ML093340468

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Draft - Outlines (Folder 2)
ML093340468
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 08/14/2009
From:
NextEra Energy Seabrook
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML092330362 List:
References
50-443/09-302, ES-401, ES-401-2, TAC U01798 50-443/09-302
Download: ML093340468 (29)
v • d • e


Text

ES-401 PWR Examination Outline Form ES-401-2 II Date of Exam: 10/1/9 RO KIA CateQory Points SRO-Only 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 2 3 4 3 3 18 6 Emergency &

Abnormal 2 I I I NiA 3 2 NiA I 9 4 Plant Evolutions Tier Totals 4 3 4 7 5 4 27 10 1 3 3 5 4 I 2 2 2 I 5 2.

Plant Systems 2 2 I 0 3 I 0 I 1 1 0 0 10 I 3 tEtE Tier Totals 5 4 5 7 2 2 3 3 2 2 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 7 Categories 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline. the "Tier Totals' in each KJA 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 KJA 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 KJAs 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 KJA categories.

7.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs.

B. On the following pages. enter the KJA 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 KJA catalog. and enter the KJA numbers. descriptions. IRs.

and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Emergenc and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

FormES~

FormES~

E/APE # I Name I Safety Function K K K A G KIA Topic(s) IR #

1 2 3 1 2 I, 000007 (BW/E02&E10; CElE02) Reactor X ...........**** EK1 Knowledge of the operational implications of 3.7 I Trip - Stabilization - Recovery 11 the following concepts as they apply to the reactor

.' trip:

EK1.06 Relationship of emergency feedwater flow

~, . /iL.

"ii to S/G and decay heat removal following reactor trip.

", ,....' (CFR 41.8/41.10/45.3)

..~.

~

000008 Pressurizer Vapor Space Accident I 3 ..,

000009 Small Break LOCA I 3 X EK1 Knowledge of the following concepts as they 3.5 1 I>I> apply to the small break LOCA:

EK1.02 Use of steam tables (CFR 41.8/41.10/45.3)

",'z;,'"" Ie",

IC" 000011 Large Break LOCA I 3 X EK3 Knowledge of the reasons for the following 4.4 1 responses as they apply to the Large Break LOCA

        • f
          • l';
          • l'i EK3.12 Actions contained in E OP for emergency LOCA (large break)

(CFR 41.5/41.10/45.6/45.13) 000015/17 RCP Malfunctions 14 *** AA2 Ability to determine and interpret the following 3.0 1 as they apply to the Reactor Coolant Malfunctions:

.. I:l!>lim; . AA2.01 Cause of RCP failure (CFR 43.5/45.13) 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4

  • i.:

000026 Loss of Component Cooling Water 18

............ X

" .. ' r,X li 2.4.6 Knowledge of EOP mitigation strategies. 3.7 1 I

I (CFR 41.10/43.5/45.13)

(CFR41.10/43.5/45.13) 000027 Pressurizer Pressure Control X AK2 Knowledge of the interrelationships beween the 2.6 1 System Malfunction I 3 I;"

I * . "1 Pressurizer Pressure Control Malfunctions and the h'~i****

h*~i* following:

AK2.03 Controllers and positioners

.* il!

  • .*l  !.;l,)'

(CFR 41.7/45.7) 000029 ATWS 11 X '> I****. .** EA1 EA 1 Ability to operate and monitor the following as 4.2 1

        • F they apply to ATWS:

EA1.14 EA1.14 Driving of control rods into the core (CFR 41.7/45.5/45.6) 000038 Steam Gen. Tube Rupture I 3 2.2.25 Knowledge of the bases in Technical 3.2 1 SpeCifications for limiting conditions for operation

i' and safety limits.

c' {CFR 41.5/41.7/43.2}

ES-401 PWR Examination Outline Form Fo ES-401-2 Eme",eo" aod A t i l l " ' E""'"'o",

E/APE # I Name 1 Safety Function K K G KIA KJA Topic(s) IR #

1 2 000040 (BWIE05; (BWIE05: CE1E05; W/E12) X AA1 AA1 Ability to operate andlor monitor the following 3.4 1 Steam Line Rupture - Excessive Heat ........ as they apply to the Steam Line Rupture:

Transfer 14 AA1.09 AA1.09 Setpoints of main steam safety and PORV's.

CFR 41.7/45.5/45.6 (CFR 2.4.21 Knowledge of the parameters and logic used 000054 (CE/E06) Loss of Main x to assess the status of safety functions, such as 4.0 1 Feedwater 14 reactivity control, core cooling and heat removal, integrity, containment reactor coolant system integrity.

. control, etc conditions, radioactivity release control. etc..

CFR 41.7/43.5/45.12)

(CFR 41.7/43.5/45.12 I *. **************

000055 Station Blackout I/ 6 000056 Loss of Off-site Power I/ 6 X

.. hi 10~,

AK3 Knowledge of the reasons for the following responses as they apply to the Loss of Offsite 4.4 1 Power:

I>'r,: AK3.02 Actions contained in the EOP for loss of offsite power

....* ****** CFR 41.5/41.10/45.6/45.1~

(CFR 41.5/41.10/45.6/45.13 CCi 000057 Loss of Vital AC Inst. Bus I/ 6 X Fe AA2 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument 3.2 1

. I ".

Bus:

AA2.06 AC instrument bus alarms for the inverter and alternate power source

.:.' CFR 43.5/45.13)

(CFR 43.5/45.13 000058 Loss of DC Power I 6 x AK1 Knowledge of the operational implications of 2.8 1

.:~~

I:*:***** the following concepts as they apply to Loss of DC Power:

AK1.01 Battery charger equipment and

".' *i' instrumentation

'. CFR 41.8/41.10/45.3)

(CFR 41.8/41.10/45.3 000062 Loss of Nuclear Svc Water I 4 X AK3 Knowledge of the reasons for the following 4.0 1 responses as they apply to the Loss of Nuclear fz'ipi~ ':. . . .* Service Water:

Service Water:

1';£;';' AK3.03 Guidance actions contained in EOP for loss

(CFR 41.4/41.8/45.7 000065 Loss of Instrument Air 18

/8 Xi' ~ AA1 Ability 'to AA1 Ablilly 0 operate and/or monitor ope,," aod/..- the follo.;09 mooi,..- lhe as they apply to the Loss of Instrument Air:

following 3.3 1

'if as they apply to the Loss of Instrument Air:

I)', AA1.05 RPS 1:';2)\ CFR 41.7/45.5/45.6)

(CFR 41.7/45.5/45.6

r;:; PWR Examination Outline Emercencv and Abnormal Plant Evolutions - Tier 1/GrouD 1 (RO I SRO)

Form ES-401-2 I E/APE # I Name I Safety Function K K K AA G KiA Topic(s) IR #

1 2 3 1 2 W/E04 LOCA Outside Containment 13 X EK2 Knowledge of the interrelations between the 3.5 1 I . LOCA Outside Containment and the following:

. ........... EK2.1 Components and functions of control and safety systems, including instrumentation, signals, I .....* interlocks, failure modes, and automatic and manual j ******

features

.~? (CFR41.7/45.7)

W/E11 Loss of Emergency Coolant I*ii* **.<'

.<' . EA 1 Ability to operate and/or monitor the following 3.5 1 X .'

Recirc./4 I> as they apply to the Loss of Emergency Coolant Recirculation II' b,.;

EA 1.2 Operating behavior characteristics of the i', facility if fli.d (CFR 41.7/45.5/45.6)

I. .......

BW1E04; WlE05 Inadequate Heat EA2 Ability to determine and interpret the following 3.4 1 Transfer - Loss of Secondary Heat Sink 14 ~; as they apply to the Loss of Secondary Heat Sink 0 EA2.1 Facility conditions and the selection of

'; appropriate procedures during abnormal and

,~ emergency operations Ii; *'.;,i ? b (CFR 43.5/45.13)

~

000077 Generator Voltage and Electric Grid Disturbances I 6 T.

W 4 3 3 Group PointT PointTotal:

otal:

ES-401 3 Form ES-401-2 ES*401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

I'~"

E/APE # I Name I Safety Function K K K A G KJA Topic(s) IR #

1 2 3 I  :':, "

000001 Continuous Rod Withdrawal 11 000003 Dropped Control Rod I 1 x AA1 AA 1 Ability to operate and/or monitor the 3.6 1 follo'Ning as they apply to the Dropped 1"+;' Control Rod I);;;i !l;;'i AA AA1.02 1.02 Controls and components necessary to recover rod (CFR 41.7/45.5/45.6) 000005 Inoperable/Stuck Control Rod 11 li 2;; I:

000024 Emergency Boration 11 I .::'

I 000028 Pressurizer Level Malfunction I 2 x r

..... AK1 Knowtedge of the operational 2.8 implications of the follo'Ning concepts as they apply to Pressurizer Level Control I""'" Malfunctions AK1.01 PZR reference leg abnormalities 1*;;;,;';;*; ,i,.,:,. (CFR 41.8141.10/45.3) 000032 Loss of Source Range Nil 7 I:::

I" t's.

000033 Loss of Intermediate RanQe Nil 7 x

f.~;:~!~* I::"

000036 (BW/A08) Fuel Handling Accident I 8 AK2 Knowtedge of the interrelationships 3.4 1 between Fuel Handling Accidents and I"', the follo'Ning:

1 h:'

1 i; AK2.02 Radiation monitoring equipment

" '"t" (portable and installed)

(CFR 41.7/45.7) 000037 Steam Generator Tube Leak I 3 x AA1 AA 1 Ability to operate andlor monitor the 3.4 1 follo'Ning as they apply to the StE~am I'***"

I' ***"

Generator Tube Leak:

AA1.11 AA 1.11 PZR level indication i (CFR 41.7/45.5/45.6)

Izi \i~(i I**.*..**.*..

000051 Loss of Condenser Vacuum 14 x AK3 Knowtedge of the reasons for the 2.8 1 follo'Ning responses as they apply to the Loss of Condenser Vacuum:

  • .r ,

AK3.01 Loss of steam dump capability upon loss of condenser vacuum

.; (CFR 41.5/41.10/45.6/45.13) 9 Accidental Liquid RadWaste ReI. 19 000060 Accidental Gaseous Radwaste ReI. 1199 000061 ARM System Alarms 17 000067 Plant Fire On-site 1 8 AA2 Ability to determine and interpret the 3.3 1 follo'Ning as they apply to the Plant Fire on site:

AA2.06 Need for pressurizing control It room (recirculation mode)

(CFR 43.5/45.13) 000068 (BW/A06) Control Room Evac. I 8

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO 1 SRO)

E/APE # 1 Name 1 Safety Function K K K A A G KJA Topic(s) IR #

1 2 3 1 2 000069 (W/E14) Loss of CTMT Integrity 1 5 000074 (W/E06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity 1 9 W/E01 & E02 Rediagnosis & SI Termination 1 3 W/E13 Steam Generator Over-pressure 1 4 W/E15 Containment Flooding 1 5 x EA2 Ability to determine and interpret the 2.7 1 following as they apply to the Containment Flooding:

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency conditions (CFR 43.5/45.13)

W/E16 High Containment Radiation 1 9 x EA 1 Ability to operate and/or monitor the 3.1 1 following as they apply to the High Containment Radiation:

EA1.1 EA 1.1 Components and functions of control and safety systems including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BW/A01 Plant Runback 1 1 BW/A02&A03 Loss of NNI-X/Y 1 7 BW/A04 Turbine Trip 1 4 BW/A05 Emergency Diesel Actuation 1 6 BW/A07 Flooding 1 8 BW/E03 Inadequate Subcooling Margin 14 BW/E08; W/E03 LOCA Cooldown - Depress. 14 BW/E09; CE/A13; W/E09&E10 Natural Circ. 1 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS 1 4 x 2.4.18 Knowledge for the specific bases 3.3 1 I"  ;' for EOP's (CFR 41.10/43.1/45.13)

CE/A16 Excess RCS Leakage 1 2 CE/E09 Functional Recovery /

KJA Category Point Totals: 1 1 1 3 2 1 Group Point Total: 914

ES-401 4 Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 21Group 1 (RO 1 SRO) i:,:i 003 Reactor Coolant Pump K

1 K

2 x

KJ]K 3 5 K

6 A

1 A

2 A

3 A

4 KJA Topic(s)

K2 Knowledge of bus power supplies to IR 3.1 ljl 1

the following:

K2.01 RCPs (CFR 41.7) 004 Chemical and Volume x 'r' K6 Knowledge of the effect of a loss or 2.7 2 Control , <

malfunction on the following CVCS components:

.~." K6.07 Heat exchangers and condensers (CFR 41.7/45.7) 3.9 2.1.23 Ability to perform specific system and integrated plant procedures

        • during all modes of operation (CFR 41.10/43.5/45.2/45.6) f\ ' "',

I~

005 Residual Heat Removal l .... K4 Knowledge of RHRS design feature 2.9 2 (s) andlor interlock (s) which provide the following:

.. K4.03 RHR heat exchanger bypass flow control I;' I (CFR 41.7) 3.8

~r 2.1.32 Ability to explain and apply system limits and precautions (CFR 41.10143.2145.12) 006 Emergency Core Cooling  :"c," x A4 Ability to manually operate andlor 4.2 1

'" monitor from the control room A4.11 Over pressure protection system.

007 Pressurizer Relief/Quench x ", K3 Knowledge of the effect that a loss 3.3 1 Tank or malfunction of the PRTS will have on the following:

K3.01 Containment I~ .... (CFR 41.7/45.6)

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21Group 1 (RO 1 SRO)

System # 1 Name K KKK K K KllL 1 2 3 4 5 A 'A A

1 2 A

A A 3 4 .....~

~I~ *...

KJA Topic(s) IR #

I****'f**~

008 Component Cooling Water x I K1 Knowledge of the physical i;- c I**.****.***.**. 3.3 2 connections and/or cause-effect relationships between the CCWS and the following systems:

i:;

b..

K1.02 Loads cooled by CCWS

\:. (CFR 41.2 to 41.9/45.7 to 45.9) kk' I"

I~~,r,i:.;

3.3 A2 Ability to predict and/or monitor

-1B .<1" I

1;01

';(.'

changes in parameters (to prevent exceeding design limits) associated with operating

°P9 the including:

CCWS controls the CCWS 00",,,,1, f

A2.01 Loss of CCW pump 010 Pressurizer Pressure Control x . K4 Knowledge of PZR PCS design 3.8 1 features andlor interlocks which provide

," for the following:

f* ';>.L i:

Ii I"~';' ~,;,

K4.03 Over pressure control ii';; . (CFR 41.7)

I.'.'

012 Reactor Protection x l:;~

~. ,

K6 Knowledge of the effect of loss or malfunction that the following will have 3.3 2 on the RPS:

K6.10 Permissive circuits IjjH j ..*.

(CFR 41.7/45.7)

I~/

I i~:! il

.' A2 Ability to (a) predict the impacts of 3.6 the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of control.

those malfunctions or operations:

r~!

K~!

A2.02 Loss of instrument power (CFR 41.5/43.5/45.3/45.5) 013 Engineered Safety Features ......

x M Ability to manually operate andlor 4.5 1 Actuation monitor in the control room:

M.Oi M.01 ESFAS -initiation equipment

,~  :',.

which fails to actuate

',/ (CFR 41.7/45.5 to 45.8) 022 Containment Cooling x K2 Knowledge of power supplies for the 3.0 1 fE¥~

.E¥~ following:

i"('

  • "(,

K2.0i K2.01 Containment COOling fans (CFR 41.7/45.6)

JJ .:,

I;S-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier~O 2fGroup 1 (RO / SRO)

System # / Name K I

K 2

K K K 3

3 4 K K 4 5 K K 5 6 K AAA 6 1 A

1 2 f  ; 3 AA 34 Ala 4 .....

I KIA Topic(s) IR #

026 Containment Spray x I l;)""i'

)""i' K4 Knowledge of the CSS design 4.1 1 feature(s) and/or interlock(s) which It It' ,;I~

"I~

provide for the following:

K4.08 Automatic swapover to 1[', .* containment sump suction for recirculation phase after LOCA(RWST I'li;"S

'" i low-low level alarm)

(CFR 41.7) 039 Main and Reheat Steam x I

./

K5 Knowledge of the operational implications of the following concepts 2.7 1

!.[.(, as they apply to the MRSS:

f i" \[

..... <...... K5.05 Bases for RCS cooldown limits

..... I (CFR 41.5/45.7) 059 Main Feedwater x *... K3 Knowledge of the effect that a loss 3.6 1 I, or malfunction of the MFW will have on

~\~i the following:

.~\' K3.02 AFW system f"" (CFR 41.7/45.6) 061 Auxiliary/Emergency x x K2 Knowledge of bus power supplies to 3.7 2 Feedwater

S~*
. . the following:

I K2.02 AFW electric drive pumps (CFR 41.7)

  • *.*. . * * * * * *. . * (CFR 41.7) i;;'"'~;I I**.*.*****.***.***.***.*** ..

[.;i;i r~;](1 NI K4 Knowledge of AFW design 2.7

"~j\..

t* feature(s) and/or interlock(s) which wihich iii." provide for the following:

i**** K4.08 AFW recirculation 1',.::+;

..... (CFR 41.7) 062 AC Electrical Distribution Xi x A 1 Ability to predict and/or monitor 3.4 2 r'r',*)) changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including:

~"~~

t"~~

A1.01 Significance of DIG load limits

  • C.i .. ; (CFR 41.5/45.5)

Ii, Ii u~i, i][~~

3.5 t,;;:" , I.,j~

",j~ A3 Ability to monitor automatic t

~;c~j operation of the ac distribution system, op,,,,tioo including: ofth, ac d"tribUlio",ysl,m.

fit,.'

fit,.::

r~~cl'"d"d"9

[..."

A3.05 Safety related indicators and controls (CFR 41.7/45.5)

n II "-'tu PWR Examination Outline ~.

~"

Pial I! "'"))

1~=================9~~F=~P~lallt~~'~'o~,,~~ ~~'~M~~i=================9==

~, .o,'~ .

System # 1 Name KKK K K K KKK 1

1 2 2 3 3 4 K K K 4 5 56 6 11 A A A

3 A G 4

KIA Topic(s)  ;=r:=

IR #

063 DC Electrical Distribution x K1 Knowledge of the physical 2.7 1 connections and/or cause-effect

.; relationships between the DC electrical

.... system and the following systems:

K 1.02 AC electrical system Iih (CFR 41.2 to 41.9/45.7 to 45.8) 064 Emergency Diesel Generator x 2.1.7 Ability to evaluate plant 4.4 1

.... performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

073 Process Radiation x

~ I."

.* *** (CFR 41.5143.5145.12/45.13)

A 1 Ability to predict andlor monitor 3.2 1 Monitoring fc ..

changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including:

';{. ........

A1.01 Radiation levels

):;< (CFR 41.5/45.7) 076 Service Water x K3 Knowledge of the effect that a loss 3.4 1 or malfunction of the SWS will have on the following:

6'\'

~~~\I K3.01 K3.01 Closed Closed cooling cooling water.

water.

'.:;i (CFR 41.7/45.6) 078 Instrument Air xx x I.f' ..

K1 Knowledge of the phYSical connections andlor cause-effect l', relationships between the lAS and the 2.7

.. ;' following systems:

K1.02 Service air

~o ":'.1 dc" (CFR 41.2 to 41.9/45.7 to 45.8)

(CFR41.2t041.9/45.7t045.8) j~~'T 3.4 t';,!I I:,>

I'uJ orK3malfunction Knowledge of the effect that a loss of the lAS will have on

.... 1:~:)2 the following:

I;",;;. K3.02 Systems having pneumatic valves and controls I~-------------------+-+~--r-+-~~-

103 Containment xx ft..

t:iiL..J~(~IC~F~R~4~1.~n~45~.6~>>

li'l I.... ..*

(CFR 41.7/45.6)______________+-__~__~1 K4 Knowledge of the containment 3.1 1

.-HI I',;. i' system design feature(s) andlor

.**.~;\!i.

~;

I;~;. ., interlock(s) which interlock(s) which provide provide for for the the ce

,; following:

.... ..... .:. K4.06 C'"talomont "".tiM ,yst"'"

K4.06 Containment isolation system IF===================*=~~=F~=*~~~~:; :c.

1~*~(IC=F=R=4=1=.7~)===============b===F==~1 (CFR41.7)

KIA Category Point Totals

16'=

KlA=

3 3 5 4 2'2 c<a=!=eg=o=ry=p=o=in=t=T=o=ta=ls=:====,==3::6:3==,==5::6:4d::.1lm Gro,p Po. !Total, Group Point Total:

! ~81

ES-401 5 Form ES-401-2

[Ov' tV PWR Examination Outline

= Plant Systems - Tier 21Group 2 RO I SRO)

System # / Name K KKK KKK KK KK A A *\ ' AAIAA GG KJA Topic(s) IR #

1 1 2 2 3 3 4 4 5 5 66 1 1 2 I

2 34 -ti-!+--'-+ ..... *. - - - - - - - - - - - - - + - - - + - - - I I 001 Control Rod Drive x K4 Knowledge of CRDS design feature(s} 3.5 and/or interlock(s} which provide for the following:

Ii K4.03 Rod control logiC (CFR 41.7) 002 Reactor Coolant I**"***.***

011 Pressurizer Level Control x "~'.'

,~ A3 Ability A3 Ability to to monitor monitor automatic automatic operation operation 3.2 of the PZR LCS, including:

....*. 1,". A3.03 Charging and letdown i

014 Rod Position Indication x>

,c A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 3.6 operating the RPIS controls, including:

I... A1.03 PDIL,PPDIL

    • .*. * ,. (CFR 41.5/45.5) 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor x I '.'

+--I K4 Knowledge of the ITM system design 3.4 1 features an/or interlocks which provide for the following:

i K4.01 Input to subcooling monitors.

I .

.. (CFR 41.7) 027 Containment Iodine Removal RecombineI'..

028 Hydrogen Recombine and Purqe Control 1~0~2~9~C~0~nta~in~m~e~n~tP~u~rq~le~----~~+_~_+_4--r_+_~~~

029 Containment Purge _ _+!~_+*.----------------------------+_--_+--~I 033 Spent Fuel Pool Cooling I:.:'> I I t~;**;;1 1~0~34tFBu~e~IH~a~n~d~lin~gE~qIUi~Plm~en~t-~12+~~-~~I~:~~~~~~~=E~~~~,~.~~-r~.r.~

034 Fuel Handling Equipment . . . ~----------------------4---~~1 035 Steam Generator x K5 Knowledge of the operational 3.4 1 implications of the following concepts as r

they apply to the S/05:

K5.01 Effect of secondary parameters, pressure, and temperature on reactivity (CFR 41.5/45.7)

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 RO 1 SRO)

System # 1 Name K K K K K K A A A A G KIA Topic(s) IR #

I 2 3 4 5 6 1 2 3 4 041 Steam Dump/Turbine x A2 Ability to (a) predict the impacts of the 3.6 1 Bypass Control following malfunctions or operations on r'";

r'".* I..... the SDS; and (b) based on those I........ ......... predictions use procedures to correct, control, or mitigate the consequences of those malfunctions or operations A2.02 Steam valve stuck open I,'I*' II (CFR 41.5/43.5/45.3/45.13)

--1JJl;r i

045 Main Turbine Generator .,

055 Condenser Air Removal xx K1 Knowledge of the physical connections 2.6 1 andlor cause-effect relationships between the CARS and the following systems:

K1.06 PRM (process radiation monitoring) system (CFR 41.2 to 41.9/45.7 to 45.8) 056 Condensate x K1 Knowledge of the physical connections 2.6 1

.... andlor cause-effect relationships between the condensate system and the following II***** ......,,

systems:

K1.03 MFW (CFR 41.2 to 41.91 45.7 to 45.8) 068 Liquid Radwaste , ... "'/"

~Z:,.X) 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water t I~1~~'!1~

I

'ii" K2 Knowledge of bus power supplies to the following:

2.6 1

"', K2.03 Emergencylessential SWS pumps (CFR 41.7) 079 Station Air xx ';;;r;i. K4 Knowledge of SAS design feature(s) 2.9 ~1 xC andlor inter1ock(s) which provide for the te

>.A

" following:

K4.01 Cross-connect with lAS I*I*.**** * *.* * * ** *** ** (CFR 41.7)

(C'R41.7) i'd",

II II

.  : 2 11 "

101 3

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3 AOCf"'\f"'\V Date of Exam: 6/15/09 Category KIA # Topic RO SRO-Only

~Q()-Only IR # IR #

2.1.3 Knowledge of shift or short-term relief turnover 3.7 1 practices.

1.

Conduct (CFR 41.10/45.13) of Operations 2.1.25 Ability to interpret reference materials, such as 3.9 1 graphs, curves, tables, etc.

(CFR 41.1 0/43.5/45.12) 2.1.26 Knowledge of industrial safety procedures (such as 3.4 1 rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen, and hydrogen.

(CFR 41.10145.12) 2.1.

2.1.

I

  • 2.1.

Subtotal 3 2.2.2 Ability to manipulate the console controls as 4.6 1 required to operate the facility between shutdown and deSignated power levels.

2.

Equipment (CFR 4160141.7/45.2)

Control 2.2.22 Knowledge of limiting conditions for operation and 4.0 1 safety limits.

(CFR 41.5/43.2/45.2) 2.2.

2.2.

2.2.

2.2.

Subtotal 2 2.3.5 Ability to use radiation monitoring systems, such as 2.9 1 fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

3.

Radiation (CFR 41.11/41.12/43.4/45.9)

Control 2.3.11 Ability to control radiation releases. 3.8 1 (CFR 41.11/43.4/45.10) 2.3.

2.3.

2.3.

SEABROOK Date of Exam: 6/15/09 Category KIA # Topic 2.3.

Subtotal 2.4.6 Knowledge of EOP mitigation strategies. 3.7 1

4. 41.10/43.5/45.1 Emergency 2.4.11 4.0 1 Procedures 1 Plan 2.4.42 2.6 2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: SEABROOK SRO section Date of Exam: 10/1/9 RO RO KIA ~p"nIS KJA Category Points SRO-Only Points Tier Group A2 K

1 K

2 K

3 K

K K 4

4 5 K K 5 6 K

6 A

1 A

2 2 3 A

3 4 A

4 ..

G Total G* Total 1.

Emergency &

Abnormal Plant 1

2 otals N/A ---H 18 9

27 II 4 2

6 2

2 4

6 4

10 tG 2r:;:c:!

Evolutions 2.

Plant 1

2 jj i

Itt I 28 10 IIII 2G:C! II 5 3

Systems Tier Totals 38 5 3 8 II

3. Generic Knowledge and Abilities Note: 1.

Categories 1 I 2 3 4 10 tt 1 2

2 2

Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" 3

1 4

2 7

in each KJA 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 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 KJA 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 KJAs 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 KJA categories.

7: The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs.

8. On the following pages, enter the KJA 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 KJA catalog, and enter the KJA numbers, descriptions. IRs.

and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergencv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

E/APE # 1 Name I Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2

-+

-+-

000007 (BW/E02&E 10; CE/E02) Reactor c.':

Trip - Stabilization - Recovery 11

  • c 000008 Pressurizer Vapor Space "

Jc; Accident 1 3 ;i 000009 Small Break LOCA I 3 i " EA2 Ability to determine or interpret the following as 4,2 1

>> they apply to a small break LOCA:

EA2.34 Conditions for throttling or stopping HPI

t; li
::"'\ (CFR 43.5/45.13) 000011 Large Break LOCA 1 3 000015/17 RCP Malfunctions 14 x 2.1.23 Ability to perform specific system and 4.4 1 integrated plant procedures during all modes of operation.

'c' (CFR 41.10/43.5/45.2/45.6) 000022 Loss of Rx Coolant Makeup I 2 c.:*:~~ I"[:f: AA2 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant 3.6 1

~ ..;

Makeup:

~~

~" AA2.03 Failures of flow control valve or controller

[i;,.",

(CFR 43.5/45.13) 000025 Loss of RHR System 14 i" 000026 Loss of Component Cooling tc" Water 18 000027 Pressurizer Pressure Control x AA2 Ability to determine and interpret the following 3.9 1 System Malfunction I 3 as they apply to the Pressurizer Pressure Control Malfunctions:

AA2.06 Conditions requiring plant shutdown me (CFR 43.5/45.13) 000029 A TWS 11 1:C;;i I 000038 Steam Gen. Tube Rupture 1 3 x EA2 Ability to determine or interpret the following as 3.3 1 they apply to a SGTR:

1"',;;,1 EA2.10 Flowpath for charging and letdown nows 1

I,*""';";

i";' (CFR 43.5/45.13) 000040 (BW/E05; CE/E05; W/E12) r,"

c, Steam Line Rupture - Excessive Heat Transfer 14 000054 (CE/E06) Loss of Main  ;

Feedwater 1 4 000055 Station Blackout I 6 000056 Loss of Off-site Power 1 6 i*:,

000057 Loss of Vital AC Inst. Bus I 6 Ifj!j

ES-401 PWR Examination Outline Form ES-401-2 Emerqenc and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1 SRO)

E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 000058 Loss of DC Power 1 6 000062 Loss of Nuclear Svc Water 1 4 000065 Loss of Instrument Air 18 x 2.1.32 Ability to explain and apply system limits and 4.0 1 precautions.

(CFR 41.10/43.2/45.12)

W/E04 LOCA Outside Containment 1 3 W/E11 Loss of Emergency Coolant Recirc. 1 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 1 4 000077 Generator Voltage and Electric Grid Disturbances 1 6 KIA Category Totals: 4 2 Group Point Total: 181 6

ES-401 3 Form ES-401-2

~ .~

ES-401 PWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)

E/APE # I/ Name I/ Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 I 000001 Continuous Rod Withdrawal I1 Withdrawal/1 1 """"'.'",, \

\

'.":hii': ' ..

000003 Dropped Control Rod I/ 1 ...."".

1;r0t 000005 Inoperable/Stuck Control Rod 11/1 x AA2 Ability to determine and interpret the 4.4 1 I" following as they apply to the I"

1 "......

Inoperabel/Stuck Rod:

InoperabellStuck

~

~ AA2.03 R",,;,.., ',,"0", If mo", .~O Reo,;'ed."""", th., 00*

0"'

.*",I:: 1:: rod is stuck or inoperable (CFR 43.5/45.13) 000024 Emergency Boration 11

". ~"':

~>,+:. I':', ..

m! ~i.'

000028 Pressurizer Level Malfunction I/ 2 000032 Loss of Source Range NI/7 000033 Loss of Intermediate Range NI/7 ',,"1"[":.

"t*;

000036 (BW/A08) Fuel Handling Accident I/ 8 ****Z ,."

.j:

',j; .. *" *"ij I 000037 Steam Generator Tube Leak I/ 3 000051 Loss of Condenser Vacuum 14 /4 000059 Accidental Liquid RadWaste ReI. 19 , 2.3.11 Ability to control radiation releases. 4.3 1 I:":'.. ",i (CFR 41.11/43.4/45.10) 000060 Accidental Gaseous Radwaste ReI. I 9 000061 ARM System Alarms I 7 I**:......*

'0:..""""*1!

000067 Plant Fire On-site I 8 I>

000068 (BW/A06) Control Room Evac. 18 1'<

f",::,

,;c"',,'.'

000069 (W/E14) Loss of CTMT Integrity 15 000074 (W/E06&E07) Inad. Core Cooling 14 ..........*....*...**.

000076 High Reactor Coolant Activity I 9

~E******:****

  • ........... . .' I

~

W/E01 & E02 Rediagnosis & SI Termination I/ 3 n'

II W/E 13 Steam Generator Over-pressure I 4 W/E15 Containment Flooding 15 I 1

rt WlE16 High Containment Radiation 19 I;: .: . .

m BW/A01 Plant Runback 11 BW/A02&A03 Loss of NNI-X/Y 1 7 BW/A04 Turbine Trip I 4

"'i~

c, BW/A05 Emergency Diesel Actuation 16 100ding/8 Wj,j I,.'

hi' Ih>

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO 1 SRO)

E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 BW/E03 Inadequate Subcooling Margin 1 4 BW/EOB; W/E03 LOCA Cooldown - Depress. 14 x 2.4.20 Knowledge of operational 4.3 1 implcations of EOP warnings, cautions, and notes.

(CFR 41.10/43.5/45.13)

BW/E09; CE/A13; W/E09&E10 Natural Circ./4 x E09 3.B 1 EA2 Ability to determine and interpret the following as they apply to the Natural Circulation Operations:

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facilities license and amendments.

(CFR 43.5/45.13)

BW/E13&E14 EOP Rules and Enclosures CE/A11; W/EOB RCS Overcooling - PTS 14 CE/A 16 Excess RCS Leakage 12 CE/E09 Functional Recovery II 1<111 r, o .. T. ,ic: 2 2 Group Point Total: 9/4

4 ES-401 PWR Examination Outline Fo Plant Systems - Tier 2/Group 1 (RO 1 SRO)

~ ~

System # 1 Name K K K K A AIi Ii A A G KIA Topic(s) IR #

I 3 4 5 6 <2 1 2 3 4 003 Reactor Coolant Pump I I 004 Chemical and Volume I,'" 2.2.22 Knowledge of limiting conditions 4.7 1 Control 17. } for operations and safety limits.

(CFR 41.5/43.2145.2) 005 Residual Heat Removal 006 Emergency Core Cooling I 1

007 Pressurizer Relief/Quench Tank 008 Component Cooling Water II i x 2.4.11 Knowledge of abnormal condition procedures.

41=

4.2 1

..... (CFR 41.10143.5/45.13) 010 Pressurizer Pressure Control .'

r***,v r"'vx I ......'"

012 Reactor Protection A2 Ability to (a) predict the impacts of 4.7 1 the following malfunctions or operations on the RPS; and (b) based on those Iii **... ..

r predictions, use procedures to correct, control, or mitigate the consequences of I those malfunctions or operations:

I~t Ie . *. A2.06 Failure of RPS signal to trip the

.' '.f reactor.

I*I*** ******

I***

1***1.*.....*..**

. ******** (CFR 41.5/43.5/45.3/45.5) 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray m

fill rTf

~::':;~r I;'

i,' 'f I

I*.**

I i'

039 Main and Reheat Steam I I

~'---

I*'.

i*'

I

=m IT I

061 Auxiliary/Emergency Feedwater l~:f;!;i l~:f;!;,

+/-+/-

062 AC Electrical Distribution i"I i .

063 DC Electrical Distribution *******************************

System # 1 Name I~

K 2

K 3

m' K

4 PWR Examination Outline

.*2

.* 2 A A 3

A 4

G "nISRO)

KIA Topic(s)

Form ES-401-2 IR #

064 Emergency Diesel Generator **** x 2.2.40 Ability to apply Technical 4.7 1 Specifications for a system.

(CFR41.10/43.2143.5/45.3) 073 Process Radiation ".

Monitoring 076 Service Water 078 Instrument Air *.... < i, 103 Containment ,'x A2 Ability to (a) predict the impacts of 3.8 1 iii the following malfunctions or operations on the containment system; and (b)

,; based on those predictions. use

'.."..... procedures to correct. control, or mitigate the consequences of those

~" malfunctions or operations:

~i;:;;;

A2.03 Phase A and B isolation

>/ (CFR 41.5/43.5145.3/45.13)

II** * * ** *. ,*

I~  ?!~<

  • KIA Category Point Totals:  : oint Total:

~" ..'"

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-M11-?

Plant S stems - Tier 2/Group 2 (RO 1 SRO)

System # 1 Name K 1 2 K K 3

K 4

K 5

K 6 ~~j ,~

A 3

A 4

G KiA Topic(s) IR #

001 Control Rod Drive

~

002 Reactor Coolant }. A2 Ability to (a) predict the impacts of the 4.4 1

    • X X following malfunctions or operations on

,,' .. ~~

the RCS; and (b) based on those

".~ predictions, use procedures to correct, c,. control, or mitigate the consequences of

~<

those malfunctions or operations:

!.;,**. i*

A2.02 Loss of coolant pressure

'?

.,,' (CFR 41.5/43.5/45.3/45.5)

}i} ~ ~~~~~ ~~~~. ~

011 Pressurizer Level Control

~;;;;;;X (']

014 Rod Position Indication riA 015 Nuclear Instrumentation x A2 Ability to (a) predict the impacts of the 3.5 1 following malfunctions or operations on I* i,.)'} the NIS; and (b) based on those ii predictions, use procedures to correct, control, or mitigate the consequences of r ~~~~~~.

those malfunctions or operations:

, A2.02 Faulty or erratic operation of detectors or compensating components

,,;;;; (CFR 41.5/43.5/45.3/45.5) 016 Non-nuclear Instrumentation Ii 017 In-core Temperature Monitor if:;;

~.'~ ~~~ .

'.~.;;;.

027 Containment Iodine Removal 1<> i 028 Hydrogen Recombiner .....

I.* * .* .* :

and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling I"x,; .**..

" A2 Ability to (a) predict the impacts of the 3.5 1 following malfunctions or operations on I:~;';;

the Spent Fuel Pool Cooling System; and A. (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions 1<*1, I **~ or operations:

Ie;;'  ;;.~

A2.03 Abnormal spent fuel pool water t'@:; level or loss of water level 

                                                                                                                        '.'>, (CFR 41.5/43.5/45.3/45.13)

I'" :2.,;;:: ';; i"; I; ["",;0 034 Fuel Handling Equipment E. 1*'1",,' ,;; .. .", ,...... j" I}I}..I i,,'f .;., 

                                                                                          'ii, 035 Steam Generator

i, .... 

   .... ".,-"TV                                PWR Examination Outline                                                     Form ES-401-2 Plant S stems - Tier 21Group 2 (RO                   eRO I SRO)

System # I Name K K K K K K A , A A G KIA Topic(s) IR # AJ1jA 1 2 3 4 5 6 1 :2 3 4 .... 041 Steam Dump/Turbine I******* k' 

                                                                              /.

Bypass Control .; i, 045 Main Turbine Generator I~ 055 Condenser Air Removal 056 Condensate 

                                                             ,i."

ii.' ~",< r'" . 

                                                          -ti........          *******
*i 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 1'[;'1 fr;'
  • i<i
                                                      ...........           n[          )..
                                                              .y.
                                                              *y        I 075 Circulating Water i'

079 Station Air i' *. 

                                                       .);
                                                       'y' 086 Fire Protection
                                                      .'~;
                                                      .i~;                        . ...
                                                                                                                             =
                                                                 ,')

KIA Category Point Totals: H . T.. 

                                                                                                         .T
                                                                                                                ,I:I:

81 ti

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: SEABROOK Date of Exam: 6/15/09 Category KIA # Topic RO SRO-Only IR # IR # 2.1.20 Ability to interpret and execute procedure steps. 4.6 1

1. (CFR 41.10/43.5/45.12)

Conduct 2.1.41 Knowledge of refueling process. 3.7 1 of Operations (CFR 41.2/41.10/43.6/45.13) 2.1. 2.1. 2.1" 2.1. Subtotal 2 2.2.5 Knowledge of the process for making design or 3.2 1 operating changes to the facility.

2. (CFR 41.10/43.3/45.13)

Equipment Control 2.2.38 Knowledge of conditions and limitations in the 4.5 1 facility license. (CFR 41.7/41.10/43.1/45.13) 2.2. 2.2. 2.2. 2.2. Subtotal 2 2.3.4 Knowledge of radiation exposure limits under 3.7 1 normal or emergency conditions.

3. (CFR 41.12/43.4/45.10)

Radiation 2.3. Control 2.3. 2.3. 2.3. 2.3. Subtotal 2.4.5 Knowledge of the organization of the operating 4.3 1 procedure network for normal, abnormal, and

4. emergency evolutions.

Emergency (CFR 41.10/43.5/45.13)

SEABROOK Date of Exam: 6/15/09 Category KIA # Topic IR Procedures / Plan 2.4.38 Ability to take actions called for in the facility emergency plan. including support or acting as emergency coordinator if required. FR 41.10/43.5/45.1 2.4. 2.4. 2.4. 2.4. Subtotal Tier 3 Point Total

Seabrook Station 2009 NRC Remediation Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA During exam outline generation the KIA's associated with Ice Tier 2/ 025 Ice Group 1 Condenser (025) were suppressed. Condenser ROand This system is N/A to Seabrook. SRO section Tier 2/ 016 Non-nuclear During exam outline generation the KIA's associated with Group 2 Instrumentation Non-Nuclear Instrumentation (016) were suppressed. ROand This system is NIN/A to Seabrook SRO section Tier 2/ 027 Containment During exam outline generation the KIA's associated with Group 2 Iodine Removal Containment Iodine Removal (027) were suppressed. ROand This system is included as part of the Containment Building SRO Spray System at Seabrook section Tier 1/ 007 Reactor Trip- Originally selected KIA EKl.05, Decay power as a function Group 1 Stabilization- of time. Rejected KlAas this subject is considered a generic RO section Recovery fundamental topic. Selected KIA EK1.06, EKl.06, Relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip. Originally selected KIA AA1.15, T-avgprotection indicators. Tier 11 040 Steam Line Group 1 Rejected KlAas this is not applicable to Seabrook. The Rupture-facility utilizes core/vessel temperature parameters with RO section Excessive Heat regard to excessive cool down conditions. Transfer Selected KIA AAl.09, Setpoint of Main Steam Safety and PORV. Tier 1/ 061 ARM System Originally selected KIA AAl.Ol, Ability to operated and/or Group 2 Alanns monitor the following as they apply to the ARM system RO section alarms: Automatic actuation. Rejected this KIA as it presents too similar a topic to the KIA selected for Tier 1/ Group 2 036, Fuel Handling Accident. Seabrook Station does not have automatic actuations from area rad monitors with the exception of the refueling crane monitor that is placed in service during refueling. This topic is covered by the 036, Fuel Handling Accident associated KIA. Selected KIA AA2.05, Need for area evacuation. Page 1 of4

Seabrook Station 2009 NRC Remediation Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 2/ 007 Pressurizer Originally selected KIA AI.03, Monitoring quench tank Group 1 Relief7Quench temperature. Rejected this KIA as the subject matter appears RO section Tank to overlap that of Question I on the original 2009 written exam. Selected KIA 3.01, Knowledge of the effect that a loss or malfunction of the PRTS will have on the following: Containment Tier 2/ 022 Containment Originally selected KIA A2.05, Major leak in CCS. Rejected Group 1 Cooling KlAas Seabrook Station does not have a Service Water RO section interface for it's CCS. Any major leak associated with the CCS system would be associated with the Component Cooling System, which is covered by another category. Selected new KIA K2.01, Knowledge of power supplies for the following: Containment Cooling Fans Tier 2/ 063 DC Electrical Originally selected KIA Kl.03, Knowledge of the physical Group 1 System connections and/or cause-effect relationships between the DC RO section electrical system and the following: Battery charger and battery. Rejected the KIA as it appeared too close to the subject matter for the KIA selected for Tier 1/ Group 1, 058, Loss of DC power. Selected new KIA Kl.02, Knowledge of the physical connections and/or cause-effect relationships between the DC electrical system and the following: AC electrical system Tier 1/ 059 Accidental Originally selected KIA 2.3.7, Ability to comply with Group 2 Liquid Rad Waste radiation work permits during normal or abnormal conditions. SRO Release KIA was rejected as the topic pertains to accidental rad section releases vice a planned release associated with rad permits. Selected new KIA 2.3.1, Ability to control radiation releases. Tier 21 063 DC Electrical Originally selected category 063 DC Electrical System. Rejected Group 1 System KIA category 063 as the same category appears multiple times on the exam. Change made pursuant to achieving diversity of subject SRO matter. section Selected new KIA category 064 Emergency Diesel Generator Page 2 of4

Seabrook Station 2009 NRC Remediation Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 21 002 Reactor Originally selected KIA A2.04, Ability to a) predict the Group 2 Coolant impacts of the following malfunctions or operations on the RCS; and b) based on those predictions, use procedures to SRO correct, control, or mitigate the consequences of those section malfunctions or operations: Loss of heat sinks. Rejected the KIA as the subject matter was too similar to the KIA selected for RO section, Tier l/Groupl, BW/E04, Inadequate Heat Transfer-Loss of Secondary Heat Sink, KIA EA2.1. Selected new KIA A2.02, Loss of coolant pressure. Tier 017 In-Core Originally selected KIA K1.02, Knowledge of the physical 2/Group 2 Temperature connections and/or cause effect relationships between ITM Monitoring and the following systems: RCS Rejected the KlAas it duplicates the subject matter associated with submitted test question #2. Selected new KIA K4.01, Knowledge if the ITM system design features and/or interlocks which provide for the following: Input to subcooling monitors. Tier 21 076 Service Water Originally selected KIA K3.07 Knowledge ofthe effect that a Group 1 loss or malfunction of the SWS will have on the following: ESF Loads. Rejected the KlAas the main ESF load is the Emergency Diesel Generator. The exam already has questions pertaining to the Emergency Diesel Generator and another discriminatory question could not be found. Selected new KIA K3.01, Knowledge of the effect that a loss or malfunction ofthe SWS will have on the following: Closed cooling water. Page 3 of4

Seabrook Station 2009 NRC Remediation Written Exam ES-401 Record of Rejected KlAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 11 061 Area Rad Originally selected KIA AA2.05 Ability to determine and Group 2 Monitoring interpret the following as they apply to the Area Radiation System Alarms Monitoring (ARM) System alarms: Need for area evacuation, check against existing limits. Rejected the KIA based on a) could not select/create a discriminatory question. The facilities actions in the Area High Radiation abnormal procedure appeared too simplistic to author a valid question and b) the exam already contains questions pertaining to Area Rad Monitor interface with Containment Ventilation Isolation equipment and also Refueling/Spent Fuel abnormal procedures. Reselected new Category and KIA from same tier. Selected W/E16 High Containment Radiation, KIA EAl.l Ability to operate andlor monitor the following as they apply to the High Containment Radiation, Components and functions of control and safety systems including instrumentation, signals, interlocks, failure modes, and automatic and manual features. Page 4 of4}}

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