ML093270132
| 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~ ____ _
DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:
4raft Written Exam sample plan (ES-401-1/2)
@>>raft Administrative Topics Outline (ES-301-1) 0' Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301~2)
Location of Electronic Files:
Submitted By: ~"""I-"<+''''"''F--fI-~~~-'---- Verified.By __
I\\..L.f~_-----:-__
FACILITY NAME:
Crystal River 3 Section 1 REPORTNUMBER: ____ ~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) o Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2)
Location of Electronic Files:
Submitted B y: 7--~"""-'"'"""F-f;L...b'-'-f-+-4~"-"-'--- verifiedBy __
F\\~*i~~
(
(
ES-401 Facility:
Tier
- 1.
Emergency
& Abnormal Plant Evolutions
- 2.
Plant Systems RO - PWR EX1Iuination O,utline - (Sept, 2009)
Form ES-401-2 Crystal River Unit #3 Group 1
2 Tier Totals 1
2 Tier Totals RO KIA Category Points K K 1
2 K K 3
4 324 2
5 3
5 K K A 561 3
N/A A
2 3
2 4
5 A
3 A
4 N/A G
3 2
5 2
3 3
3 3 223 223 2
0 1
1 1
1 1 101 1 4
3 444 3 34234 September, 2009 SRO-Only Points TOTAL A2 G*
TOTAL 18 6
9 4
27 10 28 5
10 3
38 8
- 3. Generic Knowledge and Abilities Categories 1
3 2
3 2
3 4
1 2
3 4
10 7
2 Note:
I.
- 2.
- 3.
- 4.
- 5.
- 6.
7*
- 8.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the 'Tier Totals" in each KIA category shall not be less than two).
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.
Systems/evolutions within each group 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.1.b of ES-40 1 for guidance regarding the elimination of inappropriate KIA statements.
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.
Absent a plant-specific priority, only those KI 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
The generic (G) KI As in Tiers 1 and 2 shall be selected from Section 2 ofthe 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.
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 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 f
\\
(
(
ES-401 R 0 - PWR Ex~mination outline - (Sept, 2009)
Form ES-401-2
~;-~
.~,"AFT t;,\\,":
~
\\.
k*
Facility:
Crystal River Unit #3 Date of Exam:
September, 2009 RO KJ A Category Points SRO-Only Points Tier Group K K K K K K A A A A G 4
TOTAL A2 G*
TOTAL 1 2 3
5 6
1 2 3
4 1
3 2
4 3
3 3
18 6
L Emergency 2
2 1
1 1
2 2
9 4
& Abnormal N/A N/A Plant Tier Evolutions 5
3 5
4 5
5 27 10 Totals 1
2 3
3 3
3 2
2 3
2 2
3 28 5
- 2.
2 2
0 1
1 1
1 1
1 0
1 1
10 3
Plant Systems Tier Totals 4
3 4
4 4
3 3
4 2
3 4
38 8
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 Abilities Categories 10 7
3 2
3 2
Note:
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 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 +/- 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 me 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. Lb of ES-40 I 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 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 KIA categories.
7*
The generic (G) KlAs in Tiers 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. I.b of ES-40 I for the applicable KI As.
- 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 of14 F:INRC - 200910utlineslWrittenIRO 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 Safety Function KKK A 123 1 KIA Topic(s) 007EA2.02 - Ability to determine or interpret the following as they apply to a IR reactor trip: Proper actions to be taken if 4.3 1
008 Pressurizer Vapor Space Accident 13 009 Small Break LOCA I 3 X
015117 RCP Malfunctions 14 X
X 025 Loss ofRHR System I 4 X
the automatic safety functions have not taken place 008AG2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
009EK2.03 - Knowledge of the 4.3 interrelations between the small break 3.0 LOCA and the S/Gs.
O1IEK3.07 - Knowledge of the reasons for the following responses as they apply to the Large Break LOCA: Stopping 3.5 HPI bypass flow (recirc flow OK per GL) 015/017AK1.05 -Knowledge of the operational implications of the following concepts as they apply to RCP malfunction (Loss ofRC Flow): Effects 2.7 of unbalanced RCS flow on in-core average temperature, core imbalance, and quadrant power tilt.
022AK1.03 - Knowledge of the operational implications of the following concepts as they apply to Loss of 3.0 Reactor Coolant Makeup: Relationship between makeup flow and PZR level 025AA2.01 - Ability to determine and interpret the following as they apply to the Loss of Decay Heat Removal
2.7 System
Proper amperage of running LPI/decay heat removallRHR pump(s)
Page 2 of14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1
1 1
1 1
1 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
A }\\ G KIA Topic(s)
IR Safety Function 1
2 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 00SAG2.1.23 - Ability to perform OOS Pressurizer Vapor Space specific system and integrated plant 4.3 1
Accident 13 procedures during all modes of plant operation.
009EK2.03 - Knowledge of the 009 Small Break LOCA 1 3 X
interrelations between the small break 3.0 1
LOCA and the S/Gs.
011 EK3.07 - Knowledge ofthe 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) 015/0 17AK 1. 05 -Knowledge of the operational implications ofthe following 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 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 4 the Loss of Decay Heat Removal 2.7 1
System: Proper amperage of running LPl/decay heat removal/RHR pump(s)
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 Safety Function 026 Loss of Component Cooling Water /8 027 PZR Pressure Control System Malfunction / 3 029 ATWS /1 038 Steam Generator Tube Rupture / 3 040 (BW 1E05) Steam Line Rupture - Excessive Heat Transfer / 4 054 Loss of Main Feedwater
/4 K K 1
2 K
A 3
1 x
x x
x KIA Topic(s) 026AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Services / Decay Heat Closed Cycle Cooling: The automatic actions (alignments) within the SWS / DCS resulting from the actuation of the ESFAS 027AK3.04 - Knowledge of the reasons for the following responses as they apply to the PZR Pressure Control Malfunctions: Why, ifPZR level is lost and then restored, that pressure recovers much more slowly.
029EA1.12 - Ability to operate and monitor the following as they apply to an ATWS: Reactor trip breakers 038EG2.1.28 - Knowledge ofthe purpose and function of major system components and controls.
054AAl.Ol - Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater (MFW):
EFW controls, including the use of alternate EFW sources 055EK3.02 - Knowledge of the reasons for the following responses as they apply IR 3.6 2.8 4.1 4.1 4.5 x
to the Station Blackout: Actions 4.3 Page 3 of 14 x
contained in EOP for loss of offsite and onsite power.
056AAl.05 - Ability to operate and / or monitor the following as they apply to the Loss of Off site Power: Initiation (manual) of safety injection process F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx 3.8 ES-401 1
1 1
1 1
1 1
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
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 026 Loss of Component to the Loss of Nuclear Services / Decay X
Heat Closed Cycle Cooling: The 3.6 1
Cooling Water /8 automatic actions (alignments) within the SWS / DCS resulting from the actuation of the ESFAS 027AK3.04 - Knowledge ofthe reasons for the following responses as they apply 027 PZR Pressure Control X
to the PZR Pressure Control 2.8 1
System Malfunction / 3 Malfunctions: Why, ifPZR level is lost and then restored, that pressure recovers much more slowly.
029EA1.12 - Ability to operate and 029 ATWS /1 X
monitor the following as they apply to an 4.1 1
ATWS: Reactor trip breakers
(
038 Steam Generator Tube 038EG2.1.28 - Knowledge ofthe X
purpose and function of major system 4.1 1
Rupture / 3 components and controls.
040 (BWIE05) Steam Line Rupture - Excessive Heat Transfer / 4 054AA1.01 - Ability to operate and / or 054 Loss of Main Feedwater monitor the following as they apply to
/4 X
the Loss of Main Feedwater (MFW):
4.5 1
EFW controls, including the use of alternate EFW sources 055EK3.02 - Knowledge ofthe reasons for the following responses as they apply X
to the Station Blackout: Actions 4.3 1
contained in EOP for loss of offsite and onsite power.
056AA1.05 - Ability to operate and / or X
monitor the following as they apply to 3.8 1
the Loss of Offsite Power: Initiation (manual) of safety injection process
(
Page 3 of 14 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 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 KIA Topic(s)
IR Safety Function 1
2 3
1 057 Loss of Vital AC Instrument Bus / 6 058AKl.Ol - Knowledge of the operational implications ofthe following 058 Loss of DC Power /6 X
concepts as they apply to Loss of DC 2.8 1
Power: Battery charger equipment and instrumentation 062 Loss of Nuclear Services Water / 4 065 Loss ofInstrument Air /
065AG2.4.8 - Knowledge of how 8
abnormal operating procedures are used 3.8 1
in conjunction with EOPs.
BWIE04EA2.1 - Ability to determine BW 1E04 Inadequate Heat and interpret the following as they apply
(
Transfer - Loss of to the (Inadequate Heat Transfer):
3.2 1
Secondary Heat Sink / 4 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
077 Generator Voltage and 077 AK2.03 - Knowledge of the Electric Grid Disturbances /
X interrelations between Generator Voltage 3.0 1
6 and Electric Grid disturbances and the following: Sensors, detectors, indicators.
KIA Category Totals 3 243 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 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
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 I~! :'
operational implications of the following 058 Loss of DC Power 1 6 X
concepts as they apply to Loss of DC 2.8 1
Power: Battery charger equipment and instrumentation 062 Loss ofNuc1ear hi* ;:1'(
Services Water 1 4
- I, I;
- ;*:',: ** <, 065AG2.4.8 - Knowledge of how 065 Loss of Instrument Air 1 I*
. x. abnormal operating procedures are used 3.8 1
8 I,' *.,;
in conjunction with EOPs.
BW/E04EA2.1 - Ability to determine BW 1E04 Inadequate Heat and interpret the following as they apply Transfer - Loss of X
to the (Inadequate Heat Transfer):
3.2 1
Secondary Heat Sink 1 4 Facility conditions and selection of appropriate procedures during abnormal I:
and emergency operations.
077 Generator Voltage and 077 AK2.03 - Knowledge of the Electric Grid Disturbances 1 X
interrelations between Generator Voltage 3.0 1
6 and Electric Grid disturbances and the following: Sensors, detectors, indicators.
KIA Category Totals 3
2 4
3 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 Form ES-401-21 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I Safety Function 003 Dropped Control Rod / 1 005 Inoperable/Stuck Rod /
1 024 Emergency Boration / 1 028 PZR Level Malfunction
/2 032 Loss of Source Range NI/7 033 Loss ofIntermediate Range NI/ 7 036 (BW / A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak/3 051 Loss of Condenser Vacuum/4 059 Accidental Liquid RadWaste ReI. / 9 060 Accidental Gaseous Radwaste ReI. / 9 K K 1
2 X
K A KIA Topic(s) 3 1
001AA2.05 - Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal:
Uncontrolled rod withdrawal from available indications 003AK.1.10 - Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod: Definitions of core quadrant power tilt 005AK.3.05 - Knowledge of the reasons X
for the following responses as they apply to the Inoperable / Stuck Control Rod:
Power limits on rod misalignment Page 5 of14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx IR 4.4 1
2.6 1
3.4 1
ES-401 I 1
(
(
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 A
A G
KIA Topic(s)
IR Safety Function 1
2 3
1
~
~~r u6ts Rbd I,',
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,'
'/",::11 fi~,
'i:i.
.:; available indications 003 Dropped Control Rod / 1
.:;:i f~,'
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 /
- 'f;, 005AK3.05 - Knowledge of the reasons 1
X for the following responses as they apply 3.4 1
to the Inoperable / Stuck Control Rod:
Power limits on rod misalignment 024 Emergency Boration / 1 028 PZR Level Malfunction
/2 032 Loss of Source Range NI17 033 Loss oflntermediate
',:,/
Range NI / 7 036 (BW/A08) Fuel Handling Accident / 8 03 7 Steam Generator Tube Leak /3 051 Loss of Condenser Vacuum/4 059 Accidental Liquid
',:fiP',
RadWaste Rel. / 9 060 Accidental Gaseous Radwaste Rel. / 9 Page 5 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 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I Safety Function 061 ARM System Alarms I 7 067 Plant Fire On-site I 8 068 (BW/A06) Control Room Evac. I 8 069 Loss of CTMT Integrity 15 074 Inad. Core Cooling I 4 076 High Reactor Coolant Activity I 9 BW/AOl Plant Runback 11 BW/A02&A03 Loss ofNNI-XIY /7 BW/A04 Turbine Trip 14 BW/A05 Emergency Diesel Actuation I 6 BW I A07 Flooding I 8 K K 1
2 x
x K A 3
1 KIA Topic(s) 061AG2.2.12 - Knowledge of surveillance procedures.
BW I A06AK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Shutdown IR 3.7 Outside Control Room): Annunciators 3.4 and conditions indicating signals, and remedial actions associated with the (Shutdown Outside Control Room).
074EA2.03 - Ability to determine or interpret the following as they apply to a Inadequate Core Cooling: Availability of turbine bypass valves for cooldown BW/A02AG2.2.12 - Knowledge of surveillance procedures. (Loss of NNI-X while performing an SP OK per GL)
BW/A07AK2.l - Knowledge of the interrelations between the (Flooding) and the following: Components, and 3.8 3.7 functions of control and safety systems, 3.7 including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
Page 6 of14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1
1 1
1 1
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 2 E/APE # I Name I K
K K
A A Safety Function 1
2 3
1 2 G
KIA Topic(s)
IR 061 ARM System Alarms I 7 X
061AG2.2.12 - Knowledge of 3.7 1
surveillance procedures.
067 Plant Fire On-site I 8 068 (BW/A06) Control BW/A06AK1.3 - Knowledge of the Room Evac. I 8 operational implications of the following concepts as they apply to the (Shutdown X
Outside Control Room): Annunciators 3.4 1
and conditions indicating signals, and remedial actions associated with the
-j, I'
.":~ (Shutdown Outside Control Room).
1'_,
069 Loss of CTMT Integrity 15 074 Inad. Core Cooling I 4 074EA2.03 - Ability to determine or X
interpret the following as they apply to a 3.8 1
Inadequate Core Cooling: Availability of turbine bypass valves for cooldown 076 High Reactor Coolant Activity I 9 BW/A01 Plant Runback 11 BW/A02&A03 Loss ofNNI-BW/A02AG2.2.12 - Knowledge of XN!7 x:
surveillance procedures. (Loss of NNI-3.7 1
X while performing an SP OK per GL)
BW/A04 Turbine Trip I 4 BW/A05 Emergency Diesel Actuation I 6 BW I A07 Flooding I 8 BW/A07AK2.1 - Knowledge of the interrelations between the (Flooding) and the following: Components, and X
functions of control and safety systems, 3.7 1
including instrumentation, signals,
.. interlocks, failure modes, and automatic and manual features.
(
Page 6 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 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 E/APE # I Name I Safety Function BW IE03 Inadequate Subcooling Margin / 4 BW IE08 LOCA Cooldown -
Depress. /4 BWlE09 Natural Circ. / 4 BWIE13&E14 EOP Rules and Enclosures KIA Category Totals K K K A 1
2 3
1 X
2 1
1 1
KIA Topic(s)
IR BW IE08EA1.1 - Ability to operate and /
or monitor the following as they apply to the (LOCA Cooldown): Components, and functions of control and safety 4.0 1
systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
p Point Total 9/4 Page 7 of 14 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 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 '
BW IE03 Inadequate Subcooling Margin 1 4 BW IEOS LOCA Cooldown -
BW/EOSEAl.l - Ability to operate and 1 Depress. 14 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 t;i!;
'I:,
BWlE09 Natural Circ. 14
!\\"
,c:
BWIE13&EI4 EOP Rules and Enclosures
- 1
(
KIA Category Totals 2
1 1
1 2
2 Group Point Total 9/4 Page 7 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 / Group 1 System # / Name K K K K K K A KIA Topic(s)
IR 1 2 3 4 5 6 1 003K6.l4 - Knowledge of the effect Reactor Coolant X
of a loss or malfunction on the 2.6 1
/4 following will have on the RCPs:
Starting Requirements 004K2.06 - Knowledge of bus power X
supplies to the CVCS control 2.6 1
olume Control / 1 & 2 instrumentation.
X 005K2.01 - Knowledge of bus power 3.0 1
supplies to the DH pumps.
005 Residual Heat 005K6.03 - Knowledge of the effect
/4 of a loss or malfunction on the X
following will have on the Decay 2.5 1
Heat System: DH heat exchanger 006K5.04 - Knowledge of the
(
operational implications of the X
following concepts as they apply to 2.9 1
ECCS: Brittle fracture, including causes and preventative actions 006A2.10 - Ability to (a) predict the impacts of a low boron concentration in the ECCS; and (b) based on those predictions, use 3.4 1
procedures to correct, control, or mitigate the consequences of this malfunction.
007 A4.09 - Ability to manually operate and/or monitor in the control room: relationships between PZR 2.5 1
level and changing levels of the PRT and bleed holdup tank 008K4.02 - Knowledge ofSWS /
Component Cooling DCS design feature(s) and/or X
interlock(s) which provide for 2.9 1
ater /8 operation of the surge tank, including the associated valves and controls.
Page 8 of14 F:\\NRC - 2009\\Outiines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1 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 G
KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 003K6.14 - Knowledge ofthe effect 003 Reactor Coolant of a loss or malfunction on the X
2.6 1
Pump / 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
Volume Control /1 & 2
~; instrumentation.
Ir') 005K2.01 - Knowledge of bus power X
1';)'; supplies to the DH pumps.
3.0 1
005 Residual Heat I'
I'.:;;'
005K6.03 - Knowledge of the effect Removal / 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
! ~.',j ECCS: Brittle fracture, including
.06 ~. '","
causes and preventative actions fi~
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
'.' based on those predictions, use 3.4 1
,~::~J:;
"t'>"<1
~(~
procedures to correct, control, or
<<(:"
3'<
mitigate the consequences ofthis A~
malfunction.
}rii:)
~ 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
Water /8 operation of the surge tank, including I.: the associated valves and controls.
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 System # / Name K K K K K K A
[~~ A A t~.
KIA Topic(s)
IR 1 2 3 4 5 6 1 :~
.*.,.. 3 4 I*
.. *** i i<.
008Al.03 - Ability to predict and/or
- i**
monitor changes in parameters (to 008 Component Cooling X
i)i~
prevent exceeding design limits) 2.7 1
Water /8 U
associated with operating the SWS /
./r
)r pressure.
\\
010K5.01 - Knowledge of the operational implications of the 010 Pressurizer Pressure X
following concepts as the apply to 3.5 1
Control / 3 the PZR PCS: Determination of condition of fluid in PZR, using
.... {i steam tables
.\\
.*.*..* ~ 012G2.4.6 - Knowledge ofEOP 3.7 1
mitigation strategies.
<.i
(
012 Reactor Protection /
i* ****. <
'\\,:; 012K5.01 - Knowledge of the 7
operational implications of the X
(;
following concepts as they apply to 3.3 1
the RPS: DNB 013K2.01 - Knowledge of bus power 013 Engineered Safety X
........ supplies to the ESF AS / safeguards 3.6 1
Features Actuation / 2 i*.**... equipment control.
.. \\
i*' 022K4.01 - Knowledge ofCCS 022 Containment i
design feature(s) and/or interlock(s)
X
).
which provide for the following:
2.5 1
Cooling /5 Cooling of reactor building penetrations.
- f~f 026Al.Ol - Ability to predict and/or monitor changes in parameters (to 026 Containment Spray /
X *****...***.** i*
prevent exceeding design limits) 3.9 1
5 associated with operating the BSS
- .**.*.**** }..
- j;~
controls including: Reactor Building pressure
.i 039K3.05 - Knowledge of the effect 039 Main and Reheat X
that a loss or malfunction of the 3.6 1
Steam/4 MRSS will have on the following:
RCS Page 9 ofl4 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 / Group 1 System # / Name K K K K K K A A A A G KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 008A1.03 - Ability to predict and/or monitor changes in parameters (to 008 Component Cooling X
prevent exceeding design limits) 2.7 1
Water /8 associated with operating the SWS /
DCS controls including: CCW pressure.
010K5.01 - Knowledge ofthe operational implications of the 010 Pressurizer Pressure X
I following concepts as the apply to 3.5 1
Control/3 the PZR PCS: Determination of condition of fluid in PZR, using steam tables X 012G2.4.6 - Knowledge ofEOP 3.7 1
mitigation strategies.
(
012 Reactor Protection /
012K5.01 - Knowledge of the 7
X operational implications of the 3.3 1
, following concepts as they apply to the RPS: DNB 013K2.01 - Knowledge of bus power 013 Engineered Safety X
supplies to the ESF AS / safeguards 3.6 1
Features Actuation / 2 equipment control.
022K4.01 - Knowledge ofCCS 022 Containment design feature(s) and/or interlock(s)
X which provide for the following:
2.5 1
Cooling / 5 Cooling of reactor building penetrations.
026Al.O 1 - Ability to predict and/or monitor changes in parameters (to 026 Containment Spray /
X prevent exceeding design limits) 3.9 1
5 associated with operating the BSS controls including: Reactor Building pressure 039K3.05 - Knowledge ofthe effect 039 Main and Reheat X
that a loss or malfunction of the 3.6 1
Steam/4 MRSS will have on the following:
RCS Page 9 of14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401
(
(
I ES-401 ES-401 System # I Name Main F eedwater / 4 1 Auxiliary /
Emergency Diesel Huenerlltor/6 RO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 I Group 1 Form ES-401-2 KKKKKKA 1234561 x
x x
KIA Topic(s)
IR 059A3.04 - Ability to monitor automatic operation of the MFW, 2.5 1
including: Turbine driven feed pump 059K3.02 - Knowledge of the effect that a loss or malfunction of the MFW will have on the following:
EFW system 061K3.02 - Knowledge ofthe effect that a loss or malfunction ofthe EFW will have on the following:
S/G 062A2.16 - Ability to (a) predict the impacts of the following malfunctions or operations on the AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Degraded system voltages 063A3.01 - Ability to monitor automatic operation of the dc 3.6 1
4.2 1
2.5 1
electrical system, including: Meters, 2.7 1
annunciators, dials, recorders, and indicating lights 064G2.4.45 - Ability to prioritize and interpret the significance of each 4.1 1
annunciator or alarm.
064K4.01 - Knowledge ofED/G system design feature(s) and/or interlock(s) which provide for the following: Trips while loading the ED/G (frequency, voltage, speed) 073A4.03 - Ability to manually operate and/or monitor in the control room: Check source for operability demonstration 3.8 1
3.1 1
Page 10 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 f
(
Plant Systems - Tier 2 / Group 1 c"
K K K K K K A A A A G KIA Topic(s)
IR System # / Name 1 2 3 4 5 6 1 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 Feedwater / 4 i'
059K3.02 - Knowledge ofthe effect X
c.c,.c that a loss or malfunction of the 3.6 1
t<:
c MFW will have on the following:
I~:l:
EFW system I:
061K3.02 - Knowledge of the effect 061 Auxiliary /
X that a loss or malfunction of the 4.2 1
Emergency Feedwater /
EFW will have on the following:
4
.c:
S/G 062A2.16 - Ability to (a) predict the impacts ofthe 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 ofthe 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 c
c:
system design feature( s) and! or X
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 X
operate and/or monitor in the control 3.1 1
Monitoring / 7 room: Check source for operability 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 Plant Systems - Tier 2 I Group 1 Form ES-401-2 System # I Name K K K K K K A 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 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 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 consequences ofthose malfunctions or operations: Phase A and B isolation 103Kl.Ol - Knowledge of the physical connections and/or cause-X effect relationships between the 3.6 1
reactor building system and the following systems: CCS Category Totals 2333322 Group Point Total 28/5 Page 11 of 14 F:\\NRC - 2009\\Outiines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401
(
I ES-401 ES-401 System # / Name Service Water / 4 A Category Totals K K K 1 2 3 X
X RO Form ES-401-2 PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 K K K A KIA Topic(s)
IR 4 5 6 1 076G2.4.8 - Knowledge of how abnormal operating procedures are 3.8 used in conjunction with EOPs.
078Kl.04 - Knowledge ofthe physical connections and/or cause-effect relationships between the lAS 2.6 and the following systems: Cooling water to compressor 103A2.03 - Ability to (a) predict the impacts ofthe following malfunctions or operations on the reactor building system and (b) based on those predictions, use procedures 3.5 to correct, control, or mitigate the consequences of those malfunctions or operations: Phase A and B isolation 1 03Kl.0 1 - Knowledge of the physical connections and/or cause-effect relationships between the 3.6 reactor building system and the following systems: CCS 2 3 3 3 3 2 2 3 2 2 3 Group Point Total Page 11 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1
1 1
1
(
(
I ES-401 ES-401 System # I Name Control Rod Drive /
17 7 In-core Temperature
/7 029 Containment Purge /
8 RO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 I Group 2 Form ES-401-2 KKKKKKA 1 2 3 4 5 6 1 X
X X
KIA Topic(s) 01510.01 - Knowledge ofthe effect that a loss or malfunction ofthe NIS will have on the following: RPS 016A4.02 - Ability to manually operate and/or monitor in the control room: Recorders 017K5.02 - Knowledge of the operational implications of the following concepts as they apply to the ITM system: Saturation and subcooling of water 027K1.01 - Knowledge ofthe physical connections and/or cause-effect relationships between the CIRS and the following systems:
CSS 028A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen IR 3.9 2.7 3.7 3.4 3.5 Page 12 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1
1 1
1 1
I ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 2 System # I Name 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
'j; 1'::(::::
ITnrlir.~tion / 1 I:;;
015K3.01 - Knowledge ofthe effect
!015 Nuclear X
I:
that a loss or malfunction of the NIS 3.9 1
I Instr
/7
': will have on the following: RPS
- 016 Non-nuclear I'
f::"/;
016A4.02 - Ability to manually X
operate and/or monitor in the control 2.7 1
IInstr Jl1 /7 I':
room: Recorders
(
o 17K5.02 - Knowledge of the 1017 In-core Temperature operational implications of the X
following concepts as they apply to 3.7 1
IMonitor /7 the ITM system: Saturation and I :
subcooling of water 027Kl.Ol - Knowledge of the 1027 Containment Iodine physical connections and/or cause-X I:
effect relationships between the 3.4 1
IRemoval / 5 i;
CIRS and the following systems:
d.>
'\\,
I;';::
028A2.02 - Ability to (a) predict the I
impacts of the following malfunctions or operations on the
- l~::
IX HRPS; and (b) based on those predictions, use procedures to 3.5 1
- ' correct, control or mitigate the consequences ofthose malfunctions l;'~?
or operations: LOCA condition and
- f related concern over hydrogen 1029 Containment Purge /
8 I
- .,It
(
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 ES-401 System # I Name 4 Fuel Handling 18 Steam Generator I 4 Bypass 045 Main Turbine Generator I 4 055 Condenser Air 14 Condensate I 4 Liquid Radwaste I 9 1 Waste Gas Disposal 9
Area Radiation IIMomtonng /7 5 Circulating Water I K K K 1 2 3 X
RO Form ES-401-2 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 2 K K K A KIA Topic(s)
IR 4 5 6 1 033AI.OI - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)
X associated with operating Spent Fuel 2.7 Pool Cooling System controls including: Spent fuel pool water level.
034G2.2.40 - Ability to apply Technical Specifications for a 3.4 system.
041K6.03 - Knowledge ofthe effect of a loss or malfunction on the X
following will have on the Turbine 2.7 Bypass Valves: Controller and positioners, including ICS, S/G, CRDS 056KI.03 - Knowledge of the physical connections and/or cause-effect relationships between the 2.6 Condensate System and the following systems: MFW 068K4.01 - Knowledge of design feature(s) and/or interlock(s) which X
provide for the following: Safety 3.4 and environmental precautions for handling hot, acidic, and radioactive liquids Page 13 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401 1
1 1
1 1
I ES-401 RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 System # / Name K K K K K K A ~, A A,<S KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 033A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 033 Spent Fuel Pool X
associated with operating Spent Fuel 2.7 1
Cooling /8 Pool Cooling System controls including: Spent fuel pool water level.
}:,
034G2.2.40 - Ability to apply 034 Fuel Handling I'!~(
Technical Specifications for a 3.4 1
Equipment / 8 system.
k':
035 Steam Generator / 4
!'i:;,
I';
041K6.03 - Knowledge of the effect I,'
fi.
of a loss or malfunction on the 041 Steam following will have on the Turbine 2.7 Dump/Turbine Bypass X
Bypass Valves: Controller and 1
Control / 4 positioners, including ICS, S/G, CRDS
(
045 Main Turbine Generator / 4 055 Condenser Air Removal / 4 056K1.03 - Knowledge ofthe physical connections and/or cause-056 Condensate / 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 X
provide for the following: Safety 3.4 1
068 Liquid Radwaste / 9 and environmental precautions for handling hot, acidic, and radioactive liquids 071 Waste Gas Disposal
/9 072 Area Radiation Monitoring / 7 075 Circulating Water /
8 Page 13 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2,docx ES-401
(
c I ES-401 ES-401 System # / Name Station Air / 8 Category Totals RO PWR Examination Outline Plant Systems - Tier 2 / Group 2 KKKKKKA 1 2 3 4 5 6 1 Form ES-401-2 I Form ES-401-2 KIA Topic(s)
IR 201 1 1 1 Group Point Total Page 14 of 14 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 I ES-401 PWR Examination Outline Form ES-401-2
(
Plant Systems - Tier 2 / Group 2 System # / Name K K K K K K A A A A,'G KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 079 Station Air / 8 086 Fire Protection / 8 KIA Category Totals 2 0 1 1 1 1 1 1. 0 1 I, Group Point Total 10/3
(
(
Page 14 of 14 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline (401-2) Rev 2.docx ES-401
C ES-401, Rev. 9 Category
- 1.
Conduct of Operations
- 2.
Equipment Control
- 3.
Radiation Control
- 4.
Emergency Procedures /
Plan Tier 3 Point Total Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 RO River Unit #3 Date of Exam:
KIA #
2.1.3 2.1.36 2.1.40 Subtotal 2.2.20 2.2.38 Subtotal 2.3.11 2.3.12 2.3.14 Subtotal 2.4.8 2.4.35 Subtotal Topic Knowledge of shift or short-term relief turnover ofthe process for managing activities.
Ability to control radiation releases.
Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation etc.
Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or conditions or activities.
Knowledge of how abnormal operating procedures are used in with EOPs.
Knowledge oflocal auxiliary operator tasks during an and the resultant effects.
2009 RO IR IR 2.6 1
3.6 1
3.8 3.2 1
3.4 1
3.8 1
3.8 1
Page 1 of 2 F:\\NRC - 2009\\Outlines\\Written\\RO NRC 2K9 Written Exam Outline - Generic (401-3) Rev l.docx ES-401 7
ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3)
Crystal River Unit #3 Date of Exam:
SC;PlC;111Dc;1, 2009 KJA#
Topic RO SRO-Only Category IR IR 2.1.3 Knowledge of shift or short-term relieftumover 3.7 1
nractices
~owledge~fprocedrlres and 1 U1~Xl~~a *..
2.1.36
- ,,~~.iZ':~~ f(P~ 2;1.35Y\\i/") 1,:\\;:,'. :,./'
3.0 1
- 1.
Conduct of Operations 2.1.40 Knowledge of refueling administrative requirements.
2.8 1
Subtotal l'
3
~]
2.2.20 fledge of the process for managing 2.6 1
trouhlp.~h()()timr activities.
- 2.
Knowledge of conditions and limitations in the Equipment 2.2.38 facility license.
3.6 1
Control Subtotal
)
2
./1 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 iJlbYNl,.,~:illi!
Subtotal
!tilMky,lrr£w::tl
' ** l, 3
2.4.8 Knowledge of how abnormal operating procedures 3.8 1
are used in conjunction with EOPs.
- 4.
Knowledge oflocal auxiliary operator tasks during Emergency 2.4.35 an and the resultant vpc;rational effects.
3.8 1
Procedures /
Plan Subtotal
- .~!
.'llJ~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
(
RO Tierl Randomly Reason for Rejection Group Selected KIA Not applicable to CR3. Containment fan coolers have no 111 OllEK3.04 dampers. Chief Examiner randomly selected new KA
- OlIEK3.07.
Not possible to prepare a psychometrically sound question related 1/1 022AKl.02 to this KA. High delta P, more flow. Low delta P, less flow.
Chief Examiner randomly selected new KA#022AKl.03.
111 055EK2.04 No IR value assigned in NUREG-1122. Chief Examiner randomly selected new KA #055EK3.02.
Not possible to prepare a psychometrically sound question related 112 OOlAA2.02 to this KA. Chief Examiner randomly selected new KA
- OOlAA2.05.
Not applicable to CR3. Our ECCS system has no water level 211 006K5.01 input for automatic operation and no manual operator actions based on water level. Chief Examiner randomly selected new KA#OO6K5.04.
Not possible to prepare a psychometrically sound question related 2/1 103A2.05 to this KA. Chief Examiner randomly selected new KA
- 103A2.03.
Generic 2.1.35 IR value only 2.2 for ROs. Chief Examiner randomly selected new KA #G2.l.36.
Not applicable to CR3. CR3 does not have "first-out" alarm
(
111 007EA2.05 indications for a reactor trip. Chief Examiner randomly selected new KA #OO7EA2.02.
Not applicable to CR3. CR3 does not have SWIRW flow control 111 056AA1.28 valves. Chief Examiner randomly selected new KA
- 056AAl.05.
2/2 028A2.03 At CR3 actions for this KA are SRO only level knowledge.
Chief Examiner randomly selected new KA #028A2.02.
(
Page 1 of 1F:\\NRC - 2009\\Outiines\\Written\\RO NRC 2K9 Written Exam Outline - Rejected KAs (401-4) Rev 2.docxES-401 ES-401 Record of Rejected KlAs Form ES-401-4 RO Tier/
Randomly Reason for Rejection Group Selected KIA Not applicable to CR3. Containment fan coolers have no 111 01lEK3.04 dampers. Chief Examiner randomly selected new KA
- OllEK3. 07.
Not possible to prepare a psychometrically sound question related 111 022AK1.02 to this KA. High delta P, more flow. Low delta P, less flow.
Chief Examiner randomly selected new KA#022AK1.03.
111 OSSEK2.04 No IR value assigned in NUREG-1122. Chief Examiner randomly selected new KA #OSSEK3.02.
Not possible to prepare a psychometrically sound question related 1/2 001AA2.02 to this KA. Chief Examiner randomly selected new KA
- 00lAA2.0S.
Not applicable to CR3. Our ECCS system has no water level 211 006KS.01 input for automatic operation and no manual operator actions based on water level. Chief Examiner randomly selected new KA #006KS.04.
Not possible to prepare a psychometrically sound question related 211 103A2.0S to this KA. Chief Examiner randomly selected new KA
- 103A2.03.
Generic 2.1.3S IR value only 2.2 for ROs. Chief Examiner randomly selected new KA #G2.1.36.
Not applicable to CR3. CR3 does not have "first-out" alarm
(
111 007EA2.0S indications for a reactor trip. Chief Examiner randomly selected new KA #007EA2.02.
Not applicable to CR3. CR3 does not have SW/RW flow control 111 OS6AA1.28 valves. Chief Examiner randomly selected new KA
- OS6AA 1.OS.
2/2 028A2.03 At CR3 actions for this KA are SRO only level knowledge.
Chief Examiner randomly selected new KA #028A2.02.
Page 1 of IF:\\NRC - 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 DRAFT 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 I
2 3 4 6
1 2 3 4 TOTAL A2 G*
TOTAL 5
1 18 3
3 6
L Emergency 2
9 2
2 4
& Abnormal N/A N/A Plant Tier Evolutions 27 5
5 10 Totals 1
28 3
2 5
- 2.
2 10 2
1 3
Plant Systems Tier Totals 38 5
3 8
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 Abilities Categories 10 7
2 2
1 2
Note:
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 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 +/- 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 should be added. Refer to Section D.I.b ofES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KJ 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 A categories.
7.*
The generic (G) KI As in Tiers 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.
- 8.
On the following pages, enter the KJ A 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 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.
R FT Page 1 of10 F:\\NRC - 2009\\Outlines\\ Written \\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.docx ES-401 ES-401 SRO - PWR Examination Outline - (Sept, 2009)
Form ES-401-2 FT f
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 3
4 6
1 4
TOTAL A2 G*
TOTAL 1
2 5
2 3
1 18 3
3 6
I.
Emergency 2
9 2
2 4
& Abnormal N/A N/A Plant Tier Evolutions 27 5
5 10 Totals 1
28 3
2 5
- 2.
2 10 2
1 3
Plant Systems Tier Totals 38 5
3 8
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 Abilities Categories 10 7
2 2
1 2
Note:
I.
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 ofthe SRO-only outline, the 'Tier Totals" in each KIA category shall not be
(
less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 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 should be added. Refer to Section D.I.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KlAs 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 KIA categories.
7*
The generic (G) KI As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section d.l.b ofES-401 for the applicable KI As.
- 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 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 Safety Function 007 (BW1E02 & ElO)
Reactor Trip - Stabilization
- Recovery - 1 008 Pressurizer Vapor Space Accident 1 3 009 Small Break LOCA 1 3 011 Large Break LOCA 1 3 015/17 RCP Malfunctions 14 022 Loss ofRx Coolant Makeup 1 2 025 Loss ofRHR System 1 4 026 Loss of Component Cooling Water 18 027 PZR Pres~ure Control System Malfunction 1 3 029 ATWS 1 1 038 Steam Generator Tube Rupture 1 3 040 (BW IE05) Steam Line Rupture - Excessive Heat Transfer 1 4 054 Loss of Main Feedwater 14 055 Station Blackout 1 6 K K K A 1
2 3
1 KIA Topic(s) 022AA2.01 - Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Pump Makeup: Whether makeup line leak exists 027 AG2.4.9 - Knowledge of low power 1 shutdown implications in accident (e.g.
LOCA or loss ofDH) mitigation strategies.
Page 2 oflO F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx IR 3.8 1
4.2 1
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 KIA Topic(s)
IR
- 2.. *.* G Safety Function 1
2 3
1 007 (BW/E02 & EI0)
Reactor Trip - Stabilization
- Recovery - 1 j
008 Pressurizer Vapor Space 1.\\;
Accident 1 3 009 Small Break LOCA 1 3
(*0 011 Large Break LOCA 1 3 I i",j{
015/17 RCP Malfunctions 14 1',"/.... ::...
- .. "....\\.
022AA2.01 - Ability to determine and 022 Loss ofRx Coolant interpret the following as they apply to 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 1 8 027 AG2A.9 - Knowledge of low power 1 027 PZR PresSure Control X
shutdown implications in accident (e.g.
4.2 1
System Malfunction 1 3 LOCA or loss ofDH) mitigation strategies.
029 ATWS 11 038 Steam Generator Tube Rupture 1 3
- ,':;:/,'
040 (BW/E05) Steam Line Rupture - Excessive Heat Transfer 1 4
" **1'"
054 Loss of Main Feedwater 14
(
055 Station Blackout 1 6 Page 2 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401
(
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 KIA Topic(s)
IR Safety Function 1
2 3
056 Loss of Offsite Power 1 056AG2.4.45 - Ability to prioritize and 6
interpret the significance of each 4.3 1
annunciator or alarm.
057 AA2.05 - Ability to determine and 057 Loss of Vital AC interpret the following as they apply to 3.8 1
Instrument Bus 1 6 the Loss of Vital AC Instrument Bus:
S/G pressure and level meters 058 Loss of DC Power 16 062 Loss of Nuclear Services Water 1 4 065AA2.04 - Ability to determine and 065 Loss ofInstrument Air 1 interpret the following as they apply to 8
the Loss ofInstrument Air: Typical 2.7 1
conditions which could cause a
(
compressor trip (e.g., high temperature)
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 4.1 1
6 surveillance procedures.
KIA Category Totals roup Point Total 18/6 Page 3 ofl0 F:\\NRC - 2009\\Outiines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.docx ES-401 I ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 A
E/APE # I Name I K K K A
Safety Function 1
2 3
1 2
G KIA Topic(s)
IR 056 Loss of Off site Power /
056AG2.4.45 - Ability to prioritize and interpret the significance of each 4.3 1
6 i<
annunciator or alarm.
'(.;1; "i
ii:'.
057 AA2.05 - Ability to determine and 057 Loss of Vital AC interpret the following as they apply to 3.8 1
Instrument Bus / 6 the Loss of Vital AC Instrument Bus:
S/G pressure and level meters
./
058 Loss of DC Power /6
'.. k.)
- i:
062 Loss of Nuclear Services Water / 4 i
065AA2.04 - Ability to determine and 065 Loss ofInstrument Air /
interpret the following as they apply to 8
- X the Loss of Instrument Air: Typical 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 / 4 077 Generator Voltage and 077AG2.2.12 - Knowledge of Electric Grid Disturbances /
- x surveillance procedures.
4.1 1
6 KIA Category Totals 3,.3 Group Point Total
(
Page 3 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.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 # I Name I Safety Function 001 Continuous Rod Withdrawal / 1 003 Dropped Control Rod / 1 005 Inoperable/Stuck Rod /
1 024 Emergency Boration / 1 028 PZR Level Malfunction
/2 032 Loss of Source Range NIl 7 033 Loss ofIntermediate RangeNI/7 036 (BW/A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak/3 051 Loss of Condenser Vacuum/4 059 Accidental Liquid RadWaste ReI. / 9 060 Accidental Gaseous Radwaste ReI. / 9 067 Plant Fire On-site / 8 KKK A 123 1 KIA Topic(s) 061AA2.06 - Ability to determine and interpret the following as they apply to the Area Radiation Monitoring (ARM)
System Alarms: Required actions if alarm channel is out of service Page 4 of 10 F:\\NRC - 2009\\Outiines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev 1.docx IR 4.1 1
ES-401 I ES-401 SRO Form ES-401-2 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 G
KIA Topic(s)
IR Safety Function 1
2 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
(
Range NI / 7 036 (BW/A08) Fuel Handling Accident / 8 037 Steam Generator Tube Leak /3 051 Loss of Condenser Vacuum / 4 i
059 Accidental Liquid RadWaste ReI. /9 060 Accidental Gaseous Radwaste ReI. / 9 11!!I~i!
lllli!);'!
061AA2.06 - Ability to determine and interpret the following as they apply to LI, X
the Area Radiation Monitoring (ARM) 4.1 1
System Alarms: Required actions if alarm channel is out of service 067 Plant Fire On-site / 8 Page 4 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 2 E/APE #/Namel Safety Function 068 (BW / A06) Control Room Evac. / 8 069 Loss of CTMT Integrity
/5 074 Inad. Core Cooling 1 4 076 High Reactor Coolant Activity 1 9 BW/AOI Plant Runback 11 BW/A02&A03 Loss ofNNI-XfY /7
(
BW 1 A04 Turbine Trip 1 4 BW 1 A05 Emergency Diesel Actuation 1 6 BW 1 A07 Flooding 1 8 BW 1E03 Inadequate Subcooling Margin 1 4 BW 1E08 LOCA Cooldown -
Depress. 14 BW IE09 Natural Circ. 14 KIA Category Totals KKK 123 KIA Topic(s) 069AG2.2.38 - Knowledge of conditions and limitations in the facility license.
BW/A03AG2.4.6 - Knowledge ofEOP mitigation strategies.
BW 1E09EA2.2 - Ability to determine and interpret the following as they apply to the (Natural Circulation Cooldown):
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
uroULP Point Total Page 5 of 10 F:\\NRC - 2009\\Outiines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx IR 4.5 1
4.7 1
4.0 1
9/4 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 # I Name I K K K A A i' G KIA Topic(s)
IR
,i Safety Function 1
2 3
1 2*
068 (BW/A06) Control Room Evac. I 8 069 Loss of CTMT Integrity X
069AG2.2.38 - Knowledge of conditions 4.5 1
15 and limitations in the facility license.
074 Inad. Core Cooling I 4
~i~:
076 High Reactor Coolant I
Activity I 9 i
,)"
B WI AO 1 Plant Runback I 1 BW/A02&A03 Loss ofNNI-X BW/A03AG2.4.6 - Knowledge ofEOP 4.7 1
XIY 17 mitigation strategies.
(
BW I A04 Turbine Trip 14 BW/A05 Emergency Diesel Actuation I 6 BW I A07 Flooding I 8 BW IE03 Inadequate Sub cooling Margin I 4 BW IE08 LOCA Cooldown -
Depress. I 4 BW/E09 Natural Circ. 14 I'
BW /E09EA2.2 - Ability to determine and interpret the following as they apply X
to the (Natural Circulation Cooldown):
4.0 1
Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
I £Vi-\\.,-,<negory Totals 2
2 Group Point Total 9/4 Page 5 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.docx ES-401
(
(
I ES-401 ES-401 System # / Name Reactor Coolant 14 12 Reactor Protection 1 SRO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 KKKKKKA 1 2 3 4 5 6 1 KIA Topic(s) 005A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the Decay Heat System, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation 012G2.2.12 - Knowledge of surveillance procedures.
IR 2.9 4.1 Page 6 oflO F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev Ldocx ES-401 1
1 I ES-401 SRO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 I
(
Plant Systems - Tier 2 / Group 1 System # / Name K K K K K K A :A A A a-KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump/4 004 Chemical and V olume Control / 1 & 2 i\\l:
005A2.Ol - Ability to (a) predict the impacts of the following malfunctions or operations on the Decay Heat
~C:l; System, and (b) based on those 005 Residual Heat X
predictions, use procedures to correct, 2.9 1
Removal/4
. control, or mitigate the consequences ofthose 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 012 Reactor Protection /
~ X 4.1 1
7 surveillance procedures.
013 Engineered Safety I.{'I:
Features Actuation /2
(
Page 6 oflO F:\\NRC - 2009\\Outlines\\ Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev 1.docx ES-401
(
(
l I ES-401 ES-401 System # I Name Containment Spray /
1 Auxiliary /
IElueI*gelilCY F eedwater /
Emergency Diesel Generator / 6 K K K 1 2 3 SRO Form ES-401-2 I PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 1 K K K 4 5 6 A
1 KIA Topic(s) 039G2.4.20 - Knowledge ofthe operational implications ofEOP warnings, cautions, and notes.
062A2.01 - Ability to (a) predict the impacts ofthe following malfunctions or operations on the AC distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de-energized, would degrade or hinder plant operation IR 4.3 3.9 Page 7 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401 1
1 I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 System # / Name K K K K K K A A A A G KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4,
022 Containment Cooling /5 1026 Containment Spray /
15 039 Main and Reheat 039G2.4.20 - Knowledge of the X operational implications ofEOP 4.3 1
Steam/4 warnings, cautions, and notes.
059 Main Feedwater / 4 061 Auxiliary /
El1l\\AgCUC: Feedwater /
4
(
~?! F' "sfi 062A2.01 - Ability to (a) predict the impacts ofthe following
()~~;A malfunctions or operations on the AC distribution system; and (b)
X based on those predictions, use 3.9 1
- 2 procedures to correct, control, or
- /ti!
mitigate the consequences ofthose 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 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 ES-401 System # / Name Service Water /4 Instrument Air / 8 103 Containment / 5 A Category Totals
(
Page 8 of 10 SRO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 KKKKKKA 123 4 5 6 1 KIA Topic(s) 076A2.0l - Ability to (a) predict the impacts of the following malfunctions or operations on the RWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of RWS Group Point Total IR 3.7 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev 1.docx ES-401 1
28/5 I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 System # / Name K K K K K K A \\;2\\ A A G KIA Topic(s)
IR
<it 1 2 3 4 5 6 1.;2 3 4
't*
076A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the 076 Service Water / 4 X
RWS; and (b) based on those 3.7 1
predictions, use procedures to 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 Category Totals 1
2 Group Point Total 28/5
(
(
Page 8 of10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401
I ES-401 ES-401 System # / Name Control Rod Drive /
4 Rod Position UlncllcatlOn 11
~Ins1trumlenta.tion / 7 Containment Purge /
SRO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 KKKKKKA 1 234 5 6 1 KIA Topic(s) 002A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those IR predictions, use procedures to 4.4 correct, control or mitigate the consequences of those malfunctions or operations: Loss of coolant pressure Ol4G2.1.27 - Knowledge of system purpose and / or function.
4.0 Page 9 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev l.docx ES-401 1
I ES-401 SRO Form ES-401-2 I ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 System # / Name K K K K K K A A A A Y KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 1001 Control Rod Drive /
Ie 1
1"
.'f!
002A2.02 - Ability to (a) predict the
,'\\
impacts ofthe following 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 i'k i,',
consequences of those malfunctions or operations: Loss of coolant I,
pressure 1011 Pressurizer Level I;:.
1*<',;':,.
Control/2
\\'
014G2.1.27 - Knowledge of system 014 Rod Position Ix purpose and / or function.
4.0 1
Inrlic:ation / 1
(
015 Nuclear InstrUlYlpntMion /7 016 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 iroolino / 8
>0 Page 9 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev J.docx ES-401
(
I ES-401 ES-401 System # / Name Condensate / 4 Liquid Radwaste / 9 5 Circulating Water /
9 Station Air / 8 6 Fire Protection / 8 A Category Totals SRO Form ES-401-2 I PWR Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 KKKKKKA 123 456 1 KIA Topic(s) 034A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Dropped fuel element Group Point Total IR 4.4 1
10/3 Page 10 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 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 2 System # I Name K K K K K K A A A A I,f;;
KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 034A2.01 - Ability to (a) predict the impacts ofthe following 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 / 7 075 Circulating Water /
8 079 Station Air / 8 1086 Fire Protection / 8 I,
ory Totals 2
'1 Group Point Total 10/3
~
(
Page 10 of 10 F:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline (401-2) Rev I.docx ES-401
ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 SRO River Unit #3 Date of Exam:
2009 RO Category KJA#
Topic IR IR Ability to use procedures related to shift staffing, 2.1.5 such as minimum crew complement, overtime 3.9 1
etc.
- 1.
Ability to coordinate personnel activities outside Conduct of 2.1.8 the control room.
4.1 1
Operations Subtotal 2
2.2.37 to determine operability and/or availability 4.6 related
- 2.
Knowledge of the process used to track inoperable Equipment 2.2.43 alarms.
3.3 Control
(
Subtotal 2
Knowledge of radiation monitoring systems, such 2.3.15 as fixed radiation monitors and alarms, portable 3.1 1
- 3.
survey instruments, personnel monitoring Radiation etc.
Control Subtotal 2.4.3 Ability to identify post-accident instrumentation.
- 4.
Emergency 2.4.29 Knowledge of the emergency plan.
Procedures /
Plan Subtotal Tier 3 Point Total Page 1 of 1F:\\NRC - 2009\\Outiines\\Written\\SRO NRC 2K9 Written Exam Outline - Generic (401-3) Rev O.docx ES-401
(
(
\\
ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3)
Crystal River Unit #3 Date of Exam:
SCOPLC011lUC01,2009 RO sRO-Only Category KIA #
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
2.2.37 Ability to determine operability andJor availability 4.6 1
of safety related equipment.
- 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 2.3.15 as fixed radiation monitors and alarms, portable 3.1 1
- 3.
survey instruments, personnel monitoring Radiation equil'1l1COIlL, etc.
Control Subtotal i
":~~:
1 2.4.3 Ability to identify post-accident instrumentation.
3.9 1
- 4.
Emergency 2.4.29 Knowledge ofthe emergency plan.
4.4 1
Procedures /
Plan e
- J.l.,])
Subtotal 2
II Tier 3 Point Total I,Th\\fi/",,,,,:c;'iiiUYbW.i!!!
i.l!
10 e:;::i~~~;1F"iliiiil 7
Page 1 of IF:\\NRC - 2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline - Generic (401-3) Rev O.docx ES-401
ES-401 Record of Rejected KJAs Form ES-401-4 SRO Tier!
Randomly Reason for Rejection Group Selected KJA Not possible to prepare a psychometrically sound 112 061AA2.02 question related to this KA. Chief Examiner randomly selected new KA #061AA2.06.
Not possible to prepare a psychometrically sound 211 062A2.14 question related to this KA. Chief Examiner randomly selected new KA #062A2.0l.
Not applicable to CR3. Containment iodine removal 2/2 027A2.01 is accomplished via the RB Spray system. There are 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.
(
(
Page 1 of 1 F:\\NRC -2009\\Outiines\\Written\\SRO NRC 2K9 Written Exam Outline -Rejected KAs (401-4) Rev 1.docxES-40 1 ES-40l Record of Rejected KJAs Fonn ES-40l-4
./
SRO Tierl Randomly Reason for Rejection Group Selected KJA Not possible to prepare a psychometrically sound 1/2 06lAA2.02 question related to this KA. Chief Examiner randomly selected new KA #06lAA2.06.
Not possible to prepare a psychometrically sound 211 062A2.l4 question related to this KA. Chief Examiner randomly selected new KA #062A2.0 1.
Not applicable to CR3. Containment iodine removal 2/2 027A2.01 is accomplished via the RB Spray system. There are 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.
(
Page 1 of IF:\\NRC -2009\\Outlines\\Written\\SRO NRC 2K9 Written Exam Outline -Rejected KAs (401-4) Rev l.docxES-40 1
(
ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-301-1 Facility:
Crystal River Unit #3 Date of Exam:
08/31109 thm 09118/09 Examination Level:
Operating Test Number:
1 Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures 1 Plan Type Code*
D,R M,R D,R D, M, P, R
D, S Describe activity to be performed SRO Only (COl) - Determine actions for primary to secondary leakage.
KIA - G2.1.25 SRO 4~2 CP-152 RO & SRO - (C02) - Perform a time to boil/core uncovery calculation.
KIA - G2.1.23 RO 4.3 SRO 4.4 OP-I03H RO & SRO - (EC 1) - Perform a monthly NI Imbalance Comparison.
KIA - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the Imbalance Comparison determine required ITS actions, if any.
KIA - G2.2.40 SRO 4.7 SP-312B RO & SRO - (RCI) - Calculate the maximum pennissible stay time with an Emergency Event in progress.
KIA - G2.3.4 RO 3.2 SRO 3.7 EM-202 RO & SRO - (EPl) - Complete the State of Florida Notification Message form for Nuclear Power Plants and make required notifications.
KIA - 2.4.43 RO 3.2 SRO 3.8 EM-202 Note:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator or Class(R)oom (D)irect from bank (::: 3 for ROs;::: 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 2: 1)
(P)revious 2 exams ( :::1; randomly selected)
Page 1 of 1 F:\\NRC - 2009\\Outlines\\JPM\\NRC 2009 Fonn ES-30J-J (JPM Admin Outline) Rev O.docx ES-301
(
\\
I
\\
ES-301, Rev. 9, Supp. 1 Administrative Topics Outline Form ES-30l-l Facility:
Crystal River Unit #3 Date of Exam:
08/31109 thm 09118/09 Examination Level:
Operating Test Number:
1 Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures 1 Plan Type Code*
D,R M,R D,R D,M,P, R
D, S Describe activity to be performed SRO Only - (COl) - Determine actions for primary to secondary leakage.
KIA - G2.1.25 SRO 4.2 CP-l52 RO & SRO - (C02) - Perform a time to boil 1 core uncovery calculation.
KIA - G2.1.23 RO 4.3 SRO 4.4 OP-l03H RO & SRO - (ECl) - Perform a monthly NI Imbalance Comparison.
KIA - G2.2.12 RO 3.7 SRO 4.1 SRO Only - After completing the Imbalance Comparison determine required ITS actions, if any.
KIA - G2.2.40 SRO 4.7 SP-3l2B RO & SRO - (RC l) - Calculate the maximum permissible stay time with an Emergency Event in progress.
KIA - G2.3.4 RO 3.2 SRO 3.7 EM-202 RO & SRO - (EP l) - Complete the State of Florida Notification Message form for Nuclear Power Plants and make required notifications.
KIA - 2.4.43 RO 3.2 SRO 3.8 EM-202 Note:
All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator or Class(R)oom (D)irect from bank (~3 for ROs; ~ 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 2: l)
(P)revious 2 exams ( ~l; randomly selected)
Page 1 of 1 F:\\NRC - 2009\\OutlinesIJPM\\NRC 2009 Fonn ES-30J-J (JPM Admin Outline) Rev O.docx ES-30l
ES-301, Rev. 9, Supp. 1 Control Room 1 In-Plant Systems Outline Fonn ES-301-2 Facility:
Crystal River Unit #3 Date of Exam:
08/31/09 thm 09118109 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 1 ESF)
System I JPM Title Type Safety Code*
Function
- a.
CA - Perform an RCS Boration A,D,S 1
KIA - 024AA2.04 RO 3.4 SRO 4.2 (EOP-2) fRO, SRO-I]
- 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)
[RO. SRO-IJ
- c.
RCS - Respond to a stuck open PZR spray valve
[SRO-U]
A,D,L,P, 3
KlA- 002A4.01 RO 4.2 SRO 4.4 (AP-S20)
[RO, SRO-I}
S
- d.
S/GS - Establish EFW flow to raise OTSG level D.S 4
KlA-E03EA1.3 RO 3.6 SRO 3.8 (EOP-3)
[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]
Secondary
- f.
CCS - Ensure proper alignment ofES equipment
[SRO-U]
A,EN,N, S S
KIA - 022A4.01 RO 3.6 SRO 3.6 (EOP-2)
[RO. SRO-I]
- g.
AC - Energize a dead bus D,S 6
KIA - 062A2.0S RO 2.9 SRO 3.3 (AP-770)
[RO]
- h.
ES - Respond to an invalid ES Actuation A,D,EN, S 8
KIA - 008A3.08 RO 3.6 SRO 3.7 (AP-340) fRO, SRO-I]
(
II SPARE MU - Restart a MUP following an RCS leak isolation D,S 2
KIA - 002A2.01 RO 4.3 SRO 4.4 (AP-S20)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- 1.
PPcs - Depressurize the RCS using HP Aux. Spray (SRO-U/
D,E,R 3
KlA-E14EAl.l R03.8 SR03.6 (EOP-14,Enc.13)
[RO. SRO-IJ
- j.
DHR - Establish DHR from outside control room E,L,N,R 4
KIA - A06AAl.l RO 4.3 SRO 4.2 (AP-990)
[RO, SRO-IJ Primary
- k.
AC - Transfer vital bus to normal power supply rSRO-U]
D 6
KIA - 062A3.04 RO 2.7 SRO 2.9 (OP-703)
[RO, SRO-I]
SPARE FS/OTSG - Transfer excess secondary inventory to FST D,E 3,8 KlA-038EK3.06 R04.2 SR04.S (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 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 I SRO-I I SRO-U (A)ltemate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ORAl ~Itrol room system)
- s9/:s8/:S4 (E)mergency or abnormal in-plant
~1I~1/~1 (EN)gineered safety feature I - I ~ 1 (L)ow Power I Shutdown
~1/~1/~1 (N)ew or (M)odified from bank including 1 (A)
~2/~2/~1 (P)revious 2 exams
- S3/:S3/:S2 (R)CA (randomly selected)
~1/~1/~1 (S)imulator Page 1 of 1 F:\\NRC - 2009\\Outiines\\JPM\\NRC 2009 Form ES-301-2 (JPM MCR-Plant Outline) Rev. I.docx ES-30 1 ES-301, Rev. 9, Supp. 1 Control Room 1 In-Plant Systems Outline Form ES-301-2 Facility:
Crystal River Unit #3 Date of Exam:
08/31/09 thru 09/18/09 Exam Level: RO ~ SRO-I ~ SRO-U ~
Operating Test Number:
1 Control Room systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including J ESF)
System 1 JPM Title Type Safety Code*
Function
- a.
CA - Perform an RCS Boration A,D,S I
KIA - 024AA2.04 RO 3.4 SRO 4.2 (EOP-2)
[RO, SRO-I]
- 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)
[RO. SRO-I]
- c.
RCS - Respond to a stuck open PZR spray valve
[SRO-U]
A,D,L,P, 3
KIA - 002A4.01 RO 4.2 SRO 4.4 (AP-520)
[RO,SRO-I1 S
- d.
S/GS - Establish EFW flow to raise OTSG level D. S 4
KIA - E03EA1.3 RO 3.6 SRO 3.8 (EOP-3)
[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-I1 Secondary
- f.
CCS - Ensure proper alignment of ES equipment
[SRO-U]
A,EN,N, S 5
KlA- 022A4.01 RO 3.6 SRO 3.6 (EOP-2)
[RO. SRO-I1
- g.
AC - Energize a dead bus D,S 6
KlA-062A2.05 R02.9 SR03.3 (AP-770)
[RO]
- h.
ES - Respond to an invalid ES Actuation A,D,EN,S 8
KIA - 008A3.08 RO 3.6 SRO 3.7 (AP-340)
[RO,SRO-Ij
(
- 1 SPARE MU - Restart a MUP following an RCS leak isolation D,S 2
KIA - 002A2.01 RO 4.3 SRO 4.4 (AP-520)
In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)
- l.
PPcs - Depressurize the RCS using HP Aux. Spray rSRO-Uj D,E,R 3
KlA-EI4EAl.l R03.8 SR03.6 (EOP-14,Enc.13)
[RO. SRO-Ij J.
DHR - Establish DHR from outside control room E,L,N,R 4
KIA - A06AAl.l RO 4.3 SRO 4.2 (AP-990)
IRO, SRO-l)
Primary
- k.
AC - Transfer vital bus to normal power supply
[SRO-Uj D
6 KlA- 062A3.04 RO 2.7 SRO 2.9 (OP-703)
[RO, SRO-I1 SPARE FS/OTSG - Transfer excess secondary inventory to FST D,E 3,8 KIA - 038EK3.06 RO 4.2 SRO 4.5 (EOP-14, Enc. 9)
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 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 1 SRO-I 1 SRO-U (A)ltemate path 4-6 14-6 1 2-3 (C)ontrol room (D)irect from bank RA'
~T
.::::9/.::::8/.::::4 (E)mergency or abnormal in-plant
~1/~1/~1 (EN)gineered safety feature (cItro I room system) 1 -
1 ~ I (L )ow Power 1 Shutdown
~l/~l/~l (N)ew or (M)odified from bank including I (A)
~2/~2/~1
(
(P)revious 2 exams
- 3/.::::31::::2 (R)CA (randomly selected)
~l/~l/~l (S)imulator Page 1 of 1 F:\\NRC - 2009\\Outlines\\JPM\\NRC 2009 Form ES-301-2 (JPM MCR-Plant Outline) Rev. I.docx ES-30 1