precautions.

precautions.

Ability to Ability to (a)

(a) predict predict the the impacts impacts of of the the following following malfunctions malfunctions or or operations operations on on thethe Fire Fire Protection Protection System; System: and and (b)(b) based based on those predictions, predictions, use use 086 Fire 086 Fire Protection Protection X X A2.03 A2.03 procedures procedures to to correct, correct, control, control, or or mitigate mitigate the 2.9 93 the 2.9 93 consequences of those malfunctions or consequences or operations: Inadvertent actuation of of the the FPS FPS duedue to circuit failure or welding Knowledge of the effect that a a loss or or malfunction malfunction 002 Reactor 002 Reactor Coolant Coolant X K3.03 of the RCS will have on the following: 4.2 29 4.2 29 Containment Knowledge of the effect of a loss loss or or malfunction malfunction 011 Pressurizer Pressurizer Level Level Control Control X on the following will have on the the PZR LCS: LCS:

011 K6.01 2.8 2.8 30 30 Reasons for starting charging pump pump while while increasing letdown flow rate Ability to predict and/or monitor changes in in 017 parameters to prevent exceeding exceeding design design limits) limits) 017 In-core In-core Temperature Temperature Monitor Monitor X X A1.01 3.7 37 31 31 associated with operating the ITM ITM system system controls controls including: Core exit temperature Knowledge of Knowledge of the the operational operational implications implications of of the the 027 Containment 027 Iodine Removal Containment Iodine Removal X X K5.01 K5.01 concepts as following concepts as they applyapply to to the the CIRS:

CIRS: 3.1 3.1 32 32 Purpose of Purpose of charcoal charcoal filters filters Knowledge of Knowledge of the the effect effect of of aa loss loss or or malfunction malfunction 028 Hydrogen 028 Hydrogen Recombiner Recombiner andand XX K6.01 K6.01 on the on the following following will will have have on on thethe HRPS:

HRPS: Hydrogen Hydrogen 2.6 33 Purge Purge Control Control 2.6 33 recombiners recombiners Knowledge of Knowledge of design design feature(s) feature(s) and/orand/or 033 Spent 033 Spent Fuel Fuel Pool Pool Cooling Cooling XX K4.04 K4.04 interlock(s) which interlock(s) which provide provide for for the the following:

following: 2.7 2.7 34 34 Maintenance of Maintenance of spent spent fuelfuel pool pool radiation radiation Knowledge of Knowledge of operational operational implications implications of of the the 035 Steam 035 Steam Generator Generator XX K5.03 K5.03 following concepts following concepts as as thethe apply apply to to the the S/GS:

S/GS: 2.8 2.8 35 35 Shrink and Shrink and swell swell concept concept Ability to Ability to (a)

(a) predict predict thethe impacts impacts of of the the following following malfunctions or malfunctions or operations operations on on thethe SDS; SDS; and and (b)

(b) 041 041 Steam Steam Dump/Turbin DumplTurbine e Bypass Bypass based on based on those those predictions, predictions, use use procedures procedures toto Control xX A2.02 A2.02 3.6 3.6 36 36 Control correct, control, correct, control, or or mitigate mitigate the the consequence consequences s ofof those malfunctions those malfunctions or or operations:

operations: Steam Steam valve valve stuck open NUREG-1 NUREG-1021 021 10 10

ES-401 ES-401 VC Summer VC Summer Form Form ES-401-2 ES-4O1-2 NRC Written Examination Outline NRC Written Examination Outline Plant Systems Plant Systems - Tier Tier 22 Group Group 22 System #/Name System #/Name

[

G i K2 Ki K3 K4 K5 K6 Ai A2 A3 A3 A4 A4 Number Number KIA K/A Topics Topics

[ Imp.

imp Q Knowledge Knowledge of of ARM ARM system system design design feature(s) feature(s) 072 Area 072 Radiation Monitoring Area Radiation Monitoring XX K4.03 K4.03 and/or and/or interlock(s) interlock(s) which which provide provide for for the the following:

following: 3.2 37 3.2 37 Plant Plant ventilation ventilation systems systems Ability Ability to to (a)

(a) predict predict the the impacts impacts of of the the following following malfunctions malfunctions or or operations operations onon the the Fire Fire Protection Protection 086 Fire Protection Fire Protection System; System; and and (b)

(b) based based onon those those predictions, predictions, useuse 086 X A2.01 A2 2.9 2.9 38 38 procedures procedures to to correct, correct, control, control, or or mitigate mitigate the the consequences consequences of of those those malfunctions malfunctions or or operations:

operations: Manual shutdown of Manual shutdown of FPS FPS Category Point KIA Category Point Totals:

Totals: 22 00 00 11 22 22 22 KIA 11 33 00 00 Group Group Point Point Total:

Total: I 13 13 NUREG-102 NUREG-1021 1 11 11

ES-401 0=8-401 1- Generic Generic Knowledge Knowledge and and Abilities Abilities Outline Outline (Tier3)

(Tier3) 1Form ES-401-3 I Form E8-401-3 Facility:

Facility: I VC Summer VC Summer I Date of Date of Exam:

Exam:

I 6/4/2007 6/4/2007 RO RO SRO-Only SRO-Only Category Category K/A ##

KIA Topic Topic IR lR Q#

Q# IR IR Q#

Q#

Knowledge of Knowledge of less less than than one one hour hour technical technical 2.1.11 2.1.11 3.8 3.8 94 94 specification action specification action statements statements for systems.

systems.

Ability to supervise supervise andand assume assume aa 2.1.6 2.1.6 management role management role during plant plant transients 4.3 95 upset conditions.

and upset conditions.

Ability to evaluate plant performance and 2.1.7 make operational judgments based on

1. 3.7 66 operating characteristics, reactor behavior, Conduct of and instrument interpretation. ,

Operations Ability to make accurate, clear and concise 2.1.17 3.5 67 I verbal reports.

Knowledge of system purpose and or 2.1.27 2.8 68 function.

Subtotal 3 2 Knowledge of pre- and post-maintenance 2.2.21 3.5 96 operability requirements.

Knowledge of bases in technical 2.2.25 specifications for limiting conditions for 3.7 97

2. operations and safety limits.

Equipment Control Ability to analyze the affect of maintenance 2.2.24 2.6 69 activities on LCO status.

Knowledge of new and spent fuel 2.2.28 2.6 70 movement procedures.

Subtotal 2 2 2.3.2 Knowledge of facility ALARA program. 2.9 98 Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible 2.5 71 3.

levels in excess of those authorized.

I Radiation Control Knowledge of 10 10 CFR: 20 and related 2.3.1 2.3.1 2.6 72 facility radiation control requirements Subtotal 22 1 Knowledge of of the bases for prioritizing prioritizing 2.4.22 safety functions during during 4.0 99 abnormal/emergency abnormal/emergency operations.

Knowledge of of abnormal condition 2.4.11 2.4.11 3.6 3.6 100 100 procedures.

procedures.

Knowledge Knowledge of of low power /1shutdown low power shutdown 4.

4. 2.4.9 implications 2.4.9 implications inin accident accident (e.g.

(e.g. LOCA LOCA or or loss loss 3.3 3.3 73 73 Emergency Emergency of RHR) of RHR) mitigation mitigation strategies.

strategies.

Procedures!

Procedures 1 Plan Plan 2.4.29 2.4.29 Knowledge Knowledge of of the the emergency emergency plan.plan. 2.6 2.6 74 74 Knowledge Knowledge of of crew crew roles roles and and 2.4.13 2.4.13 3.3 3.3 75 75 responsibilities responsibilities during during EOP EOP flowchart use.use.

Subtotal Subtotal 33 22 Tier3PointTotal Tier 3 Point Total 10 10 77 NUREG-1021 NUREG-1021 12 12

I ES-401

[£8-401 Record of Record of Rejected Rejected KlAs K/As Ij Form ES-401-4 II Form ES-401-4 Tier 1I Tier Randomly Randomly Group Reason for Reason for Rejection Rejection Group Selected KIA Selected K/A 3/2 3/2 2.2.3 2.2.3 Not aa dual Not dual unit unit facility.

facility. Randomly Randomly selected selected 2.2.25 2.2.25 ROs do ROs do not not operate operate or or monitor monitor any any fuel handling handling equipment, not on task equipment, not task list.

list.

11/2 12 036AA1.04 036 AA1.04 Randomly selected 036 Randomly AA11.01 036 AA .01 There no immediate actions associated with operation of this system.

no immediate 2/1 2/1 G2.4.49 022 G2.4.49 Randomly selected 2.4.46 Randomly 2/1 2/1 103 A2.03 Direct overlap with simulator scenario. Randomly selected 103 A2.04 2/2 029 G2.4.6 System is not involved anywhere in EOPs. Randomly selected 029 G2.1.32 2/2 Purpose/function of system will not yield an SRO item related to 2/2 G2. 1.28 001 G2.1.28 IOCFR55.43(b). Randomly selected 001 G2.1.23 10CFR55.43(b). I 2/2 2/2 086 A2.03 Duplicate item with SRO exam. Randomly selected 086 A2.01 I

NUREG-1021 NUREG-1021 13 13