ML101600061
| ML101600061 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/28/2010 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| ES-401-6 | |
| Download: ML101600061 (16) | |
Text
Draft Submittal (Pink Paper) ec d7 DRAFT Written Exam Quality Checklist (ES-401-6)
& Written Exam Sample Plan Draft Submittal (Pink Paper) o DRAFT Written Exam Quality Checklist (ES-401-6)
& Written Exam Sample Plan
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:
VC Summer Date of Exam:
6/4/2007 Exam RO/SRO Level:
Initial Item Description a
c#
1.
Questions and answers technically accurate and applicable to facility.
CJ1 2.
a.
NRC K/As referenced for all questions.
b.
Facility_learning_objectives_referenced_as_available.
3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 4.
The sampling process was random and systematic. (If more than 4 RO and 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL Program Office) 5.
Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
the audit exam was systematically and randomly developed, or the audit exam was completed before the license exam was started, or the examinations were developed independently, or XX the licensee certifies that there is no duplication, or other (explain) 6.
Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 41 I 13 6 /
1 28/11 question_distribution(s)_at_right.
7.
Between 50 and 60 percent of the question on the Memo CIA RO exam are written at the comprehension/
ty analysis level; the SRO exam may exceed 60 30 I 3 45 /22 percent f the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question_distribution(s)_at_right 8.
References/handouts provided do not give away answers or aid in the elimination of d istractors.
9.
Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
11.
The exam contains the required number of one-point, multiple choice items; the total is correct_and_agrees_with_value_on_cover_sheet.
Print d Name / Signytur Date a.
Author Joseph G. Arsenault 4/12007 b.
Facility Reviewer (*)
c.
NRC Chief Examiner (#)
d.
NRC Regional Supervisor Note:
The facility reviewers initials/signature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
DRAFT NUREG-1021, Revision 9 ES-401 Written Examination Quality Checklist Form ES-401-6 C Summer Date of Exam:
6/4/2007 Exam RO/SRO Leve!:
Initial Item Description a
b*
C#
- 1.
Questions and answers technically accurate and applicable to facility.
CI64
<~
- 2.
- a.
NRC KlAs referenced for all questions.
~ -
- b.
Facility learning objectives referenced as available.
(y---
- 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401
~ ~
- 4.
The sampling process was random and systematic. (If more than 4 RO and 2 SRO t
questions were repeated from the last 2 NRC licensing exams, consult the NRR OL CM ~
Program Office)
- 5.
Question duplication from the license screening/audit exam was controlled as
\\
indicated below (check the item that applies) and appears appropriate:
-- the audit exam was systematically and randomly developed, or
~ f-
-- the audit exam was completed before the license exam was started, or the examinations were developed independently, or
~
the licensee certifies that there is no duplication, or other (explain)
- 6.
Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest 41/13 6/1 28/11 ~ t-new or modified); enter the actual RO I SRO-only question distribution(s) at right.
- 7.
Between 50 and 60 percent of the question on the Memory CIA RO exam are written at the comprehensionl
\\{ZO\\ F--
analysis level; the SRO exam may exceed 60 30 I 3 45/22 percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right
- 8.
References/handouts provided do not give away answers or aid in the elimination of Q?(A ~
distractors.
- 9.
Question content conforms with specific KIA statements in the previously approved I
examination outline and is appropriate for the tier to which they are assigned;
~ ~
deviations are justified.
- 10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
~ ~
- 11.
The exam contains the required number of one-point, multiple choice items; the
~ 11 7 total is correct and agrees with value on cover sheet.
~~
prU/~~
Date Author 4/1212007
- a.
Joseph G. Arsenault
"--'II
- b.
Facility Reviewer (*)
/;J, 1/, {l ~ f( rx 1/ /Jc l/~JJ JA~' ~i~1A
'1 f'fh{J()7
- c.
NRC Chief Examiner (#)
- d.
NRC Regional Supervisor Note:
The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
R FT NUREG-1021, Revision 9
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:
VC Summer Date of Exam:
6/4/2007 Exam ROISRO Level:
Initial Item Description a
b*
c#
1.
Questions and answers technically accurate and applicable to facility.
Sj7S 2.
a.
NRC K/As referenced for all questions.
b.
Facility_learning_objectives_referenced_as_available.
3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 4.
The sampling process was random and systematic. (If more than 4 RO and 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL Program Office) 5.
Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
the audit exam was systematically and randomly developed, or the audit exam was completed before the license exam was started, or the examinations were developed independently, or XX the licensee certifies that there is no duplication, or other (explain) 6.
Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest new or modified); enter the actual RO I SRO-only 55/ 52 8 / 4 37/44 question_distribution(s)_at_right._(IN_%)
7.
Between 50 and 60 percent of the question on the Memo CIA RO exam are written at the comprehension?
analysis level; the SRO exam may exceed 60 40 / 12 60/88 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question_distribution(s)_at_right_(IN_%)
8.
References/handouts provided do not give away answers or aid in the elimination of distractors.
9.
Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
11.
The exam contains the required number of one-point multiple choice items; the total is correct and agrees with value on cover sheet.
Printed Name / Sig t
Date a.
Author Joseph G. Arsenault 4/1212007 b.
Facility Reviewer (*)
J(/,;
c.
NRC Chief Examiner (#)
d.
NRC Regional Supervisor Note:
The facility reviewers initials/signature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
DRAFT NUREG.-1021, Revision 9 pECJ7 ES-401 Written Examination Quality Checklist Form ES-401-6 I Facility:
VC Summer Date of Exam:
6/4/2007 Exam RO/SRO Level:
Initial Item Description a
b*
c#
Questions and answers technically accurate and applicable to facility.
~
p-
- i.
- 2.
- a.
NRC KlAs referenced for all questions.
@\\)
~.
- b.
Facility learning objectives referenced as available.
- 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401
_GJA I~
- 4.
The sampling process was random and systematic. (If more than 4 RO and 2 SRO Vbb I
questions were repeated from the last 2 NRC licensing exams, consult the NRR OL
(£~
Program Office)
- 5.
Question duplication from the license screening/audit exam was controlled as I
indicated below (check the item that applies) and appears appropriate:
-- the audit exam was systematically and randomly developed, or
~
-- the audit exam was completed before the license exam was started, or
~
-- the examinations were developed independently, or XX the licensee certifies that there is no duplication, or other (explain)
- 6.
Bank use meets limits (no more than 75 percent Bank Modified New from the bank at least 10 percent new, and the rest 55/52 8/4 37/44 (jtI4 rf new or modified); enter the actual RO 1 SRO-only
....9.uestion distribution(s) at right.llN %)
- 7.
Between 50 and 60 percent of the question on the Memory CIA RO exam are written at the comprehension/
~ f-analYSis level; the SRO exam may exceed 60 40/12 60/88 percent if the randomly selected KlAs support the higher cognitive levels; enter the actual RO / SRO
....9.uestion distribution(s) at right{IN %)
- 8.
References/handouts provided do not give away answers or aid in the elimination of \\iU4 ~
distractors.
- 9.
Question content conforms with specific KIA statements in the previously approved I
examination outline and is appropriate for the tier to which they are assigned; GM ~.
deviations are justified.
- 10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
~ ~
- 11.
The exam contains the required number of one-point, multiple choice items; the
<W\\ ~
total is correct and agrees with value on cover sheet.
Pc;nted Name ~
Date
- a.
Author Joseph G. Arsenault L~,J.~ ~
4/1212007
~V:(/IU'~ {(QJI~k V£0~h :l ::J~.b
- b.
Facility Reviewer (*)
y/t-r (J 007 c,
NRC Chief Examiner (#)
v
- d.
NRC Regional Supervisor Note:
The facility reviewer'S initials/signature are not applicable for NRC-developed examinations.
Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
NUREG-1021, Revision 9 b15!R (8 (JTl(JY/
/;J PEeC8J/
Form ES-401-2 Facility:
VC Summer Date of Exam:
6/4/2007 RD K/A Category Points SROOnly_Points Tier Group K
K K
K K
K A
A A
A G
Total A2 G*
Total 1 234561 234*
1 1
543 13 2
18 3
3 6
Emergency
2 012 22 2
9 2
2 4
Abnormal Plant Tier 5
5 5
3 5
4 27 5
5 10 Evolutions Totals 2
1 54321021433 28 3
2 5
Plant 2
10 0
1 2
3 Systems Tier 54443233433 38 4
4 8
Totals
- 3. Generic Knowledge and 1
2 3
10 1
2 3
7 Abilities Categories 3
2 2
3 2
2 1
2 Note:
1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RD and SRD-only outlines (i.e., except for one category in Tier 3 of the SRD-only outline, the Tier Totals in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RD exam must total 75 points and the SRD-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 ES-401, Attachment 2, for guidance regarding elimination of inappropriate K/A 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 KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RD and SRO ratings for the RD and SRD-only portions, respectively.
6.
Select SRD topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7*
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
8.
Dn the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) 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. Use duplicate pages for RD and SRD-only exams.
9.
For Tier 3, select topics from Section 2 of the K/A Catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRD selections to K/As that are linked to 1 OCFR55.43 1
DRAFT ES-401 PWR Examination Form ES-401-2 Facility:
VC Summer Date of Exam:
6/4/2007 RO KIA Category Points SRO-Only Points Tier Group K
K K K K
K A A
A A
G Total A2 G*
Total 1
2 3
4 5
6 1
2 3
4
- 1.
1 5
4 3
1 3
2 18 3
3 6
Emergency 2
0 1
2 2
2 2
9 2
2 4
Abnormal 3
27 Plant Tier 5
5 5
5 4
5 5
10 Evolutions Totals
- 2.
1 5
4 3
- 2. 1 0
2 1
4 3
3 28 3
2 5
Plant 2
0 0
1 2
2 2
1 2
0 0
0 10 0
1 2
3 Systems Tier 5
4 4
4 3
2 Totals 3
3 4
3 3
38 4
4 8
- 3. Generic Knowledge and 1
2 3
4 10 1
2 3
4 7
Abilities Categories 3
2 2
3 2
2 1
2 Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding 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 KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KlAs 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.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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. 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 10CFR55.43 NUREG-1021 1
R FT
ES401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions Tier 1 Group 1 E!APE # / Name Safety Function G
Ki K2 K3 Al A2 Number K/A Topic(s)
Imp.
Q#
I Ability to determine and interpret the following as they 022 / Loss of Reactor Coolant Makeup I 2 X
AA2.02 apply to the Loss of Reactor Coolant Pump Makeup:
3.7 76 Charging pump problems Ability to determine or interpret the following as they 029 I Anticipated Transient Without Scram (ATWS) I I X
EA2.07 apply to a ATWS: Reactor trip breaker indicating 4.3 77 lights Emergency Procedures I Plan Knowledge of 038! Steam Generator Tube Rupture! 3 X
2.4.31 annunciators alarms and indications, and use of the 3.4 78 response instructions.
Emergency Procedures I Plan Ability to verify system 040 / Steam Line Rupture I 4 X
2.4.50 alarm setpoints and operate controls identified in the 3.3 79 alarm response manual.
Ability to determine or interpret the following as they 055 / Station Blackout! 6 X
EA2.02 apply to a Station Blackout: RCS core cooling 4.6 80 through natural circulation cooling to SIG cooling 056! Loss of Off-site Power! 6 X
2.4.6 Emergency Procedures / Plan Knowledge symptom 4.0 based EOP mitigation_strategies.
Knowledge of the reasons for the followlng as the 007! Reactor Trip! 1 X
EK3.01 apply to a reactor trip: Actions contained in EOP for 4.0 39 reactor trip Knowledge of the interrelations between the 008 I Pressurizer Vapor Space Accident! 3 X
AK2.01 Pressurizer Vapor Space Accident and the followlng:
2.7 40 Valves Knowledge of the operational implications of the 009 I Small Break LOCA ! 3 X
EK1.02 following concepts as they apply to the small break 3.5 41 LOCA: Use of steam tables Knowledge of the interrelations between the and the 2.6 42 011 ! Large Break LOCA! 3 X
EK2.02 following Large Break LOCA: Pumps Knowledge of the interrelations between the Reactor 015! 17! Reactor Coolant Pump Malfunctions! 4 X
AK2.08 Coolant Pump Malfunctions (Loss of RC Flow) and 2.6 43 the following: CCWS Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor 2.7 44 022 ! Loss of Reactor Coolant Makeup I 2 X
AK1.02 Coolant Pump Makeup: Relationship of charging flow to pressure differential between charging and RCS Knowledge of the reasons for the following responses 027! Pressurizer Pressure Control System Malfunction AK3.01 as they apply to the Pressurizer Pressure Control 45
/ 3 Malfunctions: Isolation of PZR spray following loss of PZR heaters NUREG-1021 2
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function Number KIA Topic(s)
Ability to determine and interpret the following as they 022 / Loss of Reactor Coolant Makeup / 2 X
AA2.02 apply to the Loss of Reactor Coolant Pump Makeup:
3.7 76 Charging pump problems Ability to determine or interpret the following as they 029/ Anticipated Transient Without Scram (ATWS) / 1 X
EA2.07 apply to a ATWS: Reactor trip breaker indicating 4.3 77 lights Emergency Procedures / Plan Knowledge of 038 j Steam Generator Tube Rupture! 3 X
2.4.31 annunciators alarms and indications, and use of the 3.4 78 response instructions.
Emergency Procedures / Plan Ability to verify system 040 ! Steam Line Rupture / 4 X
2.4.50 alarm setpoints and operate controls identified in the 3.3 79 alarm response manual.
Ability to determine or interpret the following as they 055 / Station Blackout / 6 X
EA2.02 apply to a Station Blackout: RCS core cooling 4.6 80 through natural circulation cooling to S/G cooling 056 I Loss of Off-site Power / 6 X
2.4.6 Emergency Procedures / Plan Knowledge symptom 4.0 81 based EOP mitigation strategies.
Knowledge of the reasons for the following as the 007/ Reactor Trip / 1 X
EK3.01 apply to a reactor trip: Actions contained in EOP for 4.0 39 reactor trip Knowledge of the interrelations between the 008 / Pressurizer Vapor Space Accident / 3 X
AK2.01 Pressurizer Vapor Space Accident and the following:
2.7 40 Valves Knowledge of the operational implications of the 009 / Small Break LOCA / 3 X
EK1.02 following concepts as they apply to the small break 3.5 41 LOCA: Use of steam tables 011 / Large Break LOCA / 3 X
EK2.02 Knowledge of the interrelations between the and the 2.6 42 following Large Break LOCA: Pumps Knowledge of the interrelations between the Reactor 015/ 17/ Reactor Coolant Pump Malfunctions / 4 X
AK2.08 Coolant Pump Malfunctions (Loss of RC Flow) and 2.6 43 the following: CCWS Knowledge of the operational implications of the 022 / Loss of Reactor Coolant Makeup /2 X
AK1.02 following concepts as they apply to Loss of Reactor 2.7 44 Coolant Pump Makeup: Relationship of charging flow to pressure differential between charging and RCS Knowledge of the reasons for the following responses 027 / Pressurizer Pressure Control System Malfunction X
AK3.01 as they apply to the Pressurizer Pressure Control 3.5 45
/3 Malfunctions: Isolation of PZR spray following loss of PZR heaters NUREG-1021 2
ES401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions Tier 1 Group 1 E/APE # I Name Safety Function G
Ki K2 K3 Al A2 Number K/A Topic(s)
Imp.
L Knowledge of the interrelations between the and the 029 / Anticipated Transient Without Scram (ATWS) / 1 X
EK2.06 following an ATWS: Breakers, relays, and 2.9 46 disconnects 038 / Steam Generator Tube Rupture / 3 X
2.2.22 Equipment control Knowledge of limiting conditions 3.4 47 for operations and safety limits.
Knowledge of the operational implications of the 054 / Loss of Main Feedwater / 4 X
AK1.01 following concepts as they apply to Loss of Main 4.1 48 Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)
Ability to operate and monitor the following as they 055 / Station Blackout / 6 X
EA1.07 apply to a Station Blackout: Restoration of power 4.3 49 from offsite Ability to determine and interpret the following as they 056 / Loss of Off-site Power / 6 X
AA2.50 apply to the Loss of Offsite Power: That load and 2.8 50 VAR limits, alarm setpoints, frequency and voltage limits for ED/Gs are not being exceeded Ability to determine and interpret the following as they 057 / Loss of Vital AC Electrical Instrument Bus / 6 X
AA2.19 apply to the Loss of Vital AC Instrument Bus: The 4.0 51 plant automatic actions that will occur on the loss of a vital ac electrical instrument bus Ability to determine and interpret the following as they 058/ Loss of DC Power! 6 X
AA2 02 apply to the Loss of DC Power: 125V dc bus voltage, 3.3 52 low/critical low, alarm Knowledge of the reasons for the following responses 065 / Loss of Instrument Air? 8 X
AK3.04 as they apply to the Loss of Instrument Air: Cross-3.0 53 over to backup air supplies Knowledge of the operational implications of the following concepts as they apply to the (LOCA E04 / LOCA Outside Containment / 3 X
EK1.2 Outside Containment) Normal, abnormal and 3.5 54 emergency operating procedures associated with (LOCA Outside Containment).
Knowledge of the operational implications of the following concepts as they apply to the (Loss of 3.7 55 Eli / Loss of Emergency Coolant Recirculation / 4 X
EK1.1 Emergency Coolant Recirculation) Components, capacity, and function of emergency systems.
Equipment Control Knowledge of bases in technical El2 / Uncontrolled Depressurization of all Steam 2.2.25 specifications for limiting conditions for operations 2.5 56 Generators / 4 and safety limits.
NUREG-l 021 3
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # I Name Safety Function G
K1 K2 K3 I A1 I A2 I Number KIA Topic(s) limp. I Q# II Knowledge of the interrelations between the and the 029/ Anticipated Transient Without Scram (ATWS) /1 x
EK2.06 following an ATWS: Breakers, relays, and 2.9 46 disconnects 038/ Steam Generator Tube Rupture / 3 X
2.2.22 Equipment Control Knowledge of limiting conditions 3.4 47 for operations and safety limits.
Knowledge of the operational implications of the 054 / Loss of Main Feedwater / 4 X
AK1.01 following concepts as they apply to Loss of Main 4.1 48 Feedwater (MFW): MFW line break depressurizes the S/G (similar to a steam line break)
Ability to operate and monitor the following as they 055 / Station Blackout / 6 X
EA1.07 apply to a Station Blackout: Restoration of power 4.3 49 from offsite Ability to determine and interpret the following as they 056 / Loss of Off-site Power / 6 X
AA2.50 apply to the Loss of Offsite Power: That load and 2.8 50 VAR limits, alarm setpoints, frequency and voltage limits for ED/Gs are not being exceeded Ability to determine and interpret the following as they 057/ Loss of Vital AC Electrical Instrument Bus / 6 X
AA2.19 apply to the Loss of Vital AC Instrument Bus: The 4.0 51 plant automatic actions that will occur on the loss of a vital ac electrical instrument bus Ability to determine and interpret the following as they 058 / Loss of DC Power / 6 X
AA202 apply to the Loss of DC Power: 125V dc bus voltage, 3.3 52 low/critical low, alarm Knowledge of the reasons for the follOwing responses 065/ Loss of Instrument Air /8 X
AK3.04 as they apply to the Loss of Instrument Air: Cross-3.0 53 over to backup air supplies Knowledge of the operational implications of the following concepts as they apply to the (LOCA E04/ LOCA Outside Containment / 3 X
EK1.2 Outside Containment) Normal, abnormal and 3.5 54 emergency operating procedures associated with (LOCA Outside Containment).
Knowledge of the operational implications of the E11 / Loss of Emergency Coolant Recirculation /4 X
EK1.1 following concepts as they apply to the (Loss of 3.7 55 Emergency Coolant Recirculation) Components, capacity, and function of emergency systems.
E12/ Uncontrolled Depressurization of all Steam Equipment Control Knowledge of bases in technical X
2.2.25 specifications for limiting conditions for operations 2.5 56 Generators / 4 and safety limits.
ES4O1 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions Tier 1 Group I E/APE # I Name Safety Function G
KI K2 K3 Al A2 Number K/A Topic(s)
Imp.
Q#
K/A Category Point Totals:
5 5
4 3
1 6
GroUP Point 24 NUREG-l 021 4
ES-401 E/APE # I Name Safety Function KJA Category Point Totals:
NUREG-1021 VC Summer NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 I G I K1 I K2 I K3 I A 1 I A2 I Number I 4
Group Point Total:
Form ES-401-2 KIA Topic(s)
Imp. I Q# II
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions Tier 1 Group 2 E/APE # / Name Safety Function G
Kl K2 K3 Al A2 Number K/A Topic(s)
Imp.
Q#
Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal:
001 / Continuous Rod Withdrawal / 1 X
AA2.05 4.6 82 Uncontrolled rod withdrawal, from available indications Ability to determine and interpret the following as they apply to the (Saturated Core Cooling)
E07 / Saturated Core Cooling / 4 X
EA2.2 Adherence to appropriate procedures and operation 3.9 83 within the limitations in the facilitys license and amendments.
E08 / Pressurized Thermal Shock I 4 X
2.2.22 Equipment Control Knowledge of limiting conditions 41 84 for operations and safety limits.
Conduct of Operations: Knowledge of system status El 5 I Containment Flooding / 5 X
2.1.14 criteria which require the notification of plant 3.3 85 personnel.
Ability to determine and interpret the following as 001 / Continuous Rod Withdrawal / 1 X
AA2.04 they apply to the Continuous Rod Withdrawal:
4.2 57 Reactor power and its trend Knowledge of the reasons for the following responses as they apply to the Pressurizer Level 028 / Pressurizer Level Control Malfunction / 2 X
AK3.03 Control Malfunctions: False indication of PZR level 3.5 58 when PORV or spray valve is open and RCS saturated Ability to operate and / or monitor the following as 036 / Fuel Handling Incidents / 8 X
Ml.01 they apply to the Fuel Handling Incidents: Reactor 3.3 59 Building Containment Purge Ventilation System Knowledge of the reasons for the following 051 / Loss of Condenser Vacuum / 4 AK3.01 responses as they apply to the Loss of Condenser 2.8 60 Vacuum: Loss of steam dump capability upon loss of condenser vacuum Conduct of Operations: Ability to recognize indications for system operating parameters which 3.4 61 E03 I LOCA Cooldown and Depressurization /4 X
2.1.33 are entry-level conditions for technical specifications.
Knowledge of the interrelations between the (Degraded Core Cooling) and the following:
Facilitys heat removal systems, including primary E06 I Degraded Core Cooling I 4 X
EK2.2 coolant, emergency coolant, the decay heat removal 3.8 62 systems, and relations between the proper operation of these systems to the operation of the facility.
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # I Name Safety Function Number KIA Topic(s)
Ability to determine and interpret the following as 001 ! Continuous Rod Withdrawal; 1 X
AA2.05 they apply to the Continuous Rod Withdrawal:
4.6 82 Uncontrolled rod withdrawal, from available indications Ability to determine and interpret the following as they apply to the (Saturated Core Cooling)
E07 ! Saturated Core Cooling! 4 X
EA2.2 Adherence to appropriate procedures and operation 3.9 83 within the limitations in the facility's license and amendments.
E08; Pressurized Thelmal Shock! 4 X
2.2.22 Equipment Control Knowledge of limiting conditions 4.1 84 for operations and safety limits.
Conduct of Operations: Knowledge of system status E 15 ; Containment Flooding / 5 X
2.1.14 criteria which require the notification of plant 3.3 85 personnel.
Ability to determine and interpret the following as 001 ; Continuous Rod Withdrawal! 1 X
AA2.04 they apply to the Continuous Rod Withdrawal:
4.2 57 Reactor power and its trend Knowledge of the reasons for the following responses as they apply to the Pressurizer Level 028 ; Pressurizer Level Control Malfunction! 2 X
AK3.03 Control Malfunctions: False indication of PZR level 3.5 58 when PORV or spray valve is open and RCS saturated Ability to operate and! or monitor the following as 036! Fuel Handling Incidents! 8 X
AA1.01 they apply to the Fuel Handling Incidents: Reactor 3.3 59 Building Containment Purge Ventilation System Knowledge of the reasons for the following 051 ; Loss of Condenser Vacuum! 4 X
AK3.01 responses as they apply to the Loss of Condenser 2.8 60 Vacuum: Loss of steam dump capability upon loss of condenser vacuum Conduct of Operations: Ability to recognize E03 ! LOCA Cooldown and Depressurization! 4 X
2.1.33 indications for system operating parameters which 3.4 61 are entry-level conditions for technical specifications.
Knowledge of the interrelations between the (Degraded Core Cooling) and the following:
Facility's heat removal systems, including primary E06 ! Degraded Core Cooling! 4 X
EK2.2 coolant, emergency coolant, the decay heat removal 3.8 62 systems, and relations between the proper operation of these systems to the operation of the facility.
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions Tier I Group 2 E/APE # I Name Safety Function G
Ki K2 K3 Al A2 Number K/A Topic(s)
Imp.
Q#
Ability to operate and / or monitor the following as they apply to the (Pressurized Thermal Shock)
E08 / Pressurized Thermal Shock /4 X
EA2.1 Facility conditions and selection of appropriate 3.4 63 procedures during abnormal and emergency operations.
conduct of Operations: Ability to perform specific ElO / Natural Circulation with Steam Void in Vessel X
2.1.23 system and integrated plant procedures during all 3.9 64 with/without RVLIS / 4 modes of plant operation.
Ability to operate and / or monitor the following as they apply to the (High Containment Radiation) 2.9 65 E16/ High Containment Radiation/9 X
EA1.3 Desired operating results during abnormal and emergency situations.
K/A Category Point Total:
4 0
1 2
2 4
Group Point Total:
13 NUREG-1021 6
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # I Name Safety Function Number KIA Topic(s)
Ability to operate and / or monitor the following as they apply to the (Pressurized Thermal Shock)
E08/ Pressurized Thermal Shock / 4 X
EA2.1 Facility conditions and selection of appropriate 3.4 63 procedures during abnormal and emergency operations.
E10/ Natural Circulation with Steam Void in Vessel Conduct of Operations: Ability to perform specific with/without RVLlS / 4 X
2.1.23 system and integrated plant procedures during all 3.9 64 modes of plant operation.
Ability to operate and / or monitor the following as E16/ High Containment Radiation / 9 X
EA1.3 they apply to the (High Containment Radiation) 2.9 65 Desired operating results during abnormal and emergency situations.
KJA Category Point Total:
4 0
1 2
2 4
Group Point Total: I 13 NUREG-1021 6
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Plant Systems Tier 2 Group 1 System #/Name G
Ki K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp.
Q#
Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS: and (b) 004 Chemical and Volume based on those predictions, use procedures to X
A2.15 3.7 86 Control correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS: and 010 Pressurizer Pressure Control A2.02 (b) based on those predictions, use procedures to 3.9 87 correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures Emergency Procedures / Plan Knowledge of 022 Containment Cooling X
2.4.30 which events related to system operations/status 3.6 88 should be reported to outside agencies.
Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS: and (b) based on predictions, use procedures to correct, 039 Main and Reheat Steam X
A2.05 control, or mitigate the consequences of those 3.6 89 malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power 076 Service Water X
2.4.6 Emergency Procedures / Plan Knowledge 4.0 90 symptom based EOP mitigation strategies.
003 Reactor Coolant Pump Ability to manually operate and/or monitor in the 3.2 control room: RCP cooling water supplies 004 Chemical and Volume Ability to monitor automatic operation of the X
A3.05 3.9 2
Control CVCS, including: RCS pressure and temperature Knowledge of the effect that a loss or malfunction 005 Residual Heat Removal X
K3.07 of the RHRS will have on the following: Refueling 3.2 3
operations Knowledge of bus power supplies to the following:
3.6 4
006 Emergency Core Cooling X
K2.01 ECCS pumps Ability to monitor automatic operation of the 3.6 5
006 Emergency Core Cooling X
A3.07 ECCS, including: RHR pumps 007 Pressurizer Relief/Quench Ability to manually operate and/or monitor in the X
A4.04 control room: PZR vent valve 2.6 6
Tank Knowledge of the physical connections and/or 008 Component Cooling Water X
Kl.03 cause-effect relationships between the CCWS and 2.8 7
the following systems: PRMS NUREG-1 021 7
ES-401 System #/Name 004 Chemical and Volume Control 010 Pressurizer Pressure Control 022 Containment Cooling X
039 Main and Reheat Steam 076 Service Water X
003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling X
006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water X
VC Summer NRC Written Examination Outline Plant Systems - Tier 2 Group 1 X
A2.15 X
A2.02 2.4.30 X
A2.05 2.4.6 X
A4.08 X
A3.05 K3.07 K2.01 X
A3.07 X
A4.04 K1.03 7
Form ES-401-2 KIA Topics Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to 3.7 86 correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to 3.9 87 correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures Emergency Procedures! Plan Knowledge of which events related to system operations/status 3.6 88 should be reported to outside agencies.
Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the ccnsequences of those 3.6 89 malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power Emergency Procedures / Plan Knowledge 4.0 90 symptom based EOP mitigation strategies.
Ability to manually operate and/or monitor in the 3.2 1
control room: RCP cooling water supplies Ability to monitor automatic operation of the 3.9 2
CVCS, including: RCS pressure and temperature Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: Refueling 3.2 3
operations Knowledge of bus power supplies to the following:
3.6 4
ECCS pumps Ability to monitor automatic operation of the 3.6 5
ECCS, including: RHR pumps Ability to manually operate and/or monitor in the 2.6 6
control room: PZR vent valve Knowledge of the physical connections and/or cause-effect relationships between the CCWS and 2.8 7
the following systems: PRMS
ES-401 VC Summer Form ES-401 -2 NRC Written Examination Outline Plant Systems Tier 2 Group 1 System #/Name G
Kl K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp.
Q#
Ability to monitor automatic operation of the PZR 010 Pressurizer Pressure Control X
A3.0l PCS, including: PRT temperature and pressure 3.0 8
during PORV testing Knowledge of the physical connections and/or 012 Reactor Protection X
K1.07 cause effect relationships between the RPS and 2.9 9
the following systems: SDS 012 Reactor Protection
[<2.01 Knowledge of bus power supplies to the following:
3.3 10 RPS channels, components, and interconnections Knowledge of the physical connections and/or 013 Engineered Safety Features X
K1.06 cause effect relationships between the ESFAS 4.2 11 Actuation and the following systems: ECCS Knowledge of the effect that a loss or malfunction 013 Engineered Safety Features X
K3.03 of the ESFAS will have on the following:
4.3 12 Actuation Containment Emergency Procedures / Plan Ability to verify that 022 Containment Cooling X
2.4.46 the alarms are consistent with the plant 3.5 13 conditions.
Knowledge of bus power supplies to the following:
2.7 14 026 Containment Spray X
K2.02 MOVs Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
3.8 15 026 Containment Spray K4.07 Adequate level in containment sump for suction Knowledge of MRSS design feature(s) and/or 039 Main and Reheat Steam X
K4.06 interlock(s) which provide for the following:
3.3 16 Prevent reverse steam flow on steam line break Emergency Procedures / Plan Ability to verify 059 Main Feedwater X
2.4.50 system alarm setpoints and operate controls 3.3 17 identified in the alarm response manual.
Knowledge of the operational implications of the 061 AuxilIary/Emergency X
K5.02 following concepts as the apply to the AFW:
3.2 18 Feedwater
Decay heat sources and magnitude Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution 2.5 19 062 AC Electrical Distribution X
Al.03 system controls including: Effect on instrumentation and controls of switching power supplies NUREG-1 021 8
ES-401 II System #/Name 010 Pressurizer Pressure Control 012 Reactor Protection 012 Reactor Protection 013 Engineered Safety Features Actuation 013 Engineered Safety Features Actuation 022 Containment Cooling 026 Containment Spray 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution NUREG-1021 VC Summer NRC Written Examination Outline Plant Systems - Tier 2 Group 1 G
Ki K2 I K3 I K4 K5 K6 Ai A2 A3 A4 Number X
A3.01 X
K1.07 X
K2.01 X
K1.06 X
K3.03 X
2.4.46 X
K2.02 X
K4.07 X
K4.06 X
2.4.50 X
K5.02 X
A1.03 8
Form ES-401-2 KIA Topics Imp.
Q#
Ability to monitor automatic operation of the PZR PCS, including: PRT temperature and pressure 3.0 8
during PORV testing Knowledge of the physical connections and/or cause effect relationships between the RPS and 2.9 9
the following systems: SDS Knowledge of bus power supplies to the following:
3.3 10 RPS channels, components, and interconnections Knowledge of the physical connections and/or cause effect relationships between the ESFAS 4.2 11 and the following systems: ECCS Knowledge of the effect that a loss or malfunction of the ESFAS will have on the following:
4.3 12 Containment Emergency Procedures / Plan Ability to verify that the alarms are consistent with the plant 3.5 13 conditions.
Knowledge of bus power supplies to the following:
2.7 14 MOVs Knowledge of CSS design feature(s) and/or interlock(s) which provide for the following:
3.8 15 Adequate level in containment sump for suction (interlock)
Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following:
3.3 16 Prevent reverse steam flow on steam line break Emergency Procedures / Plan Ability to verify system alarm setpoints and operate controls 3.3 17 identified in the alarm response manual.
Knowledge of the operational implications of the following concepts as the apply to the AFW:
3.2 18 Decay heat sources and magnitude Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution 2.5 19 system controls including: Effect on instrumentation and controls of switching power supplies
ES4O1 VC Summer Form ES-401-2 NRC Written Examination Outline Plant Systems Tier 2 Group 1
- System #/Name G
Kl K2 K3 K4 K5 K6 Al A2 A3 A4 Number K/A Topics Imp.
Q#
Ability to monitor automatic operation of the ac 062 AC Electrical Distribution X
A3.04 distribution system, including: Operation of 2.7 20 inverter (e.g., precharging synchronizing light,
static transfer)
Emergency Procedures / Plan Ability to recognize 063 DC Electrical Distribution X
2.4.4 abnormal indications for system operating 4.0 21 parameters which are entry-level conditions for
emergency and abnormal operating procedures.
Ability to predict and/or monitor changes in 064 Emergency Diesel Generator X
Al.05 parameters (to prevent exceeding design limits) 2.5 22 associated with operating the ED/G system controls including: D/G room temperature Knowledge of the physical connections and/or 064 Emergency Diesel Generator X
Kl.01 cause-effect relationships between the ED/G 4.1 23 system and the following systems: AC distribution 073 Process Radiation Monitoring A4.01 Ability to manually operate and/or monitor in the control room Effluent release 3.9 24 Knowledge of the physical connections and/or 073 Process Radiation Monitoring X
1<1.01 cause-effect relationships between the PRM 3.6 25 system and the following systems: Those systems Knowledge of the effect that a loss or malfunction 076 Service Water K3.05 of the SWS will have on the following: RHR 3.0 26 components, controls, sensors, indicators, and
alarms, including rad monitors 078 Instrument Air K2.02 Knowledge of bus power supplies to the following 3.3 27
Emergency air compressor Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use 103 Containment X
A2 04 procedures to correct, control, or mitigate the 3.5 28 consequences of those malfunctions or operations Containment evacuation (including recognition of thealarm)
K/A Category Point Totals:
5 5
4 3
2 1
0 2
4 4
3 Group Point Total:
33 NUREG-1021 9
ES-401 System #/Name 062 AC Electrical Distribution 063 DC Electrical Distribution X
064 Emergency Diesel Generator 064 Emergency Diesel Generator X
073 Process Radiation Monitoring 073 Process Radiation Monitoring X
076 Service Water X
078 Instrument Air X
103 Containment KIA Category Point Totals:
5 5
4 3
2 1
NUREG-1021 VC Summer NRC Written Examination Outline Plant Systems - Tier 2 Group 1 X
A3.04 2.4.4 X
A1.05 K1.01 X
A4.01 K1.01 K3.05 K2.02 X
A204 Form ES-401-2 KIA Topics Ability to monitor automatic operation of the ac distribution system, including: Operation of 2.7 20 inverter (e.g., precharging synchronizing light, static transfer)
Emergency Procedures / Plan Ability to recognize abnormal indications for system operating 4.0 21 parameters which are entry-level conditions for emergency and abnormal operating procedures.
Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 2.5 22 associated with operating the ED/G system controls including: D/G room temperature Knowledge of the physical connections and/or cause-effect relationships between the ED/G 4.1 23 system and the following systems: AC distribution system Ability to manually operate and/or monitor in the 3.9 24 control room Effluent release Knowledge of the physical connections and/or cause-effect relationships between the PRM 3.6 25 system and the following systems: Those systems served by PRMs Knowledge of the effect that a loss or malfunction of the SWS will have on the following: RHR 3.0 26 components, controls, sensors, indicators, and alarms, including rad monitors Knowledge of bus power supplies to the following 3.3 27 Emergency air compressor Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-and (b) based on those predictions, use procedures to correct, control, or mitigate the 3.5 28 consequences of those malfunctions or operations Containment evacuation (including recognition of the alarm) 0 2
4 4
3 Group Point Total:
I 33 9
ES-401 VC Summer Form ES-401-2 NRC Written Examination Outline Plant Systems Tier 2 Group 2 System #/Name G
KI K2 K3 K4 K5 K6 j Al A2 A3 A4 Number K/A Topics Imp.
Q#
Conduct of Operations: Ability to perform specific 001 Control Rod Drive X
2.1.23 system and integrated plant procedures during all 4.0 91 modes of plant operation.
Emergency Procedures / Plan Ability to explain 3.8 92 029 Containment Purge X
2.1.32 and apply all system limits and precautions.
Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System: and (b) based on those predictions, use 086 Fire Protection X
A2.03 procedures to correct, control, or mitigate the 2.9 93 consequences of those malfunctions or operations: Inadvertent actuation of the FPS due to circuit failure or welding Knowledge of the effect that a loss or malfunction 002 Reactor Coolant X
K3.03 of the RCS will have on the following:
4.2 29 Containment Knowledge of the effect of a loss or malfunction on the following will have on the PZR LCS:
2.8 30 011 Pressurizer Level Control X
K6.01 Reasons for starting charging pump while increasing letdown flow rate Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) 37 31 017 In-core Temperature Monitor X
A1.01 associated with operating the ITM system controls Core exit temperature Knowledge of the operational implications of the 027 Containment Iodine Removal X
K5.01 following concepts as they apply to the CIRS:
3.1 32 Purpose of charcoal filters Knowledge of the effect of a loss or malfunction 028 Hydrogen Recombiner and X
K6.01 on the following will have on the HRPS: Hydrogen 2.6 33 Purge Control recombiners Knowledge of design feature(s) and/or 033 Spent Fuel Pool Cooling X
K4.04 interlock(s) which provide for the following:
2.7 34 Maintenance of spent fuel pool radiation Knowledge of operational implications of the 035 Steam Generator X
K5.03 following concepts as the apply to the S/GS:
2.8 35 Shrink and swell concept Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) 041 Steam Dump/Turbine Bypass x
A2.02 based on those predictions, use procedures to 3.6 36 Control correct, control, or mitigate the consequences of those malfunctions or operations: Steam valve NUREG-1 021 10 ES-401 System #/Name 001 Control Rod Drive X
029 Containment Purge X
086 Fire Protection 002 Reactor Coolant X
011 Pressurizer Level Control 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 033 Spent Fuel Pool Cooling X
035 Steam Generator 041 Steam DumplTurbine Bypass Control NUREG-1021 X
X VC Summer NRC Written Examination Outline Plant Systems - Tier 2 Group 2 2.1.23 2.1.32 X
A2.03 K3.03 X
K6.01 X
A1.01 K5.01 X
K6.01 K4.04 K5.03 X
A2.02 10 Form ES-401-2 KIA Topics Conduct of Operations: Ability to perform specific system and integrated plant procedures during all 4.0 91 modes of plant operation.
Emergency Procedures / Plan Ability to explain 3.8 92 and apply all system limits and precautions.
Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use procedures to correct, control, or mitigate the 2.9 93 consequences of those malfunctions or operations: Inadvertent actuation of the FPS due to circuit failure or welding Knowledge of the effect that a loss or malfunction of the RCS will have on the following:
4.2 29 Containment Knowledge of the effect of a loss or malfunction on the following will have on the PZR LCS:
2.8 30 Reasons for starting charging pump while increasing letdown flow rate Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) 3.7 31 associated with operating the ITM system controls including: Core exit temperature Knowledge of the operational implications of the following concepts as they apply to the CIRS:
3.1 32 Purpose of charcoal filters Knowledge of the effect of a loss or malfunction on the following will have on the HRPS: Hydrogen 2.6 33 recombiners Knowledge of design feature(s) and/or interlock(s) which provide for the following:
2.7 34 Maintenance of spent fuel pool radiation Knowledge of operational implications of the following concepts as the apply to the S/GS:
2.8 35 Shrink and swell concept Ability to (a) predict the impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions, use procedures to 3.6 36 correct, control, or mitigate the consequences of those malfunctions or operations: Steam valve stuck open
ES-401 VC Summer Form ES-4O1-2 NRC Written Examination Outline Plant Systems Tier 2 Group 2 System #/Name
[ i A3 A4 Number K/A Topics
[
imp Knowledge of ARM system design feature(s) 072 Area Radiation Monitoring X
K4.03 and/or interlock(s) which provide for the following:
3.2 37 Plant ventilation systems Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection A2 System; and (b) based on those predictions, use 086 Fire Protection procedures to correct, control, or mitigate the 2.9 38 consequences of those malfunctions or operations: Manual shutdown of FPS KIA Category Point Totals:
2 0
0 1
2 2
2 1
3 0
0 Group Point Total:
13 NUREG-1021 11 ES-401 System #/Name G
Ki K2 K3 K4 K5 072 Area Radiation Monitoring X
086 Fire Protection KIA Category Point Totals:
2 0
0 1
2 2
NUREG-1021 VC Summer NRC Written Examination Outline Plant Systems - Tier 2 Group 2 K6 Ai A2 A3 A4 Number K4.03 X
A2.01 Form ES-401-2 KIA Topics Imp.
Q Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:
3.2 37 Plant ventilation systems Ability to (a) predict the impacts of the following malfunctions or operations on the Fire Protection System; and (b) based on those predictions, use 2.9 38 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Manual shutdown of FPS 2
1 3
0 0
Group Point Total: I 13 11
ES-401 Generic Knowledge and Abilities Outline (Tier3)
Form ES-401-3 Facility:
VC Summer Date of Exam:
6/4/2007 RO SRO-Only Category K/A #
Topic lR Q#
IR Q#
Knowledge of less than one hour technical 2.1.11 3.8 94 specification action statements for systems.
Ability to supervise and assume a 2.1.6 management role during plant transients 4.3 95 and upset conditions.
Ability to evaluate plant performance and 2.1.7 make operational judgments based on 3.7 66 Conduct of operating characteristics, reactor behavior, and instrument interpretation.
Operations 2.1.17 Ability to make accurate, clear and concise 3.5 67 verbal reports.
Knowledge of system purpose and or 2.1.27 2.8 68 function.
Subtotal 3
2 Knowledge of pre-and post-maintenance 2.2.21 3.5 96 operability requirements.
Knowledge of bases in technical 2.2.25 specifications for limiting conditions for 3.7 97 2.
operations and safety limits.
Equipment Control 2.2.24 Ability to analyze the affect of maintenance 2.6 69 activities on LCO status.
Knowledge of new and spent fuel 2.2.28 2.6 70 movement procedures.
Subtotal 2
2 2.3.2 Knowledge of facility ALARA program.
2.9 98 Knowledge of radiation exposure limits and 2.3.4 contamination control, including permissible 2.5 71 3.
levels in excess of those authorized.
Radiation Control Knowledge of 10 CFR: 20 and related 2.3.1 2.6 72 facility radiation control requirements Subtotal 2
Knowledge of the bases for prioritizing 2.4.22 safety functions during 4.0 99 abnormal/emergency operations.
Knowledge of abnormal condition 2.4.11 3.6 100 procedures.
Knowledge of low power / shutdown 4.
2.4.9 implications in accident (e.g. LOCA or loss 3.3 73 Emergency of RHR) mitigation strategies.
Procedures! Plan 2.4.29 Knowledge of the emergency plan.
2.6 74 Knowledge of crew roles and 2.4.13 3.3 75 responsibilities during EOP flowchart use.
Subtotal 3
2 Tier3PointTotal 10 7
NUREG-1021 12 0=8-401 1-Generic Knowledge and Abilities Outline (Tier3) 1 Form E8-401-3 I Facility: I VC Summer I Date of Exam: I 6/4/2007 RO SRO-Only Category KIA #
Topic IR Q#
IR Q#
2.1.11 Knowledge of less than one hour technical 3.8 94 specification action statements for systems.
Ability to supervise and assume a 2.1.6 management role during plant transients 4.3 95 and upset conditions.
Ability to evaluate plant performance and
- 1.
2.1.7 make operational judgments based on 3.7 66 Conduct of operating characteristics, reactor behavior, Operations and instrument interpretation.
2.1.17 Ability to make accurate, clear and concise 3.5 67 I
verbal reports.
2.1.27 Knowledge of system purpose and or 2.8 68 function.
Subtotal 3
2 2.2.21 Knowledge of pre-and post-maintenance 3.5 96 operability requirements.
Knowledge of bases in technical 2.2.25 specifications for limiting conditions for 3.7 97
- 2.
operations and safety limits.
Equipment Control 2.2.24 Ability to analyze the affect of maintenance activities on LCO status.
2.6 69 2.2.28 Knowledge of new and spent fuel 2.6 70 movement procedures.
Subtotal 2
2 2.3.2 Knowledge of facility ALARA program.
2.9 98 Knowledge of radiation exposure limits and
- 3.
2.3.4 contamination control, including permissible 2.5 71 I Radiation Control levels in excess of those authorized.
2.3.1 Knowledge of 10 CFR: 20 and related 2.6 72 facility radiation control requirements Subtotal 2
1 Knowledge of the bases for prioritizing 2.4.22 safety functions during 4.0 99 abnormal/emergency operations.
2.4.11 Knowledge of abnormal condition 3.6 100 procedures.
- 4.
Knowledge of low power 1 shutdown 2.4.9 implications in accident (e.g. LOCA or loss 3.3 73 Emergency of RHR) mitigation strategies.
Procedures 1 Plan 2.4.29 Knowledge of the emergency plan.
2.6 74 2.4.13 Knowledge of crew roles and 3.3 75 responsibilities during EOP flowchart use.
Subtotal 3
2 Tier 3 Point Total 10 7
NUREG-1021 12
I ES-401 Record of Rejected K/As j Form ES-401-4 I
Tier I Randomly Reason for Rejection Group Selected K/A 3 / 2 2.2.3 Not a dual unit facility. Randomly selected 2.2.25 ROs do not operate or monitor any fuel handling equipment, not on task list.
1/2 036AA1.04 Randomly selected 036 AA1.01 There no immediate actions associated with operation of this system.
2 / 1 022 G2.4.49 Randomly selected 2.4.46 2 / 1 103 A2.03 Direct overlap with simulator scenario. Randomly selected 103 A2.04 2/2 029 G2.4.6 System is not involved anywhere in EOPs. Randomly selected 029 G2.1.32 2 / 2 001 G2. 1.28 Purpose/function of system will not yield an SRO item related to IOCFR55.43(b). Randomly selected 001 G2.1.23 2 / 2 086 A2.03 Duplicate item with SRO exam. Randomly selected 086 A2.01 NUREG-1021 13
[£8-401 Record of Rejected KlAs I Form ES-401-4 I Tier 1 Randomly Reason for Rejection Group Selected KIA 3/2 2.2.3 Not a dual unit facility. Randomly selected 2.2.25 1 12 036 AA1.04 ROs do not operate or monitor any fuel handling equipment, not on task list.
Randomly selected 036 AA 1.01 2/1 022 G2.4.49 There no immediate actions associated with operation of this system.
Randomly selected 2.4.46 2/1 103 A2.03 Direct overlap with simulator scenario. Randomly selected 103 A2.04 2/2 029 G2.4.6 System is not involved anywhere in EOPs. Randomly selected 029 G2.1.32 2/2 001 G2.1.28 Purpose/function of system will not yield an SRO item related to I
10CFR55.43(b). Randomly selected 001 G2.1.23 2/2 086 A2.03 Duplicate item with SRO exam. Randomly selected 086 A2.01 I
NUREG-1021 13