ML15127A413

Initial Exam 2014-301 Draft Administrative Documents

ML15127A413
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/08/2013
From:	Phillip Capehart Division of Reactor Safety II
To:	Duke Energy Carolinas
References
50-369/14-301, 50-370/14-301
Download: ML15127A413 (20)

Text

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: m ~ GulAe Date of Examination: Clu9itfbf ;20/4 v

Initials Item Task Description a

b*

c;#

1.

a. Verify that the outline{s) fit{s) the appropriate model, in accordance with ES-401.

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b. Assess whether the outline was systematically and randomly prepared in accordance with tl-2 'JA ~

I Section D.1 of ES-401 and whether all KIA categories are appropriately sampled.

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

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d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.

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2.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number IJ-1 of normal evolutions, instrument and component failures, technical specifications, N-1 J.J-f s

and major transients.

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b. Assess whether there are enough scenario sets (and spares) to test the projected number u

and mix of applicants in accordance with the expected crew composition and rotation schedule L

without compromising exam integrity, and ensure that each applicant can be tested using A

at least one new or significantly modified scenario, that no scenarios are duplicated T

from the applicants' audit test(s}. and that scenarios will not be repeated on subsequent days.

0

c.

To the extent possible, assess whether the outline{s) conform{s} with the qualitative R

and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3.

a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

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

distributed among the safety functions as specified on the form I

(2) task repetition from the last two NRC examinations is within the limits specified on the form T

(3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified

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(3) no more than one task is repeated from the last two NRC licensing examinations

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c.

Determine if there are enough different outlines to test the projected number and mix

/./-( /\\(I AH of applicants and ensure that no items are duplicated on subsequent days.

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered N-l 14 ~

in the appropriate exam sections.

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

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c. Ensure that KIA importance ratings {except for plant-specific priorities) are at least 2.5.

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d. Check for duplication and overlap among exam sections.

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e. Check the entire exam for balance of coverage.

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f.

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

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a. Author

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b. Facility Reviewer(*)

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c. NRC Chief Examiner {#)

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d. NRC Supervisor

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Note:

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

• Not applicable for NRC-prepared examination outlines

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

IV\\ §" Gui r-e--

Date of Exam:

flu-i:vuM 02-014-v RO KIA Catep orv Points SRO-Onlv Points Tier Group K

K K

K K

K A

A A

A G

A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

1.

1 3

z. 4 3 3 3

18 3

3 6

Emergency &

2 d-I ~

I Abnormal N/A N/A I

9

z,,

4 Plant Tier Totals 5 4 5 4-Evolutions 5

t 27

'5 5

10 1

}_ 3 J....

2 3 3 J_ 3 3 3 f}_

28 3

02..

5

2.

I I I J

I I I

(

I I

0 ro

~

I Plant 2

10 3

Systems TierTotals 3 4 3 3 4 4-3 4-4 4 J....

38 5'

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

~

2.

3 02..

I

2

2...

Note:

1.

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

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA 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 KIAs having an importance rating (IR} of 2.5 or higher shall be selected.

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

6.

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

7.*

The generic (G} KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

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 the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

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.

ES-401 2

Form ES-401-2 I ES-401 PWR Examination Outline iliROY~

Emeraencv and A

~1,.,1 t=volutions - Tier 1/Grouo 1 RO SRO\\

• Form ES-401-2

' E/APE #I Name I Safety Function I Kl K K A A

G KIA Topic(s)

IR 1

2 3

1 2

000007 (BW/E02&E10; CE/E02) Reactor Q<) EK.:2. 03 Trio - Stabilization - Recoverv I 1 000008 Pressurizer Vapor Space (Z

(F.) At.:::3. 03 Accident/ 3 000009 Small Break LOCA I 3 s

($) ~A.2.3+

000011 Larae Break LOCA / 3 s ~' c:~z.z.~

000015/17 RCP Malfunctions I 4 I<

CR) A1<"3.o1 000022 Loss of Rx Coolant Makeuo t 2

_!?-)

(J?. ),A t\\.;l. D I 000025 Loss of RHR Svstem I 4 R

{!<)AAl.09 000026 Loss of Component Cooling rz (It) A 1(3. 04-Water/ 8 000027 Pressurizer Pressure Control s <S) AGt Z.4. ~I Svstem Malfunction I 3 000029 A TWS I 1 fZ

(£.) £1(2,bb 000038 Steam Gen. Tube Ruoture / 3

{R) s (P..) f:-f>.,c;<.03

(!">) E~Z. l. ~o 000040 (BW/E05; CE/E05; W/E12)

~

([<) f\\A \\. 1)3 Steam Line Rupture - Excessive Heat Transfer t 4 000054 (CE/E06) Loss of Main R

Q?,) AKI. 01 Feedwater I 4 000055 Station Blackout I 6 R

LP..) (;..K3.0I 000056 Loss of Off-site Power I 6 s

CS) AA z.. '55 000057 Loss of Vital AC Inst. Bus I 6

~

CR) AAI. o I 000058 Loss of DC Power I 6

({<.)

IJ..) AAG2.. o l 000062 Loss of Nuclear Svc Water I 4

~) l{F.) AG.2.4.8 000065 Loss of Instrument Air I 8

'S I lg.) ~) AG;?..4-. II/ \\.SJ AAZ.oS W/E04 LOCA Outside Containment I 3 I W/E11 Loss of Emergency Coolant CE-) SKI. I Recirc. / 4 BW/E04~adequate Heat tf0 Cf) EG\\ 2.2.44-Transfer - Loss of Secondarv Heat Sink/ 4 000077 Generator Voltage and Electric I<

Cl<-) AKI. DJ,.

Grid Disturbances 16 KIA Cateaorv Totals:

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3 d_ 4 3 3 3 Grouo Point Total:

1 R/fi II 3 3

ES-401, REV 9

~

PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 D ~ D 0 D 0 0 0 D 0 0 11 008AK3.03 Pressurizer Vapor Space Accident/ 3 4.1 4.6 D O ~ O O D 0 0 O 0 015AK3.07 RCP Malfunctions 14 4.1 4.2 O 0 ~ 0 D 0 0 0 0 0 0 022AA2.01 Loss of Rx Coolant Makeup 12 3.2 3.8 O O O 0 0 O 0 ~ 0 0 025AA 1.09 Loss of RHR System 14 3.2 3.1 0 0 0 0 0 0 ~ 0 0 0 0 026AK3.04 Loss of Component Cooling Water 18 3.5 3.7 O O ~ O O O O O O 0 0 029EK2.06 ATWS 11 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 038EA2.03 Steam Gen. Tube Rupture/ 3 4.4 4.6 O O O 0 O O 0 ~ 0 0 0 040AA1.03 Steam Line Rupture - Excessive Heat Transfer 14 4.3 4.3 0 0 0 0 0 0 ~ 0 0 054AK1.01 Loss of Main Feedwater 14 4.1 4.3

~ 000000000 055EK3.01 Station Blackout I 6 2.7 3.4 0 0 ~ 0 0 0 0 0 0 0 0 Page 1of2 FORM ES-401 *2 TOPIC:

Reactor trip status panel Actions contained in EOP for PZR vapor space accidenU LOCA Ensuring that SIG levels are controlled properly for natural circulation enhancement Whether charging line leak exists LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators Effect on the CCW flow header of a loss of CCW Breakers, relays, and disconnects.

Which SIG is ruptured Isolation of one steam line from header MFW line break depressurizes the SIG (similar to a steam line break)

Length of lime for which battery capacity is designed 8/8/2013 10:41 AM

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

057AA1.01 058AA2..01 062AG2.4.8 065AG2.4.11 077AK1.02 Loss of Vital AC Inst. Bus f 6 Loss of DC Power f 6 Loss of Nuclear Svc Water I 4 Loss of Instrument Air f 8 Generator Voltage and Electric Grid Disturbances f 6 we05EG2.2.44 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4

~

PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G RO SRO 3.7. 3.7 0 0 0 0 0 0 ~ 0 0 0 0 3.7 4.1 0000000~000 3.8 4.5 0000000000~

4.0 4.2 nooooooooo~

3.3 3.4

~ 0 0 0 0 0 0 0 0 0 0 4.2 4.4 0 0 0 0 0 0 0 0 0 ~

FORM ES-401 *2 TOPIC:

Manual inverter swapping That a loss of de power has occurred; verification that substitute power sources have come on line Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

Knowledge of abnormal condition procedures.

Over-excitation Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions WE11EK1.1 Loss -of Emergency Coolant Recirc. / 4 3.7 0 0 0 0 0 0-0 D o-[j-components, capacity, and functionOfemergency-~--*

systems.

Page 2 of 2 81812013 10:41 AM

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

009EA2.34 Small Break LOCA I 3 011EG2.2.44 Large Break LOCAi 3 027 AG2.4.31 Pressurizer Pressure Control System Malfunction I 3 038EG2.1.30 Steam Gen. Tube Rupture/ 3 056AA2..55 Loss of Off-site Power/ 6 065AA2..05 Loss of Instrument Air I 8

~1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 3.6 4.2 D D D D D D D ~ D D D 4.2 4.4 D D D D D D D D D D ~

4.2 4.1 D D D D D D D D 0 D ~

4.4 4.o D D D D D D 0 D D D ~

3.a 3.9 D O D D D D 0 ~ 0 D D 3.4 4.1 D 0 D D D 0 0 ~ D 0 D Page 1 of 1 FORM ES-401-2 TOPIC:

Conditions for throttling or stopping HPI Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Knowledge of annunciators alarms, indications or response procedures Ability to locate and operate components, including local controls.

Subcooled margin monitora When to commence plant shutdown if instrument air pressure is decreasing 8/812013 10:44 AM

ES-401 3

Form ES-401-2 PWR Examination Outline

~KRd 1~

Emeroencv and Abnonnal Plant Evolutions - Tier 1/Grouo 2 R I RO)

APE# I Name I Safety Function K K K A A G

KIA Topic(s)

IR 1 2 3

1 2

000001 Continuous Rod Withdrawal I 1 000003 Droooed Control Rod / 1 000005 lnooerable/Stuck Control Rod / 1 000024 Emeraencv Boration / 1

/<.

(J() At!-2. o4 000028 Pressurizer Level Malfunction I 2

{<)

(15) AA2.ort 000032 Loss of Source Ranae NI I 7 000033 Loss of Intermediate Ranru:1 NI I 7 000036 {BW/A08) Fuel Handlina Accident I 8 000037 Steam Generator Tube Leak I 3 fl

~) AAl. 08 000051 loss of Condenser Vacuum 14 f?.

l(f?.)AA2.02 000059 Accidental liauid RadWaste Rel. I 9 R.

(R) AKI.DI 000060 Accidental Gaseous Radwaste Rel. I 9 P.

4?.),A K3. OOL 000061 ARM System Alarms 17 s KS) A<ii ~.1.1' 000067 Plant Fire On-site I 8 000068 (BW/A06} Control Room Evac. I 8 s C$) A" Z. t.31 000069 IW/E14) Loss ofCTMT lntearitv / 5 ft (B.} £1(:iL4 000074 IW/E06&E07} lnad. Core Coolina 14 000076 Hiah Reactor Coolant Activitv I 9 W/E01 & E02 Rediaanosis & SI Termination I 3 W/E13 Steam Generator Over-oressure / 4 (1... (!2.) E:G; '2. I. 25 W/E15 Containment Floodina / 5 W/E16 Hiah Containment Radiation/ 9 S'

~> EAZ.2.

BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNl-X/Y I 7 BW/A04 Turbine Trio I 4 BW/A05 Emeraencv Diesel Actuation I 6 BW/A07 Floodina I 8 BW/E03 lnadeauate Subcoolina Marain I 4 BWJEOa{wJE03'LocA Cooldown - Deoress. / 4

~

(ti.) E.Kl.3 BW/E09; CEIA13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11(WJEOSlRCS Overcoolina - PTS / 4 s

.:>) E.A2.2.

CEIA16 Excess RCS Leakaae 12 CEIE09 Functional Recoverv KIA Cateaorv Point Totals:

JZO J.. l ;( I :2 I Grouo Point Total:

=;=i

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS KG A1 A2 A3 A4 G RO SRO 024AK2.04 Emergency Boration / 1 2.6 2.5 0 li2l 0 0 0 0 0 0 0 0 0 028AA2.08 Pressurizer Level Malfunction I 2 3.1 3.5 0 0 0 0 0 0 0 li2l 0 0 0 037AA1.08 Steam Generator Tube Leak I 3 3.3 3.1 0 0 0 0 0 0 li2l 0 0 0 0 051AA2.02 Loss of Condenser Vacuum 14 3.9 4.1 0 0 0 0 li2l 0 0 0 059AK1.01 Accidental Liquid RadWaste Rel. / 9 2.7 3.1 li2l 0 0 0 0 0 0 0 0 0 060AK3.02 Accidental Gaseous Radwaste Rel. / 9 3.3 3.5 O O 1i2J 0 O 0 0 0 0 0 0 WE03EK1.3 LOCA Cooldown - Depress./ 4 3.5 3.8 li2l 0 0 0 0 0 0 0 0 0 0 we13EG2.1.25 Steam Generator Over-pressure 14 3.9 4.2 0 0 0 0 0 0 0 0 0 0 li2l WE14EK3.4 Loss of CTMT Integrity I 5 3.3 3.6 0 0 li2l 0 0 0 0 0 0 0 0 Page 1of1 FORM ES-401-2 TOPIC:

Pumps PZR level as a function of power level Charging flow indicator Conditions requiring reactor and/or turbine trip Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant Isolation of the auxiliary building ventilation Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Cooldown and Depressurization).

Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

08/07/2013 9:00 AM

ES-401, REV 9 1 G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G RO SRO 061AG2.1.19 ARM System Alarms /7 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~

068AG2.1.31 Control Room Evac. I 8 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~

WE08EA2..2 RCS Overcooling - PTS I 4 3.5 4.1 O 0 0 0 D 0 0 ~ 0 0

WE16EA2..2 High Containment Radiation/ 9 3.o 3.3 D O O 0 O 0 0 ~ 0 0 0 Page 1of1 FORM ES-401-2 TOPIC:

Ability to use plant computer to evaluate system or component status.

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

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

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

08/07/2013 8:30 AM

ES-401 4

Form ES-401-2 ES-401 PWR Examination Ou\\1~

1~

Plant S stems - Tier 2/Grouo 1 R I SRO Form ES-401-2 System # I Name K

K K K K K A A A

A G

KIA Topic(s}

IR 1

2 3

4 5

6 1

2 3

4 003 Reactor Coolant Pump R.

s

({<.) Kt. 04-

'5) A.2..0I 004 Chemical and Volume R

(<

~)A3.14-Control

(!Z) I( 5, 32 005 Residual Heat Removal R

ff.) ~(... 03 006 Emeraencv Core Coolina IZ.

CR) Al.Db 007 Pressurizer Relief/Quench R

<F.) Al.ol Tank 008 Component Coolina Water R

f.B.,)G,2.1.3!

010 Pressurizer Pressure Control R

<!<) A3.DI 012 Reactor Protection R

Q<.) AQi. o I 013 Engineered Safety Features p..

CR) Gi :z. 4. 4fo Actuation 022 Containment Cooling

{Z s (R.)

~oi.. 01 c:;s) ~ 2..(. 28 025 Ice Condenser R

IZ

{fl,) A3.D~; (R) l<.1.03 026 Containment Sorav P-s

~)Af.05 <S) GZ.*4.31 039 Main and Reheat Steam

~

(fl-) IG..5,05 059 Main Feedwater R

s

r.

(R) A4-. 121 <R) K4. 13,, C.S)AZ.'2.

061 Auxiliary/Emergency R

(11-) /(k,' DJ-Feedwater 062 AC Electrical Distribution R.

s

([!.) K.;t.,o 11 CS) A2..\\3 063 DC Electrical Distribution R

{f-) K4.ol 064 Ememencv Diesel Generator R

R

\\P.) Aoi., 131 'P-) 1q,, 07 073 Process Radiation

{<_

(I\\) K.5.0I Monitorina 076 Service Water R R.

LI'> /(~.og/ (12-) /1..3.o\\

078 Instrument Air ll

([{) K'~.OJ 103 Containment R.

R (p_) AQ.05 I Cf<..) A4-.04-KIA Cateaorv Point Totals: e.o J I :s J m 2.. '3 3 3 J._

Grouo Point Total:

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

IR K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G RO SRO 003K1.04 Reactor Coolant Pump 2.6 2.9 0 D D D D D D D D D D 004A3.14 Chemical and Vdume Control 3.4 3.1 D D D D D D D D 0 D D 004K5.32 Chemical and Vdurne Control 3.1 3.4 D D D D 0 D D D D D D 005K6.03 Residual Heat Removal 2.s 2.6 D D D D D 0 D D D D D 006A1.06 Emergency Core Cooling 3.6 3.9 D D D D D D ~ D D D D 007A1.01 Pressurizer Relief/Quench Tank 2.9 3.1 D D D D D D ~ D D D D 008G2.1.31 Component Cooling Water 4.6 4.3 D D D D D D D D D D 0 010A3.01 Pressurizer Pressure Control 3.o 3.2 D D D D D D D D 0 D D 012A2..01 Reactor Protection 3.1 3.6 D D D D D D D 0 D D D 013G2.4.46 Engineered Safety Features Actuation 4.2 4.2 D D D D D D D D D 0 ~

022K2.01 Containment Cooling 3.o 3.1 O ~ D D 0 D 0 0 D 0 D Page 1of3 FORM ES-401-2 TOPIC:

eves Letdown and charging flows Purpose and control of heat tracing (prevent crystallization)

RHR heat exchanger Subcooling margin Maintaining quench tank water level within limits Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

PRT temperature and pressure during PORV testing Faulty bis table operation Ability to verify that the alarms are consistent with the plant conditions.

Containment cooling fans 08/07/2013 8:30 AM

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

025A3.02 Ice Condenser 025K1.03 Ice Condenser 026M.05 Containment Spray 039K5.05 Main and Reheat Steam 059A4.12 Main Feedwater 059K4.13 Main Feedwater 061K6.02 Auxiliary/Emergency Feedwater 062K2.01 AC Electrical Distribution 063K4.01 DC Electrical Distribution 064A2..13 Emergency Diesel Generator 064K6.07 Emergency Diesel Generator T~

PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 3.4 3.4 D D D D D D D D ~ D D 3.2 3.o

~ D D D D D D D D D D 3.s 3.s D D D D D D D D D ~ D 2.1 3.1 D D D D ~ D D D D D D 3.4 3.s D D D D D D D D D ~ D 2.9 2.9 D D D ~ D D D D D D D 2.6 2.1 D D D D D ~ D D D D D 3.3 3.4 D ~ D D D D D D D D D 2.1 3.o D D D ~ D D D D D D D 2.6 2.8 D D D D D D D ~ D D D 2.1 2.9 D D D D D ~ D D D D D Page2 of 3 FORM ES-401-2 TOPIC:

Isolation valves Containment sump system Containment spray reset switches Bases for RCS cooklown limits Initiation of automatic feedwater isolation Feedwater fill for SIG upon loss of RCPs Pumps Major system loads ManuaVautomatic transfers of control Consequences of opening auxiliary feeder bus (ED/G sub supply)

Air receivers 08/07/2013 8:30 AM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G TOPIC:

RO SRO 073K5.01 Process Radiation Monitoring 2.s 3.o D D D D ~ D D D 0 D D Radiation theory, including sources. types, units and effects 0761<2.08 Service Water 3.1 3.3 D~DDDDODODD ESF-actuated MOVs 076K3.01 Service Water 3.4 3.6 DD~DDDODODD Closed cooling water 078K3.01 Instrument Air 3.1 3.4 D000DDODODO Containment air system 103A2..05 Containment 2.9 3.9 DDDDDDO~O D Emergency containment entry 103A4.04 Containment 3.5 3.5 DODODDODD~D Phase A and phase B resets Page3of3 08/07/2013 8:30 AM

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

003A2..01 Reactor Coolant Pump 022G2.1.28 Containment Cooling 026G2.4.31 Containment Spray 059A2..12 Main Feedwater 062A2..13 AC Electrical Distribution 2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G RO SRO 3.5 3.9 0 0 0 0 0 0 0 0 0 0 0 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~

4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

3.1 3.4 0 0 0 0 0 0 0 0 0 0 0 2.2 2.6 O O 0 O 0 D 0 0 0 0 0 Page 1 of 1 FORM ES-401-2 TOPIC:

Problems with RCP seals, especially rates of seal leak-off Knowledge of the purpose and function of major system components and controls.

Knowledge of annunciators alarms, indications or response procedures Failure of feedwater regulating valves Identification and ranking of the most probable cause of grounds, referring to electrical distribution diagrams 08/07/2013 8:30 AM

ES-401 5

Form ES-401-2 ES-401 PWR Examination Out!I~

Plant s~stems - Tier 2/Grouo 2 RO SRO}

Form ES-401-2 System #I Name K K K K K K A A A A G KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 001 Control Rod Drive R

lf<)A2.03 002 Reactor Coolant s

(S)A2..o+

011 Pressurizer Level Control

~

(f.J K4-.DI 014 Rod Position Indication 015 Nuclear Instrumentation F

~)Al.D']

016 Non-nuclear Instrumentation R

(/3.) Nr. ();J.._

017 In-core Temoerature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purae Control 029 Containment Purae 033 Soent Fuel Pool Coolini:i s '5) Gt..+. I\\

034 Fuel Handlina Eauioment

/(

fB) ~ (o, D;l..

035 Steam Generator

({

(f.) /<..3. Of 041 Steam Dump/Turbine Bvoass Control 045 Main Turbine Generator

~

{ft) J<S, 23 055 Condenser Air Removal R.

(f?.) AS,03 056 Condensate 068 Liauid Radwaste 071 Waste Gas Disoosal 072 Area Radiation Monitorini:i 075 Circulatina Water R

';!.>I<:;;,_. 03 079 Station Air s

~SJ A.2..o}

086 Fire Protection R.

'P..)t.;,o~

KIA Cateaorv Point Totals:

IZO I I ! *I I I \\ I I lO Groua Point Total:

10/3

ES-401, REV 9 T~

PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G TOPIC:

RO SRO 001A2..03 Control Rod Drive 3.s 4.2 O O O 0 0 D D ~ 0 0 D Effect of stuck rod or Misaligned rod 011K4.01 Pressurizer Level Control 3.3 3.7 ODD~ DD 0 0 0 0 D Operation of PZR heater cutout at low PZR level 015A1.07 Nuclear Instrumentation

=-----~-----**--

3.3 3.4 D D O D D D ~ 0 0 D 0 Changes in boron concentration 016A4.02 Non-nuclear Instrumentation 2.1 2.e O 0 O 0 DD 0 0 D ~ D Recorders 034K6.02 Fuel Handling Equipment 2.6 3.3 O O 0 D ~ O 0 0 D 0 Radiation monitoring systems..

035K3.01 Steam Generator 4.4 4.6 OD~DODOODOD RCS 045K5.23 Main Turbine Generator 2.7 2.8 DDDD~DODODD Relationship between rod control and RCS boron concentration during T/G load increases 055A3.03 Condenser Air Removal 2.5 2.7 ODODDODD~DD Automatic diversion of CARS exhaust 075K2.03 Circulating Water 2.6 2.7 O~DDDDOOOOD Emergency/essential SWS pumps 086K1.02 Fire Protection 2.7 3.2

~ODODDODDDD Raw service water Page 1 of 1 08/07/2013 10:14 AM

E~-401, REV 9

~T2G2 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 002A2.04 Reactor Coolant 4.3 4.6 D D D D D D D ~ D D D 033G2.4.11 Spent Fuel Pool Cooling 4.o 4.2 D D D D D D D D D D ~

079A2.01 Station Air 2.9 3.2 D D D D D D ~ D D D Page 1 of 1 FORM ES-401-2 TOPIC:

Loss of heat sinks Knowledge of abnormal condition procedures.

Cross-connection with IAS (MA*4hA hL- ~h

~ 41.ct

-h S(Lb (eu&_... -)

08/07/2013 8:30 AM

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

Form ES-401-3 Facilitv: VY\\ ~ &dre..-

Date of Exam:

~VJ.A ;LO 14 v

(Ro)

Category KJA#

Topic rsRO-Only)

IR IR 2.1. 7 C:.v~ pµ- ~l\\)M.l>>tce...*. rVL~ -,~h'"le...tf 4.4 2.1.1+

t

"" *.P..,o::e cl_ c.-v't+er~ c~fi6Yl.Sfll a1111tl'vlMle.

3.(

1.

Conduct 2.1. IZ.l UM1ti11 -}-v ve;v1k, ~

~vp~re._ :;,,S-of Operations

\\

I 2.1.

2.1. 3

~* - J.. -0.t.,J. sk~.\\-/s-W ~

re.A'4 prac.'kl!

3.<J 2.1.4-S"" u.l!J ih.1 +u '"*rpruf J..\\.<ce.. i~ldi~.. -.

4.3 Subtotal 1

'3 2-2.2.3~ Ct.A* AP XA~ {.r\\'.ut v1, ~Wl-tce. ~vb'vrh0.. -,

6,[

2.2.3& l~e..q~

1; Vitt :f.J\\MJ ; V\\. l1't~ 3,l v

2.

2.2.

Equipment 2.2.1..'S ff,.--.P~JAe.,/.T.S.J,~ In w~J s,~ l~~d 4.2 Control c

2.2.

2.2.

Subtotal "2.-

J 2.3. 4- (4£ Uf.P ~Si.tr C _li~r-ts - ~

/e *..::

• r* q. " ;_

3,;;L 2.3.5 Mnlt'-hi-t ftM....-1,. ),,,, /j I S;,

ft,() i -......... *- I. 'i l.!1-t~ ~.: ~

-o/a.11.

4.~

II I..)

c 3

~

Subtotal Tier 3 Point Total JD 10 1';)C.

7

~

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

G2.1.14 Conduct of operations G2.1.21 Conduct of operations G2.1.7 Conduct of operations G2.2.36 Equipment Control G2.2.38 Equipment Control G2.3.4 Radiation Control G2.3.5 Radiation Control G2.4.11 Emergency Procedures/Plans G2.4.25 Emergency Procedures/Plans G2.4.30 Emergency Procedures/Plans T3 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 3.1 3.1 D D D D D D D D D D ~

3.s 3.6 D D D D D D D D D ~

4.4 4.7 DD DD D 0 DD DD~

3.1 4.2 DD DD DD DD DD~

3.6 4.s D D D D D D D D D D ~

3.2 3.7 DD DD DD DD DD~

2.9 2.9 D O D D D D D D D ~

4.o 4.2 D 0 D D D D D D D D ~

3.3 3.7 D D D D 0 D D D D D ~

2.1 4.1 DD DD DD DD D 0 ~

Page 1 of 1 FORM ES-401-2 TOPIC:

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

Ability verify the controlled procedure copy.

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

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations Knowledge of conditions and limitations in the facility license.

Knowledge of radiation exposure limits under normal and emergency conditions Ability to use radiation monitoring systems Knowledge of abnormal condition procedures.

Knowledge of fire protection procedures.

Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

08/07/2013 8:30 AM

ES-401, REV 9

~3 PWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO G2.1.3 Conduct of operations 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~

G2.1.45 Conduct of operations 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~

G2.2.25 Equipment Control 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

G2.3.15 Radiation Control 2.9 3.1 0 0 0 0 0 0 0 0 0 0 ~

G2.3.6 Radiation Control 2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~

G2.4.21 Emergency Procedures/Plans 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

G2.4.40 Emergency Procedures/Plans 2.7 4.5 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-2 TOPIC:

Knowledge of shift or short term relief turnover practices.

Ability to identify and interpret diverse indications to validate the response of another indication Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Knowledge of radiation monitoring systems Ability to aprove release permits Knowledge of the parameters and logic used to assess the status of safety functions Knowledge of the SRO's responsibilities in emergency plan implementation.

08/07/2013 8:30 AM