ML15127A413

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Initial Exam 2014-301 Draft Administrative Documents
ML15127A413
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
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)
v • d • e


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.

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a. Verify that the outline{s) fit{s) the appropriate model, in accordance with ES-401. N-2 ~ 7jJ(_

R b. Assess whether the outline was systematically and randomly prepared in accordance with T

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

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T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. N-2 ~ 1!U-

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E N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. /\J-Z 1tf/A._

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

I M 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 To the extent possible, assess whether the outline{s) conform{s} with the qualitative c.

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 (3) no more than one task is repeated from the last two NRC licensing examinations ../ ' / ~1

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

/./-( /\(I AH

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered G

in the appropriate exam sections. N-l 14 ~

E b. Assess whether the 10 CFR 55.41 /43 and 55.45 sampling is appropriate. t.J-l Jf/}t a N

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c. Ensure that KIA importance ratings {except for plant-specific priorities) are at least 2.5. rJ-2 AJ)J Jlil__

R d. Check for duplication and overlap among exam sections. N-1. ~ t- 13i{

A L e. Check the entire exam for balance of coverage. tJ-2 ~i $K

f. Assess whether the exam fits the appropriate job level (RO or SRO). N-Z ~~ 1?J1<-

'i' _£>~edI/in~ame/Sig!l1,ure- -~t- .i)

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a. Author '1-flL C/<l>J=._"mt .I ~
b. Facility Reviewer(*) I Al/A _
c. NRC Chief Examiner {#) ~12..U.ND C...-~A Ll~ '1':k.;., _,/ ',,;(Inf'f.t?A.ll
d. NRC Supervisor , ~*~ .::~:~'-0 ..... *tl /, /J'- .:.

~ ~L.- ...~

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Note: # 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 &

Abnormal 2 d- I ~ N/A I  ;;:;_

N/A I 9  ;;_ ;z,, 4 Plant Evolutions Tier Totals 5 4 5 4- 5 t 27 '5 5 10 1  ;}_ 3 J.... :2 3 3 J_ 3 3 3 f}_ 28 3 02.. 5 2.

Plant 2 I I I J I I I ( I I 0 10 ro ~ I 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~ Form ES-401-2

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

' E/APE #I Name I Safety Function Emeraencv and A I Kl1 2K K A A G KIA Topic(s) IR 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

_!?-) (J?. ) ,A t\.;l . D I 000022 Loss of Rx Coolant Makeuo t 2 R {!<)AAl.09 000025 Loss of RHR Svstem I 4 (It) A 1(3 . 04-000026 Loss of Component Cooling Water/ 8 rz 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 R Q?,) AKI. 01 000054 (CE/E06) Loss of Main Feedwater I 4 R LP..) (;..K3.0I 000055 Station Blackout I 6 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

~) l{F.) AG.2.4.8 000062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8

'S Ilg.) ~) 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 "' tf0 Cf) EG\ 2.2.44-BW/E04~adequate Heat Transfer - Loss of Secondarv Heat Sink/ 4 000077 Generator Voltage and Electric I< Cl<-) AKI. DJ,.

Grid Disturbances 16 KIA Cateaorv Totals: fl.'() 3 d_ 43 3 3 Grouo Point Total: 1R/fi II 3 3

ES-401, REV 9 ~ 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 007EK2.03 Reactor Trip - Stabilization - Recovery 3.5 3.6 D ~ D 0 D 0 0 0 D 0 0 Reactor trip status panel 11 008AK3.03 Pressurizer Vapor Space Accident/ 3 4.1 4.6 D O ~ O O D 0 0 O 0 Actions contained in EOP for PZR vapor space accidenU LOCA 015AK3.07 RCP Malfunctions 14 4.1 4.2 O 0 ~ 0 D 0 0 0 0 0 0 Ensuring that SIG levels are controlled properly for natural circulation enhancement 022AA2.01 Loss of Rx Coolant Makeup 12 3.2 3.8 O O O 0 0 O 0 ~ 0 0 Whether charging line leak exists 025AA1.09 Loss of RHR System 14 3.2 3.1 0 0 0 0 0 0 ~ 0 0 0 0 LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators 026AK3.04 Loss of Component Cooling Water 18 3.5 3.7 O O ~ O O O O O O 0 0 Effect on the CCW flow header of a loss of CCW 029EK2.06 ATWS 11 2.9 3.1 0 ~ 0 0 0 0 0 0 0 0 0 Breakers, relays, and disconnects.

038EA2.03 Steam Gen. Tube Rupture/ 3 4.4 4.6 O O O 0 O O 0 ~ 0 0 0 Which SIG is ruptured 040AA1.03 Steam Line Rupture - Excessive Heat 4.3 4.3 0 0 0 0 0 0 ~ 0 0 Isolation of one steam line from header Transfer 14 054AK1 .01 Loss of Main Feedwater 14 4.1 4.3 ~

000000000 MFW line break depressurizes the SIG (similar to a steam line break) 055EK3.01 Station Blackout I 6 2.7 3.4 0 0 ~ 0 0 0 0 0 0 0 0 Length of lime for which battery capacity is designed Page 1of2 8/8/2013 10:41 AM

ES-401, REV 9 ~ 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 057AA1.01 Loss of Vital AC Inst. Bus f 6 3.7 . 3.7 0 0 0 0 0 0 ~ 0 0 0 0 Manual inverter swapping 058AA2..01 Loss of DC Power f 6 3.7 4.1 0000000~000 That a loss of de power has occurred; verification that substitute power sources have come on line 062AG2.4.8 Loss of Nuclear Svc Water I 4 3.8 4.5 0000000000~ Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

065AG2.4.11 Loss of Instrument Air f 8 4.0 4.2 nooooooooo~ Knowledge of abnormal condition procedures.

077AK1.02 Generator Voltage and Electric Grid 3.3 3.4 ~ 0 0 0 0 0 0 0 0 0 0 Over-excitation Disturbances f 6 we05EG2.2.44 Inadequate Heat Transfer - Loss of 4.2 4.4 0 0 0 0 0 0 0 0 0 ~ Ability to interpret control room indications to verify the Secondary Heat Sink I 4 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, systems.

capacity, and functionOfemergency-~--*

Page 2 of 2 81812013 10:41 AM

ES-401, REV 9 ~1G1 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 009EA2.34 Small Break LOCA I 3 3.6 4.2 D D D D D D D ~ D D D Conditions for throttling or stopping HPI 011EG2.2.44 Large Break LOCAi 3 4.2 4.4 D D D D D D D D D D ~ 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 027AG2.4.31 Pressurizer Pressure Control System 4.2 4.1 D D D D D D D D 0 D ~ Knowledge of annunciators alarms, indications or response Malfunction I 3 procedures 038EG2.1.30 Steam Gen. Tube Rupture/ 3 4.4 4.o D D D D D D 0 D D D ~ Ability to locate and operate components, including local controls.

056AA2. .55 Loss of Off-site Power/ 6 3.a 3.9 D O D D D D 0 ~ 0 D D Subcooled margin monitora 065AA2..05 Loss of Instrument Air I 8 3.4 4.1 D 0 D D D 0 0 ~ D 0 D When to commence plant shutdown if instrument air pressure is decreasing Page 1 of 1 8/812013 10:44 AM

ES-401 3 Form ES-401-2 PWR Examination Outline Emeroencv and Abnonnal Plant Evolutions - Tier 1/Grouo 2 R I RO) 1

~KRd ~

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

{<) (15) AA2.ort 000028 Pressurizer Level Malfunction I 2 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 f?. l(f?.)AA2 .02 000051 loss of Condenser Vacuum 14 000059 Accidental liauid RadWaste Rel. I 9 R. (R) AKI.DI P. 4?.) ,A K3. OOL 000060 Accidental Gaseous Radwaste Rel. I 9 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 (1... (!2.) E:G; '2. I. 25 W/E13 Steam Generator Over-oressure / 4 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

~ (ti.) E.Kl.3 BWJEOa{wJE03'LocA Cooldown - Deoress. / 4 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 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 KS KG A1 A2 A3 A4 G TOPIC:

RO SRO 024AK2.04 Emergency Boration / 1 2.6 2.5 0 li2l 0 0 0 0 0 0 0 0 0 Pumps 028AA2.08 Pressurizer Level Malfunction I 2 3.1 3.5 0 0 0 0 0 0 0 li2l 0 0 0 PZR level as a function of power level 037AA1.08 Steam Generator Tube Leak I 3 3.3 3.1 0 0 0 0 0 0 li2l 0 0 0 0 Charging flow indicator 051AA2.02 Loss of Condenser Vacuum 14 3.9 4.1 0 0 0 0 li2l 0 0 0 Conditions requiring reactor and/or turbine trip 059AK1 .01 Accidental Liquid RadWaste Rel. / 9 2.7 3.1 li2l 0 0 0 0 0 0 0 0 0 Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 060AK3.02 Accidental Gaseous Radwaste Rel. / 9 3.3 3.5 O O 1i2J 0 O 0 0 0 0 0 0 Isolation of the auxiliary building ventilation WE03EK1 .3 LOCA Cooldown - Depress./ 4 3.5 3.8 li2l 0 0 0 0 0 0 0 0 0 0 Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Cooldown and Depressurization).

we13EG2.1.25 Steam Generator Over-pressure 14 3.9 4.2 0 0 0 0 0 0 0 0 0 0 li2l Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

WE14EK3.4 Loss of CTMT Integrity I 5 3.3 3.6 0 0 li2l 0 0 0 0 0 0 0 0 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.

Page 1of1 08/07/2013 9:00 AM

ES-401, REV 9 1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G TOPIC:

RO SRO 061AG2.1.19 ARM System Alarms /7 3.9 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ability to use plant computer to evaluate system or component status.

068AG2.1.31 Control Room Evac. I 8 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

WE08EA2..2 RCS Overcooling - PTS I 4 3.5 4.1 O 0 0 0 D 0 0 ~ 0 0 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

WE16EA2..2 High Containment Radiation/ 9 3.o 3.3 D O O 0 O 0 0 ~ 0 0 0 Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Page 1of1 08/07/2013 8:30 AM

ES-401 4 Form ES-401-2 PWR Examination Ou\1~ ~

1 ES-401 Form ES-401-2 Plant S stems - Tier 2/Grouo 1 R I SRO 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 R (< ~)A3.14-004 Chemical and Volume Control (!Z) I( 5, 32 R ff.) ~(... 03 005 Residual Heat Removal IZ. CR) Al.Db 006 Emeraencv Core Coolina R <F.) Al .ol 007 Pressurizer Relief/Quench Tank R f.B.,)G,2.1.3!

008 Component Coolina Water R <!<) A3.DI 010 Pressurizer Pressure Control R Q<.) AQi. o I 012 Reactor Protection 013 Engineered Safety Features p.. CR) Gi :z. 4. 4fo Actuation

{Z s (R.) ~oi.. 01 c:;s) ~ 2..(. 28 022 Containment Cooling R IZ {fl,) A3.D~; (R) l<.1.03 025 Ice Condenser 026 Containment Sorav P- s ~)Af.05 <S) GZ.*4.31

~ (fl-) IG..5,05 039 Main and Reheat Steam 059 Main Feedwater R s r. (R) A4-. 121 <R) K4. 13,, C.S)AZ.'2.

(11-) /(k,' DJ-061 Auxiliary/Emergency R Feedwater 062 AC Electrical Distribution R. s ([!.) K.;t.,o 11 CS) A2..\3 063 DC Electrical Distribution R {f-) K4.ol R R \P.) Aoi., 13 1 'P-) 1q,, 07 064 Ememencv Diesel Generator

{<_ (I\) K.5.0I 073 Process Radiation Monitorina R R. LI'> /(~.og/ (12-) /1..3.o\

076 Service Water 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 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2. A3 A4 G TOPIC:

RO SRO 003K1.04 Reactor Coolant Pump 2.6 2.9 0 D D D D D D D D D D eves 004A3.14 Chemical and Vdume Control 3.4 3.1 D D D D D D D D 0 D D Letdown and charging flows 004K5.32 Chemical and Vdurne Control 3.1 3.4 D D D D 0 D D D D D D Purpose and control of heat tracing (prevent crystallization) 005K6.03 Residual Heat Removal 2.s 2.6 D D D D D 0 D D D D D RHR heat exchanger 006A1.06 Emergency Core Cooling 3.6 3.9 D D D D D D ~ D D D D Subcooling margin 007A1.01 Pressurizer Relief/Quench Tank 2.9 3.1 D D D D D D ~ D D D D Maintaining quench tank water level within limits 008G2.1.31 Component Cooling Water 4.6 4.3 D D D D D D D D D D 0 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

010A3.01 Pressurizer Pressure Control 3.o 3.2 D D D D D D D D 0 D D PRT temperature and pressure during PORV testing 012A2..01 Reactor Protection 3.1 3.6 D D D D D D D 0 D D D Faulty bis table operation 013G2.4.46 Engineered Safety Features Actuation 4.2 4.2 D D D D D D D D D 0 ~ Ability to verify that the alarms are consistent with the plant conditions.

022K2.01 Containment Cooling 3.o 3.1 O ~ D D 0 D 0 0 D 0 D Containment cooling fans Page 1of3 08/07/2013 8:30 AM

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 025A3.02 Ice Condenser 3.4 3.4 DD DD DDD D ~ DD Isolation valves 025K1.03 Ice Condenser 3.2 3.o ~ D DDDDD DD DD Containment sump system 026M.05 Containment Spray 3.s 3.s DD DDDDD DD ~ D Containment spray reset switches 039K5.05 Main and Reheat Steam 2.1 3.1 DDDD ~ DD DD DD Bases for RCS cooklown limits 059A4.12 Main Feedwater 3.4 3.s DD DD DDD DD ~ D Initiation of automatic feedwater isolation 059K4.13 Main Feedwater 2.9 2.9 DD D ~ DDD DDDD Feedwater fill for SIG upon loss of RCPs 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.1 DD DD D ~ D DDDD Pumps 062K2.01 AC Electrical Distribution 3.3 3.4 D ~ DD DDD DDD D Major system loads 063K4.01 DC Electrical Distribution 2.1 3.o DD D ~ DDDDD DD ManuaVautomatic transfers of control 064A2..13 Emergency Diesel Generator 2.6 2.8 DD DD DDD ~ DD D Consequences of opening auxiliary feeder bus (ED/G sub supply) 064K6.07 Emergency Diesel Generator 2.1 2.9 DDDD D ~ D DDDD Air receivers Page2 of 3 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 DDDD~ DDD0 DD 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 2G1 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 003A2..01 Reactor Coolant Pump 3.5 3.9 0 0 0 0 0 0 0 0 0 0 0 Problems with RCP seals, especially rates of seal leak-off 022G2.1.28 Containment Cooling 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the purpose and function of major system components and controls.

026G2.4.31 Containment Spray 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of annunciators alarms, indications or response procedures 059A2..12 Main Feedwater 3.1 3.4 0 0 0 0 0 0 0 0 0 0 0 Failure of feedwater regulating valves 062A2..13 AC Electrical Distribution 2.2 2.6 O O 0 O 0 D 0 0 0 0 0 Identification and ranking of the most probable cause of grounds, referring to electrical distribution diagrams Page 1 of 1 08/07/2013 8:30 AM

ES-401 5 Form ES-401-2 ES-401 PWR Examination Out!I~ Form ES-401-2 Plant s~stems - Tier 2/Grouo 2 RO SRO}

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 R lf<)A2.03 001 Control Rod Drive 002 Reactor Coolant s (S)A2..o+

~ (f.J K4-.DI 011 Pressurizer Level Control 014 Rod Position Indication

~)Al .D']

015 Nuclear Instrumentation F R (/3.) Nr. ();J.._

016 Non-nuclear Instrumentation 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\

/( fB) ~ (o, D;l..

034 Fuel Handlina Eauioment 035 Steam Generator

({ (f.) /<..3. Of .

041 Steam Dump/Turbine Bvoass Control

~ {ft) J<S, 23 045 Main Turbine Generator R. (f?.) AS,03 055 Condenser Air Removal 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 OOO0 0 DD~ 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 DDODDD~ 0 0 D0 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 OO0 D~ O0 0 D0 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 FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 002A2.04 Reactor Coolant 4.3 4.6 D D D D D D D ~ D D D Loss of heat sinks 033G2.4.11 Spent Fuel Pool Cooling 4.o 4.2 D D D D D D D D D D ~ Knowledge of abnormal condition procedures.

079A2.01 Station Air 2.9 3.2 D D D D D D ~ D D D Cross-connection with IAS (MA* hA hL- ~h ~ 41.ct 4

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

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facilitv: VY\ ~ &dre..- Date of Exam: ~VJ.A  ;LO 14 v

Category KJA# Topic (Ro) 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 1

Subtotal '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 2.2.

  • c -

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 ,. ) ,,,, S;,ft,() i - .........' *- I. 'i l.!1-t~ ~.: ~-o/a.11. 4.~

I 2.4 . /j II I..) c Subtotal 3 ~

Tier 3 Point Total JD 10 1';)C. 7

~

ES-401, REV 9 T3 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 G2.1.14 Conduct of operations 3.1 3.1 D D D D D D D D D D ~ Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1.21 Conduct of operations 3.s 3.6 D D D D D D D D D ~ Ability verify the controlled procedure copy.

G2.1.7 Conduct of operations 4.4 4.7 DD DD D 0 DD DD~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.36 Equipment Control 3.1 4.2 DD DD DD DD DD~ Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations G2.2.38 Equipment Control 3.6 4.s D D D D D D D D D D ~ Knowledge of conditions and limitations in the facility license.

G2.3.4 Radiation Control 3.2 3.7 DD DD DD DD DD~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.5 Radiation Control 2.9 2.9 D O D D D D D D D ~ Ability to use radiation monitoring systems G2.4.11 Emergency Procedures/Plans 4.o 4.2 D 0 D D D D D D D D ~ Knowledge of abnormal condition procedures.

G2.4.25 Emergency Procedures/Plans 3.3 3.7 D D D D 0 D D D D D ~ Knowledge of fire protection procedures.

G2.4.30 Emergency Procedures/Plans 2.1 4.1 DD DD DD DD D 0 ~ Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

Page 1 of 1 08/07/2013 8:30 AM

ES-401, REV 9 ~3 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 G2.1.3 Conduct of operations 3.7 3.9 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of shift or short term relief turnover practices.

G2.1.45 Conduct of operations 4.3 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to identify and interpret diverse indications to validate the response of another indication G2.2.25 Equipment Control 3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.3.15 Radiation Control 2.9 3.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation monitoring systems G2.3.6 Radiation Control 2.0 3.8 0 0 0 0 0 0 0 0 0 0 ~ Ability to aprove release permits G2.4.21 Emergency Procedures/Plans 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the parameters and logic used to assess the status of safety functions G2.4.40 Emergency Procedures/Plans 2.7 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the SRO's responsibilities in emergency plan implementation.

Page 1 of 1 08/07/2013 8:30 AM

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