ML101650158
| ML101650158 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/28/2010 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML101650158 (42) | |
Text
ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6 Facility:
Date of Exam:
b*
c#
1.
Questions and answers are technically accurate and applicable to the facility.
2.
a.
NRC KIAs are referenced for all questions.
b.
Facility learning objectives are referenced as available.
JJ iJfj 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401
)J
ékL 4.
The sampling process was random and systematic (If more than 4 RO or 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 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);
)JL.
enter the actual RO 1 SRO-only question distribution(s) at right.
tj3 311 010 72124 7.
Between 50 and 60 percent of the questions on the RO exam Memory CIA are written at the comprehension! analysis level; the SRO exam may exceed 60 percent if the randomly selected KIAs support the higher cognitive levels; enter the actual RO I SRO question distribution(s) at right.
3315 42120 8.
Referenceslhandouts provided do not give away answers or aid in the elimination of distractors.
i) j&j
</
9.
Question content conforms with specific KIA statements in the previously approved examination 1
J outline and is appropriate for the tier to which they are assigned; deviations are justified.
iAJ
&oc 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
)
L.
and agrees with the value on the cover sheet.
Printed Name I Signature Date kA i
Ii
- a. Author U1 L&.,.
I c / LV...
O2.2?-D7
- b. Facility Reviewer (*)
( A.
1 a.4.
- c. NRC Chief Examiner (#)
Z-.
7.
tc/ J-f v
...Z
- d. NRC Regional Supervisor
[-- i4AA-/ 7Z._4-.4 Note:
- The facility reviewers initialslsignature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
12 ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6 I
Facility:
. Date of Exam:
- 1.
Questions and answers are technically accurate and applicable to the facility.
- 2.
- a.
NRC K/As are referenced for all questions.
- b.
Facility learning objectives are 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 or 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:
X 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
_ the licensee certifies that there is no duplication, or
_ other (explain)
- 6.
Bank use meets limits (no more than 75 percent from the bank, at least 10 percent new, and the rest new or modified);
enter the actual RO I SRO-only question distribution(s) at right.
- 7.
Between 50 and 60 percent of the questions on the RO exam are written at the comprehensionl analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO I SRO question distribution(s) at right.
Bank Modified 311 0 I 0 Memory 33/5 New 72/24 CIA 42/20
- 8.
References/handouts provided do not give away answers or aid in the elimination of distractors.
- 9.
Question content conforms with specific KIA 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 the value on the cover sheet.
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor
{
'/
Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
w
\\J Initial
/J~ IL~;L~)
j:Jd.- I,/;i Date Ol-27-D7 ilElo"l
~7
~7
- Independent NRC reviewer initial items in Column HC"; chief examiner concurrence required.
12
ES-401 PWR Examination Outline (RO Exam)
Form ES-401-2
{PRIVATE ) Facility:
Turkey Point RO KIA Category Points Tier Group KKKKKKAAAAG 1
2 3
4 5
6 1
2 3
4 Total 1.
1 523 23 3
18 Emergency
& Abnormal NIA NIA Plant Evolutions 2
204 01 2
9 TierTotal 7
2 7
2 4
5 27 S
1 42041134243 28 2.
Plant Systems 2
102011 11012 10 TierTotal 5
2 2
4 2
2 4
5 2
5 5
38 S
- 3. Generic Knowledge and Abilities 1
2 3
4 Categories 2
3 3
2 10 1
ES-401 PWR Examination Outline (RO Exam)
Form ES-401-2
{PRIVATE} Facility: Turkey Point RO KIA Category Points Tier Group K
K K
K K
K A
A A
A G
1 2
3 4
5 6
1 2
3 4
Total II*
- 1.
1 5
2 3
2 3
3 18 Emergency
& Abnormal N/A N/A Plant Evolutions 2
2 0
4 0
1 2
9 Tier Total 7
2 7
2 4
5 27 s
1 4
2 0
4 1
1 3
4 2
4 3
28
- 2.
Plant Systems 2
1 0
2 0
1 1
1 1
0 1
2 10 Tier Total 5
2 2
4 2
2 4
5 2
5 5
38 s
- 3. Generic Knowledge and Abilities 1
2 3
4 Categories 2
3 3
2 10 1
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.
Systemslevolutions 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 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 K!As having an importance rating (lR) 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 I and 2 from the shaded systems and K!A categories.
7*
The generic (G) KIAs in Tiers I 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.
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 # I does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
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:t1 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 the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
2
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group I (RO)
E!APE #1 Name I Safety Function K
1<
K A
A G
K!A Topic(s) lR 12312 000007 Reactor Trip - Stabilization -
0 Able to determine and interpret 4.3!
1 Recovery I 1 2
following as they apply to reactor trip:
4.6 Proper actions to be taken if the automatic safety functions have not taken place 000008 Pressurizer Vapor Space 0
Knowledge for the reasons for the 4.0!
1 Accident I 3 5
following responses as they apply to the 4.5 PRZ vapor space accident: ECCS terminating or throttling criteria 000009 Small Break LOCA /3 NOT SELECTED 0
000011 Large Break LOCA I 3 0
Able to determine and interpret the 3.3!
1 2
following as they apply to a LBLOCA:
3.7
Consequences to RHR of not resetting SI 000015/17 RCP Malfunctions /4 0
Able to operate and/or monitor the 2.8/
1 2
following as they apply to the RCP 2.7 Malfunctions (Loss of RC flow): RCP Oil
Reservoir level and alarm indicators 000022 Loss of Rx Coolant Makeup!
0 Knowledge for the reasons for the 3.0/
1 2
7 following responses as they apply to the 3.2 Loss of Reactor Coolant Makeup:
Isolating charging 000025 Loss of RHR System /4 0
Able to operate and/or monitor the 2.8!
1 4
following as they apply to the Loss of 2.6 RHR System: Closed cooling water pumps 000026 Loss of Component Cooling 0
Knowledge for the reasons for the 4.0!
1 Water! 8 3
following responses as they apply to the 4.2 loss of CCW: Guidance contained in EOP for loss of CCW.
000027 Pressurizer Pressure Control 0
Knowledge of the operational 2.8!
1 System Malfunction! 3 2
implications of the following concepts as 3.1 they apply to the pressurizer pressure control malfunctions: Expansion of liquids as temperature increases 000029 ATWS I 1 1.30 As It relates to the ATWS event: Able to 3.9/
1 locate and operate components, 4.0 including local controls 000038 Steam Gen. Tube Rupture I 3 0
Knowledge of the operational 3.21 1
2 implications of the following concepts as 3.5 they apply to the SGTR: Leak rate vs pressure drop 000040 (W!E12) Steam Line Rupture -
0 000040 SELECTED, W!E12 NOT 2.6!
1 Excessive Heat Transfer! 4 1
SELECTED Knowledge of the 2.5 interrelations between the steam line rupture and the following: Valves 3
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
EIAPE # I Name I Safety Function K K K A A G
KIA Toplc(s)
IR 1
2 3 1 2 000007 Reactor Trip - Stabilization -
0 Able to determine and Interpret 4.31 1
Recovery 11 2
following as they apply to reactor trip:
4.6 Proper actions to be taken If the automatic safety functions have not taken place 000008 Pressurizer Vapor Space 0
Knowledge for the reasons for the 4.01 1
Accident I 3 5
following responses as they apply to the 4.5 PRZ vapor space accident: ECCS terminating or throttling criteria 000009 Small Break LOCA I 3 NOT SELECTED 0
000011 Large Break LOCA I 3 0
Able to determine and Interpret the 3.31 1
2 following as they apply to a LBLOCA:
3.7 Consequences to RHR of not resetting SI 000015/17 RCP Malfunctions I 4 0
Able to operate andlor monitor the 2.81 1
2 following as they apply to the RCP 2.7 Malfunctions (Loss of RC flow): RCP Oil Reservoir level and alarm Indicators 000022 Loss of Rx Coolant Makeup I 0
Knowledge for the reasons for the 3.01 1
2 7
following responses as they apply to the 3.2 Loss of Reactor Coolant Makeup:
Isolating charging.
000025 Loss of RHR System I 4 0
Able to operate andlor monitor the 2.81 1
4 following as they apply to the Loss of 2.6 RHR System: Closed cooling water pumps 000026 Loss of Component Cooling 0
Knowledge for the reasons for the 4.01 1
Water 18 3
following responses as they apply to the 4.2 loss of CCW: Guidance contained In EOP for loss of CCW.
000027 Pressurizer Pressure Control 0
Knowledge of the operational 2.81 1
System Malfunction I 3 2
Implications of the following concepts as 3.1 they apply to the pressurizer pressure control malfunctions: Expansion of liquids as temperature Increases 000029 A TWS 11 1.30 As It relates to the ATWS event: Able to 3.91 1
locate and operate components, 4.0 including local controls 000038 Steam Gen. Tube Rupture I 3 0
Knowledge of the operational 3.21 1
2 implications of the following concepts as 3.5 they apply to the SGTR: Leak rate vs pressure drop 000040 (W/E12) Steam Line Rupture-0 000040 SELECTED, W/E12 NOT 2.61 1
Excessive Heat Transfer I 4 1
SELECTED Knowledge of the 2.5 Interrelations between the steam line rupture and the following: Valves 3
{PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier llGroup I (RO)
E!APE #1 Name! Safety Function K
K K
A A
G K/A Topic(s)
IR 12312 000054 Loss of Main Feedwater!4 0
Knowledge of the operational 4.1/
1 I
Implications of the following concepts as 4.3 they apply to the Loss of Main FW: MFW line break depressurizes the S!G (similar to a steam line break) 000055 Station Blackout!6 0
Knowledge of the operational 4.1!
1 2
implications of the following concepts as 4.4 they apply to the station blackout:
Natural Circulation Cooling 000056 Loss of Off-site Power! 6 NOT SELECTED 0
000057 Loss of Vital AC Inst. Bus /6 NOT SELECTED 0
000058 Loss of DC Power! 6 4.4 As it relates to the loss of DC power 4.0!
1 event: Able to recognize abnormal 4.3 Indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.
000062 Loss of Nuclear Svc Water! 4
NOT SELECTED 0
000065 Loss of Instrument Air! B 1.23 As It relates to the loss of Instrument air 3.9!
1 event: Able to perform specific system 4.0 and Integrated plant procedures during all modes of plant operation W/E04 LOCA Outside Containment! 3 1
Able to determine and interpret the 3.4!
1 following as they apply to the LOCA OC:
4.3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
W!E1 I Loss of Emergency Coolant 2
Knowledge of the Interrelations between 3.9!
1 Recirc. I 4 the loss of emergency coolant recirc 4.3 and the following: facilitys heat removal systems md primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
W!E05 Inadequate Heat Transfer -
2 Knowledge of the operational implications 3.9!
1 Loss of Secondary Heat Sink! 4 of the following concepts as they apply to 4.5 the Loss of secondary heat sink: Normal, abnormal and emergency operating procedures associated with the loss of secondary heat sink K!ACategoryTotals:
[5 2
3 2
3 3
Group PointTotal:
18 4
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
EIAPE # I Name I Safety Function K K K A A G
KIA Topic(s)
IR 1
2 3 1 2 000054 Loss of Main Feedwater I 4 0
Knowledge of the operational 4.11 1
1 implications of the following concepts as 4.3 they apply to the Loss of Main FW: MFW line break depressurizes the S/G (similar to a steam line break) 000055 Station Blackout 16 0
Knowledge of the operational 4.11 1
2 implications of the following concepts as 4.4 they apply to the station blackout:
Natural Circulation Cooling 000056 Loss of Off-site Power 16 NOT SELECTED 0
000057 Loss of Vital AC Inst. Bus I 6 NOT SELECTED 0
000058 Loss of DC Power 16 4.4 As it relates to the loss of DC power 4.01 1
event: Able to recognize abnormal 4.3 indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures.
000062 Loss of Nuclear Svc Water I 4 NOT SELECTED 0
000065 Loss of Instrument Air 18 1.23 As it relates to the loss of instrument air 3.91 1
event: Able to perform specific system 4.0 and integrated plant procedures during all modes of plant operation.
W/E04 LOCA Outside Containment I 3 1
Able to determine and interpret the 3.41 1
following as they apply to the LOCA OC:
4.3 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
W/E11 Loss of Emergency Coolant
- 2 Knowledge of the interrelations between 3.91 1
Recirc./4 the loss of emergency coolant recirc 4.3 and the following: facility's heat removal systems inc I primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
W/E05 Inadequate Heat Transfer-2 Knowledge of the operational implications 3.91 1
Loss of Secondary Heat Sink I 4 of the following concepts as they apply to 4.5 the Loss of secondary heat sink: Normal, abnormal and emergency operating procedures associated with the loss of secondary heat sink KIA Category Totals:
5 2 3 2 3 3 ~up Point Total:
18 4
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
EIAPE #1 Name / Safety Function K
K K
A A
G K/A Topic(s)
IR 12312 000001 Continuous Rod Withdrawal / I NOT SELECTED 0
000003 Dropped Control Rod I I
NOT SELECTED 0
000005 Inoperable/Stuck Control Rod / I NOT SELECTED 0
000024 Emergency Boratlon I I NOT SELECTED 0
000028 Pressurizer Level Malfunction /2 NOT SELECTED 0
000032 Loss of Source Range NI /7
NOT SELECTED 0
000033 Loss of Intermediate Range NI I 7
NOT SELECTED 0
000036 Fuel Handling Accident! 8 0
Able to determine and interpret the 3.2!
1 I
following as they apply to the fuel 3.9 handling Incidents: ARM system Indications 000037 Steam Generator Tube Leak! 3 0
Knowledge for the reasons for the 3.1!
1 3
following responses as they apply to 3.3 the SGTL: comparison of makeup flow and letdown flow for various modes of operation 000051 Loss of Condenser Vacuum /4 0
Knowledge for the reasons for the 2.8!
1 I
following responses as they apply to 3.1 the loss of condenser vacuum: loss of steam dump capability upon loss of condenser vacuum 000059 Accidental Liquid RadWaste Rel. /9 NOT SELECTED 0
000060 Accidental Gaseous Radwaste Rel.!
NOT SELECTED 0
9 000061 ARM System Alarms! 7 NOT SELECTED 0
000067 Plant Fire On-site/B NOT SELECTED 0
000068 Control Room Evac. /8 1.28 As it relates to the control room 3.2!
1 evacuation event: Knowledge of the 3.3 purpose and function of major system components and controls 000069 (W!E14) Loss of CTMT Integrity! 5 3
W!E14 SELECTED, 000069 NOT 3.5!
1 SELECTED Knowledge for the 3.5 reasons for the following responses as they apply to the high containment pressure: manipulation of controls required to obtain desired operating results during abnormal and emergency situations.
5
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
EIAPE # I Name I Safety Function K K K A A G
KIA Topic(s)
IR 1
2 3 1 2 000001 Continuous Rod Withdrawal/1 NOT SELECTED 0
000003 Dropped Control Rod 11 NOT SELECTED 0
000005 InoperablelStuck Control Rod 11 NOT SELECTED 0
000024 Emergency Boration 11 NOT SELECTED 0
000028 Pressurizer Level Malfunction 12 NOT SELECTED 0
000032 Loss of Source Range NI/7 NOT SELECTED 0
000033 Loss of Intermediate Range Nil 7 NOT SELECTED 0
000036 Fuel Handling Accident I 8 0
Able to determine and interpret the 3.21 1
1 following as they apply to the fuel 3.9 handling incidents: ARM system indications 000037 Steam Generator Tube Leak 13 0
Knowledge for the reasons for the 3.11 1
3 following responses as they apply to 3.3 the SGTL: comparison of makeup flow and letdown flow for various modes of operation 000051 Loss of Condenser Vacuum I 4 0
Knowledge for the reasons for the 2.81 1
1 following responses as they apply to 3.1 the loss of condenser vacuum: loss of steam dump capability upon loss of condenser vacuum 000059 Accidental Liquid RadWaste Rei. I 9 NOT SELECTED 0
000060 Accidental Gaseous Radwaste Rei. I NOT SELECTED 0
9 000061 ARM System Alarms I 7 NOT SELECTED 0
000067 Plant Fire On-site 18 NOT SELECTED 0
000068 Control Room Evac. I 8 1.28 As it relates to the control room 3.21 1
evacuation event: Knowledge ofthe 3.3 purpose and function of major system components and controls 000069 (W/E14) Loss of CTMT Integrity 15 3
W/E14 SELECTED, 000069 NOT 3.51 1
SELECTED Knowledge for the 3.5 reasons for the following responses as they apply to the high containment pressure: manipulation of controls required to obtain desired operating results during abnormal and emergency situations.
5
{PRIVATE )ES-4o1 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier llGroup 2 (RO)
EIAPE #1 Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 12312 000074 (WIEO6&E07) Inad. Core Cooling! 4 1
WIEO6 SELECTED, 000074 & WIEO7 3.6!
1 NOT SELECTED Knowledge of the 4.0 operational implications of the following concepts as they apply to the degraded core cooling: components, capacity and function of emergency systems.
000076 High Reactor Coolant Activity! 9
NOT SELECTED 0
WIEOI & E02 Rediagnosis & SI Termination I
WIEO2 SELECTED WIEOI NOT 3.3!
1 I 3 SELECTED Knowledge for the 3.6 reasons for the following responses as they apply to the SI termination:
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
WIEI3 Steam Generator Over-pressure 14 NOT SELECTED 0
WIEI5 Containment Flooding! 5
NOT SELECTED 0
WIEI6 High Containment Radiation! 9 NOT SELECTED 0
WIEO3 LOCA Cooldown - Depress. I 4 3
Knowledge of the operational 3.5!
1 implications of the following concepts 3.8 as they apply to LOCA Cooldown and Depressurization: annunciators and conditions, indicating signals and remedial actions associated with the (LOCA cooldown and depressurization W!E09&E1 0 Natural Circ. ! 4 NOT SELECTED 0
WIEO8 RCS Overcooling - PTS 14 1.28 As it relates to the PTS event:
3.2!
1 Knowledge of the purpose and 3.3 function of major system components and controls.
K!A Category Point Totals:
2[0[4 0
1 2
Group Point Total:
9 6
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)
E/APE # I Name I Safety Function K K K A A G
KIA Toplc(s)
IR 1
2 3
1 2
000074 (W/E06&E07) Inad. Core Cooling 14 1
W/E06 SELECTED, 000074 & W/E07 3.61 1
NOT SELECTED Knowledge of the 4.0 operational implications of the following concepts as they apply to the degraded core cooling: components, capacity and function of emergency systems.
000076 High Reactor Coolant Activity I 9 NOT SELECTED 0
W/E01 & E02 Redlagnosis & SI Termination 1
W/E02 SELECTED W/E01 NOT 3.31 1
13 SELECTED Knowledge for the 3.6 reasons for the following responses as they apply to the SI termination:
Facility operating characteristics during transient conditions, Including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
W/E13 Steam Generator Over-pressure I 4.
NOT SELECTED 0
W/E15 Containment Flooding I 5 NOT SELECTED 0
W/E16 High Containment Radiation 19 NOT SELECTED 0
W/E03 LOCA Cooldown - Depress. I 4 3
Knowledge of the operational 3.51 1
implications of the following concepts 3.8 as they apply to LOCA Cooldown and Depressurization: annunciators and conditions, indicating signals and remedial actions associated with the (LOCA cooldown and depressurization W/E09&E10 Natural Circ. 14 NOT SELECTED 0
W/E08 RCS Overcooling - PTS I 4 1.28 As it relates to the PTS event:
3.21 1
Knowledge of the purpose and 3.3 function of major system components and controls.
I~ry Point Totals:
2 0 4 0 1 2
Group Point Total:
9 6
{PRIVATE }ES-4o1 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2!Group I (RO)
System #! Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1234561234 003 Reactor Coolant Pump 0
Ability to manually operate and/or 2.6/
7 monitor In the control room RCP 2.6 seal bypass 004 Chemical and Volume 2
1 Knowledge of the physical 3.4!
Control 3
1 connectIon andlor cause-effect 3.7 relationships between the CVCS and the RWST Ability to (a) predict the impacts 3.6!
of the following malfunctions or 4.2 operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
loss of lAS 005 ResIdual Heat Removal 1.30 As It relates to RHR, ability to 3.9!
locate and operate components, 3.4 including local controls 006 Emergency Core Cooling 0
Ability to manually operate and/or 4.2!
8 monitor in the control room 4.3 007 Pressurizer Relief/Quench 0
Ability to predict and/or monitor 2.71 Tank 2
changes In parameters (to 2.9 prevent exceeding design limits) associated with operating the PRTS controls Including maintaining PRT pressure.
008 Component Cooling Water 0
Ability to manually operate and/or 3.11 B
monitor In the control room: CCW 2.8 pump control switch 010 Pressurizer Pressure 0
Ability to (a) predict the impacts 3.3!
Control I
of the following malfunctions or 3.6 operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Heater failures 7
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K K K K K K A A A A G
K/A Topic(s)
IR 1
2 3 4 5
6 1 2 3 4 003 Reactor Coolant Pump 0
Ability to manually operate and/or 2.6/
1 7
monitor in the control room RCP 2.6 seal bypass 004 Chemical and Volume 2
1 Knowledge of the physical 3.4/
1 Control 3
1 connection and/or cause-effect 3.7 relationships between the CVCS and the RWST Ability to (a) predict the impacts 3.6/
of the following malfunctions or 4.2 1
operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
loss of lAS 005 Residual Heat Removal 1.30 As it relates to RHR, ability to 3.9/
1 locate and operate components, 3.4 including local controls 006 Emergency Core Cooling 0
Ability to manually operate and/or 4.2/
1 8
monitor in the control room 4.3 007 Pressurizer Relief/Quench 0
Ability to predict and/or monitor 2.7/
1 Tank 2
changes in parameters (to 2.9 prevent exceeding design limits) associated with operating the PRTS controls including maintaining PRT pressure.
008 Component Cooling Water 0
Ability to manually operate and/or 3.1/
1 8
monitor in the control room: CCW 2.8 pump control switch 010 Pressurizer Pressure 0
Ability to (a) predict the impacts 3.3/
1 Control 1
of the following malfunctions or 3.6 operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose malfunctions or operations:
Heater failures 7
061 AuxIliary/Emergency Feedwater Knowledge of the AFW design feature(s) andlor Interlock(s) which provide for: AFW automatic start upon loss of MFW pump, SIG level, blackout or SI Ability to monitor automatic operation of the AFW, Including:
AFW startup and flows
{PRIVATE }ES-4o1 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group I (RO)
System # I Name K
K K
K K
K A
A A
A G
K/A Topic(s)
IR 1234561234 012 Reactor ProtectIon 0
0 Knowledge of the RPS design 3.2!
6 2
feature(s) and/or interlock(s) 3.5 which provide for automatic or manual enable/disable of RPS trips Knowledge of the effect of a loss 2
or malfunction of the following will have on the RPS: Redundant Channels 013 Engineered Safety 0
Ability to manually operate and/or 4 3/
Features Actuation 2
monitor in the control room reset 4 4 of ESFAS channels 022 Containment Cooling 0
x Knowledge of the power supplies 3.0!
I
to the containment cooling fans 3.1 026 Containment Spray 0
0 Knowledge of the CSS design 4.2!
I I
feature(s) and/or interlock(s) 4.3 which provide for: source of water for CSS, Including recirculatlon phase after LOCA Ability to predict and/or monitor 3,
changes in parameters (to 42 prevent exceeding design limits) associated with operating the CSS controls Including containment pressure 039 MaIn and Reheat Steam 0
x Knowledge of the operational 2.7/
5 implicatIons of the following 3.1 concept as It applies to the MRSS: Basis for the RCS cooldown limits 059 Main Feedwater 0
x 0
Knowledge of the physical 3.1!
3 2
connection and/or cause-effect 3.3 relationships between the main feedwater and the S/Gs.
Ability to monitor automatic 291 31 operation of the MFW, including programmed levels of the SIG 0
2 0
I 4.5!
4.6 4.2/
4.2 I
I 8
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # / Name K K K K K K A A A A G
K/A Topic(s)
IR 1
2 3 4 5
6 1 2 3 4 012 Reactor Protection 0
0 Knowledge of the RPS design 3.2/
1 6
2 feature(s) and/or interlock(s) 3.5 which provide for automatic or manual enable/disable of RPS trips Knowledge of the effect of a loss 2.9/
or malfunction of the following will 3.1 1
have on the RPS: Redundant Channels 013 Engineered Safety 0
Ability to manually operate and/or 4.3/
1 Features Actuation 2
monitor in the control room reset 4.4 of ESFAS channels 022 Containment Cooling 0
x Knowledge of the power supplies 3.0/
1 1
to the containment cooling fans 3.1 026 Containment Spray 0
0 Knowledge of the CSS design 4.2/
1 1
1 feature(s) and/or interlock(s) 4.3 which provide for: source of water for CSS, including recirculation phase after LOCA Ability to predict and/or monitor 3.9/
changes in parameters (to 4.2 1
prevent exceeding design limits) associated with operating the CSS controls including containment pressure 039 Main and Reheat Steam 0
x Knowledge of the operational 2.7/
1 5
implications of the following 3.1 concept as it applies to the MRSS: Basis for the RCS cooldown limits 059 Main Feedwater 0
x 0
Knowledge of the physical 3.1/
1 3
2 connection and/or cause-effect 3.3 relationships between the main feedwater and the S/Gs.
Ability to monitor automatic 2:9/
operation ofthe MFW, including 3.1 1
programmed levels ofthe S/G 061 Auxiliary/Emergency 0
0 Knowledge of the AFW design 4.5/
1 Feedwater 2
1 feature(s) and/or interlock(s) 4.6 which provide for: AFW automatic start upon loss of MFW pump, S/G level, blackout or SI Ability to monitor automatic 4.2/
operation ofthe AFW, including:
4.2 1
AFW startup and flows 8
062 AC Electrical Distribution x
2.25 As It relates to the AC Electrical 2.5!
1 Distribution: Knowledge of the 3.7 bases in Tech Specs for LCOs and safety limits 9
062 AC Electrical Distribution x
2.25 As it relates to the AC Electrical 2.5/
1 Distribution: Knowledge of the 3.7 bases in Tech Specs for LCOs and safety limits 9
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System #1 Name K
K K
K K
K A
A A
A G
KIA Topic(s) lR 1234561234 063 DC Electrical DistributIon 0
Knowledge of the physical 2.9/
3 connection and/or cause-effect 3.5 relationships between the DC Electrical Distribution and the battery charger and battery 064 Emergency Diesel 0
x 1.23 Knowledge of the power supplies 2.9!
Generator 3
to the control power 3.3 As it relates to the EDG, ability to 3.9!
perform specific system and 4.0 integrated plant procedures during all modes of plant operatiion 073 Process Radiation 0
AbilIty to (a) predict the impacts 2.7!
Monitoring 2
of the following malfunctions or 3.2 operations on the PRMS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
detector failure 076 Service Water 0
Ability to predict and/or monitor 2.6!
2 changes in parameters (to 2.6 prevent exceeding design limits) associated with operating the Service Water controls including reactor and turbine building closed cooling water temperatures 078 Instrument Air 0
x Knowledge of the physical 2.7!
2 connection and/or cause-effect 2.8 relationships between the Instrument air and the service air 103 Containment 0
0 Knowledge of the Ctmt design 3.1/
6 3
feature(s) and/or interlock(s) 3.7 which provide for containment isolation system Ability to (a) predict the impacts of the following malfunctions or operations on the Ctmt; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Phase A & B Isolation K/A Category Point Totals:
] 4 2 0J 4 1 [
[
3 Group Point Total:
28 10
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)
System # I Name K K K K K K A A A A G
KIA Toplc(s)
IR 1
2 3
4 5
6 1
2 3
4 063 DC Electrical Distribution 0
Knowledge of the physical 2.91 1
3 connection andlor cause-effect 3.5 relationships between the DC Electrical Distribution and the battery charger and battery 064 Emergency Diesel 0
x 1.23 Knowledge of the power supplies 2.91 1
Generator 3
to the control power 3.3 As It relates to the EDG, ability to 3.91 perform specific system and 4.0 1
Integrated plant procedures during all modes of plant operatllon 073 Process Radiation 0
Ability to (a) predict the impacts 2.71 1
Monitoring 2
of the following malfunctions or 3.2 operations on the PRMS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
detector failure 076 Service Water 0
Ability to predict andlor monitor 2.61 1
2 changes In parameters (to 2.6 prevent exceeding design limits) associated with operating the Service Water controls Including reactor and turbine building closed cooling water temperatures 078 Instrument Air 0
x Knowledge of the physical 2.71 1
2 connection andlor cause-effect 2.8 relationships between the Instrument air and the service air 103 Containment 0
0 Knowledge ofthe Ctmt design 3.11 1
6 3
feature(s) andlor Interlock(s) 3.7 which provide for containment isolation system Ability to (a) predict the Impacts of the following malfunctions or 3.51 operations on the Ctmt; and (b) 3.8 1
based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Phase A & B Isolation KIA Category Point Totals:
4 2
0 4
1 1
3 4
2 4
3 Group Point Total:
28 10
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2
Plant Systems - Tier 2lGroup 2 (RO)
System #1 Name K
K K
K K
K A
A A
A G
K/A Topic(s) lR 1234561234 001 Control Rod Drive 0
Knowledge of the effect that a loss 2.9!
1 i
or malfunction of the CRDS will have 3.0 on the CVCS 002 Reactor Coolant 0
Knowledge of the effect of a loss or 3.6!
1 2
malfunctIon of the following RCS
3.8 components
011 Pressurizer Level 0
Ability to predict andlor monitor 3.5!
1 Control I
changes in parameters (to prevent 3.6 exceeding design limits) associated with operating the PRZ LCS controls including PRZ level and pressure 014 Rod Position Indication NOT SELECTED 0
015 Nuclear Instrumentation 0
Ability to manually operate and/or 3.8!
1 3
monitor In the control room: trip 3.9 bypasses 017 In-core Temperature NOT SELECTED 0
Monitor 027 Containment Iodine
NOT SELECTED o
Removal 028 Hydrogen Recombiner NOT SELECTED 0
and Purge Control 029 Containment Purge NOT SELECTED 0
033 Spent Fuel Pool Cooling NOT SELECTED 0
034 Fuel Handling Equipment 0
AbIlity to (a) predict the Impacts of 3.6/
1 I
the following malfunctions or 4.4 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 035 Steam Generator I
Knowledge of the physical 3.9!
1 4
connection and/or cause-effect 4.1 relationships between the SIG and the ESF 11
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # I Name K K K K K K A A A A G
KIA Toplc(s)
IR 1
2 3 4 5 6 1 2 3 4 001 Control Rod Drive 0
Knowledge of the effect that a loss 2.91 1
1 or malfunction of the CRDS will have 3.0 on the CVCS 002 Reactor Coolant 0
Knowledge of the effect of a loss or 3.61 1
2 malfunction of the following RCS
3.8 components
RCP 011 Pressurizer Level 0
Ability to predict andlor monitor 3.51 1
Control 1
changes in parameters (to prevent 3.6 exceeding design limits) associated with operating the PRZ LCS controls Including PRZ level and pressure 014 Rod Position Indication NOT SELECTED 0
015 Nuclear Instrumentation 0
Ability to manually operate andlor 3.81 1
3 monitor In the control room: trip 3.9 bypasses 017 In-core Temperature NOT SELECTED 0
Monitor 027 Containment Iodine NOT SELECTED 0
Removal 028 Hydrogen Recomblner NOT SELECTED 0
and Purge Control 029 Containment Purge NOT SELECTED 0
033 Spent Fuel Pool Cooling NOT SELECTED 0
034 Fuel Handling Equipment 0
Ability to (a) predict the Impacts of 3.61 1
1 the following malfunctions or 4.4 operations on the fuel handling system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose malfunctions or operations:
dropped fuel element 035 Steam Generator 1
Knowledge of the physical 3.91 1
4 connection andlor cause-effect 4.1 relationships between the SIG and the ESF 11
{PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System #1 Name K
K K
K K
K A
A A
A G
K/A Topic(s)
IR 1234561234 041 Steam Dump/Turbine 1.28 As it relates to the SD Sys:
3.21 1
Bypass Control Knowledge of the purpose and 3.3 function of major system components and controls 045 Main Turbine Generator NOT SELECTED 0
055 Condenser Air Removal x
0 Knowledge of the effect that a loss 2.5/
1 I
or malfunction of the CARS will have 2.7 on the main condenser 056 Condensate x
x x
4.50 As it relates to the condensate 3.3!
1 system: Ability to verify system 3.3 alarm setpoints and operate controls identified In the alarm response manual 068 LIquid Radwaste NOT SELECTED 0
071 Waste Gas Disposal 0
x Knowledge of the operational 2.5!
1 4
ImplicatIons of the following 3.1 concept as it applies to the WGD system: relationship of H2!02 concentrations to flammability 072 Area Radiation NOT SELECTED 0
Monitoring 075 CIrculating Water
NOT SELECTED 0
079 Station Air
NOT SELECTED 086 Fire Protection NOT SELECTED 0
K/A Category Point Totals:
1 01 21 01 1
Ifi i
0 1
2 Group Point Total:
io 12
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)
System # I Name K K K K K K A A A A G
KIA Toplc(s)
IR 1
2 3 4 5
6 1 2
3 4 041 Steam DumplTurblne 1.28 As It relates to the SD Sys:
3.21 1
Bypass Control Knowledge of the purpose and 3.3 function of major system components and controls 045 Main Turbine Generator NOT SELECTED 0
055 Condenser Air Removal x
0 Knowledge ofthe effect that a loss 2.51 1
1 or malfunction of the CARS will have 2.7 on the main condenser 056 Condensate x
x x
4.50 As It relates to the condensate 3.31 1
system: Ability to verify system 3.3 alarm setpoints and operate controls Identified In the alarm response manual 068 Liquid Radwaste NOT SELECTED 0
071 Waste Gas Disposal 0 x Knowledge of the operational 2.51 1
4 Implications of the following 3.1 concept as it applies to the WGD system: relationship of H2/02 concentrations to flammability 072 Area Radiation NOT SELECTED 0
Monitoring 075 Circulating Water NOT SELECTED 0
079 Station Air NOT SELECTED 0
086 Fire Protection NOT SELECTED 0
KIA Category Point Totals:
1 0 2 0 1 1 1 1 0 1 2
Group Point Total:
10 12
ES-401, Rev. 9 RO Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3
{PRIVATE } Facility:
Turkey Point Date of Exam:
04/2007 Category K/A #
Topic RO lR 1.
2.1.
Conduct of Operations 2.1.8 Ability to coordinate personnel activities outside of the control 3.8/3.6 1
room 2.1.11 Knowledge of less than one hour technical specification action 3.0/3.8 1
statements for systems Subtotal 2
2.
2.2.
Equipment Control 2.2.4 Ability to explain the variations in control board layouts, systems, 2.8/3.0 1
Instrumentation and procedural actions between units at a 2.2.11 Knowledge of the process for controlling temporary changes 2.5/3.4 1
2.2.28 Knowledge of new and spent fuel movement procedures 2.6/3.5 1
Subtotal 3
3.
2.3.
Radiation Control 2.3.1 Knowledge of IOCFR2O and related facility radiation control 2.6/3.0 1
requirements 2.3.2 Knowledge of facility AL.ARA program 2.5/2.9 1
2.3.4 Knowledge of radiation exposure limits and contamination 2.5/3.1 1
control, including permissible levels in excess of those authorized Subtotal 3
4.
2.4.
Emergency Procedures I Plan 2.4.4 AbIlity to recognize abnormal indications for system operating 4.0/4.3 1
parameters which are entry level conditions for emergency and abnormal operating procedures 2.4.5 Knowledge of the organIzation of the operating procedures 2.9/3.6 1
nph*,nrk fnr nnrm,iI hnnrmsi inrI AmPrnPnrv Aunh..tinng Subtotal 2
Tler3PointTotal 10 13 ES-401, Rev. 9 RO Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3
{PRIVATE} Facility: Turkey Point Date of Exam: 04/2007 Category K/A#
Topic RO IR
- 1.
2.1.
Conduct of Operations 2.1.8 Ability to coordinate personnel activities outside of the control 3.8/3.6 1
room 2.1.11 Knowledge of less than one hour technical specification action 3.0/3.8 1
statements for systems Subtotal 2
- 2.
2.2.
Equipment Control 2.2.4 Ability to explain the variations in control board layouts, systems, 2.8/3.0 1
instrumentation and procedural actions between units at a 2.2.11 Knowledge of the process for controlling temporary changes 2.5/3.4 1
2.2.28 Knowledge of new and spent fuel movement procedures 2.6/3.5 1
Subtotal 3
- 3.
2.3.
Radiation Control 2.3.1 Knowledge of 1 OCFR20 and related facility radiation control 2.6/3.0 1
requirements 2.3.2 Knowledge offacility ALARA program 2.5/2.9 1
2.3.4 Knowledge of radiation exposure limits and contamination 2.5/3.1 1
control, including permissible levels in excess ofthose authorized Subtotal 3
- 4.
2.4.
Emergency Procedures / Plan 2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 1
parameters which are entry level conditions for emergency and abnormal operating procedures 2.4.5 Knowledge ofthe organization ofthe operating procedures 2.9/3.6 1
nAtwnrk fnr nnrmAI I Ann
' Aunl"tinn..
Subtotal 2
Tier 3 point Total 10 13
ES-401, Rev. 9 Record of Rejected KIAs Form ES-401 -4 (PRIVATE Randomly Reason for Rejection jTier I Selected K/A Group Ill 000025 K2.12 KA value < 2.5 111 000040K1.03 Zero K-2s. Too Many K-Is (9). Random choice to make K-2.
Ill WIEI I EKI.3 Zero K-2s. Too Many K-Is (9). Random choice to make K-2.
1/2 000068G2.4.31 Alarm response procedure not used during CR Evac.
211 059K5 No choices 2.5 2/I 062K5 No choices 2.5 2/I 078K6 No choices 2.5 2/2 055K2 No choices 2.5 2/2 056K3 No choices 2.5 2/2 056K4 No choices 2.5 2/2 056A3 No choices 2.5 212 071 K6 No choices 2.5 2/I 022G2.4.31 Zero K-2s. Too many Gs (7). Random choice to make K-2 2/I 039G2.4.49 One K-S. Too many Gs (7). Random choice to make K-5 2/I 064A2.03 Zero K-2s. Too many Gs (7). Random choice to make K 2
3I1 G21.17 Changed after phone call with Edwin Lea - Better to evaluate verbal communications in other settings, written question was not acceptable during the NRC draft review 14 ES-401, Rev. 9 Record of Rejected K/As Form ES-401-4
{PRIVATE Randomly Reason for Rejection
}Tier I Selected KIA Group 1/1 000025 K2.12 KA value < 2.5 1/1 000040K1.03 Zero K-2s. Too Many K-1s (9). Random choice to make K-2.
1/1 W/E11 EK1.3 Zero K-2s. Too Many K-1s (9). Random choice to make K-2.
1/2 000068G2.4.31 Alarm response procedure not used during CR Evac.
2/1 059K5 No choices 2': 2.5 2/1 062K5 No choices 2': 2.5 2/1 078K6 No choices 2': 2.5 2/2 055K2 No choices 2': 2.5 2/2 056K3 No choices 2': 2.5 2/2 056K4 No choices 2': 2.5 2/2 056A3 No choices 2': 2.5 2/2 071K6 No choices 2': 2.5 2/1 022G2.4.31 Zero K-2s. Too many Gs (7). Random choice to make K-2 2/1 039G2.4.49 One K-5. Too many Gs (7). Random choice to make K-5 2/1 064A2.03 Zero K-2s. Too many Gs (7). Random choice to make K-2 3/1 G21.17 Changed after phone call with Edwin Lea - Better to evaluate verbal communications in other settings, written question was not acceptable during the NRC draft review 14
I-fl 1
II II 15
ES-401, Rev. 9 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-
Reference:
Group#
KIA#
Importance Rating Proposed Question:
Proposed Answer:
Explanation (Optional):
Technical Reference(s):
(Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective:
(As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam (Optional: Questions validated at the facility since 10/95 willgenerally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review ofevery question.)
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 Comments:
16 ES-401, Rev. 9 Sample Written Examination Question Worksheet Examination Outline Cross-
Reference:
Level Proposed Question:
Proposed Answer:
Explanation (Optional):
Tier #
Group #
KIA #
Importance Rating __
Form ES-401-5 RO SRO Technical Reference(s):
__________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination: _
Learning Objective:
__________ (As available)
Question Source:
Bank#
Modified Bank #
New
___ (Note changes or attach parent)
Question History:
Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 Comments:
16
ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6 (PRIVATE )Facility:
Date of Exam:
b*
c 1.
Questions and answers are technically accurate and applicable to the facility.
2.
a.
NRC KIAs are referenced for all questions.
b.
Facility learning objectives are 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 or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).
5.
Question duplication from the license screeninglaudit 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 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 question distribution(s) at right.
I I
7.
Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension! analysis level; the SRO exam may exceed 60 percent If the randomly selected KIA5 support the higher cognitive levels; enter the actual RO I SRO question distribution(s) at right.
I I
8.
Referenceslhandouts provided do not give away answers or aid in the elimination of distractors.
9.
Question content conforms with specific KIA 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 the value on the cover sheet.
Printed Name! Signature Date
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The facility reviewers initialslsignature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items In Column c; chief examiner concurrence required.
17 ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6
{PRIVATE }Facility:
Date of Exam:
- 1.
Questions and answers are technically accurate and applicable to the faCility.
- 2.
- a.
NRC K/As are referenced for all questions.
- b.
Facility learning objectives are 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 or 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
_ 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 question distribution(s) at right.
/
/
/
- 7.
Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if 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 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 the value on the cover sheet.
Printed Name / Signature
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
Initial b*
Date
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
17 cf
ES-401, Rev. 9Site-Specific RO Written Examination Form ES-401-7 Cover Sheet (PRIVATE }
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
FacilitylUnit:
Region:
I II III IV Reactor Type:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results Examination Value Points Applicants Score Points Applicants Grade Percent 18 ES-401, Rev. 9Site-Specific RO Written Examination Form ES-401-7 Cover Sheet
{PRIVATE}
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date:
Facility/Unit:
Region:
I II III IV Reactor Type:
W CE Start Time:
Finish Time:
Instructions BW GE Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value Points Applicant's Score Points Applicant's Grade Percent 18
ES-401, Rev. 9 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet (PRIVATE }
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date:
FacilitylUnit:
Region:
I II III IV Reactor Type:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results RO/SRO-OnlyITotal Examination Values I
I Points Applicants Scores I
I Points 19 ES-401, Rev. 9 Name:
Date:
Region:
I II Start Time:
Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet
{PRIVATE}
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Facility/Unit:
III IV Reactor Type:
W CE BW Finish Time:
Instructions GE Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-0t:'ly/Total Examination Values
-- / -- / --
Points Applicant's Scores
-- / -- / --
Points 19
Applicants Grade I
I Percent Q
20 i
Applicant's Grade I
I Percent II 20
ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401 -9
{PRIV 1.
2.
- 3. psychometric Flaws
- 4. Job Content Flaws
- 5. Other 6.
7.
ATE)
LOK LOD Q#
(FIH)
(1-5)
UIEIS Explanation Stem Cues TIF Cred. IPartial Job-Minutia
- 1 Back-Q SRO Focus f
Dist.
Link units ward KIA Only nstructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
2.
Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 24 range are acceptable).
3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
5.
Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6.
Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
7.
At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
21 ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9
{PRIV
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
ATE} LOK LOD Q#
(F/H)
(1-5)
UJElS Explanation Stem Cues TIF Credo Partial Job-Minutia
- I Back-Q=
SRO Focus Dist.
Link units ward KIA Only Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LaD) of each question using a 1 - 5 (easy-difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (i.e., clues, speCific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid KIA but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
- 5.
Check questions that are sampled for conformance with the approved KIA and those that are deSignated SRO-only (KIA and license level mismatches are unacceptable).
- 6.
Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 7.
At a minimum, explain any "un ratings (e.g., how the Appendix B psychometric attributes are not being met).
21
ES-401, Rev. 9 2
Form ES-401-9
{PRI 1.
2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other 6.
7.
VAT 10K LOD E }
(F/H)
(1-5)
UIEIS Explanation Q#
Stem Cues T/F Cred. IPartia Job-Minutia
- 1 Back-Q=
SRO Focus Dist.
I Link units ward K/A Only 22 ES-401, Rev. 9 2
Form ES-401-9
~-~--
~-
{PRI
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
I VAT LOK LOD E} (F/H) (1-5)
UlE/S Explanation Q#
Stem;lcuesl TIF I cred'lpartia Focus Dist.
I JOb-IMinutial, #1 ;IBack-Link units ward Q= ISRO KIA Only 22
NJ U) 23
ES-401 PWR Examination Outline (SRO Exam)
Form ES-401-2
{PRIVATE ) Facility:
Turkey Point SRO-Only Points Tier Group A2 G*
Total 1.
1 3
3 6
Emergency
& Abnormal Plant Evolutions 2
1 3
4 Tier Total 4
6 10 S
1 2
3 5
2.
Plant Systems 2
02 1
3 TierTotal 4
4 8
- 3. Generic Knowledge and Abilities 1
2 3
4 Categories 2
2 1
2 7
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.
Systemslevolutlons 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 the elimination of inappropriate KIA statements.
4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5.
Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
7*
The generic (G) KIAs in Tiers I 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.
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 # I does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
1 ES-401 PWR Examination Outline (SRO Exam)
Form ES-401-2
{PRIVATE} Facility:
Turkey Point SRO-Only Points Tier Group A2 G*
Total
- 1.
1 3
3 6
Emergency
& Abnormal Plant Evolutions 2
1 3
4 Tier Total 4
6 10 s
1 2
3 5
- 2.
Plant Systems 2
0 2
1 3
Tier Total 4
4 8
s
- 3. Generic Knowledge and Abilities 1
2 3
4 Categories 2
2 1
2 7
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 the elimination of inappropriate KIA statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
- 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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.
1
(PRIVATE )ES-4o1 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group I (SRO)
E!APE #1 Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 12312 000007 Reactor Trip - Stabilization -
NOT SELECTED 0
Recovery/I 000008 Pressurizer Vapor Space NOT SELECTED 0
Accident/3
000009 Small Break LOCA I 3 0
Able to determine and interpret the 3.8!
1 4
following as they apply to Small Break 4.0 LOCA: PRZ Level 000011 Large Break LOCA / 3
NOT SELECTED 0
000015/17 RCP Malfunctions /4
NOT SELECTED 0
000022 Loss of Rx Coolant Makeup /
NOT SELECTED 0
2 000025 Loss of RHR System /4
NOT SELECTED 0
000026 Loss of Component Cooling NOT SELECTED 0
Water 18 000027 Pressurizer Pressure Control NOT SELECTED 0
System Malfunction I 3 000029 ATWS! I NOT SELECTED 0
000038 Steam Gen. Tube Rupture! 3 NOT SELECTED 0
000040 (W!E12) Steam Line Rupture -
2 W!E12 SELECTED 000040 NOT SELECTED 3/4 1
Excessive Heat Transfer! 4 Able to determine and interpret the 3/9 following as they apply to Uncontrolled Depressurization of all S/Gs: Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments 000054 Loss of Main Feedwater / 4
NOT SELECTED 0
000055 Station Blackout! 6
NOT SELECTED 0
000056 Loss of Off-site Power! 6 4
Able to determine and interpret the 3.8/
1 7
following as they apply to Loss of Off-site
3.9 Power
Proper operation of the EDG load sequencer 000057 Loss of Vital AC Inst. Bus! 6 1.33 As it relates to Loss of Vital AC Inst. Bus:
3.4/
1 Ability to recognize indications for systme 4.0 operating parameters which are entry-level conditions for technical specifications 000058 Loss of DC Power! 6 NOT SELECTED 0
000062 Loss of Nuclear Svc Water! 4 2.22 As it relates to Loss of Nuclear Svc Water:
3.4!
1 Knowledge of limiting conditions for 4.1 operations & safety limits 2
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
EIAPE # I Name I Safety Function K K K A A G
KIA Topic(s)
IR 1
2 3 1 2
000007 Reactor Trip - Stabilization -
NOT SELECTED 0
Recovery 11 000008 Pressurizer Vapor Space NOT SELECTED 0
Accident I 3 000009 Small Break LOCA I 3 0
Able to determine and interpret the 3.81 1
4 following as they apply to Small Break 4.0 LOCA: PRZ Level 000011 Large Break LOCA I 3 NOT SELECTED 0
000015/17 RCP Malfunctions I 4 NOT SELECTED 0
000022 Loss of Rx Coolant Makeup I NOT SELECTED 0
2 000025 Loss of RHR System 14 NOT SELECTED 0
000026 Loss of Component Cooling NOT SELECTED 0
Water I 8 000027 Pressurizer Pressure Control NOT SELECTED 0
System Malfunction I 3 000029 A TWS 11 NOT SELECTED 0
000038 Steam Gen. Tube Rupture I 3 NOT SELECTED 0
000040 (W/E12) Steam Line Rupture -
2 W/E12 SELECTED 000040 NOT SELECTED 3/4 1
Excessive Heat Transfer I 4 Able to determine and interpret the 3/9 following as they apply to Uncontrolled Depressurization of all S/Gs: Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 000054 Loss of Main Feedwater I 4 NOT SELECTED 0
000055 Station Blackout 16 NOT SELECTED 0
000056 Loss of Off-site Power I 6 4
Able to determine and interpret the 3.81 1
7 following as they apply to Loss of Off-site
3.9 Power
Proper operation of the EDG load sequencer 000057 Loss of Vital AC Inst. Bus I 6 1.33 As it relates to Loss of Vital AC Inst. Bus:
3.41 1
Ability to recognize indications for systme 4.0 operating parameters which are entry-level conditions for technical speCifications 000058 Loss of DC Power I 6 NOT SELECTED 0
000062 Loss of Nuclear Svc Water I 4 2.22 As it relates to Loss of Nuclear Svc Water:
3.41 1
Knowledge of limiting conditions for 4.1 operations & safety limits 2
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1!Group I (SRO)
EIAPE #1 Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 12312 000065 Loss of Instrument Air I 8
NOT SELECTED 0
WIEO4 LOCA Outside Containment! 3 NOT SELECTED
o WIEI I Loss of Emergency Coolant NOT SELECTED 0
Recirc.14 W!E05 Inadequate Heat Transfer -
4.30 As it relates to Loss of secondary Heat Sink:
2.2!
1 Loss of Secondary Heat Sink 14 Knowledge of which events related to 3.6 system operatlonslstatus should be reported to outside agencies KIA Category Totals:
=
=
3 3
Group Point Total:
6 3
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K K K A A G
K/A Topic(s)
IR 1
2 3 1 2 000065 Loss of Instrument Air 1 8 NOT SELECTED 0
W/E04 LOCA Outside Containment / 3 NOT SELECTED 0
W/E11 Loss of Emergency Coolant NOT SELECTED 0
Recirc./4 W/E05 Inadequate Heat Transfer -
4.30 As it relates to Loss of secondary Heat Sink:
2.21 1
Loss of Secondary Heat Sink 1 4 Knowledge of which events related to 3.6 system operations/status should be reported to outside agencies K/A Category Totals:
3 3
Group Point Total:
6 3
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier llGroup 2 (SRO)
EIAPE #! Name! Safety Function K
K K
A A
G KIA Topic(s)
IR 12312 000001 Continuous Rod Withdrawal ! I
NOT SELECTED 0
000003 Dropped Control Rod I 1 4.6 As it relates to the dropped control 3.1!
1 rod event: Knowledge of symptom 4.0 based EOP mitigation strategies 000005 InoperablelStuck Control Rod I 1 2.22 As it relates to the InoperablelStuck 3.4!
1 Control Rod: knowledge of limiting 4.1 conditions for operations and safety limits 000024 Emergency Boratlon II
NOT SELECTED 0
000028 Pressurizer Level Malfunction ! 2 0
Able to determine and Interpret the 3.1!
1 8
following as they apply to Pressurizer 3.5 Level Malfunction: PZR level as a function of power level 000032 Loss of Source Range NI I 7
NOT SELECTED 0
000033 Loss of Intermediate Range NI I 7
NOT SELECTED 0
000036 Fuel Handling Accident I 8 NOT SELECTED 0
000037 Steam Generator Tube Leak! 3 1.33 As it relates to Steam Generator 3.4!
1 Tube Leak: Ability to recognize 4.0 indications for system operating parameters which are entry-level conditions for technical specifications 000051 Loss of Condenser Vacuum 14 NOT SELECTED 0
000059 Accidental Liquid RadWaste Rel. 19 NOT SELECTED 0
000060 Accidental Gaseous Radwaste Rel.!
NOT SELECTED 0
9 000061 ARM System Alarms I 7 NOT SELECTED 0
000067 Plant Fire On-site! 8 NOT SELECTED 0
000068 Control Room Evac. ! 8 NOT SELECTED 0
000069 (WIEI4) Loss of CTMT Integrity! 5 NOT SELECTED 0
000074 (WIEO6&E07) Inad. Core Cooling 14
NOT SELECTED 0
000076 High Reactor Coolant Activity! 9
NOT SELECTED 0
WIEOI & E02 Rediagnosis & SI Termination NOT SELECTED 0
13 W!E1 3 Steam Generator Over-pressure! 4
NOT SELECTED 0
W!E15 Containment Flooding! 5
NOT SELECTED
0 W!E16 High Containment Radiation! 9
NOT SELECTED
0 W!E03 LOCA Cooldown Depress ! 4
NOT SELECTED
0 WIEO9&E10 Natural Clrc 14
NOT SELECTED
0 W!E08 RCS Overcooling PTS 14
NOT SELECTED 0
K!A Category Point Totals:
=
= [
I I Group Point Total:
4 4
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
E/APE # I Name I Safety Function K K K A A G
KIA Topic(s)
IR 1
2 3
1 2 000001 Continuous Rod Withdrawal/1 NOT SELECTED 0
000003 Dropped Control Rod 11*
4.6 As it relates to the dropped control 3.11 1
rod event: Knowledge of symptom 4.0 based EOP mitigation strategies 000005 Inoperable/Stuck Control Rod 11 2.22 As it relates to the Inoperable/Stuck 3.41 1
Control Rod: knowledge of limiting 4.1 conditions for operations and safety limits 000024 Emergency Boration 11 NOT SELECTED 0
000028 Pressurizer Level Malfunction I 2 0
Able to determine and interpret the 3.11 1
8 following as they apply to Pressurizer 3.5 Level Malfunction: PZR level as a function of power level 000032 Loss of Source Range Nil 7 NOT SELECTED 0
000033 Loss of Intermediate Range Nil 7 NOT SELECTED 0
000036 Fuel Handling Accident I 8 NOT SELECTED 0
000037 Steam Generator Tube Leak 13 1.33 As it relates to Steam Generator 3.41 1
Tube Leak: Ability to recognize 4.0 indications for system operating parameters which are entry-level conditions for technical specifications 000051 Loss of Condenser Vacuum I 4 NOT SELECTED 0
000059 Accidental Liquid RadWaste Rei. I 9 NOT SELECTED 0
000060 Accidental Gaseous Radwaste Rei. I NOT SELECTED 0
9 000061 ARM System Alarms I 7 NOT SELECTED 0
000067 Plant Fire On-site 18 NOT SELECTED 0
000068 Control Room Evac. I 8 NOT SELECTED 0
000069 (W/E14) Loss of CTMT Integrity 15 NOT SELECTED 0
000074 (W/E06&E07) Inad. Core Cooling 14 NOT SELECTED 0
000076 High Reactor Coolant Activity I 9 NOT SELECTED 0
W/E01 & E02 Rediagnosis & SI Termination NOT SELECTED 0
13 W/E13 Steam Generator Over-pressure I 4 NOT SELECTED 0
W/E15 Containment Flooding I 5 NOT SELECTED 0
W/E16 High Containment Radiation I 9 NOT SELECTED 0
W/E03 LOCA Cooldown - Depress. 14 NOT SELECTED 0
W/E09&E10 Natural Circ./4 NOT SELECTED 0
W/E08 RCS Overcoollng - PTS 14 NOT SELECTED 0
KIA Category Point Totals:
1 3
Group Point Total:
4 4
(PRIVATE )ES-4o1 PWR Examination Outline Form ES-401-2
Plant Systems - Tier 2/Group I (SRO)
System #1 Name K
K K
K K
K A
A A
A G
K/A Topic(s)
IR 1234561234 003 Reactor Coolant Pump 0
Ability to (a) predict the impacts of 27/
1 3
the following malfunctions or 3.1 operations on the RCP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems 004 Chemical and Volume NOT SELECTED 0
Control 005 Residual Heat Removal
NOT SELECTED o
006 Emergency Core Cooling 4.6 As it relates to Emergency Core 3.1/
1 Cooling: Knowledge of symptom 4.0 based EOP mitigation strategies 007 PressurIzer Relief/Quench NOT SELECTED 0
Tank 008 Component Cooling Water NOT SELECTED o
010 Pressurizer Pressure NOT SELECTED 0
Control 012 Reactor Protection
NOT SELECTED 013 Engineered Safety NOT SELECTED Features Actuation 022 Containment Cooling 0
Ability to (a) predict the impacts of 2.9/
1 4
the following malfunctions or 3.2 operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Loss of servIce water 026 Containment Spray
NOT SELECTED a
039 Main and Reheat Steam NOT SELECTED 0
059 Main Feedwater NOT SELECTED 0
5
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # I Name K K K K K K A A A A G
KIA Topic(s)
IR 1
2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 0
Ability to (a) predict the impacts of 2.71 1
3 the following malfunctions or 3.1 operations on the RCP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems 004 Chemical and Volume NOT SELECTED 0
Control 005 Residual Heat Removal NOT SELECTED 0
006 Emergency Core Cooling 4.6 As it relates to Emergency Core 3.11 1
Cooling: Knowledge of symptom 4.0 based EOP mitigation strategies 007 Pressurizer Relief/Quench NOT SELECTED 0
Tank 008 Component Cooling Water NOT SELECTED 0
010 Pressurizer Pressure NOT SELECTED 0
Control 012 Reactor Protection NOT SELECTED 0
013 Engineered Safety NOT SELECTED 0
Features Actuation 022 Containment Cooling 0
Ability to (a) predict the impacts of 2.91 1
4 the following malfunctions or 3.2 operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
Loss of service water 026 Containment Spray NOT SELECTED 0
039 Main and Reheat Steam NOT SELECTED 0
059 Main Feedwater NOT SELECTED 0
5
{PRIVATE )ES-4o1 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2lGroup I (SRO)
System #1 Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1234561234 061 Auxillary!Emergency 2.22 As It relates to the AFW system:
Feedwater knowledge of limiting conditions 41 for operations and safety limits 062 AC Electrical Distribution
NOT SELECTED 0
063 DC Electrical Distribution
NOT SELECTED o
064 Emergency Diesel NOT SELECTED o
Generator 073 Process Radiation 1.33 As it relates to Process Radiation 3.4!
1 Monitoring Monitoring: Ability to recognize 4.0 indicatIons for system operating parameters which are entry-level conditions for technical specifications.
076 Service Water NOT SELECTED a
078 Instrument Air NOT SELECTED 0
103 Containment NOT SELECTED a
[ K!A Category Point Totals:
J
=1=1
2
=
3 Group Point Total:
5 6
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # I Name K K K K K K A A A A G
KIA Topic(s)
IR 1
2 3 4 5 6 1 2
3 4 061 AuxiliarylEmergency 2.22 As it relates to the AFW system:
3.41 1
Feedwater knowledge of limiting conditions 4.1 for operations and safety limits 062 AC Electrical Distribution NOT SELECTED 0
063 DC Electrical Distribution NOT SELECTED 0
064 Emergency Diesel NOT SELECTED 0
Generator 073 Process Radiation 1.33 As it relates to Process Radiation 3.41 1
Monitoring Monitoring: Ability to recognize 4.0 indications for system operating parameters which are entry-level conditions for technical specifications.
076 Service Water NOT SELECTED 0
078 Instrument Air NOT SELECTED 0
103 Containment NOT SELECTED 0
KIA Category Point Totals:
2 3
Group Point Total:
5 6
(PRIVATE )ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System #1 Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1234561234 001 Control Rod Drive NOT SELECTED 0
002 Reactor Coolant NOT SELECTED 0
011 Pressurizer Level NOT SELECTED 0
Control 014 Rod Position IndIcation 0
AbilIty to (a) predict the Impacts of 3.1/
1 2
the following malfunctions or 3.6 operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: loss of
power to the RPls 015 Nuclear Instrumentation NOT SELECTED 0
NOT SELECTED 0
017 In-core Temperature 0
AbIlity to (a) predict the Impacts of 3.6!
1 Monitor 2
the following malfunctions or 4.1 operations on the ITM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core
Damage 027 Containment Iodine NOT SELECTED 0
Removal 028 Hydrogen Recombiner NOT SELECTED 0
and Purge Control
029 Containment Purge
NOT SELECTED o
033 Spent Fuel Pool Cooling
NOT SELECTED o
034 Fuel Handling Equipment
NOT SELECTED o
035 Steam Generator NOT SELECTED 0
041 Steam Dump/Turbine NOT SELECTED 0
Bypass Control
045 Main Turbine Generator NOT SELECTED 0
7
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # I Name K K K K K K A A A A G
KIA Topic(s)
IR 1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive NOT SELECTED 0
002 Reactor Coolant NOT SELECTED 0
011 Pressurizer Level NOT SELECTED 0
Control 014 Rod Position Indication 0
Ability to (a) predict the impacts of 3.11 1
2 the following malfunctions or 3.6 operations on the RPIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: loss of power to the RPls 015 Nuclear Instrumentation NOT SELECTED 0
NOT SELECTED 0
017 In-core Temperature 0
Ability to (a) predict the impacts of 3.61 1
Monitor 2
the following malfunctions or 4.1 operations on the ITM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core Damage 027 Containment Iodine NOT SELECTED 0
Removal 028 Hydrogen Recombiner NOT SELECTED 0
and Purge Control 029 Containment Purge NOT SELECTED 0
033 Spent Fuel Pool Cooling NOT SELECTED 0
034 Fuel Handling Equipment NOT SELECTED 0
035 Steam Generator NOT SELECTED 0
041 Steam DumplTurbine NOT SELECTED 0
Bypass Control 045 Main Turbine Generator NOT SELECTED 0
7
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2lGroup 2 (SRO)
System #1 Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1234561234 055 Condenser Air Removal NOT SELECTED o
056 Condensate NOT SELECTED 0
068 Liquid Radwaste NOT SELECTED o
071 Waste Gas Disposal NOT SELECTED 0
072 Area Radiation 1.14 As It relates to Area Radiation 2.51 1
Monitoring Monitoring: Knowledge of system 3.3 status criteria which require the notification of plant personnel 075 CIrculating Water NOT SELECTED 0
079 Station Air NOT SELECTED 0
086 Fire Protection
NOT SELECTED 0
KIA Category Point Totals:
=1
=
=
=
=
I Group Point Total:
3 8
{PRIVATE }ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # I Name K K K K K K A A A A G
KIA Toplc(s)
IR 1
2 3 4
5 6 1 2 3 4 055 Condenser Air Removal NOT SELECTED 0
056 Condensate NOT SELECTED 0
068 liquid Radwaste NOT SELECTED 0
071 Waste Gas Disposal NOT SELECTED 0
072 Area Radiation 1.14 As It relates to Area Radiation 2.51 1
Monitoring Monitoring: Knowledge of system 3.3 status criteria which require the notification of plant personnel 075 Circulating Water NOT SELECTED 0
079 Station Air NOT SELECTED 0
086 Fire Protection NOT SELECTED 0
KIA Category Point Totals:
2 1
Group Point Total:
3_JI 8
ES-401,_Rev.9 SRO Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 (PRIVATE } Facility:
Turkey Point Date of Exam: April 2007
]
Category KIA #
Topic SRO-Only IR 1.
2.1.
Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational 4.4 1
judgements based on operating charasteristics, reactor behavior, and Instrument interpretation 2.1.32 Ability to explain and apply all system limits and precautions 3.8 1
Subtotal 2
2.
2.2.
Equipment Control 2.2.24 Ability to analyze the effect of maintenance activities on LCO 3.8 1
2.2.27 Knowledge of the refueling process 3.5 1
Subtotal
2 3.
2.3.
Radiation Control 2.3.10 Ability to perform procedures to reduce excessive levels of 3.3 1
radiation and guard against personnel exposure Subtotal I
4.
2.4.
Emergency Procedures I Plan 2.4.7 Knowledge of the event based EOP mitigation strategies 3.8 1
2.4.44 Knowledge of emergency plan protective action recommendations 4.0 1
Subtotal 2
Tier 3 Point Total 7
9 ES-401, Rev. 9 SRO Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Date of Exam: April 2007 category KIA #
Topic SRO-Only IR
- 1.
2.1.
Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational 4.4 1
jUdgements based on operating charasteristics. reactor behavior.
and instrument interpretation 2.1.32 Ability to explain and apply all system limits and precautions 3.8 1
Subtotal 2
- 2.
2.2.
Equipment Control 2.2.24 Ability to analyze the effect of maintenance activities on LCO 3.8 1
2.2.27 Knowledge of the refueling process 3.5 1
Subtotal 2
- 3.
2.3.
Radiation Control 2.3.10 Ability to perform procedures to reduce excessive levels of 3.3 1
radiation and guard against personnel exposure Subtotal 1
- 4.
2.4.
Emergency Procedures I Plan 2.4.7 Knowledge of the event based EOP mitigation strategies 3.8 1
2.4.44 Knowledge of emergency plan protective action recommendations 4.0 1
Subtotal 2
Tier 3 Point Total 7
9
ES-401, Rev. 9 Record of Rejected KIAs Form ES-401 -4 (PRIVATE Randomly Reason for Rejection
)Tier I Selected KIA Group 212 086G2.4.4 Unable to write SRO level question based on this KA 10 ES-401, Rev. 9 Record of Rejected KIAs Form ES-401-4
{PRIVATE Randomly Reason for Rejection
}Tier I Selected KIA Group 2/2 086G2.4.4 Unable to write SRO level question based on this KA 10
ES-401, Rev. 9 Sample Written Examination Form ES-401-5 Question Worksheet Examination Outline Cross-
Reference:
Group#
KIA#
Importance Rating Proposed Question:
Proposed Answer:
Explanation (Optional):
Technical Reference(s):
(Attach if not previously provided)
Proposed references to be provided to applicants during examination:
Learning Objective:
(As available)
Question Source:
Bank #
Modified Bank #
(Note changes or attach parent)
New Question History:
Last NRC Exam (Optional: Questions validated at the facility since 10/95 willgenerally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailedreview ofevery question.)
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 Comments:
11 ES-401, Rev. 9 Sample Written Examination Question Worksheet Examination Outline Cross-
Reference:
Level Proposed Question:
Proposed Answer:
Explanation (Optional):
Tier#
Group #
KIA #
Importance Rating __
Form ES-401-5 RO SRO Technical Reference(s):
__________ (Attach if not previously provided)
Proposed references to be provided to applicants during examination:_
Learning Objective:
__________ (As available)
Question Source:
Bank#
Modified Bank #
New
___ (Note changes or attach parent)
Question History:
Last NRC Exam (Optional: Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC,. failure to provide the information will necessitate a detailed review of every question.)
Question Cognitive Level:
Memory or Fundamental Knowledge Comprehension or Analysis 10 CFR Part 55 Content:
55.41 55.43 Comments:
11
ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6 (PRIVATE )Facility:
Date of Exam:
b*
c 1.
QuestIons and answers are technically accurate and applicable to the facility.
2.
a.
NRC KIAs are referenced for all questions.
b.
Facility learning objectives are 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 or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office).
5.
Question duplication from the license screeninglaudit 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 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 question distribution(s) at right.
311 010 72124 7.
Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehensionl analysis level; the SRO exam may exceed 60 percent if the randomly selected KIAs support the higher cognitive levels; enter the actual RO I SRO question distribution(s) at right.
3315 42120 8.
Referenceslhandouts provided do not give away answers or aid in the elimination of distractors.
9.
Question content conforms with specific KIA 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 the value on the cover sheet.
Printed Name I Signature Date
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The facility reviewers Inltialslslgnature are not applicable for NRC-developed examinations.
- Independent NRC reviewer Initial Items in Column ac; chief examiner concurrence required.
12 ES-401, Rev. 9 Written Examination Quality Checklist Form ES-401-6
{PRIVATE }Facility:
Date of Exam:
- 1.
Questions and answers are technically accurate and applicable to the facility.
- 2.
- a.
NRC K/As are referenced for all questions.
- b.
Facility learning objectives are 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 or 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
_ 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 question distribution(s) at right.
3/1 0/0 72/24
- 7.
Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right.
33/5 42/20
- 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 the value on the cover sheet.
Printed Name / Signature
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The faCility reviewer's initials/signature are not applicable for NRC-developed examinations.
Initial b*
c' Date
- Independent NRC reviewer initial Items in Column "c"; chief examiner concurrence required.
12
ES-401, Rev. 9 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet
{PRIVATE)
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: May 2007 Facility/Unit: Turkey Point Region:
I ii III IV Reactor Type:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results Examination Value
_100.
Points Applicants Score Points Applicants Grade Percent 13 ES-401, Rev. 9 Site-Specific RO Written Examination Form ES-401-7 Cover Sheet
{PRIVATE}
U.S. Nuclear Regulatory Commission Site-Specific RO Written Examination Applicant Information Name:
Date: May 2007 Facility/Unit: Turkey Point Region:
I 11 III IV Reactor Type:
Finish Time:
Instructions Use the answer sheets prQvided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination, you must achieve a final grade of at least 80.00 percent. Examination papers will be collected 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the examination begins.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value
_100_ Points Applicant's Score Points Applicant's Grade Percent 13
ES-401, Rev.
Site-Specific SRO Written Examination Form ES-401 -8 Cover Sheet (PRIVATE)
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:
Date:
May 2007 FacilitylUnit: Turkey Point Region:
I fl Ill IV Reactor Type:
Finish Time:
Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicants Signature Results ROISRO-OnlylTotal Examination Values 75 I
25 I
100 Points Applicants Scores I
I Points Applicants Grade I
I Percent 14 ES-401, Rev.
Name:
Date:
May 2007 Region:
I Start Time:
Site-Specific SRO Written Examination Cover Sheet Form ES-401-8
{PRIVATE}
U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Facility/Unit: Turkey Point II III IV Reactor Type:
W CE BW Finish Time:
Instructions GE Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80.00 percent overall, with 70.00 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80.00 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results RO/SRO-Only/Total Examination Values 75
/
25
/
100 Points Applicant's Scores
-- / -- / --
Points Applicant's Grade
-- / -- / --
Percent 14
LI, 15
ES-401, Rev. 9 Written Examination ReviewWorksheet Form ES-401-9
{PRIV 1.
2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other 6.
7.
ATE)
LOK 100 Q#
(FIll)
(1-5)
UIEIS Explanation Stem Cuesi TIF Cred. Partial Job-Minutia
- 1 Back-Q SRO Focus 01st.
Link units ward KIA Only nStructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.)
1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
2.
Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 24 range are acceptable).
3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
V.
The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
5.
Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
6.
Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
7.
At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
16 ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9
{PRIV
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
ATE} LOK LOD Q#
(F/H)
(1-5) utE/S Explanation Stem Cues T/F Credo Partial Job-Minutia
- I Back-Q..
SRO Focus Dist.
Link units ward KIA Only Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1.
Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2.
Enter the level of difficulty (LaD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3.
Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (Le., clues, speCific determiners, phrasing, length, etc).
The answer choices are a collection of unrelated true/false statements.
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4.
Check the appropriate box if a job content error is identified:
The question is not linked to the job requirements (Le., the question has a valid KIA but, as written, is not operational in content).
The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory).
The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
The question requires reverse logic or application compared to the job requirements.
- 5.
Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable).
- 6.
Based on the reviewer's jUdgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 7.
At a minimum, explain any "un ratings (e.g., how the Appendix B psychometric attributes are not being met).
16
ES-401. Rev. 9 2
2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other 6.
7.
VAT LOK LOD E)
(FIH)
(1-5)
UIEIS Explanation Q#
Stem Cues! T!F Cred.IPartia Job-Minutia
- 1 iBack-Q SRO Focus Dist.
I Link unitsj ward KIA Only 17 ES-401, Rev. 9 2
Form ES-401-9
{PRI
- 1.
- 2.
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
- 7.
VAT LOK LOD E} (F/H) (1-5)
UlE/S Explanation Q#
Stem Cues TIF ! cred.!partia Job-Minutia!1 #1 ;! Back-Q= !SRO Focus Dist.
I Link units ward KIA Only 17
18