ML17069A284
| ML17069A284 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/31/2016 |
| From: | Entergy Nuclear Indian Point 2 |
| To: | Operations Branch I |
| Shared Package | |
| ML16076A436 | List: |
| References | |
| U01926 | |
| Download: ML17069A284 (19) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facilitv:
IPEC Unit2 Date of Exam:
10/31/2016 RO K/A Cate:iorv Points SRO-Onlv Points Tier Group K
K K
K K
K A
A A
A G*
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 3
3 3
3 3
3 1B 0
0 0
Emergency &
Abnormal 2
2 2
2 N/A 1
2 NIA 0
9 0
0 0
Plant Evolutions Tier Totals 5
5 5
4 5
3 27 0
0 0
1 3
2 3
3 3
2 2
3 2
3 2
28 0
0 0
- 2.
Plant 2
1 1
1 1
1 1
1 1
1 0
1 10 0
0 0
0 Systems Tier Totals 4
3 4
4 4
3 3
4 3
3 3 I 38 0
0 0
- 3. Generic Knowledge and Abilities 1
2 3
4 1
2 3
4 0
Categories 10 2
3 3
2 0
0 0
0 0
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). (One Tier 3 Radiation Control KIA is allowed if the K/A is replaced by a K/A from another Tier 3 Category).
- 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 with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those K/As 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) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category 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 K/A numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G*
Generic K/As
PWR RO Examination Outline Printed:
08/31/2016 I*'acility:
IPEC ES- -401 Emergenc)* and Abnormal Plant Evolutions - Tier l I Group l Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000008 Pressurizer Vapor Space Accident I 3 x 2.4.21 - Knowledge of the parameters and 4.0 I
logic used to assess the status of safety functions. such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions.
radioactivity release control. etc.
000009 Small Break LOCA I 3 x
EAL! I -AFW/MFW 4.1 I
0000 l I Large Break LOCA I 3 x
EK3.08 - Flowpath for sump recirculation 3.9 I
000015/000017 RCP Malfunctions I 4 x
AK3.07 - Ensuring that SIG levels are 4.1 1
controlled properly for natural circulation enhancement 000022 Loss of Rx Coolant Makeup I 2 x
000025 Loss of RHR System I 4 x
AKl.01 - Loss ofRHRS during all modes 3.9 I
of operation 000026 Loss of Component Cooling Water I 8 x 2.4.4 - Ability to recognize abnormal 4.5 I
indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
000027 Pressurizer Pressure Control System x
AK2.03 - Controllers and positioners 2.6 I
Malfunction I 3 000029 A TWS I I x
EAl.15 - AFW System 4.1 I
000038 Steam Gen. Tube Rupture I 3 x 2.4.45 - Ability t{1 prioritize and interpret 4.1 1
the significance of each annunciator or alarm.
000054 Loss of Main Feedwater I 4 x
AK 1.02
- Effects of feedwater 3.6 l
introduction on dry SIG 000057 Loss of Vital AC lnsi. Bus I 6 x
AA.2.03 - RPS panel alann annunciators 3.7 I
and trip indicators 000058 Loss of DC Power! 6 x
AA2.0 l - That a loss of de power has 3.7 I
occurred; verification that substitute power sources have come on line 000065 Loss of Instrument Air I 8 x
AK3.04 - Cross-over to backup air 3.0 l
supplies 000077 Generator Voltage and Electric Grid x
AA2.03 - Generator current outside the 3.5 I
Disturbances I 6 capability curve 08/3112016 9:22:06 am
PWR RO Examination Outline Printed:
08/31/2016 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier I I Group 1 form ES-401-2 E/ APE #I Name I Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points W/E04 LOCA Outside Containment I 3 x
EK2.2 - Facility's heat removal systems, 3.8 1
including 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/EI I Loss of Emergency Coolant Recirc. / 4 x
EK2. l - Components, and functions of 3.6 1
control and safety systems, including instrumentation, signals. interlocks, failure modes. and automatic and manual features W /E 12 - Steam Line Rupture - Excessive Heat x
EKl.3 - Annunciators and conditions 3.4 1
Transfer/ 4 indicating signals, and remedial actions associated with the Uncontrolled Depressurization of all Steam Generators KIA Category Totals:
3 3
3 3
3 3
Group Point Total:
18 08/3112016 9:22:06 am
PWR RO Examination Outline Printed:
08/3112016 f<'acility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - rier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al AZ G
KA Topic Imp.
Points 000005 Inoperable/Stuck Control Rod I 1 x
AKJ.01 - Boration and emergency 4.0 I
boration in the event of a stuck rod during trip or normal evoluticms 000033 Loss of Intermediate Range NI I 7 x
AKJ.02 - Guidance contained in EOP for 3.6 1
loss of intermediate-range instrumentation 000051 Loss of Condenser Vacuum i 4 x
AA2.02 - Conditions requiring reactor 3.9 1
and/or turbine trip 000061 ARM System Alarms I 7 x
AKI.OJ - Detector limitations 2.5*
1 000069 Loss of CTMT Integrity I 5 x
AK2.03 - Personnel access hatch and 2.8*
l emergency access hatch W/E02 SI Termination I 3 x
EA2.2 - Adherence to appropriate 3.5 1
procedures and operation within the limitations in the facility's license and amendments W/E03 LOCA Cooldown - Depress. I 4 x
EK2.2 - facility's heat removal systems, 3.7 I
including 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/E07 lnad. Core Cooling/ 4 x
EA!.2 - Operating behavior 3.2 I
characteristics of the facility W/El6 High Containment Radiation I 9 x
EK1.2 - Normal. abnormal and 2.7 1
emergency operating procedures associated with High Containment Radiation KIA Category Totals:
2 2
2 I
2 0
Group Point Total:
9 08/3112016 9:22:13 am
PWR RO Examination Outline Printed:
08/3 l/2016 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group I Form ES-401-2 Sys/Evol #I Name Kl Kl K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 003 Reactor Coolant Pump x
K2.0I - RCPS 3.1 I
004 Chemical and Volume Control x
K5.l 9 - Concept of SDM 3.5 I
004 Chemical and Volume Control x
K5.35 - Heat exchanger 2.5 1
principles and the effects of flow. temperature and other parameters 005 Residual Heat Removal x
K4.01 - Overpressure 3.0 1
mitigation system 006 Emergency Core Cooling x 2.1.45 - Ability to identify 4.3 I
and interpret diverse indications tu validate the response of another indication.
006 Emergency Core Cooling x
K6.03 - Safoty Injection 3.6 I
Pumps 007 Pressurizer RelietiQuench Tank x
K4.01 - Quench tank cooling 2.6 I
008 Component Cooling Water x 2.1.43 - Ability to use 4.1 I
procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
008 Component Cooling Water x
A2.02 - High/low surge tank 3.2 I
level 0 I 0 Pressurizer Pressure Control x
K.2.02 - Controller for PZR 2.5 1
spray valve 012 Reactor Protection x
KJ.03 - SDS 3.1
- 1 013 Engineered Safety Features x
K6.01 - Sensors and detectors
.:...I l
Actuation 022 Containment Cooling x
K.J.01 - SWS/couling ~ystem 3.5 1
022 Containment Cooling x
A4.03 - Damper~ in the CCS
~ "*
.),_
1 026 Containment Spray x
A4.05 - Containment spray 3.5 1
reset switches 026 Containml.'lll Spray x
KJ.02 - Recirculation spray 4.2*
1 system 039 Main and Reheat Stearn x
K.5.05 - Ba~es for RCS 2.7 I
cooldown limits 059 Main Feedwater x
A 1.03 - Power leYel 2.7*
l restrictions for operation of 11.1FW pumps and valves 059 Main Feedwater x
AHJ6 - Fce<lwater isolation 3.2*
l O<i l Au xi I 1ary/Emergem.:y foclh~aler x
KJ.02 - s:G 4.2 062 AC Electrical Distribution x
Kl.03 - DC distribution 3.5 I
08/31/2016 9 22 19 am
PWR RO Examination Outline Printed:
Ol</31/2016 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group l Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 063 DC Electrical Distribution x
A2.ll l - Grounds 2.5 1
064 Emergency Diesel Generator x
A2.06 - Operating unloaded, 2.9 1
lightly loaded, and highly loaded time limit 064 Emergency Diesel Generator x
K.1.05 - Starting air system 3.4 1
073 Process Radiation Monitoring x
K.4.0 I - Release termination 4.0 I
when radiation exceeds setpoint 076 Service Water x
A4.02 - SWS valves 2.6 1
078 Instrument Air x
A3.0l - Air pressure 3.1 I
I 03 Containment x
A 1.0 I - Containment 3.7 I
pressLtre, temperature, and humidity KJA Category Totals:
3 2
3 3
3 2
2 3
2 3
2 Group Point Total:
28 08/31/2016 9:2219am
P\\VR RO Examination Outline Printed:
08/31/2016 Facility:
IPEC ES -401 Plant Systems - Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kt K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 011 Pressurizer Level Control x
K2.02 - PZR heaters 3.1 1
015 Nuclear Instrumentation x
KJ.03 - CRDS 3.1
- 1 033 Spent Fuel Pool Cooling x
A 1.0 I - Spent fuel pool water 2.7 I
level 035 Steam Generator x
K6.0 I - MSJV s 3.2 1
041 Steam Dump/Turbine Bypass x
A2.03 - Loss of IAS 2.8 I
Control 045 Main Turbine Generator x
KJ.01 - Remainder of the 2.0 I
plant 055 Condenser Air Removal x
A3.03 - Automatic diversion 2.5*
I of CARS exhaust 071 Waste Gas Disposal x
K5.04 - Relationship of 2.5 l
hydrogen/oxygen concentrations to flammability 072 Area Radiation Monitoring x 2. l.15 - Knowledge of 2.7 I
administrative requirements for temporary management directives. such as standing orders. night orders.
Operations memos, etc.
075 CircLtlating Water x
K4.0J - Heat sink 2.5 1
Kl A Category Totals:
1 1
1 1
I 1
I 1
1 0
1 Group Point Total:
10 08/31/2016 9:22 24 am
Generic Knowledge and Abilities Outline (Tier 3)
PWR RO Examination Outline Printed: 08/31/201 fl Facilitv:
IPEC Form ES-401-3 Generic Categorv KA Topic Conduct of Operations 2.1.1 Knowledge of conduct of operations rcquin:ments.
3.8 1
2.1.45 Ability to identify and interpret diverse indications 4.3 1
to validate the response of another indication.
Category Total:
2 Equipment Control 2.2.25 Knowledge of the bases in Technical Specifications 3.2 1
for limiting conditions for operations and safety limits.
2.2.36 Ability to analyze the effect of maintenance 3.1 1
activities, such as degraded power sources, on the status of limiting conditions for operations.
2.2.37 Ability to determine operability and/or availability 3.6 1
of safety related equipment.
Category Total:
3 Radiation Control 2.3.5 Ability to use radiation monitoring sy~1ems, such as 2.9 I
fixed radiation monitors and alarms, portable survey instruments. personal monitoring equipment, etc.
2.3.D Knowledge of radiological safety procedures J.4 1
pertaining to licensed operator duties. such as response to radiation monitor alarms. containment entry requirements. fuel handling responsibilities.
access to locked high-radiation areas, aligrnng filters. etc.
2.3.15 Knowledge of radiation monitoring systems, such as 2.9 1
fixed radiation monitors and alarms. portable sur>ey instruments, persorllld nwnituring equipment, etc.
Category Total:
3 Emergency Procedures/Plan 2.4.27 Knowledge of fire in the plant" procedure.
3.4 l
2.4.35 Knowledge of local auxiliary operator tasks during
.l8 I
an emergency and the resultant operational effects.
Category Total:
2 Generic Total:
10 08131/2016
ES-401 PWR Examination Outline Form ES-401*2 I Facilitv:
IPEC Unit 2 Date of Exam:
10/31/2016 I
RO KIA Cate::iorv Points SRO-Onlv Points Tier Group K
K K
K K
K A
A A
A G*
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 0
0 0
0 0
0 0
3 3
6 Emergency &
Abnormal 2
0 0
0 N/A 0
0 NIA 0
0 2
2 4
Plant Tier Totals 0
0 0
0 Evolutions 0
0 0
5 5
10 1
0 0
0 0
0 0
0 0
0 0
0 0
3 2
5
- 2.
Plant 2
0 0
0 0
0 0
0 0
0 0
0 0
2 1
3 Systems Tier Totals 0
0 0
0 0
0 0
0 0
0 0
0 5
3 8
- 3. Generic Knowledge and Abilities 1
2 3
4 1
2 3
4 Categories 0
7 0
0 0
0 2
2 2
1 Note:
- 1.
Ensure that at least two topics from every applicable K/A 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). (One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).
- 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 with justification: operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 (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) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog. but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the Ki A numbers. a brief description of each topic, the topics' importance ratings (!Rs) 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 a category 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 exarns.
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, !Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 1 O CFR 55.43.
G*
Generic K/As
PWR SRO Examination Outline Printed:
08/31/2016 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier l /Group I Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G
KA. Topic Imp.
Points 000011 Large Break LOCA I 3 x
EA2.13 - Difference between overcooling 3.7*
I and LOCA indications 000015/00001 7 RCP Mal functions I 4 x 2.1.45 - Ability to identify and interpret 4.3 1
diverse indications to validate the response of another indication.
000040 Steam Line Rupture - Excessive Heat x 2.4.29 - Knowledge of the emergency 4.4 I
Transfer/ 4 plan.
000058 Loss of DC Power I 6 x
AA2.01 - That a loss of de power has 4.1 1
occurred: verification that substitute power sources have come on line 000077 Generator Voltage and Electric Grid x 2.2.25 - Knowledge of the ba'ies in 4.2 1
Disturbances/ 6 Technical Specifications for limiting conditions for operations and safety limits.
W/E05 Inadequate Heat Trans!Cr - Loss of x
EA2.2 - Adherence to appropriate 4.3 l
Secondary Heat Sink I 4 procedures and operation within the limitations in the facility's license and amendments KIA Category Totals:
0 0
0 0
3 3
Group Point Total:
6 08131/2016 9:38.19 am
PWR SRO Examination Outline Printed:
08131/2016 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier l I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al AZ G
KA Topic Imp.
Points 000024 Emergency Boration / I x 2.2.36 - Ability to analyze the effect of 4.2 I
maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
000032 Loss of Source Range NI I 7 x
AA2.0 I
- Normal/abnormal power supply 2.9 I
operation 000076 High Reactor Coolant Activity I CJ x
AA2.06
- Response of PZR LCS to 2.5 I
changes in the letdown flow rate W/E14 Loss of CTMT Integrity I 5 x 2.4.::!3 - Knowledge of the bases for 4.4 I
prioritizing emergency procedure implementation during emergency operations.
KIA Category Totals:
0 0
0 0
2 2
Group Point Total:
4 08/3112016 9.38:25 am
PWR SRO Examination Outline Printed:
08/31/2016 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group I Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A.3 A4 G KA Topic Imp.
Points 006 Emergency Core Cooling x
A2.08 - Effect of electric 3.3 1
power loss on valve position 012 Reactor Protection x
A2.0l - Faulty bistable Hi I
operation OU Engineered Safety Features x 2.3.15 - Knowledge of 1.1 1
Actuation radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
061 Auxiliary/Emergency Feedwater x
A2.08 - Flow rates expected 2.9*
I from various combinations of AFW pump discharge valves 076 Service Water x 2.2.22 - Knowledge of 4.7 1
limiting conditions for operations and safety limits.
KIA Category Totals:
0 0
0 0
0 0
()
3 0
0 2
Group Point Total:
5 08/31/2016 9:38 30 am
PWR SRO Examination Outline Printed:
08/3112016 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 034 Fuel Handling Equipment x
A2.03 - Mispositioned fuel 4.0 1
element 041 Steam Dump/Turbine Bypass x
A2.02 - Steam valve stuck 3.9 1
Control open 056 Condensate x 2.1.45 - Ability to identify 4.3 I
and interpret diverse indications to validate the response of another indication.
Kl A Category Totals:
0 0
0 0
0 0
0 2
0 0
1 Group Point Total:
3 08/31/2016 9:38:36 am
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Printed:
08/31/2016 f'acilitv:
!PEC Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, 3.9 I
such as minimum crew complement, overtime limitations. etc.
2.1.25 Ability to interpret reference materials, such as 4.2 1
graphs, curves, tables, etc.
Category Total:
2 Equipment Control 2.2.17 Knowledge of the process for managing 3.8 1
maintenance activities during power operations, such as risk assessments, work prioritization. and coordination woth the transmission system operator.
2.2.40 Ability to apply Technical Specifications for a 4.7 1
system.
Category Total:
2 Radiation Control 2.3.11 Ability to control radiation releases.
4.3 I
2.3.14 Knowledge of radiation or contamination hazards 3.8 1
that may arise during normal, abnormal. or emergency conditions or activities.
Category Total:
2 Emergency Procedures/Plan 2.4.6 Knowledge of EOP mitigation strategies.
4.7 I
Category Total:
I Generic Total:
7 08131/2016
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Group ____ -----------------------1 i
i RO
! Loss of Off-Site Power KA rejected because equipment does not 000056AA2.04 I
1 / 1 I Service Water Pump Ammeter and Flow meter exist in Indian Point Control Room I
-- -------1-~~~s~:;izer Level Malfunction RO I Change in PZR level with power change, even KA Rejected because TAVG is not constant 000028AK3.04 1 / 2 though RCS T avg constant, due to loop size with power change at Indian Point differences
--- ------------~------------
**------------------------~------------*-----
Containment Flooding RO OOWE152413 Knowledge of the bases for prioritizing emergency KA Rejected because overlap with SRO 1 I 2 procedure implementation during emergency question 85 operations J
RO DC Electrical Distribution KA Rejected because this ability is evaluated 0630002.1.21 2 I 1 I
Ability to verify the controlled procedure copy during JPM or Simulator Scenarios I
--l---
RO Reactor Coolant Pump KA Rejected because too much overlap with 03000A304 2 I 1 RCS Flow question 28- 003000K201
---**--~-----*
ES-401 RO 2 / 1 RO 2 I 1 Record of Rejected Kl As Form ES-401-4
*-.---------------------------------~---------------------------~
004000K413 076000K120 Chemical and Volume Control System Interlock between letdown isolation valve and flow control valve Service Water System AFW KA Rejected because no such interlock exists at IPEC KA Rejected because there is no interface between the service water system and the AFW system at IPEC.
e---*----- ---------- -t--------------------+-----------------------------------------+---
I RO 2 / 1 RO 2/2 1030002305 002000A401 Containment Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment etc.
Reactor Coolant RCS Leakage calculation program using the computer KA rejected because overlap with question
- 51.
KA Rejected because this ability is evaluated during JPM or Simulator Scenarios f------------j-----------
+----------------------------------------
+------------------------<
l RO 1 1Fire Protection KA Rejected because there is no interface 086DOOK101 between Fire Protection and Service Water at 2 12 High Pressure Service Water IPEC
~-------
2
ES-401 Record of Rejected K/As Form ES-401-4
~--~-
~----*--
I RO I
_Jlf Containment Iodine Removal 027000K201 2 I 2 Fans
-~0-1 :
I 029000A40~
I ~:~:_:_:~::~: ~~;~: Flow rate
4-------------------------l----------------*-
RO I
Control Rod Drive 001000K551 212 Definition of Xenon Oscillation
!--------+--
+---
+
Area Radiation Monitoring RO 212 0700002115 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.
3 KA rejected because power supply KA results in LOO 1.
KA rejected because Containment Purge Flow rate cannot be controlled or monitored from the Unit 2 Control room.
KA rejected because current procedures do not clearly define Xenon Oscillation.
KA rejected because unusual generic KA and System combination does not result in an RO level question. Rejected at Chief Examiners recommendation.
ES-401 Record of Rejected KJAs Form ES-401-4 I I Loss of RHR lsRO Ability to use procedures related to shift staffing KA rejected because Generic KA statement is i
0000252.1.5 1 I 1 such as minimum crew compliment, overtime not applicable to APE Loss of RHR limitations, etc.
~------------
SRO Reactor Trip Stabilization KA rejected because unusual KA resulted in 000007A2.06 LOO 1 questions. Rejected at Chief 1 I 1 Occurrence of a reactor trip Examiners recommendation.
*--*------------~-~------
SRO Continuous Rod Withdrawal KA rejected because Generic KA statement is i
1 I 2 I 0000012.2. 1 Knowledge of process for conducting special or not applicable to APE Continuous Rod i
infrequent tests Withdrawal I
I
1---------------------
Loss of Intermediate Range NI KA rejected because loss of intermediate SRO Knowledge of the bases for prioritizing emergency 0000332433 range Nls does not impact EOP 1 I 2 procedure implementation during emergency implementation.
operations
e--------------*---- --------------------------------------------
SRO High Reactor Coolant Activity KA rejected because it does not create an 000076A2.06 Response of PZR LCS to changes in the letdown 1 I 2 flow rate SRO level question per Chief Examiner.
4
ES-401 Record of Rejected K/As Form ES-401-4 SRO Main Feedwater 0590002.2.6 Knowledge of the process for making changes to KA rejected because this KA is best 2 I 1 evaluated using a JPM.
procedures SRO Waste Gas Disposal KA rejected because the Waste Gas System 071000A2.03 212 Rupture Disk Failures at IPEC does not contain rupture disks Conduct of Operations SRO Knowledge of criteria or conditions that require This KA is evaluated during Simulator 2.1.14 3
plant-wide announcements, such as pump starts, Scenarios.
reactor trips, mode changes, etc.
~--
L__ _____________________ --------------
5