ML093270132

Initial Exam 2009-301 Draft Administrative Documents

ML093270132
Person / Time
Site:	Crystal River
Issue date:	11/18/2009
From:	Division of Nuclear Materials Safety II
To:	Progress Energy Co
References
50-302/09-301
Download: ML093270132 (31)

Text

FACILITY NAME: Crystal River 3 Section 1 REPORTNUMBER: ____ ~O~50~O~O~30~~~2=O~09~-~30~1~

____~O=5~O~OO=3~O=~~2~OO~9~-3~O~1 _________

DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

4raft Written Exam sample plan (ES-401-1/2)

Gf)lraft Administrative Topics Outline (ES-301-1)

@>>raft o0' Draft Control Room Systems && Facility Walk-Through Test Outline (ES-301~2)

(ES-301-2)

Location of Electronic Files:

Submitted By: ~"""I-"<+''''"''F--fI-~~~-'---- I\..L.f~_-----:-

Verified.By_ _F\~*i~~

By: 7--~"""-'"'"""F-f;L...b'-'-f-+-4~"-"-'--- verifiedBy _ __ __ __

ES-401 R 0 - PWR Ex~mination RO EX1Iuination outline O,utline - (Sept, 2009) Form ES-401-2

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\ Facility: Crystal River Unit #3 Date of Exam: September, 2009 RO KIA KJ A Category Points SRO-Only Points Tier Group K K K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 5 6 6 11 2 3 4 **

1 3 3 2 2 4 4 3 3 3 18 6 1.

L Emergency 2 2 1 1 1 2 2 9 4

& Abnormal N/A N/A Plant Evolutions Tier 5 3 5 4 5 5 27 10 Totals 1 2 3 3 3 3 22 2 2 33 22 2 2 33 28 5 2.

Plant 2 2 0 1 1 1 1 1 1 0 1 0 11 1 10 3 Systems Tier Totals 4 3 44 4 4 4 4 3 3 3 4 4 2 2 3 3 4 4 38 8

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 3 2 3 2 Note: I.

L 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 "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 +/- 1I 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 me aTe identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to Section D. D.1.bLb of ES-40 1I 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 KI As having an importance rating (IR) of25 of2.5 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 1I and 2 from the shaded systems and KIA categories.

7* KI As in Tiers 1I and 2 shall be selected from Section 2 of The generic (G) KlAs the KIA Catalog, but the topics must be relevant to ofthe the applicable evolution or system. Refer to section d. d.l.b ES-401I for the applicable KI As.

I.b of ES-40

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 KlAs that are linked to 10 CFR 55.43.

((

Page 1 of14of 14 F:\NRC - 200910utlineslWrittenIRO F:INRC 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 I I ES-401 PWR Examination Outline Form ES-401-2

( Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 E/APE # I Name I K KKK K K A }\

G KIA Topic(s) IR #

Safety Function 1 1 2 2 3 3 1 2.

007EA2.02 - Ability to determine or interpret the following as they apply to a X reactor trip: Proper actions to be taken if 4.3 1 the automatic safety functions have not taken place 008AG2.1.23 - Ability to perform 00SAG2.1.23 OOS Pressurizer Vapor Space 008 specific system and integrated plant Accident 13 procedures during all modes of plant 4.3 1 operation.

009EK2.03 - Knowledge of the 009 Small Break LOCA 1 I3 X interrelations between the small break 3.0 1 LOCA and the S/Gs.

011 EK3 .07 - Knowledge ofthe O1IEK3.07 of the reasons for the following responses as they apply X to the Large Break LOCA: Stopping 3.5 1 HPI bypass flow (recirc flow OK per

( GL) 015/017AK1.05 015/0 17AK 1. 05 -Knowledge of the of the following operational implications ofthe concepts as they apply to RCP 015117 RCP Malfunctions 14 X malfunction (Loss ofRC Flow): Effects 2.7 1 of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrant power tilt.

022AK1.03 - Knowledge ofthe of the operational implications of the following X concepts as they apply to Loss of 3.0 1 Reactor Coolant Makeup: Relationship between makeup flow and PZR level 025AA2.01 - Ability to determine and interpret the following as they apply to 025 Loss ofRHR System 1 I4 the Loss of Decay Heat Removal 2.7 1 System: Proper amperage of running LPI/decay heat removal/RHR LPl/decay removallRHR pump(s)

(

of14 Page 2 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2

( Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 E/APE # I Name I K K K K K K A A G KIA Topic(s) IR #

Safety Function 1 2 3 1 2 026AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Services / Decay 026 Loss of Component Cooling Water /8 xX Heat Closed Cycle Cooling: The 3.6 1 automatic actions (alignments) within the SWS / DCS resulting from the actuation of the ESFAS 027AK3.04 - Knowledge ofthe of the reasons for the following responses as they apply 027 PZR Pressure Control to the PZR Pressure Control System Malfunction / 3 xX Malfunctions: Why, ifPZR level is lost 2.8 1 and then restored, that pressure recovers much more slowly.

029EA1.12 - Ability to operate and 029 ATWS /1 xX monitor the following as they apply to an 4.1 1 ATWS: Reactor trip breakers

( 038 Steam Generator Tube X

038EG2.1.28 - Knowledge ofthe purpose and function of major system 4.1 1 Rupture / 3 components and controls.

040 (BW (BWIE05) 1E05) Steam Line Rupture - Excessive Heat Transfer / 4 054AAl.Ol 054AA1.01 - Ability to operate and / or monitor the following as they apply to 054 Loss of Main Feedwater

/4 xX the Loss of Main Feedwater (MFW): 4.5 1 EFW controls, including the use of alternate EFW sources 055EK3.02 - Knowledge ofthe of the reasons for the following responses as they apply xX to the Station Blackout: Actions 4.3 1 contained in EOP for loss of offsite and onsite power.

056AAl.05 056AA1.05 - Ability to operate and / or monitor the following as they apply to xX Offsite Power: Initiation the Loss of Offsite 3.8 1 (manual) of safety injection process

(

Page 3 of 14 F:\NRC - 2009\OutIines\Written\RO 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2

( Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 E/APE # I Name I K K K K K K A A G KIA Topic(s) IR #

Safety Function 1 2 3 1 2 057 Loss of Vital AC Instrument Bus 1/ 6  !\

I:;II~> ,I> 058AK1.01 - Knowledge of the 058AKl.Ol I~! :'

of the following operational implications ofthe 058 Loss of DC Power 1/66 X concepts as they apply to Loss of DC 2.8 1 Power: Battery charger equipment and instrumentation ofNuc1ear 062 Loss of Nuclear Services Water 1/ 4 hi* ;:1'(  ; I, I;:;*:',: * <, 065AG2.4.8 - Knowledge of how 065 Loss ofInstrument of Instrument Air 1/

8 I* . x. abnormal operating procedures are used 3.8 1 I,' * . ,; EOPs .

in conjunction with EOPs.

BW/E04EA2.1 - Ability to determine BWIE04EA2.1 and interpret the following as they apply BW1E04 Inadequate Heat to the (Inadequate Heat Transfer):

3.2

( Transfer - Loss of Secondary Heat Sink 1/ 4 X Facility conditions and selection of appropriate procedures during abnormal 1

I:

and emergency operations.

077 AK2.03 - Knowledge of the 077 Generator Voltage and interrelations between Generator Voltage Electric Grid Disturbances 1/ X and Electric Grid disturbances and the 3.0 1 6

following: Sensors, detectors, indicators.

KIA Category Totals 3 2 2 4 4 33 3 3 Group Point Total 18/6 Page 4 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO ES-401-2 I Form ES-401-21 ES-401 PWR Examination Outline Form ES-401-2 (1

I Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I K K K A A G KIA Topic(s) IR #

Safety Function 1 2 3 1 ~

~~r I,',

u6ts Rbd 001AA2.05 001AA2,05 - Ability to determine and

.~

hdr~Mral/l  :,. interpret the following as they apply to nge:dfr6m AA ~:fl2' the Continuous Rod Withdrawal: 4.4 1

,;/', ,:'i~  :., Uncontrolled rod withdrawal from y,'

.:; available indications fi~,

'/",::11

'i:i.

f~,'

003 Dropped Control Rod / 1 .:;:i 003AK.1.10 003AKLIO - Knowledge of the

~ ... operational implications of the following X concepts as they apply to Dropped 2.6 1 Control Rod

Definitions of core quadrant power tilt 005 Inoperable/Stuck Rod / 005AK.3.05 005AK3.05 - Knowledge of the reasons

'f;, for the following responses as they apply 1

X to the Inoperable / Stuck Control Rod:

3.4 1 Power limits on rod misalignment 024 Emergency Boration / 1 >.

( 028 PZR Level Malfunction

/2 032 Loss of Source Range NI/7 NI17

',:,/

033 Loss ofIntermediate oflntermediate ,",

Range NI/

NI / 7 036 (BW (BW/A08)/A08) Fuel  ;,

Handling Accident / 8 "

03 7 Steam Generator Tube 037 "

Leak/3 Leak /3 .. ';

051 Loss of Condenser .'

Vacuum/4

',:fiP' ,

059 Accidental Liquid RadWaste ReI. Rel. / 9 060 Accidental Gaseous Radwaste ReI. Rel. / 9

(  :.

Page 5 of14 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx 2,docx ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I K K K K K A A KIA Topic(s)

G IR #

Safety Function 1 2 3 1 2 061 ARM System Alarms I 7 061AG2.2.12 - Knowledge of X surveillance procedures. 3.7 1 067 Plant Fire On-site I 8 068 (BW/A06) Control BWI A06AK1.3 - Knowledge of the BW/A06AK1.3 Room Evac. I 8 operational implications of the following concepts as they apply to the (Shutdown xX Outside Control Room): Annunciators 3.4 1

!.... ' .. ':; and conditions indicating signals, and remedial actions associated with the I' .":~ (Shutdown Outside Control Room).

-j, 1'_,

069 Loss of CTMT Integrity 15 ,

074 Inad. Core Cooling I 4 074EA2.03 - Ability to determine or interpret the following as they apply to a X 3.8 1

( Inadequate Core Cooling: Availability of turbine bypass valves for cooldown 076 High Reactor Coolant Activity I 9 BW/AOl Plant Runback 11 BW/A01 BW/A02&A03 Loss ofNNI- BW/A02AG2.2.12 - Knowledge of XIY XN!7 /7 x: surveillance procedures. (Loss of NNI-X while performing an SP OK per 3.7 1 GL)

BW/A04 Turbine Trip 14 I4 BW/A05 Emergency Diesel Actuation I 6 .'

BWI A07 Flooding I 8 BW/A07AK2.l - Knowledge of the BW/A07AK2.1 interrelations between the (Flooding) and the following: Components, and xX functions of control and safety systems, 3.7 1 including instrumentation, signals, interlocks, failure modes, and automatic

( . and manual features.

Page 6 of of14 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2

(

(

f Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I K K K A A ,?

KIA Topic(s) IR #

Safety Function 1 2 3 1 :2 '

BWIE03 Inadequate Subcooling Margin 1/ 4 IEOS LOCA Cooldown -

BWIE08 IE08EA1.1 - Ability to operate and 1 BW/EOSEAl.l BW /

Depress. 14

/4 or monitor the following as they apply to the (LOCA Cooldown): Components, X

and functions of control and safety 4.0 1

~t~

...< systems, including instrumentation, signals, interlocks, failure modes, and

)," automatic and manual features.

'co

'I:,

BWlE09 Natural Circ. 14/4 t;i!; !\"

,c:

BWIE13&EI4 EOP Rules BWIE13&E14 ,

and Enclosures

• 1

( KIA Category Totals 2 1 1 1 2 2 Groupp Point Total 9/4

(

Page 7 of 14 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx F:\NRC - 2009\Outiines\Written\RO ES-401

I ES-401 1 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K K K K K K A A A A "

System # / Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003K6.14 003K6.l4 - Knowledge of ofthe the effect

", of a loss or malfunction on the 003 Reactor Coolant X 2.6 1 Pump //4 4 ,>> following will have on the RCPs:

Starting Requirements

~.::., 004K2.06 - Knowledge of bus power 004 Chemical and "",'

X "

supplies to the CVCS control 2.6 1 olume Control //11 & 2 Volume

~; instrumentation.

X Ir') 005K2.01 - Knowledge of bus power 3.0 1 1';)'; supplies to the DH pumps.

005 Residual Heat I' I'.:;;' 005K6.03 - Knowledge of the effect Removal /4 /4 of a loss or malfunction on the X

I.'. following will have on the Decay 2.5 1 Heat System: DH heat exchanger

,!~t" rI. 006K5.04 - Knowledge of the operational implications of the

( X following concepts as they apply to 2.9 1 ECCS: Brittle fracture, including

.06 ~ .'"," !fi~

~.',j causes and preventative actions co~~isc; ,;:,::\; 006A2.10 - Ability to (a) predict the ch~t!ied impacts of a low boron IOO6K.5l01{'<?~

concentration in the ECCS; and (b)

,~::~J:; X

" "t'>"<1 j"

based on those predictions, use 3.4 1

~(~

<<(:" procedures to correct, control, or 3'<

mitigate the consequences of ofthis this A~

}rii:) malfunction.

~ i1i:t ,,:

007 A4.09 - Ability to manually operate and/or monitor in the control 007 PZR Relief/Quench \

X room: relationships between PZR 2.5 1 Tank /5 I*:c~ level and changing levels of the PRT and bleed holdup tank

.. ~

008K4.02 - Knowledge ofSWS /

. DCS design feature(s) and/or 008 Component Cooling X interlock(s) which provide for 2.9 1 ater /8 Water ," operation of the surge tank, including the associated valves and controls.

I.:

Page 8 of14 F:\NRC - 2009\Outiines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

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

[~~

K K K K K K A A A A System # / Name 1 2 3 4 5 6 1 :~2 ,.. 3 4 .*. t~. G KIA Topic(s) IR #

i I* .***

i<. 008Al.03 - Ability to predict and/or 008A1.03 monitor changes in parameters (to

i** prevent exceeding design limits) 008 Component Cooling i)i~

X associated with operating the SWS /

2.7 1 Water /8 U DCS controls including: CCW

)r pressure.

./r "

\

010K5.01 - Knowledge ofthe of the operational implications of the 010 Pressurizer Pressure , I following concepts as the apply to X the PZR PCS

Determination of 3.5 1 Control / 3 Control/3 condition of fluid in PZR, using

. . {i steam tables

.\ .*.*..* ~

X 012G2.4.6 - Knowledge ofEOP 3.7 1 mitigation strategies.

<********* <.i 012 Reactor Protection /

7 i** * . < '\,:; 012K5.01 - Knowledge of the operational implications of the X , 3.3 1

( .<< following concepts as they apply to

(;

the RPS: DNB 013 Engineered Safety 013K2.01 - Knowledge of bus power X supplies to the ESF AS / safeguards 3.6 1 Features Actuation / 2 ****** i*.**. equipment control.

.. \

i*' ********* 022K4.01 - Knowledge ofCCS design feature(s) and/or interlock(s) 022 Containment Cooling //55 X i ). which provide for the following: 2.5 1 Cooling of reactor building penetrations .

penetrations.

f~f

< * . . .

• 026Al.Ol 026Al.O 1 - Ability to predict and/or monitor changes in parameters (to 026 Containment Spray / prevent exceeding design limits)

X * * *. .* *.* i*

associated with operating the BSS 3.9 1 5

• .**.*.**** } .. ;j;~ controls including: Reactor Building pressure of the effect 039K3.05 - Knowledge ofthe

.i that a loss or malfunction of the 039 Main and Reheat X 3.6 1 Steam/4 MRSS will have on the following:

RCS Page 9 ofl4 of14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 I f

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

( Plant Systems - Tier 2 I/ Group 1 c"

KKKKKKA K K K K K K A A A A System # I/ Name G KIA Topic(s) IR #

1 1 2 2 3 3 4 4 5 56 6 11 2 3 4 cc:

059A3.04 - Ability to monitor X automatic operation of the MFW, 2.5 1 including: Turbine driven feed pump ccccc 059 Main F Feedwater eedwater / 4 i' 059K3.02 - Knowledge of ofthe the effect that a loss or malfunction of the xX t<:

c.c,.c c

MFW will have on the following:

3.6 1 I~:l: EFW system I:

061K3.02 - Knowledge ofthe of the effect 0611 Auxiliary / of the that a loss or malfunction ofthe Emergency Feedwater / xX EFW will have on the following:

4.2 1 4 .c: S/G 062A2.16 - Ability to (a) predict the impacts ofofthe the following malfunctions or operations on the AC distribution system; and (b) 062 AC Electrical X based on those predictions, use 2.5 1

( Distribution / 6 procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Degraded system voltages 063A3.01 - Ability to monitor automatic operation ofofthe the dc 063 DC Electrical X electrical system, including: Meters, 2.7 1 Distribution / 6 annunciators, dials, recorders, and indicating lights I 064G2.4.45 - Ability to prioritize and I X interpret the significance of each 4.1 1 annunciator or alarm.

064 Emergency Diesel 064K4.01 - Knowledge ofED/G Generator / 6 Huenerlltor/6 design feature(s) system design feature( s) and/or and! or c c:

xX I interlock(s) which provide for the 3.8 1 following: Trips while loading the ED/G (frequency, voltage, speed) 073A4.03 - Ability to manually 073 Process Radiation operate and/or monitor in the control X room: Check source for operability 3.1 1 Monitoring / 7 demonstration

(

Page 10 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I/ Group 1 K K K K K K A System # I/ Name KIA Topic(s) IR #

1 2 3 4 5 6 1 076G2.4.8 - Knowledge of how Service Water / 4 abnormal operating procedures are 3.8 1 used in conjunction with EOPs.

078Kl.04 - Knowledge of ofthe the physical connections and/or cause-X effect relationships between the lAS 2.6 1 and the following systems: Cooling water to compressor 103A2.03 - Ability to (a) predict the ofthe impacts of the following malfunctions or operations on the reactor building system and (b) based on those predictions, use procedures 3.5 1 to correct, control, or mitigate the of those malfunctions consequences ofthose or operations: Phase A and B isolation

( 103Kl.0 1 - Knowledge of the 103Kl.Ol physical connections and/or cause-X effect relationships between the 3.6 1 reactor building system and the following systems: CCS A Category Totals 2 3 2 3 3 3 3 3 3 32 2 22 3 2 2 3 Group Point Total 28/5

(

Page 11 of 14 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx F:\NRC - 2009\Outiines\Written\RO ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 2 System # I Name KKKKKKA K K K K K K A IA A A i~j KIA Topic(s) IR #

1 2 3 4 5 6 1 , 3 4 1001 Control Rod Drive /

1 '"

1002 Reactor Coolant / 2 1&4 011 Pressurizer Level i:'

irontrol /2  ;:

[)':'::[,

!014 Rod Position 1'::(::::

ITnrlir.~tion / 1 'j; >

I:;; 015K3.01 - Knowledge ofthe effect 01510.01

!015 Nuclear X of the NIS that a loss or malfunction ofthe 3.9 1 IInstr 17

/7 I: ':

will have on the following: RPS I' 016A4.02 - Ability to manually

016 Non-nuclear IInstr Jl1 /7 X f::"/; operate and/or monitor in the control 2.7 1 I': room: Recorders o17K5.02 - Knowledge of the

( 017K5.02 operational implications of the 10177 In-core Temperature X following concepts as they apply to 3.7 1 IMonitor /7 the ITM system: Saturation and I : subcooling of water of the 027Kl.Ol - Knowledge ofthe 027K1.01 physical connections and/or cause-1027 Containment Iodine X effect relationships between the 3.4 1 I:

IRemoval / 5 ' .. i; CIRS and the following systems:

d.> CSS

'\, I;';:: 028A2.02 - Ability to (a) predict the I impacts of the following malfunctions or operations on the HRPS; and (b) based on those

l~: IX '.  :'

predictions, use procedures to correct, control or mitigate the 3.5 1 consequences of ofthose those malfunctions l;'~?

or operations: LOCA condition and

f  : .::

related concern over hydrogen 1029 029 Containment Purge /

8  :.,It I

(

Page 12 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401

I ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2

/

\ Plant Systems - Tier 2 I/ Group 2 K K K K K K A ~, A A System # I/ Name ,, system.

k': ,

035 Steam Generator I/ 4 ,:':.'

!'i:;,

I'; 041K6.03 - Knowledge oftheof the effect I,'

fi. of a loss or malfunction on the 041 Steam following will have on the Turbine Dump/Turbine Bypass X Bypass Valves: Controller and 2.7 1 Control / 4 positioners, including ICS, S/G, CRDS

(( 045 Main Turbine Generator I/ 4 055 Condenser Air Removal 14/4 056K1.03 - Knowledge of 056KI.03 ofthe the physical connections and/or cause-056 Condensate I/ 4 X effect relationships between the 2.6 1 Condensate System and the following systems: MFW 068K4.01 - Knowledge of design feature(s) and/or interlock(s) which provide for the following: Safety 068 Liquid Radwaste I/ 9 X and environmental precautions for 3.4 1 handling hot, acidic, and radioactive liquids 0711 Waste Gas Disposal

/99 072 Area Radiation Monitoring /7 IIMomtonng /7 0755 Circulating Water I/

( 8 ,,':

Page 13 of 14 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx 2,docx ES-401

I ES-401 RO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2

( Plant Systems - Tier 2 / Group 2 KKKKKKA K K K K K K A A A A System # / Name ,'G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 079 Station Air / 8 "

086 Fire Protection / 8 ,

KIA Category Totals 2 0 1 1 1 1 1 1. 0 1 I, Group Point Total 201 10/3

(

c(

Page 14 of 14 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx F:\NRC - 2009\Outiines\Written\RO ES-401

ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 RO Facility: Crystal River Unit #3 Date of Exam: SC;PlC;111Dc;1, 2009 KIA KJA# # Topic RO SRO-Only Category IR # IR #

Knowledge of shift or short-term reliefrelieftumover turnover 2.1.3 nractices 3.7 1

~owledge~fprocedrlres and 1 "" U1~Xl~~a *..

1.

2.1.36

,,~~.iZ':~~ f(P~ 2;1.35Y\i/") 1,:\;:,'. :,./' 3.0 1 Conduct of Operations Knowledge of refueling administrative 2.1.40 2.8 1 requirements.

Subtotal l' 3 ~]

fledge ofthe of the process for managing 2.2.20 trouhlp.~h()()timr activities. 2.6 1

2. Knowledge of conditions and limitations in the Equipment 2.2.38 facility license. 3.6 1 C Control

./1 Subtotal ) 2 2.3.11 Ability to control radiation releases. 3.8 1 Knowledge of radiological safety principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 1 responsibilities, access to locked high-radiation

3. areas, <IIi Pllins:r filters, etc.

Radiation Control Knowledge of radiation or contamination hazards 2.3.14 that may arise during normal, abnormal, or 3.4 1 C;1l1C;[gency conditions or activities.

['. f Subtotal !tilMky,lrr£w::tl ' **l, 3 iJlbYNl,.,~:illi!

Knowledge of how abnormal operating procedures 2.4.8 are used in conjunction

. . with EOPs. 3.8 1 4.

Knowledge oflocal auxiliary operator tasks during Emergency 2.4.35 3.8 1 an and the resultant vpc;rational effects.

Procedures /

Plan Subtotal  ;.~! .'l J~li]?; 2 J~~;~

Tier 3 Point Total !lool:l[ 10 i,:"; ... ;~I~;I 7 Page 1 of 2 F:\NRC - 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline - Generic (401-3) Rev l.docx ES-401

ES-401 Record of Rejected KlAs Form ES-40 1-4 ES-401-4

( RO Tierl Tier/ Randomly Reason for Rejection Group Selected KIA Not applicable to CR3. Containment fan coolers have no 111 OllEK3.04 01lEK3.04 dampers. Chief Examiner randomly selected new KA

1. OlIEK3.07.

1. OllEK3. 07.

Not possible to prepare a psychometrically sound question related 111 1/1 022AKl.02 022AK1.02 to this KA. High delta P, more flow. Low delta P, less flow.

Chief Examiner randomly selected new KA#022AKl.03.

KA#022AK1.03.

No IR value assigned in NUREG-1122. Chief Examiner 111 055EK2.04 OSSEK2.04 randomly selected new KA #055EK3.02.

1. OSSEK3.02.

Not possible to prepare a psychometrically sound question related 112 1/2 001AA2.02 OOlAA2.02 to this KA. Chief Examiner randomly selected new KA

1. OOlAA2.05.

1. 00lAA2.0S.

Not applicable to CR3. Our ECCS system has no water level input for automatic operation and no manual operator actions 211 006KS.01 006K5.01 based on water level. Chief Examiner randomly selected new KA#OO6K5.04.

KA #006KS.04.

Not possible to prepare a psychometrically sound question related 2/1 211 103A2.0S 103A2.05 to this KA. Chief Examiner randomly selected new KA

1. 103A2.03.

IR value only 2.2 for ROs. Chief Examiner randomly selected Generic 2.1.35 2.1.3S new KA #G2.l.36.

1. G2.1.36.

Not applicable to CR3. CR3 does not have "first-out" alarm 111 007EA2.0S 007EA2.05 indications for a reactor trip. Chief Examiner randomly selected

( #007EA2.02.

new KA #OO7EA2.02.

Not applicable to CR3. CR3 does not have SWIRW SW/RW flow control 111 056AA1.28 OS6AA1.28 valves. Chief Examiner randomly selected new KA

1. 056AAl.05.

1. OS6AA 1.OS.

At CR3 actions for this KA are SRO only level knowledge.

2/2 028A2.03 Chief Examiner randomly selected new KA #028A2.02.

(

Page 1 of 1F:\NRC IF:\NRC - 2009\Outiines\Written\RO 2009\Outlines\Written\RO NRC 2K9 Written Exam Outline - Rejected KAs (401-4) Rev 2.docxES-401

ES-401 SRO - PWR Examination Outline - (Sept, 2009) Form ES-401-2 f

DRAFT FT Facility: Crystal River Unit #3 Date of Exam: September, 2009 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL I1 2 3 4 5 6 1 2 3 4

• 1 18 3 3 6 L

I.

Emergency

& Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier 27 5 5 10 Totals 1 28 3 2 5 2.

Plant 2 10 2 1 3 Systems Tier 38 5 3 8 Totals

3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 2 2 1 2 Note: LI. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only ofthe outlines (i.e., except for one category in Tier 3 of 'Tier Totals" in each KIA category shall not be the SRO-only outline, the "Tier 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 +/- I 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 that are not included on the outline of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

should be added. Refer to Section D.I.b ofES-401

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 KJKlAs As having an importance rating (IR) of2.5 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 I and 2 from the shaded systems and KJ KIAA categories.

7*

7.* The generic (G) KIAs in Tiers 1 I 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.l.b of ES-401 for the applicable KI As.

ofES-401

8. On the following pages, enter the KJKIAA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the and the point totals (#) for each system and category. Enter the group and tier totals for each applicable license level, "and 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. KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#)

For Tier 3, select topics from Section 2 of the KJA on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

R FT Page 1 of10of 10 2009\Outlines\Written\SRO F:\NRC - 2009\Outlines\ Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.docx l.docx ES-401

I ES-401 SRO Form ES-401-2 I

, ES-401 PWR Examination Outline Form ES-401-2

( Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 E/APE # I Name I K K K A 'A . .

G KIA Topic(s) IR #

Safety Function 1 2 3 1 *2 . *.

007 (BW1E02 (BW/E02 & ElO)EI0)

Reactor Trip - Stabilization

- Recovery - 1 ,.,

j 008 Pressurizer Vapor Space Accident 1 3 1.\;

009 Small Break LOCA 1 3

(*0 .

011 Large Break LOCA 1 3 I i",j{ .....*.

1',"/ ....\ .... ::...

015/17 RCP Malfunctions 14

...... .' 022AA2.01 - Ability to determine and interpret the following as they apply to 022 Loss ofRx Coolant Makeup 1 2 X the Loss of Reactor Coolant Pump 3.8 1 Makeup: Whether makeup line leak exists

( 025 Loss ofRHR System 1 4 026 Loss of Component Cooling Water 18 18 AG2A.9 - Knowledge of low power 1 027 AG2.4.9 027 PZR Pres~ure PresSure Control shutdown implications in accident (e.g.

System Malfunction 1 3 X LOCA or loss ofDH) mitigation 4.2 1 strategies.

029 ATWS 1 111 038 Steam Generator Tube . ,

Rupture 1 3 040 (BW IE05) Steam Line (BW/E05)  :,':;:/,'

Rupture - Excessive Heat Transfer 1 4 054 Loss of Main Feedwater

" **1'"

14 055 Station Blackout 1 6

(

Page 2 oflO of 10 F:\NRC - 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401

I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2

( Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 E/APE # I Name I K K K A A  ::,'"

Safety Function 1 2 3 1 2 G KIA Topic(s) IR #

056AG2.4.45 - Ability to prioritize and Offsite Power 1/

056 Loss of Offsite 6

interpret the significance of each 4.3 1 i< annunciator or alarm.

"i

'(.;1; ii:'. 057 AA2.05 - Ability to determine and 057 Loss of Vital AC interpret the following as they apply to Instrument Bus 1/ 6 the Loss of Vital AC Instrument Bus:

3.8 1 S/G pressure and level meters

./

'.. k.)

058 Loss of DC Power 16 /6

"'. :i:

062 Loss of Nuclear Services Water 1/ 4 i

065AA2.04 - Ability to determine and interpret the following as they apply to 065 Loss ofInstrument Air 1/ **X 8

of Instrument Air: Typical the Loss ofInstrument 2.7 1 conditions which could cause a compressor trip (e.g., high temperature)

( .ii BW/E04 Inadequate Heat Transfer -~ Loss of Secondary Heat Sink 1/ 4 077 Generator Voltage and 077AG2.2.12 - Knowledge of Electric Grid Disturbances 1/

6

x surveillance procedures.

4.1 1 KIA Category Totals 3, .3 Group roup Point Total 18/6

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I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I K K K A A KKK G KIA Topic(s) IR #

Safety Function 11 2 2 3 3 1 2 001 Continuous Rod Withdrawal / 1 003 Dropped Control Rod / 1 005 Inoperable/Stuck Rod /

1 r'

024 Emergency Boration / 1  ;\

028 PZR Level Malfunction

/2 032 Loss of Source Range NIl 7 033 Loss ofIntermediate RangeNI/7 Range NI / 7

(

036 (BW/A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak /3 Leak/3 051 Loss of Condenser i

Vacuum / 4 Vacuum/4 059 Accidental Liquid RadWaste ReI. //99 060 Accidental Gaseous Radwaste ReI. / 9 11!!I~i! lllli!);'!

061AA2.06 - Ability to determine and interpret the following as they apply to X the Area Radiation Monitoring (ARM) 4.1 1 LI, System Alarms: Required actions if alarm channel is out of service

( 067 Plant Fire On-site / 8 Page 4 of 10 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev 1.docx F:\NRC - 2009\Outiines\Written\SRO l.docx ES-401

I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE #/Namel# I Name I KKK K K K A A i' G KIA Topic(s) IR

,i Safety Function 11 2 2 3 3 1 2*

(BW/A06) 068 (BW /A06) Control Room Evac. I/ 8 069 Loss of CTMT Integrity 069AG2.2.38 - Knowledge of conditions X and limitations in the facility license. 4.5 1

/5 15 074 Inad. Core Cooling 1 I4 "

076 High Reactor Coolant Activity 1 I9

~i~: I i '.

,)"

BWI AO 1 Plant Runback 11 BW/AOI I 1 BW/A02&A03 Loss ofNNI- BW/A03AG2.4.6 - Knowledge ofEOP X mitigation strategies. 4.7 1 XIY 17 XfY /7 ,

(

( BW1 I A04 Turbine Trip 1 144 1A05 Emergency Diesel BW/A05 BW Actuation 1I 6 BW1 I A07 Flooding 1 I8 BW1E03 IE03 Inadequate Sub cooling Margin 1 Subcooling I4 IE08 LOCA Cooldown -

BW1E08 Depress. 14 I4 BW/E09 BW IE09 Natural Circ. 14 BW1E09EA2.2

/E09EA2.2 - Ability to determine I' and interpret the following as they apply to the (Natural Circulation Cooldown):

X Adherence to appropriate procedures and 4.0 1 operation within the limitations in the facility's license and amendments.

I KIA

£Vi-\. Category

,-,<negory Totals 2 2 Group Point Total uroULP 9/4 Page 5 of 10 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx F:\NRC - 2009\Outiines\Written\SRO I.docx ES-401

I ES-401 SRO Form ES-401-2 I I

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

( Plant Systems - Tier 2 / Group 1 a-KKKKKKA K K K K K K A :A A A System # / Name KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump/4 14 004 Chemical and V olume Control / 1 & 2 005A2.Ol - Ability to (a) predict the 005A2.01 impacts of the following malfunctions

'.' i\l: or operations on the Decay Heat

~C:l; System, and (b) based on those predictions, use procedures to correct, 005 Residual Heat Removal/4 X . control, or mitigate the consequences 2.9 1 ofthose of those malfunctions or operations:

Failure modes for pressure, flow,

,,'I pump motor amps, motor temperature, and tank level instrumentation 006 Emergency Core

(( Cooling /2 & 3 i,

007 PZR Relief/Quench "

Tank/5 008 Component Cooling Water /8 008 Component Cooling Water /8 01 0 Pressurizer Pressure Control / 3 ,.!

~c

,....'i:)

~

012G2.2.12 - Knowledge of 12 Reactor Protection 1/

012 X surveillance procedures. 4.1 1 7

013 Engineered Safety I.{'I:

Features Actuation /2

(

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I ES-401 SRO Form ES-401-2 I I ES-401 PWR Examination Outline Form ES-401-2

( Plant Systems - Tier 2 I/ Group 1 KK KK K K K K K K K K A A A A System # I/ Name ,G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 022 Containment Cooling /5 1026 Containment Spray /

15 039G2.4.20 - Knowledge ofthe of the 039 Main and Reheat X operational implications ofEOP 4.3 1 Steam/4 warnings, cautions, and notes.

059 Main Feedwater / 4 ..

0611 Auxiliary /

IElueI*gelilCY El1l\AgCUC: F eedwater /

Feedwater 4

( ~?! F' "sfi 062A2.01 - Ability to (a) predict the impacts ofthe following malfunctions or operations on the

()~~;A AC distribution system; and (b) based on those predictions, use X procedures to correct, control, or 3.9 1

2 mitigate the consequences of ofthose those

/ti! malfunctions or operations

Types of

\,~'~,

loads that, if de-energized, would degrade or hinder plant operation 063 DC Electrical Distribution / 6 064 Emergency Diesel Generator / 6 073 Process Radiation Monitoring / 7 l

Page 7 of 10 F:\NRC - 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401

I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 K K K K K K A <it\;2\ A A KKKKKKA System # / Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 .;2 3 4 123

't* 076A2.01 - Ability to (a) predict the 076A2.0l impacts of the following malfunctions or operations on the RWS; and (b) based on those 076 Service Water /4

/4 X predictions, use procedures to 3.7 1 correct, control, or mitigate the consequences of those malfunctions or operations: Loss of RWS

\i 078 Instrument Air / 8 103 Containment / 5 ~ ;i

<Ii:

KIA A Category Totals 1 2 Group Point Total 28/5

(

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I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 K K K K K K A A A A KKKKKKA System # / Name 1 234 2 3 4 5 6 1 2 3 4 Y KIA Topic(s) IR #

1001 Control Rod Drive / Ie 1 1"

',', 002A2.02 - Ability to (a) predict the

,'\

.'f! impacts of the following ofthe Ir malfunctions or operations on the RCS; and (b) based on those X predictions, use procedures to 4.4 1 correct, control or mitigate the consequences of those malfunctions i,', or operations: Loss of coolant i'k I, pressure I;:. 1*<',;':,.

1011 Pressurizer Level \'  !,

Control/2 014G2.1.27 - Knowledge of system Ol4G2.1.27 0144 Rod Position Inrlic:ation 11 UlncllcatlOn /1 Ix purpose and / or function. 4.0 1 015 Nuclear

( InstrUlYlpntMion

~Ins1trumlenta.tion //77 016 Non-nuclear Instmmentation / 7 017 In-core Temperature Monitor / 7 027 Containment Iodine Removal/5 028 Hydrogen 1\

R and Purge

'Control / 5  ::.  :, '

029 Containment Purge /

!y; .. ':

8 033 Spent Fuel Pool ir oolino /8

>0 Page 9 of 10 J.docx F:\NRC - 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401

I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 /I Group 2 KKKKKKA K K K K K K A A A A System # I/ Name KIA Topic(s) IR #

123 1 2 3 456 4 5 6 1 2 3 4 I,f;;

034A2.01 - Ability to (a) predict the

,<. impacts of the following ofthe

.. malfunctions or operations on the Fuel Handling System; and (b) based

• i

',' X on those predictions, use procedures 4.4 1 frOl i!' to correct, control or mitigate the r~JI¢ consequences of those malfunctions

" lir/," ,:. or operations: Dropped fuel element 0: 5 Steam Generator / 4 041 Steam ,>

Dump/Turbine Bypass  ;',

Control / 4 .,;, . ....,.

045 Main Turbine Generator / 4 055 Condenser Air iRemoval / 4

(

!056 Condensate / 4 068 Liquid Radwaste / 9 071 Waste Gas Disposal 1/9 072 Area Radiation IMoniLuring / 7 0755 Circulating Water /

8 0799 Station Air / 8 I,

10866 Fire Protection / 8 A Category

~

ory Totals 2 '1 Group Point Total 10/3

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ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 SRO Facility: Crystal River Unit #3 Date of Exam: SCOPLC011lUC01,2009 2009 RO sRO-Only Category KIA #

KJA# Topic IR # IR #

Ability to use procedures related to shift staffing, 2.1.5 such as minimum crew complement, overtime 3.9 1 limitMiom etc.

1. Ability to coordinate personnel activities outside Conduct of 2.1.8 the control room. 4.1 1 Operations Subtotal 111°. 11:i 2 Ability to determine operability and/or andJor availability 2.2.37 of safety related equipment. 4.6 1

2. Knowledge of the process used to track inoperable Equipment 2.2.43 alarms. 3.3 1 Control

( Subtotal .J'H;:j~rii~ jf:t;*ii 2 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable 2.3.15 survey instruments, personnel monitoring 3.1 1 3.

Radiation equil'1l1COIlL, etc.

Control

.. ':, i ":~~:

Subtotal 1 2.4.3 Ability to identify post-accident instrumentation. 3.9 1 4.

Emergency 2.4.29 Knowledge of the emergency plan.

ofthe 4.4 1 Procedures /

Plan II Tier 3 Point Total Subtotal eI,Th\fi/",,,,,:c;'iiiUYbW.i!!!

i.l! 10

J.l.,])

e:;::i~~~;1F"iliiiil 2

7

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Page 11 of 1F:\NRC IF:\NRC - 2009\Outiines\Written\SRO 2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline - Generic (401-3) Rev O.docx ES-401

ES-401 ES-40l Record of Rejected KJAs Form Fonn ES-401-4 ES-40l-4

./ SRO Tierl Tier! Randomly Reason for Rejection Group Selected KJA Not possible to prepare a psychometrically sound 1/2 112 06lAA2.02 061AA2.02 question related to this KA. Chief Examiner randomly selected new KA #061AA2.06.

1. 06lAA2.06.

Not possible to prepare a psychometrically sound 211 062A2.14 062A2.l4 question related to this KA. Chief Examiner randomly

1. 062A2.0 1.

selected new KA #062A2.0l.

Not applicable to CR3. Containment iodine removal is accomplished via the RB Spray system. There are 2/2 027A2.01 NO filters associated with this system. Chief Examiner randomly selected new KA #034A2.01.

Not applicable to CR3. No hydrogen recombiner or 2/2 028A2.01 hydrogen recombining equipment at CR3. Chief Examiner randomly selected new KA #OO2A2.02.

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Page 1 of 1IF:\NRC F:\NRC -2009\Outiines\Written\SRO

-2009\Outlines\Written\SRO NRC 2K9 Written Exam Outline -Rejected KAs (401-4) Rev 1.docxES-40 l.docxES-40 1

ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 ES-30l-l Facility: Crystal River Unit #3 Date of Exam: 08/31109 thm 09118/09 Examination Level: RO ~ SRO ~ Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (See Note) Code*

SRO Only - (COl) - Determine actions for primary to secondary leakage.

Conduct of Operations D,R KIA - G2.1.25 SRO 4.2 4~2 CP-l52 CP-152 RO && SRO - (C02) - Perform a time to boil 1 core uncovery boil/core calculation.

Conduct of Operations M,R KIA - G2.1.23 RO 4.3 SRO 4.4 OP-l03H OP-I03H RO & SRO - (ECl) (EC 1) - Perform a monthly NI Imbalance Comparison.

KIA - G2.2.12 RO 3.7 SRO 4.1 Equipment Control D,R SRO Only - After completing the Imbalance Comparison

( determine required ITS actions, if any.

KIA - G2.2.40 SRO 4.7 SP-3l2B SP-312B RO & SRO - (RCI) (RC l) - Calculate the maximum permissiblepennissible D,M,P, D, M, P, stay time with an Emergency Event in progress.

Radiation Control R KIA - G2.3.4 RO 3.2 SRO 3.7 EM-202 RO & SRO - (EPl) (EP l) - Complete the State of Florida Notification Message form for Nuclear Power Plants and Emergency Procedures D, S make required notifications.

1 Plan KIA - 2.4.43 RO 3.2 SRO 3.8 EM-202 All items (5 total) are required for SROs. RO applicants require only 4 items unless Note:

they are retaking only the administrative topics, when all 5 are required.

(C)ontrol room, (S)imulator or Class(R)oom (D)irect from bank (:::(~3 ROs; ~ 4 for SROs &

3 for ROs;::: & RO retakes)

• Type Codes & Criteria:

(N)ew or (M)odified from bank ( 2: 1) l)

(P)revious 2 exams ( :::1;~l; randomly selected)

\I

\

Page 1 of 1 F:\NRC - 2009\Outlines\JPM\NRC 2009\OutlinesIJPM\NRC 2009 Fonn ES-30J-J (JPM Admin Outline) Rev O.docx ES-30l ES-301

ES-301, Rev. 9, Supp. 1 Control Room 1 In-Plant Systems Outline Form ES-301-2 Fonn Facility: Crystal River Unit #3 Date of Exam: 08/31/09 thm thru 09118109 09/18/09 Exam Level: RO [g] ~ SRO-I [g] ~ SRO-U [g] ~ Operating Test Number: 1 Control Room systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1J ESF)

Type Safety System I1 JPM Title Code* Function

a. CA - Perform an RCS Boration A,D,S 1I KIA - 024AA2.04 RO 3.4 SRO 4.2 (EOP-2) [RO, SRO-I]

fRO,

b. CVCS - Restore PZR level during OTSG tube rupture A,D,P,S 2 KlA- 006A4.02 RO 4.0 SRO 3.8 (EOP-6) SRO-I]

[RO. SRO-IJ

c. RCS - Respond to a stuck open PZR spray valve [SRO-U] A,D,L,P, 3

KlA-KIA - 002A4.01 RO 4.2 SRO 4.4 (AP-S20) (AP-520) [RO, SRO-I}

[RO,SRO-I1 S

d. S/GS - Establish EFW flow to raise OTSG level D.S D. S 4

KlA-KIA - E03EA1.3 RO 3.6 SRO 3.8 (EOP-3) [RO. SRO-I}

[RO.SRO-I] Primary

e. MSS - Perform actions for a stuck open MSSV [SRO-U]

D,P,S 4

KIA - 039A2.04 RO 3.4 SRO 3.7 (EOP-2) [RO. SRO-I]

SRO-I1 Secondary

f. CCS - Ensure proper alignment ofES of ES equipment [SRO-U]

A,EN,N, S 5 S

KIA KlA-- 022A4.01 RO 3.6 SRO 3.6 (EOP-2) [RO. SRO-I]

SRO-I1

g. AC - Energize a dead bus D,S 6 KIA - 062A2.0S RO KlA-062A2.05 2.9 SRO R02.9 SR03.33.3 (AP-770) [RO]

h. ES - Respond to an invalid ES Actuation A,D,EN, A,D,EN,S S 8 KIA - 008A3.08 008A3 .08 RO 3.6 SRO 3.7 (AP-340) [RO,SRO-Ij fRO, SRO-I]

( II:1 SPARE MU - Restart a MUP following an RCS leak isolation KIA - 002A2.01 RO 4.3 SRO 4.4 (AP-S20) (AP-520)

D,S 2 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 1.

l. PPcs - Depressurize the RCS using HP Aux. Spray (SRO-U/

rSRO-Uj D,E,R 3 KlA-E14EAl.l KlA-EI4EAl.l R03.8 SR03.6 (EOP-14,Enc.13) SRO-Ij

[RO. SRO-IJ j.

J. DHR - Establish DHR from outside control room 4 E,L,N,R KIA - A06AAl.l RO 4.3 SRO 4.2 (AP-990) [RO, IRO, SRO-IJ SRO-l) Primary

k. AC - Transfer vital bus to normal power supply [SRO-Uj rSRO-U]

D 6 KIA KlA- - 062A3.04 RO 2.7 SRO 2.9 (OP-703) [RO, SRO-I]

SRO-I1 SPARE FS/OTSG - Transfer excess secondary inventory to FST D,E 3,8 KlA-038EK3.06 KIA - 038EK3.06 R04.2 RO 4.2 SR04.S SRO 4.5 (EOP-14,Enc.

(EOP-14, Enc. 9)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety

@ functions; all S 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I1 SRO-I I1 SRO-U (A)ltemate path 4-6 14-6 I 4-6 I1 2-3 (C)ontrol room (D)irect from bank :s9/:s8/:S4

.::::9/.::::8/.::::4 (E)mergency or abnormal in-plant (EN)gineered safety feature ORAlRA'~Itrol ~T (cItro I room system)

~1I~1/~1

~1/~1/~1

- 1I - I1~ 1I (L)ow Power I1 Shutdown (L)ow ~1/~1/~1

~l/~l/~l (N)ew or (M)odified from bank including 1I (A) ~2/~2/~1 (P)revious 2 exams :S3/:S3/:S2

3/.::::31::::2

( (R)CA (randomly selected) ~1/~1/~1

~l/~l/~l (S)imulator Page 1 of 1F:\NRC - 2009\Outiines\JPM\NRC 2009\Outlines\JPM\NRC 2009 Form ES-301-2 (JPM MCR-Plant Outline) Rev. I.docx ES-30 1