ML15160A470
| ML15160A470 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 06/04/2015 |
| From: | D'Antonio J Operations Branch I |
| To: | Indian Point |
| Shared Package | |
| ML14352A136 | List: |
| References | |
| TAC U01908 | |
| Download: ML15160A470 (25) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facilitv:
Indian Point Unit 3 Date of Exam:
5/11/15 RO K/A Cateqory Points SRO-Only 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 18 0
0 0
Emergency &
Abnormal 2
I 2
2 N/A I
2 N/A I
9 0
0 0
Plant Evolutions Tier Totals 4
5 5
4 5
4 27 0
0 0
1 2
2 3
3 3
2 2
3 2
3 3
28 0
0 0
- 2.
Plant 2
I I
I I
0 I
I I
I I
I 10 0
0 0
0 Systems Tier Totals 3
3 4
4 3
3 3
4 3
4 4
38 0
0 0
- 3. Generic Knowledge and Abilities 1
2 3
4 10 1
2 3
4 0
Categories 2
3 2
3 0
0 0
0 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 K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final 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/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 K/A categories.
7.*
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the K/A 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.
Page 1 of9
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqenc and Abnormal Plant Evolutions - Tier 1/Group 1 (ROl E/APE #I Name I Safety Function K
K K A A
G KIA Topic(s)
IR 1
2 3
1 2
000007 (BW/E02&E10; CE/E02) Reactor N/A - Not randomly selected Trip - Stabilization - Recovery I 1 000008 Pressurizer Vapor Space x
AK3.05 - ECCS termination or throttling criteria 4.0 1
Accident/ 3 000009 Small Break LOCA I 3 x
EA1.09 - RCP 3.6 2
000011 Large Break LOCA I 3 x
EK1.01 - Natural circulation and cooling, including 4.1 3
reflux boilinq 000015/17 RCP Malfunctions I 4 x
AK2.08 - CCWS 2.6 4
000022 Loss of Rx Coolant Makeup I 2 x
AK1.01 - Consequences of thermal shock to RCP 2.8 5
seals 000025 Loss of RHR System I 4 x
2.4.13 - Knowledge of crew roles and 4.0 6
responsibilities durinq EOP usaqe 000026 Loss of Component Cooling x
AA2.03 - The valve lineups necessary to restart 2.6 7
Water I 8 the CCWS while bypassing the portion of the system causing the abnormal condition 000027 Pressurizer Pressure Control x
AK3.03 - Actions contained in EOP or PZR PCS 3.7 8
Svstem Malfunction I 3 malfunction 000029 A TWS I 1 x
EK2.06 - Breakers, relays, and disconnects 2.9 9
000038 Steam Gen. Tube Rupture I 3 N/A - Not randomly selected 000040 (BW/E05; CE/E05; W/E12) 000040 - Not randomly selected Steam Line Rupture - Excessive Heat W/E 12 selected - see# 18 below Transfer I 4 000054 (CE/E06) Loss of Main x
AA2.06 - AFW adjustments needed to maintain 4.0 10 Feedwater I 4 proper T-ave. and S/G level 000055 Station Blackout I 6 x
EK1.02 - Natural circulation coolinq 4.1 11 000056 Loss of Off-site Power I 6 N/A - Not randomly selected 000057 Loss of Vital AC Inst. Bus I 6 x
2.4.11 - Knowledge of abnormal condition 4.0 12 procedures 000058 Loss of DC Power I 6 x
AK3.02 - Actions contained in EOP for loss of de 4.0 13 power 000062 Loss of Nuclear Svc Water I 4 x
2.1.39 - Knowledge of conservative decision 3.6 14 makinq practices 000065 Loss of Instrument Air I 8 x
AA2.05 - When to commence plant shutdown if 3.4 15 instrument air pressure is decreasinq W/E04 LOCA Outside Containment I 3 x
EA 1.3 - Desired operating results during abnormal 3.8 16 and emeraency situations W/E11 Loss of Emergency Coolant N/A - Not randomly selected Recirc. I 4 W/E05 Inadequate Heat Transfer - Loss x
EA 1.2 - Operating behavior characteristics of the 3.7 17 of Secondary Heat Sink I 4 facility 000077 Generator Voltage and Electric N/A - Not randomly selected Grid Disturbances I 6 Page 2 of9
ES-401 2 - cont.
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqenc and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)
E/APE #I Name I Safety Function K
K K A A
G KIA Topic(s)
IR 1
2 3
1 2
W/E12 Steam Line Rupture - Excessive x
EK2.2 - Facility's heat removal systems, including 3.6 18 Heat Transfer I 4 primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility KIA Category Totals:
3 3
3 3
3 3
Group Point Total:
18 Page 3 of9
ES-401 3
Form ES-401-2 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 Topic(s)
IR 1
2 3
1 2
000001 Continuous Rod Withdrawal / 1 x
AK1.02 - SUR 3.6 19 000003 Dropped Control Rod I 1 x
AA2.03 - Dropped rod, uing in-core/excore 3.6 20 instrumentation, in-core or loop temperature measurements 000005 Inoperable/Stuck Control Rod / 1 x
AK2.01 Controllers and positioners 2.5 21 000024 Emergency Boration / 1 x
AK3.01 - When emergency boration is 4.1 22 required 000028 Pressurizer Level Malfunction I 2 N/A - Not randomly selected 000032 Loss of Source Ranae NI I 7 NIA - Not randomly selected 000033 Loss of Intermediate Ranae NI/ 7 NIA - Not randomly selected 000036 IBW/A08) Fuel Handlina Accident I 8 NIA - Not randomly selected 000037 Steam Generator Tube Leak I 3 NIA - Not randomly selected 000051 Loss of Condenser Vacuum/ 4 NIA - Not randomly selected 000059 Accidental Liquid RadWaste Rel. I 9 x
AA2.02 - The permit for liquid radioactive-2.9 23 waste release 000060 Accidental Gaseous Radwaste Rel. I 9 N/A - Not randomly selected 000061 ARM Svstem Alarms I 7 NIA - Not randomly selected 000067 Plant Fire On-site I 8 NIA - Not randomly selected 000068 IBW/A06) Control Room Evac. I 8 NIA - Not randomly selected 000069 Loss of CTMT Integrity I 5 N/A - Not randomly selected W/E14 selected see # 27 below 000074 (W/E06) lnad. Core Cooling I 4 N/A - Not randomly selected W/E07 selected see # 25 below 000076 High Reactor Coolant Activity I 9 x 2.1.28 - Knowledge of the purpose and 4.1 24 function of major system components and controls W/E01 & E02 Rediaqnosis & SI Termination 13 N/A - Not randomly selected W/E13 Steam Generator Over-oressure I 4 NIA - Not randomly selected W/E15 Containment Floodina / 5 N/A - Not randomly selected W/E16 Hiah Containment Radiation/ 9 N/A - Not randomly selected BW/A01 Plant Runback / 1 N/A - Not randomly selected BW/A02&A03 Loss of NNl-X/Y I 7 NIA - Not randomly selected BW/A04 Turbine Trip I 4 N/A - Not randomly selected BW/A05 Emeraencv Diesel Actuation I 6 NIA - Not randomly selected BW/A07 Floodina I 8 N/A - Not randomly selected BW/E03 Inadequate Subcoolina Marain I 4 NIA - Not randomly selected BW/E08; W/E03 LOCA Cooldown - Depress. I 4 N/A - Not randomly selected BW/E09; CE/A13; W/E09 Natural Circ. / 4 NIA - Not randomly selected W/E10 selected see #26 below BW/E13&E14 EOP Rules and Enclosures N/A - Not randomly selected CE/A 11; W/E08 RCS Overcoolinq - PTS I 4 N/A - Not randomly selected CE/A16 Excess RCS Leakage/ 2 N/A - Not randomly selected Page 4 of9
ES-401 3 - cont.
Form ES-401-2
. 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 Topic(s)
IR 1
2 3
1 2
CE/E09 Functional Recovery N/A - Not randomly selected W/E07 lnad. Core Cooling I 4 x
EA 1.2 - Operating behavior characteristics 3.2 25 of the facilitv W/E10 Natural Circ. I 4 x
EK3.3 - Manipulation of controls required 3.4 26 to obtain desired operating results during abnormal, and emerqencv situations W/E14 Loss of CTMT Integrity/ 5 x
EK2.1 - Components, and functions of 3.4 27 control and safety systems, including instrumentation signals, interlocks, failure modes and automatic and manual features KIA Category Point Totals:
I 2
2 I
2 I
Group Point Total:
9 Page 5 of9
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems - Tier 2/Group 1 (RO)
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 x
A 1.03 - RCP motor stator winding 2.6 28 temperatures 004 Chemical and Volume x
K6.04 - Knowledge pf the effect of a 2.8 29 Control loss or malfunction on the following CVCS components: Pumps 005 Residual Heat Removal x
K5.05 - Plant response during "solid 2.7 30 plant": pressure change due to the relative incompressibility of water 006 Emergency Core Cooling x
2.1.23 - Ability to perform specific 4.3 31 system and integrated plant procedures durinq all modes of plant operation 006 Emergency Core Cooling x
K5.06 - Relationship between ECCS 3.5 32 flow and RCS pressure 007 Pressurizer Relief/Quench x
A 1.02 - Maintaining quench tank 2.7 33 Tank pressure 008 Component Cooling Water x
K4.01 - Knowledge of the CCWS 3.1 34 design feature(s) and/or interlock(s) which provide for the following:
Automatic start of standby pump 010 Pressurizer Pressure Control x
K6.02 - PZR 3.2 35 012 Reactor Protection x
K5.02 - Power density 3.1 36 012 Reactor Protection x
2.1.45 - Ability to identify and interpret 4.3 37 diverse indications to validate the response of another indication 013 Engineered Safety Features x
K3.01 - Fuel 4.4 38 Actuation 022 Containment Cooling x
A4.05 - Ability to manually operate 3.8 39 and/or monitor in the control room:
Containment readings of temperature, pressure, and humidity system 022 Containment Cooling x
K2.01 - Knowledge of power supplies 3.0 40 to the following: Containment cooling fans 025 Ice Condenser NIA - Not randomly selected, not applicable to Indian Point Unit 3 026 Containment Spray x
K2.02 - Knowledge of bus power 2.7 41 supplies to the followinq: MOVs 026 Containment Spray x
A4.05 - Containment spray reset 3.5 42 switches 039 Main and Reheat Steam x
K4.06 - Prevent reverse steam flow on 3.3 43 steam line break 059 Main Feedwater x
A2.06 - Loss of steam flow to MFW 2.7 44 system Page 6 of9
ES-401 4-cont.
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S* stems - Tier 2/Group 1 (RO)
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 Auxiliary/Emergency x
K3.01 - RCS 4.4 45 Feedwater 062 AC Electrical Distribution x
A3.04 - Operation of inverter (e.g.,
2.7 46 precharging synchronizing light, static transfer) 063 DC Electrical Distribution x
A2.01 - Grounds 2.5 47 064 Emerqencv Diesel Generator x
K4.05 - Incomplete-start relay 2.8 48 064 Emergency Diesel Generator x
2.1.32 - Ability to explain and apply 3.8 49 system limits and precautions 073 Process Radiation x
K3.01 - Radioactive effluent releases 3.6 50 Monitorinq 076 Service Water x
A4.01 - SWS pumps 2.9 51 076 Service Water x
K1.07 - Secondary closed cooling 2.5 52 water 078 Instrument Air x
K 1.03 - Containment air 3.3 53 103 Containment x
A2.05 - Emergency containment entry 2.9 54 103 Containment x
A3.01 - Containment isolation 3.9 55 KIA Category Point Totals:
2 2
3 3
3 2
2 3
2 3
3 Group Point Total:
28 Page 7 of9
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems - Tier 2/Group 2 (RO)
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 x
K2.05 - M/G sets 3.1 56 002 Reactor Coolant N/A - Not randomlv selected 011 Pressurizer Level Control x
K4.01 - Operation of PZR heater cutout at 3.3 57 low PZR level 014 Rod Position Indication x
A2.02 - Loss of power to the RPIS 3.1 58 015 Nuclear Instrumentation N/A - Not randomly selected 016 Non-nuclear Instrumentation N/A - Not randomly selected 017 In-core Temperature Monitor N/A - Not randomly selected 027 Containment Iodine Removal N/A - Not randomly selected 028 Hydrogen Recombiner N/A - Not randomly selected and Puroe Control 029 Containment Puroe N/A - Not randomly selected 033 Spent Fuel Pool Coolino x
A3.02 - Spent fuel leak or rupture 2.9 59 034 Fuel Handling Equipment x 2.1.40 - Knowledge of refueling 2.8 60 administrative requirements 035 Steam Generator x
K1.13 - Condensate system 2.7 61 041 Steam Dump/Turbine N/A - Not randomly selected Bypass Control 045 Main Turbine Generator x
A 1.06 - Expected response of secondary 3.3 62 plant parameters following T/G trip 055 Condenser Air Removal N/A - Not randomly selected 056 Condensate N/A - Not randomly selected 068 Liquid Radwaste N/A - Not randomly selected 071 Waste Gas Disposal x
K3.05 - ARM and PRM systems 3.2 63 072 Area Radiation Monitoring NIA - Not randomly selected 075 Circulatino Water NIA - Not randomly selected 079 Station Air x
A4.01 - Cross-tie valves with IAS 2.7 64 086 Fire Protection x
K6.04 - Fire, smoke, and heat detectors 2.6 65 KIA Cateoorv Point Totals:
I I
I l
0 l
I I
l l
I Group Point Total:
10 Page8of9
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Category K/A#
Topic RO IR 2.1.29 Knowledge of how to conduct system lineups, such as valves, 4.1 66 breakers, switches, etc.
- 1.
2.1.44 Knowledge of RO duties in the control room during fuel handling, such 3.9 67 Conduct of Operations as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fuelinq operations, and suooortinq instrumentation.
Subtotal 2
2.2.23 Ability to track Technical Specification limitinq conditions for operations.
3.1 68 2.2.38 Knowledqe of conditions and limitations in the facility license.
3.6 69
- 2.
2.2.40 Ability to apply Technical Specifications for a system.
3.4 70 Equipment Subtotal 3
Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency 3.2 71 conditions.
- 3.
2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation 2.9 72 Radiation monitors and alarms, portable survey instruments, personnel Control monitorino equipment, etc.
Subtotal 2
2.4.12 Knowledge of general operating crew responsibilities during emergency 4.0 73 operations.
- 4.
2.4.23 Knowledge of the bases for prioritizing emergency procedure 3.4 74 Emergency Procedures I implementation durinq emerqency operations.
Plan 2.4.30 Knowledge of events related to system operation/status that must be 2.7 75 reported to internal organizations or external agencies, such as the State, the NRC, or the transmission svstem operator.
Subtotal 3
Tier 3 Point Total 10 Page 9 of9
ES-401 Record of Rejected K/As - RO Exam Form ES-401-4 Tier I KIA Randomly Selected KIA Reason for Rejection Group T1 I G1 000022AK1.04 Knowledge of the operational implications of This KIA does not apply to Indian Point Unit 3. No the following concepts as they apply to Loss procedural or operational guidance to require auto of Reactor Coolant Makeup: Reason for operation related to loss of RCS makeup. Typically, changing from manual to automatic control of procedural guidance would take the controls to charging flow valve controller.
manual for a failure related to RCS makeup.
T1 I G2 000001AK1.19 Knowledge of the operational implications of This KIA does not apply to Indian Point Unit 3.
the following concepts as they apply to Indian Point does not have procedural guidance Continuous Rod Withdrawal: Voids related to the voids coefficient. Not operationally Coefficient.
significant for a PWR.
T1 I G2 000005AK2.03 Knowledge of the interrelations between the This KIA does not apply to Indian Point Unit 3. It Inoperable I Stuck Control Rod and the does not apply to IP3 rod control equipment.
following: Metroscope.
T1 I G2 000076G2.2. 7 High Reactor Coolant Activity: Knowledge of This generic KIA does not apply well to the event.
the process for conducting special or This Abnormal event and IPTE requirements do not infrequent tests.
share any defined relationships I procedural Quidance.
T2 I G1 004000K6.26 Knowledge of the effect of a loss or This KIA as rejected due to overlap with question malfunction on the following eves
- 30 which was the same concept of solid pressure components: Methods of pressure control of operations related to RHR. Concept is too limited solid plant (PZR relief and water inventory).
with regard to systems operation to generate two operationally valid and discriminating questions.
T2 I G1 008000K4.07 Knowledge of CCWS design feature(s)
This KIA does not apply to Indian Point Unit 3. It and/or interlock(s) which provide for the does not apply to the IP3 CCW System.
following: Operation of the CCW swing-bus power supply and its associated breakers and controls.
Page 1 of2
ES-401 Record of Rejected K/As - RO Exam Form ES-401-4 Tier I KIA Randomly Selected KIA Reason for Rejection Group T2 I G1 012000G2.3.11 Reactor Protection System: Ability to control This Generic KIA does not apply well to this system.
radiation releases.
No known direct relationships. Would be difficult to generate an operationally relevant, valid, and discriminatinq question.
T2 I G1 022000A4.02 Containment Cooling System - CCS Pumps This KIA as rejected due to overlap with questions 40 and 41 associated with the Containment Spray System. Although containment spray pumps could be related to this KIA, there are no "pumps" in the Containment Cooling System, only Containment Fan Cooler Units (FCUs). The Containment Spray System is already being evaluated by questions 40 and 41.
T2 I G1 064000G2.2.43 Emergency Diesel Generator - Knowledge This Generic KIA does not apply well to this system.
of the process used to track inoperable The EOG controls are not in the control room at IP3 alarms.
and the alarms that are in the control room are not required for operability. It would be difficult to write an operationally relevant, valid, and discriminating question for this generic KA applied to this system.
T2/G2 034000G2.4.42 Fuel Handling Equipment - Knowledge of This Generic KIA does not apply well to this emergency response facilities.
equipment I system. No known direct relationships.
Would be difficult to generate an operationally relevant, valid, and discriminatinq question.
Page 2 of2
ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:
IPEC Printed: 05/04/15 Date Of Exam:
05/11/2015 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G*
- 1.
1 0
0 0
0 0
0 0
3 3
Emergency 2
0 0
0 0
0 0
0 2
2 N/A N/A Abnormal Tier Plant Totals 0
0 0
0 0
0 0
5 5
Evolutions
- 2.
1 0
0 0
0 0
0 0
0 0
0 0
0 3
2 Plant 2
0 0
0 0
0 0
0 0
0 0
0 0
0 I 2
1 Systems Tier 0
0 0
0 0
0 0
0 0
0 0
0 5
3 Totals
- 3. Generic Knowledge And 1
2 3
4 1
2 3
4 0
Abilities Categories 0
0 0
0 2
1 2
2 Note:
- 1.
Ensure that at least two topics from every applicable KJA 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 KJA 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/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 KJA 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 KJA categories.
?.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 Kl As.
- 8.
On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (I 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 other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3.
Limit SRO selections to Kl As that are linked to 10 CFR 55.43.
Total 6
4 10 5
3 8
7
PWR SRO Examination Outline Printed: 05/04/15 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 El APE # I Name I Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000007 Reactor Trip - Stabilization - Recovery x
EA2.04 - If reactor should have tripped 4.4 1
I 1 but has not done so, manually trip the reactor and carry out actions in A TWS EOP 000038 Steam Gen. Tube Rupture I 3 x
EA2. l 0 - Flowpath for charging and 3.3 1
letdown flows 000040 Steam Line Rupture - Excessive Heat x 2.4.21 - Knowledge of the parameters and 4.6 1
Transfer I 4 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.
000056 Loss of Off-site Power I 6 x 2.4.18 - Knowledge of the specific bases 4.0 1
for EOPs.
000077 Generator Voltage and Electric Grid x 2.2.25 - Knowledge of bases in Technical 4.2 1
Disturbances I 6 Specifications.
W/El 1 Loss of Emergency Coolant Recirc. I 4 x
EA2. l - Facility conditions and selection 4.2 1
of appropriate procedures during abnormal and emergency operations KIA Category Totals:
0 0
0 0
3 3
Group Point Total:
6
PWR SRO Examination Outline Printed: 05/04/15 Facility:
IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE #I Name I Safety Function Kl K2 K3 Al A2 G
KA Topic Imp.
Points 000033 Loss oflntermediate Range NI I 7 x 2.2.25 - Knowledge of the bases in 4.2 l
Technical Specifications.
000036 Fuel Handling Accident I 8 x 2.1.23 - Ability to perform specific system 4.4 1
and integrated plant procedures during all modes of plant operation.
000060 Accidental Gaseous Radwaste Rel. I 9 x
AA2.02 - The possible location of a 4.0 1
radioactive-gas leak, with the assistance of PEO, health physics and chemistry personnel 000074 lnad. Core Cooling I 4 x
EA2.02 - Availability of main or auxiliary 4.6 1
feed water KIA Category Totals:
0 0
0 0
2 2
Group Point Total:
4
PWR SRO Examination Outline Printed:
05104115 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group 1 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp.
Points 003 Reactor Coolant Pump x
A2.0l - Problems with RCP 3.9 1
seals, especially rates of seal leak-off 008 Component Cooling Water x 2.1.7 - Ability to evaluate 4.7 1
plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
039 Main and Reheat Steam x
A2.04 - Malfunctioning steam 3.7 1
dump 061 Auxiliary/Emergency Feedwater x
A2.04 - Pump failure or 3.8 1
improper operation.
062 AC Electrical Distribution x 2.4.40 - Knowledge of SRO 4.5 1
responsibilities in emergency plan implementation.
KIA Category Totals:
0 0
0 0
0 0
0 3
0 0
2 Group Point Total:
5
PWR SRO Examination Outline Printed:
05/04/15 Facility:
IPEC ES - 401 Plant Systems - Tier 2 I Group 2 Form ES-401-2 Sys/Evol #I Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.
Points 002 Reactor Coolant x
A2.04 - Loss of heat sinks 4.6 1
028 Hydrogen Recombiner and x
A2.02 - LOCA condition and 3.9 1
Purge Control related concern over hydrogen 072 Area Radiation Monitoring x 2.4.l - Knowledge of EOP 4.8 1
entry conditions and immediate action steps.
Kl A Category Totals:
0 0
0 0
0 0
0 2
0 0
1 Group Point Total:
3
Generic Knowledge and Abilities Outline (Tier 3)
PWR SRO Examination Outline Printed: 05/04/15 Facility:
IPEC Form ES-401-3 Generic Category KA Topic Conduct of Operations 2.1.35 Knowledge of the fuel-handling responsibilities of 3.9 1
SR Os.
2.1.5
. Ability to use procedures related to shift staffing, 3.9 1
such as minimum crew complement.
Category Total:
2 Equipment Control 2.2.37 Ability to determine operability and I or availability 4.6 1
of safety related equipment.
Category Total:
1 Radiation Control 2.3.5 Ability to use radiation monitoring systems, such as 2.9 1
fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.
2.3.11 Ability to control radiation releases.
4.3 1
Category Total:
2 Emergency Procedures/Plan 2.4.38 Ability to take actions called for in the facility 4.4 1
emergency plan, including supporting or acting as emergency coordinator if required.
2.4.45 Ability to prioritize and interpret the significance of 4.3 1
each annunciator or alarm.
Category Total:
2 Generic Total:
7
ES-401 Record of Rejected K/As - SRO Exam Form ES-401-4 Tier I KIA Randomly Selected KIA Reason for Rejection Group T1 I G1 000077G2.1.39 Generator Voltage and Electric Grid This KIA was rejected due to overlap with RO Disturbances - Knowledge of conservative question 14 which tested the same generic KIA decision making practices.
associated with conservative decision making. Too difficult to generate two operationally valid, relevant, and discriminating questions related to this generic topic.
T1 I G2 000033G2.1.6 Loss of Intermediate Range NI -Ability to This KIA was rejected because it would be difficult to manage the control room crew during plant write an operationally valid, relevant, and transients.
discriminating question that adequately matches the KIA. This generic KIA is more applicable to the operating exam.
T2 I G1 061OOOA2.06 Auxiliary Feedwater - Back leakage of MFW This KIA was rejected due to the difficultly in writing a question that is operationally valid, relevant, and discriminating while not testing "trivial information".
This condition has not been a problem at Indian Point and the instructions to mitigate are in an un-used attachment of a normal operating instruction.
T3/COO 194000G2. 1. 39 Knowledge of conservative decision making This KIA was rejected due to overlap with RO practices.
question 14 which tested the same generic KIA associated with conservative decision making. Too difficult to generate two operationally valid, relevant, and discriminating questions related to this generic topic.
T3/ EC 194000G2.2.35 Ability to determine Technical Specification This KIA was rejected because of the difficultly Mode of Operation.
writing an SRO level question based on RO required level knowledge. Technical Specification Mode I Applicability is RO level knowledge ("above the line").
Page 1 ofl
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Indian Point 3 Date of Examination:
5/11/15 Examination Level: ROX SRO D Operating Test Number:
1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Perform Offsite Power Sources Surveillance Conduct of Operations NS 2.1.18 - Ability to make accurate, clear, and concise logs, records, status boards, and reports.
RO - 3.6 (45.13)
Hydrogen Recombiner Operation Conduct of Operations NR Determine Required Heater Power IAW 3-SOP-CB-007.
2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
RO - 3.9 (45.12)
NIA Equipment Control NIA Determine Radiological Conditions, RWP Radiation Control Requirements, and Potential Dose NR 2.3.7 -Ability to comply with radiation work permit requirements during normal or abnormal conditions.
RO-3.5 (45.10)
Perform Initial Unusual Event Notification Emergency Procedures/Plan OS 2.4.39 - Knowledge of RO responsibilities in emergency plan implementation.
R0-3.9 (45.11)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank(::; 3 for ROs;::; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams(::; 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Indian Point 3 Date of Examination:
5/11 /15 Examination Level: ROD SRO x Operating Test Number:
1 Administrative Topic Type Describe activity to be performed (see Note)
Code*
NR Update Electrical Power Availability for Shutdown Safety Assessment Conduct of Operations 2.1.18 - Ability to make accurate, clear, and concise logs, records, status boards, and reports.
SRO - 3.8 (45.13)
Determine Isolation Boundaries for CCW Leak Using Plant Prints Conduct of Operations D RorS 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.
SRO-4.2 (45.12)
NR Review completed Service Water Pump Surveillance.
Equipment Control 2.2.12 - Knowledge of surveillance procedures.
SR0-4.1 (45.13)
NR Review I Authorize a Liquid Waste Release Radiation Control 2.3.6 - Ability to approve release permits.
SRO - 3.8 (45.10)
D RorS Classify Event and Complete Form EP-1, Part 1 Emergency Procedures/Plan 2.4.41 - Knowledge of the emergency action level thresholds and classifications.
SRO - 4.6 (45.11)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank(:::; 3 for ROs;:::; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (2 1)
(P)revious 2 exams (:::; 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Indian Point 3 Date of Examination:
5/11/15 Exam Level: RO X SRO-ID SRO-U D Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function S-1 Respond to Turbine 1*t Stage Pressure Transmitter Failure (412A) IAW 3-A,D,S 1
INST-1 and subsequent Tavg recovery with manual rods (Continuous rod motion) IAW 3-AOP-ROD-1. (use 50% Power IC)
S-2 Transfer Buses 1-4 to the Station Aux Transformer D,P,S 6
S-3 Fill an Accumulator with a SI Pump D,S 2
S-4 Depressurize the RCS following a SGTR (using PORVs) IAW E-3.
A,D,S 3
S-5 RHR Pump Trip while on shutdown cooling IAW 3-AOP-RHR-1 L,S 4P S-6 Swap Essential Service Water Pumps (Check valve on O/S pump sticks open)
A,N,S 4S (ensure pressure does not drop below trip setpoint)
S-7 Verify Containment Spray Operation IAW E-0, step 9. (Manually initiate and A,D,S 5
stop RCPs)
S-8 Pressurizer Pressure Channel fails low, trip bistables.
D,S 7
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 Locally Start and Synchronize for Parallel Operation# 31 EOG IAW 3-SOP-D 6
EL-001.
P-2 Perform a Radioactive Liquid Release (Monitor Tank) IAW 3-SOP-WDS-014 A,N, R 9
P-3 Local Charging Pump Operation (sect. 4.10) from RWST with CCW not A,E,M,R 8
available, requiring alignment to city water cooling (sect. 4.11) IAW 3-SOP-ESP-001.
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank
- S9/:S8/:S4 (E)mergency or abnormal in-plant 21121121 (EN)gineered safety feature
- I -
I 21 (control room system)
(L)ow-Power I Shutdown 21121121 (N)ew or (M)odified from bank including 1 (A) 22122121 (P)revious 2 exams
- s; 3 I :s; 3 I :s; 2 (randomly selected)
(R)CA 21121121 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Indian Point 3 Date of Examination:
5/11/15 Exam Level: RO SRO-I X SRO-LI Operating Test No.:
1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function S-1 Respond to Turbine 1*t Stage Pressure Transmitter Failure (412A) IAW 3-A,D,S 1
INST-1 and subsequent Tavg recovery with manual rods (Continuous rod motion) IAW 3-AOP-ROD-1. (use 50% Power IC)
S-3 Fill an Accumulator with a SI Pump D,S 2
S-4 Depressurize the RCS following a SGTR (using PORVs) IAW E-3.
A,D,S 3
S-5 RHR Pump Trip while on shutdown cooling IAW 3-AOP-RHR-1 L,S 4P S-6 Swap Essential Service Water Pumps (Check valve on O/S pump sticks open)
A,N,S 4S (ensure pressure does not drop below trip setpoint)
S-7 Verify Containment Spray Operation IAW E-0, step 9. (Manually initiate and A,D,S 5
stop RCPs)
S-8 Pressurizer Pressure Channel fails low, trip bistables.
D,S 7
In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P-1 Locally Start and Synchronize for Parallel Operation# 31 EOG IAW 3-SOP-D 6
EL-001.
P-2 Perform a Radioactive Liquid Release (Monitor Tank) IAW 3-SOP-WDS-014 A,N,R 9
P-3 Local Charging Pump Operation (sect. 4.10) from RWST with CCW not A,E,M,R 8
available, requiring alignment to city water cooling (sect. 4.11) IAW 3-SOP-ESP-001.
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank
- g/
- ::;8/:::;4 (E)mergency or abnormal in-plant 21/21/21 (EN)gineered safety feature
- I -
I 21 (control room system)
(L)ow-Power I Shutdown 21/21/21 (N)ew or (M)odified from bank including 1 (A) 22/22/21 (P)revious 2 exams
- 3 I
- ::; 3 /:::; 2 (randomly selected)
(R)CA 21/21/21 (S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 3 Scenario No.:
1 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions: A1212rox. 75% Power, 12ower ascension in 12rogress to 100% 12ower IAW 3-POP-2.1, Attachment 2. 2 Condensate Pum12s are in service. Fuel is Conditioned.
Turnover:
Continue Qower ascension to 100% IAW 3-POP-2.1, Attachment 2 Returning from maintenance on 32 MBFP (oil leak}. 32 Charging PumQ is out of service, tagged due to a 12acking leak (maintenance has QUmQ disassembled}.
Event Malf. No.
Event Event No.
Type*
Description 1
N/A R (ATC)
Raise load IAW 3-POP-2.1 N (BOP)
N (CRS) 2 MAL-SGN002B I (BOP) 31 Steam Generator Pressure (PT-419B)
I (ATC)
Channel fails high.
TS (CRS) 3 MAL-SIS003C I (BOP) 33 Accumulator Low Pressure Alarm actuates.
TS (CRS) 4 MAL-A TS004B C (ALL) 32 MBFP trips.
5 MAL-GEN001 C(ALL)*
IF crew does not trip reactor due to 32 MBFP MAL-GEN002 trip, insert MTG Voltage Regulator Failure and within 3 minutes a direct MTG Trip from Buchanan.*
6 MAL-SGN004A M(ALL)
Automatic Turbine I Reactor Trip I Safety MAL-SGN004B Injection. Coincident with the Reactor Trip, #31 SG Safety Valve will fail open.
7 MAL-SIS004A C (CRS) 31 Safety Injection Pump fails to auto start.
C(BOP) 8 MAL-SGN005A M(ALL) 31 SG Tube Rupture (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Page 2 of16
Appendix D Scenario Outline Form ES-D-1 Facility:
Indian Point 3 Scenario No.:
3 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions: 100% Power, # 32 ComQonent Cooling Water PumQ is out of service for Maintenance (Motor re12lacement)
Turnover: 100% Power, # 32 Com12onent Cooling Water Pum12 is out of service for Maintenance (Motor reQlacement}. Maintain 100%
Event Malf. No.
Event Event No.
Type*
Description 1
MAL-CFW005C c
- 33 Condensate Pump Trips, crew responds IAW BOP/CRS 3-AOP-FW-1.
R (ATC)
Technical Specification for delta I (discuss at TS (CRS) minimum after scenario) 2 MAL-SGN001 F I (ATC or 32 SG Controlling level channel fails low (LT 427B).
BOP)
TS (CRS) 3 MAL-MSS009A M (ALL)
Steam Leak in Turbine Buildino.
4 MAL-RPS002A C/M (ALL)
The reactor will not trip from the control room and MAL-RPS002B the crew responds per FR-S-1, ATWS 5
MAL-RHR001 B C (BOP)
Following SI actuation, #32 RHR Pump and #33 SI MAL-SIS004C did not start. BOP starts pumps per 3-R0-1 RNO.
6 MAL-MSS013A M (ALL)
Failure of MSIVs to close from Control Room. (2 MAL-MSS013B will be closed locally after AFW is throttled to 100 gpm per ECA-2.1 ).
MAL-MSS013C MAL-MSS013D (Nlormal, (R)eactivity, (l)nstrument, (C)omponent, (M)aior Page 2 of14
Appendix D Scenario Outline Form ES-D-1 Facility:
Indian Point 3 Scenario No.:
4 Op-Test No.:
1 Examiners:
Operators:
Initial Conditions: 100% Power with 31 EOG out of service due to malfunctioning governor. 31 Charging PumQ l/S, 35 Service Water PumQ 1/S Turnover: 100% Power with 31 EOG out of service due to malfunctioning governor. Maintain 100% QOWer.
31 Charging PumQ l/S, 35 Service Water PumQ l/S.
Event Malf. No.
Event Event No.
Type*
Description 1
MAL-C (BOP) 35 SWP trips SWS001E TS (CRS) 2 MAL-C (ATS)
Power Range Channel 41 Upper Detector Fails High NIS006A C (CRS)
TS (CRS) 3 MAL-C (ALL) 480V Bus 5A Fault EPS005C TS (CRS) 4 N/A R (ATC)
Tech Spec required plant shutdown 5
MAL-M(ALL)
Station Blackout EPS001 6
MAL-C (BOP) 32 EOG fail to start DSG001B 7
MAL-C (ATC)
PZR PORV Fails Open (455C fails open after loss of all PRS003C AC, we need to isolate block valve later) 8 MAL-C (BOP)
SW pump does not auto start after bus energized SWS001F 32 EOG comes back, 6A bus back. Failure of 36 SW pump to auto start.
(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Page 2 of13