ES-401 PWR Examination Outline Form ES-401-2 · 7* The generic (G) K/As in Tiers 1 and 2 shall be...
35
ES-401 PWR Examination Outline Form ES-401-2 Facility: FARLEY Date of Exam: JUNE 2012 — — ROKJACapo 1 yPohts — SRO-Only_Points Tier Group T KIKKK KKAAAAG A2 G* Total 112 3 4 5 6 1 2 3 4 * Total 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency & Abnormal 2 j_ j... . N/A .1 i... N/A 2 9 2 2 4 Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10 1 33332322322 28 3 2 5 2. Plant 2 11111101111 10 1 1 1 3 Systems Tier Totals 4 4 4 4 3 4 2 3 4 3 3 38 5 3 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 1 2 2 2 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, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
Transcript of ES-401 PWR Examination Outline Form ES-401-2 · 7* The generic (G) K/As in Tiers 1 and 2 shall be...
ES-401 PWR Examination Outline Form ES-401-2
Facility: FARLEY Date of Exam: JUNE 2012
—
— ROKJACapo1yPohts — SRO-Only_PointsTier Group T
KIKKK KKAAAAG A2 G* Total112 3 4 5 6 1 2 3 4 * Total
1. 1 3 3 3 3 3 3 18 3 3 6Emergency &
Abnormal 2 j_ j... . N/A .1 i... N/A 2 9 2 2 4
Evolutions Tier Totals 4 4 5 5 4 5 27 5 5 10
1 33332322322 28 3 2 52.
Plant 2 11111101111 10 1 1 1 3Systems
Tier Totals 4 4 4 4 3 4 2 3 4 3 3 38 5 3 8
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7Categories
2 2 3 3 1 2 2 2
Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand 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 applyat the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are notincluded on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the eliminationof inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group beforeselecting 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 totalsfor each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on theSRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicatepages 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, IRs,and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2 Form ES-401-2
ES-401 PWR Examination OutHne Form ES-401-2Emergency and Abnorrna! Plant Evolutions - Tier 1/Group 1 0 / SRO) —
E/APE#/Name/SafetyFunction K K K A A G K/ATopic(s) IR #12312
000007 (BW/E02&E1 0; CE/E02) Reactor 7 1. 0 4,Trip - Stabilization - Recovery / 1 — — — — — —
000008 Pressurizer Vapor Space R 0 0 g A 1<3. 04 -
Accident! 3
000009 Small Break LOCA /3 — R — — 009 EE 1< 03000011 Large Break LOCA/3 — — R — O( EA000015/17 RCP Malfunctions /4
000022 Loss of Rx Coolant Makeup / 2 — — — — — R 0 2 G 4. 34 4..000025 Loss of RHR System / 4 —
— R — —— 0 S A K 3, 0_ a3
000026 Loss of Component CoolingWater/8
000027 Pressurizer Pressure Control o2 A K i o a gSystem Malfunction / 3
000029ATWS/1 R — — — —— O EKJ..o3
000038 Steam Gen. Tube Rupture / 3 — — — — R U 3 4, 4?000040 (BW/E05; CE/E05 W/E12Steam Line Rupture - Excessive eat R 040 V)/& 12 A A , I I 2Transfer/4 — — — — —
— —
000054 (CE/E06) Loss of Main 0 0 4- AFeedwater/4 ‘. ‘ —,
000055 Station Blackout / 6 — — — — R — 0 A, 0 4,4000056 Loss of Off-site Power / 6
000057 Loss of Vital AC Inst. Bus / 6 — — — — — 057 AA I .0 3.7000058 Loss of DC Power! 6 — — — — — A I DI000062 Loss of Nuclear Svc Water.! 4 — — — —
— 0 ( 2 A A 1 0 7000065 LossoflnstrumentAir/8 — — R — —
—
Qc5 A<3, o3 2
W/E04 LOCA Outside Containment/3 — — — — — W1D4 1.. 31g
W/E1 1 Loss of Emergency CoolantRecirc. / 4
Transfercs of Secondary Heat Sink/4 — — — — —0 I I 37
000077 Generator Voltage and ElectricGrid Disturbances / 6
K/A Category Totals:• I 3 3 Group Point Total; 14)6
ES-401 3 Form ES-401-2
ES-401 PWR Examination Outline ,.—.. Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2’! SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #12312
000001 Continuous Rod Withdrawal / 1
000003 Dropped Control Rod / 1 — — — R — — 003 AA I. O’7 3,g Q000005 Inoperable/Stuck Control Rod / 1
— R — — —— 0 05 A . 2..,
. 000024 Emergency Boration / I — — — R — —O4 AA I
000028 Pressurizer Level Malfunction / 2
000032 Loss of Source Range NI/7 R — V3 AAD000033 Loss of Intermediate Range NI / 7 — — g — — — 0 3 A K 3 0 3.2-000036 (BW/A08) Fuel Handling Accident! 8
000037 Steam Generator Tube Leak / 3
000051 Loss of Condenser Vacuum / 4
000059 Accidental Liquid RadWaste Rel. / 9
000060 Accidental Gaseous Radwaste Rel. / 9
000061 ARM System Alarms / 7 g — — — — — &( A K 1,01000067 Plant Fire On-site/8 — — — — — R D7 A ,4.000068 (BW/A06) Control Room Evac. / 8
000069 (W/E14) Loss of CTMT Integrity / 5
000074 (W/E06&E07) mad. Core Cooling /4
000076 High Reactor Coolant Activity / 9
W/EO1 & E02 Rediagnosis & SI Termination / 3 — — —
W/E13 Steam Generator Over-pressure/4 — — — — — vJ/-L3W/E1 5 Containment Flooding / 5
W/E16 High Containment Radiation / 9
BW/A01 Plant Runback / 1
BW/A02&A03 Loss of NNI-X/Y / 7
BW/A04 Turbine Trip /4
BW/A05 Emergency Diesel Actuation / 6
BW/A07 Flooding / 8 —
BW/E03 Inadequate Subcooling Margin / 4 —
BW/E08; W/E03 LOCA Cooldown - Depress. / 4 — — — —
BW/E09; CE/A13;E ElO Natural Circ. /4 — — — — P W/O9BW/E13&E14 EOP Rules and Enclosures —
CE/All; W/E08 RCS Overcooling - PTS / 4 — — — — —
CE/Al 6 Excess RCS Leakage / 2 —
CE/E09 Functional Recovery —
K/A Category Point Totals: t} I I 1 QI Group Point Total: K4
ES-401 4 Form ES-401-2
ES-401 PWR Examination Outli Form ES-401-2
=— Rant Svsterns..11er2/Grouo6)SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #1234561234 4——
003 Reactor Coolant Pump —g 3 2. 23
004 Chemical and Volume pControl o4 AhiO 3.7
--
005 Residual Heat Removal — — — — — —— 0O’’ A f<5.o —
006 Emergency Core Cooling — — —
—
— 00 K* 1/
007 Pressurizer Relief/QuenchTank KSIOZ 3!j
008 Component Cooling Water OL) A 3, o , K3,o010 Pressurizer Pressure Control — — —
—
— 0) A 4’ 03012 Reactor Protection — — — — — — — —
— oi2 k) 6 Ob
013 Engineered Safety Features .-y / /Actuation 1 34
O22ContainmentCooling 1<.0Q- 3,0
025 Ice Condenser AJ/,t
026 Containment Spray 2 • 0 f 4.2
039 Main and Reheat Steam K )‘4oZ 3 I059 Main Feedwater 0 9 A 3.061 Auxiliary/EmergencyFeedwater Ic 0 ‘2
062 AC Electrical Distribution—
— 0b2 Ak,1 03 ‘3 , 02.
063 DC Electrical Distribution 1 t73 2, 2 44 42/A 171 4 3%’
064 Emergency Diesel Generator ——
—O’ Ni. 07’ K4 0+
073 Process RadiationMonitoring R V73076 Service Water V”7 j’D 3.1
O78lnstrumentAir —g
— o7 A4.; , K0103 Containment — —
—R — — 103 AZ. 0
K/A Category Point Totals:.. I I Group Point Total:
II
‘I
‘I
II
ES-401 5 Form ES-401-2
ES-401 PWR Examination Outr Form ES-401-2PlantSystems-Tier2/Group CRC SRO) —
System #1 Name K K K K K K A A A A G K/A Topic(s) IR #1234561234
001 Control Rod Drive
002 Reactor Coolant R OO- K 0 2S I011 Pressurizer Level Control 01 / K I 3,1
014 Rod Position Indication ô /4 A, P4-
015 Nuclear Instrumentation
016 Non-nuclear Instrumentation
017 In-core Temperature Monitor 917 KS 02 3’7
027 Containment Iodine Removal
028 Hydrogen Recombinerand Purge Control
029 ContainmentPurge O2 2239 3,9
033 Spent Fuel Pool Cooling — — — 33 A 01
034 Fuel Handling Equipment R. 034 X h 01 25
035 Steam Generator 03 5 )<3 0/ 44-
041 Steam Dump/TurbineBypass Control
045 Main Turbine Generator
055 Condenser Air Removal
056 Qondensate
068 Liquid Radwaste 4, °4 3 $
071 Waste Gas Disposal
072 Area Radiation Monitoring
075 Circulating Water
079 StationAir —086 Fire Protection
K/A Category Point Totals: L I. .L I I 1.. 2 1 ui j Group Point Total:
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3
Facility: rritt/ Date of Exam: JuA’ ti 2.
Category K/A# Topic SRO-Only
2.1.1 JCt Oj tQ1t5 3.g
1. 2.1.4 w-So&.. 3Conduct 2.1.of Operations
2.1.
2.1.
2.1.
Subtotal
2.2.4O ppLj %cs 4k. sr4t 3.+2.2.41
2. 2.2.EquipmentControl 2.2.
2.2.
2.2.
Subtotal 22.3. 1 Z 5-JL iri 2
2.3.5 4/ih -b rt
3. 2.3. ti RJPRadiationControl 2.3.
2.3.
2.3.
Subtotal 32.4. 14- 6c-uvtiz
,g
4. 2.4.43 Ccnio 3,2Emergency 2.4. 2 €pOic1 /opak- 4 2.Procedures I )
Plan 2.4.
2.4.
2.4.
Subtotal 3Tier3PointTotal 7
ES-401 2 Form ES-401-2
ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions-Tier 1/Group 1 (RO SRO —
E/APE #1 Name / Safety Function K K K A A G K/A Topic(s) IR #12312
000007 (BW/E02&E10; CE/E02) ReactorTrip - Stabilization - Recovery / 1
000008 Pressurizer Vapor SpaceAccident / 3
000009 Small Break LOCA / 3
000011 Large Break LOCA/3 — — —— 0 — ‘1 EAa_
000015/17 RCP Malfunctions / 4
000022 Loss of Rx Coolant Makeup / 2
000025 Loss of RHR System / 4 — — — — — 0O25 AA 2000026 Loss of Component Cooling
000027 Pressurizer Pressure ControlSystem Malfunction I 3
000029 ATWS/1
000038 Steam Gen. Tube Rupture / 3
000040 (BW/E05; CE/E05; W/E12)Steam Line Rupture - Excessive HeatTransfer / 4
000054 (CE/E06) Loss of MainFeedwater / 4
000055 Station Blackout / 6
000056 Loss of Off-site Power / 6 — — — — —O& A I 7
000057 Loss of Vital AC Inst. Bus / 6
000058 Loss of DC Power / 6
000062 Loss of Nuclear Svc Water / 4
000065 Loss of Instrument Air / 8
W/E04 LOCA Outside Containment / 3
Loss of Emergency Coolant L 4,2
BW/E04; W/E05 Inadequate HeatTransfer- Loss of Secondary Heat Sink/4
000077 Generator Voltage and ElectricGrid Disturbances / 6
K/A Category Totals: = = Group Point Total: 1861
ES-401 3 Form ES-401-2
ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (R /SRO
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #12312
000001 Continuous Rod Withdrawal / 1
000003 Dropped Control Rod/I 003 A 22 z2 4;r1
000005 Inoperable/Stuck Control Rod / 1
000024 Emergency Boration/ 1 024 4 2’, 4-. 4’ 42-000028 Pressurizer Level Malfunction / 2
000032 Loss of Source Range NI / 7
000033 Loss of Intermediate Range NI / 7
000036 (BW/A08) Fuel Handling Accident / 8 —
000037 Steam Generator Tube Leak / 3
000051 Loss of Condenser Vacuum / 4
000059 Accidental Liquid RadWaste Rel. / 9
000060 Accidental Gaseous Radwaste Rel. / 9
000061 ARM System Alarms / 7
000067 Plant Fire On-site / 8 o’7 A/\ OX
000068 (BW/A06) Control Room Evac. / 8 —
000069 (W/E14) Loss of CTMT Integrity / 5
000074 (W/E06&E07) mad. Core Cooling / 4 —
000076 High Reactor Coolant Activity / 9
W/EO1 & E02 Rediagnosis & SI Termination / 3 —
WIE13 Steam Generator Over-pressure /4
W/E1 5 Containment Flooding / 5 —
W/E16 High Containment Radiation / 9
BW/A0I_Plant_Runback_/_1
BW/A02&A03 Loss of NNI-X1Y /7
BW/A04 Turbine Trip / 4
BW/A05 Emergency Diesel Actuation / 6
BW/A07 Flooding / 8
BW/E03 Inadequate Subcooling Margin / 4
BW/E08; W/E03 LOCA Cooldown - Depress. / 4
BW/E09; CE/Al 3; W/E0Q atural Circ. / 4 1t) I 0 -.2.BW/El3&E14 EOP Rules and Enclosures
CE/All; W/E08 RCS Overcooling - PTS / 4
CE/Al 6 Excess RCS Leakage / 2
CE/E09 Functional Recovery
K/A Category Point Totals: = = = = dZ i Group Point Total:
ES-401 4 Form ES-401-2
ES-401 PWR Examination Outline Form ES-4012— Plant Systems - Tier 2/Group 1(RO i(
System #1 Name K K K K K K A A A A G K/A Topic(s) IR #123456 1234
003 Reactor Coolant Pump — — —
004 Chemical and Volume
Control
005 Residual Heat Removal OOS r4 4 7Oo6EmergencyCoreCooling OO& 413
007 Pressurizer Relief/Quench
Tank
008 Component Cooling Water A . o I 3.6
010 Pressurizer Pressure Control O1 43012 Reactor Protection
013 Engineered Safety Features
Actuation
022 Containment Cooling — — — —
025 Ice Condenser
026 Containment Spray — — — 2L AI,t/039 Main and Reheat Steam
059 Main Feedwater
061 Auxiliary/Emergency
Feedwater
062 AC Electrical Distribution
063 DC Electrical Distribution
064 Emergency Diesel Generator
073 Process Radiation
Monitoring
076 Service Water
078 Instrument Air
103 Containment
K/A Category Point Totals: — —
— f — — —
3 — — Group Point Total: 281
ES-401 5 Form ES-401-2
ES-401 PWR Examination Outline Form ES-401-2
Plant Systems - Tier 2/Group 2 (RO / SO .. —
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1234561234
001 Control Rod Drive
002 Reactor Coolant
01 1 Pressurizer Level Control
014 Rod Position Indication
015 Nuclear Instrumentation
016 Non-nuclear Instrumentation
017 In-core Temperature Monitor — — — — — — — — — — — —
027 Containment Iodine Removal
028 Hydrogen Recombiner
and Purge Control — — — — — — — — — — —
029 Containment Purge
033 Spent Fuel Pool Cooling
034 Fuel Handling Equipment — — — — 034- k4 01035 Steam Generator
041 Steam Dump/Turbine
Bypass Control
045 Main Turbine Generator
055 Condenser Air Removal
056 Condensate
068 Liquid Radwaste
071 Waste Gas Disposal
072 Area Radiation Monitoring — O12 1.2
075 Circulating Water
079 Station Air
086 Fire Protection 3,3
K/A Category Point Totals: — — —I ] Group Point Total: 1 q1)
.7
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3
Facility: ALY Date of Exam: I.UVE 201Z
Category KIA# Topic RO SRO-Only
IR lR #
2.1. 7d4L udsi& CR.1. 2.1.
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2.1.
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Subtotal
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2.2.
Subtotal
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.
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Subtotal
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2.4.3
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Tier 3 Point Total
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ican
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atur
es.
Pag
e2
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9/29
/201
18:
10A
M
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XA
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9/29
/201
18:
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e1
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9/29
/201
18:
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e2
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9/29
/201
18:
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Page3of3
9/29
/201
18:
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Pag
e1
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9/29
/201
18:
10A
M
Kno
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lity
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tech
nica
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asy
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.
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lity
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and
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com
mun
icat
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syst
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lity
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setp
oint
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dop
erat
eco
ntro
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entif
ied
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eal
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resp
onse
man
ual.
Pag
e1
of1
9/29
/201
18:
10A
M
FOR
ME
S-4
01-2
TO
PIC
:
Co
nse
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ases
inT
echn
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ons
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limiti
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for
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lity
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.
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ater
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ES-301-i Administrative Topics OutlineDraft Submittal
Facility: Farley Nuclear Plant Date of Examination: June 18, 2012Examination Level: RO X SRO X Operating Test Number: FA2012-301
Administrative Topic Type Describe activity to be performed
(see Note) Code*
a. A.1 .a Title: Determine maximum RHR flow and time toConduct of Operations N, R saturation for a loss of RHR event while at midloop.(RO and SRO)
G2.1.25 39I4.2
b. A.1 .b Title: Determine if shift manning requirements are met perConduct of Operations D, P SOP-0.0, General Instruction to Operations Personnel.(RO and SRO)
G2.1 .5 2.9*1 39
c. A.2 Title: Perform STP-9.0, RCS Leakage Test, and evaluateEquipment Control M, R Acceptance Criteria.(RO only)
G2.2.12 3.7/4.1
c. A.2 Title: Perform STP-9.0, RCS Leakage Test, evaluateEquipment Control M, R Acceptance Criteria and evaluate TS.(SRO only)
G2.2.12 3.7/4.1
d. A.3 Title: Calculate dose from local equipment operation andRadiation Control M, R determine if it can be performed by a Relocation per EIP(RO only) 14, Personnel Movement, Relocation, Re-entry and Site
Evacuation.
G2.3.14 3.4/3.8
d. A.3 Title: Calculate dose from local equipment operation andRadiation Control M, R determine if a volunteer is required to perform the(SRO only) emergency actions.
G23.14 3.4/38
e. A.4 Title: Classify an Emergency Event.Emergency Procedures/Plan N, R(SRO only) G2.4.41 SRO 4.6
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking 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) 1/1(N)ew or (M)odified from bank ( 1) 3/4(P)revious 2 exams ( 1; randomly selected) 0/0
ES-301-1 Administrative Topics Outline Explanation sheetDraft Submittal
Facility: Farley Nuclear Plant Date of Examination: June 18, 2012Examination Level: RO X SRO X Operating Test Number: FA2012-301
Administrative Topic Type Describe activity to be performed(see Note) Code*
a. A.1 .a Determine maximum RHR flow and time to saturationConduct of Operations
N R
for a loss of RHR event while at midloop.
‘ AOP-12, Residual Heat Removal System Malfunction —
entry:1) determine maximum RHR flow for current RCS levelof 122’8.5” to prevent cavitation and2) If both RHR pumps are tripped, determine time tosaturation with RCS level at 122’8.5”, after refuelingwith 1/3 new core, 350 hours after shutdown. Candidatewill have to make determinations from tables andgraphs in AOP-12.G2.1 .25 Ability to interpret reference materials, such asgraphs, curves, tables, etc.3.9/4.2
b. A.1 .b Determine if shift manning requirements are met perConduct of Operations Scip-o.o, General Instruction to Operations Personnel.(RO and SRO)
D, RDue to a family emergency, an OPS shift person has togo home. The candidate will determine if adequatepersonnel are available to staff the shift for both Unit 1and Unit 2, from the personnel that remain.G2.1 .5 Ability to use procedures related to shift staffing,such as minimum crew complement, overtimelimitations, etc.2.9*! 39
C. A.2 Perform STP..9.0, RCS Leakage Test, and evaluateEquipment Control Acceptance Criteria.(RO only)
M,RCandidate will be required to perform STP-9.0 manually(with the plant computer unavailable). He will be given atable of parameters for the start of the leak rate, andthen for parameters two hours later. Candidate mustcalculate the leakrate from the parameters given. Thecalculation will show 1.1 gpm unidentified leakage.Candidate has to evaluate the test and determine ifAcceptance Criteria is met (Acceptance Criteria is notmet).G2.2.12 Knowledge of surveillance procedures.3.7! 4.1
C. A.2Equipment Control(SRO only)
d. A.3Radiation Control(RO only)
d. A.3Radiation Control(SRO only)
Perform STP-9.O, RCS Leakage Test, evaluateAcceptance Criteria and evaluate TS.
Candidate will be required to perform STP-9.O manually(with the plant computer unavailable). He will be given atable of parameters for the start of the leak rate, andthen for parameters two hours later. Candidate mustcalculate the leakrate from the parameters given. Thecalculation will show 1.1 gpm unidentified leakage.Candidate has to evaluate the test and determine ifAcceptance Criteria is met (Acceptance Criteria is notmet). The second part of the JPM is to evaluate TechSpecs for the RCS Leakage.G2.2.12 Knowledge of surveillance procedures.3.7/ 4.1
Calculate dose from local equipment operation anddetermine if it can be performed by a Relocation perEIP-14, Personnel Movement, Relocation, Re-entry andSite Evacuation.
Candidate will be required to calculate dose receivedfrom emergency field actions associated with isolating afailed open atmospheric relief valve with a SGTR inprogress. Determine if the action can be performedwithout exceeding dose limits per EIP-14.O.G2.3.14 Knowledge of radiation or contaminationhazards that may arise during normal, abnormal, oremergency conditions or activities.3.4/ 3.8
Calculate dose from local equipment operation anddetermine if a volunteer is required to perform theemergency actions.
Calculate dose from emergency field actions associatedwith isolating a failed open atmospheric relief valve witha SGTR in progress and failed fuel.
SRO part- Determine if the individual performing thetask is required to be a willing volunteer, per EIP-14.O.
G2.3.14 Knowledge of radiation or contaminationhazards that may arise during normal, abnormal, oremergency conditions or activities.3.4/3.8
M,R
M, R
M,R
e. A.4 N, R Classify an Emergency Event.Emergency Procedures/Plan(SRO only) Classify an event from given information and complete
Checklist 1, Classification Determination (page 1 of 1)within 15 minutes.G2.4.41 Knowledge of the emergency action levelthresholds and classifications.SRO 4.6
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they areretaking 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) i/l(N)ew or (M)odified from bank ( 1) 3/4(P)revious 2 exams ( 1; randomly selected) 0/0
Notes: There will be a total of 4 SRO events on the JPM exams.One on the simulator, JPM F. to evaluate Tech Specs for a failed NI.3 from this page;A.2 will evaluate Tech specs for the leak in progress.A.3 will have the SRO determine if the task during the emergency can be accomplished if theperson does not volunteer, which will have the SRO calculate the dose for the event in progressand then determine from EIP-14 if the person is required to sign as a volunteer or not.A.4 will be the classification of an event. At Southern company plants, with the new NMPs thatour SROs use to classify the event, the ED is required to classify the event. Then the SRO willget an extra person to fill out the Emergency Notification form (NMP-EP-1 11 Figure 1) on thecomputer and then have the SRO review it and then the extra person will send it to the states.The ED will return to oversight of the facility while the form is being filled out and then review andapprove it prior to sending it out. On Checklist 1 — Classification Determination, all theinformation that is required to be filled out on the Emergency Notification form is there so theextra will know what to put on the form.
ES-301-2 Control Room/In-Plant Systems OutlineDraft Submittal
Facility: Farley Nuclear Plant Date of Examination: June 18, 2012
Exam Level: RO SRO-l Operating Test No.: FA2012-301
Control Room Systems@ (8 for RO); (7 for SRO-l)
System / JPM Title Type Code* SafetyFunction
a. CRO-033E - Perform Corrective Actions In Response To aA DMalfunction of the Rod Control System for a Continuous Rod ‘
‘ S
Withdrawal.
001A2.11 3.4/3.7APEOO1AA2.05 4.4/4.6EPEOO7EA2.02 4.3/4.6
b. CR0-NEW 1- Re-establish HHSI flow due to a SGTR per N, L, 52
Attachment 3 of ESP-1 .1, SI Termination.
006A4.01 4.1/3.9006A4.02 4.0/3.8006A4.07 4.4/4.4
c. CR0-NEW 2- Perform lOAs of AOP-4.0 while at 25% power A, N, S 4Pfor a RCP trip.
003A1.07 3.4/3.4003A2.02 3.7/3.9APEO15/O17AA1 .08 3.0/2.9APEO15/O17AA1 .09 3.1/3.2
d. CR0-NEW 3- Start Containment spray system during the A, N, L, 5 5performance of EEP-0 during a LB LOCA.
026A2.03 4.1/4.4026A2.04 3.9/4.2
e. CRO-258 modified - Start the 1 B DG and energize the 1 G A, M, S 64160V Bus.
064A3.06 3.3/3.4064A4.06 3.9/3.9EPEO55EA1.06 4.1/4.5EPEO55EA2.03 3.9/4.7
f. CR0-i 27A - Perform actions of AOP-i00 for a Nl-42 failure. D, 5 7
015A2.01 3.5/3.9015A3.02 3.7/3.90i5A4.03 3.8/3.9015G2.2.40 SRO 4.7
g. CRO-091A - Place the Standby CCW Hx on service on the ‘A’ D, 5 8Train.
008A4.01 3.3/3.1008A4.09 3.0/2.9
h. CRO-350A - Operate Post LOCA Hydrogen Recombiner D, E, C 5
028A2.01 3.4/3.6 (RO only)028A4.01 4.0/4.0
In-Plant Systems (3 for RO); (3 for SRO-l)
i. SO-430B and C (combined) - Mechanically align the 1 C SW D 4Spump to the B Train and select it for B Train autostart.
076A2.01 3.5/3.7076A2.02 2.7/3.1
j. SO-351A - Start the 1-2A DG from the DLCP in Mode 4. D, E 6
064A2.02 2.7/2.9APEO56AA2.21 3.6/3.8EPEO55EA1 .02 4.3/4.4
k. SO-372B modified - Perform a #2 WMT release. A, M, E, R 9
068A2.04 3.3/3.3068A3.02 3.6/3.6
@ All RO and SRO-l control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.
* Type Codes Criteria for AC I SAC-I ACTUAL
(A)lternate path 4-6 I 4-6 (5/5)(C)ontrol room (1/0)(D)irect from bank 9 / 8 (6/5)(E)mergency or abnormal in-plant 1 / 1 (2/2)(EN)gineered safety feature - I -
(L)ow-Power I Shutdown 1 / 1 (2/2)(N)ew or (M)odified from bank including 1 (A) 2 / 2 (5/5)(P)revious 2 exams 3 / 3 (randomly selected) 0(R)CA 1l1 (1/1)(S)imulator (7/7)
ES-301-2 Control Room/In-Plant Systems Outline Explanation sheetDraft Submittal
Facility: Farley Nuclear Plant Date of Examination: June 18, 2012
Exam Level: RO SRO-l Operating Test No.: FA2012-301
Control Room Systems@ (8 for RO); (7 for SRO-l)
System / JPM Title Type Code* SafetyFunction
a. CRO-033E - Perform Corrective Actions In Response To aA D 1Malfunction of the Rod Control System for a Continuous Rod ‘
S
Withdrawal.Reactor power is at apprx 72% with a significant oil leak on the 1 BSGFP, Candidate is to ramp down at 4 MW/mm to remove theSGFP from service. A malfunction will occur in the Rod ControlSystem such that rods will start stepping out continuously(regardless of Auto/Manual position). AOP-19 actions will requirea Reactor trip due the malfunction of rod control with a continuousrod withdrawal. The Rx trip handswitches will not work and the Rxwill be tripped by opening CRDM MG set breakers. A manualturbine trip will be required due to no P-4 signal. An SI may occurdue to the Main Turbine remaining online when the Reactor istripped. Terminate JPM when candidate verifies IOA’s.
001A2.11 3.4/3.7APEOO1AA2.05 4.4/4.6EPEOO7EA2.02 4.3/4.6
b. CR0-NEW 1 - Re-establish HHSI flow due to a SGTR per N, L, S 2Attachment 3 of ESP-1 .1, SI Termination.
Even thoughA SG Tube Rupture occurs while in ESP 1 1, SI Termination this meets KAprocedure Candidate must perform actions of the foldout page we02eal 1 in(Attachment 3) to Re establish HHSI flow SF3, I believe it
006A4 01 4 1/3 9 safety function 2 better fits SF2
006A4.02 4.0/3.8 safety function 2 from inventory
006A4.07 4.4/4.4 safety function 2 control
W/EO2EA1 1 4 0/3 9 safety function 3
c. CR0-NEW 2 - Perform lOAs of AOP-4.0 while at 25% power A, N, S 4Pfor a RCP trip.
Reactor power is apprx 25%. 1 B RCP will trip when anadjustment is made to the Main FRV during the transfer, requiringAOP-4.0 entry (Rx trip is not required due to one RCP trip when <
30% power). AOP-4.0 actions are required (to close thePressurizer spray valve and isolate FW flbw) when the RCP trips.The 1 B Main FRV will stick open in its current position.. Thecandidate will have to perform RNO actions to close M0V3232Bto isolate feed flow to 1 B SG to prevent overfill. In addition, AOP4.0 will require Reactor trip due to RCS temp <541°F. Ifcandidate’s response is inadequate, the SG level will go high, andthe Turbine will trip. The SGFP’s should trip, but that trip will beblocked so that if the candidate does not control FW flow, a SGoverfill will occur. The automatic Reactor trip will be blocked, butmanual will work by operating the Rx Trip HS. SGFP(s) will notautomatically trip. (Closing M0V3232B or tripping SGFP’s iscritical to prevent overfilling the SG.) Terminate when lOA’s ofEEP-0 are complete.
Discussion: The simulator exam has a RCP high vibrations at >30% Rxpower and requires a Rx trip. The Audit exam has a mode 3 JPM thathas the student secure the RCP and then implement AOP-4.O which hasdifferent actions from this JPM.
003A1 .07 3.4/3.4003A2.02 3.7/3.9APEO1 5/01 7AA1 .08 3.0/2.9APEO15/O17AA1 .09 3.1/3.2
___________ ________
d. CR0-NEW 3 - Start Containment spray system during the A, N, L, S 5performance of EEP-0 during a LB LOCA.
A LOCA has occurred and the candidate is at step 6 of EEP-0.Containment pressure is 30 psi, requiring RNO actions. Phase Bactuates, CS does not, perform Attachment 5 is required. Bothtrains of CS will have to be started manually and dischargeMOV’s opened, M0V8820B, the discharge on 1 B CS pump willnot open. Candidate will have to reset the CS actuation signal andS/D the 1 B CS pump.
Discussion: This is alternate path cluetotheft4hat during theperformance of the RNO coIumnfaiIures occur that require alternatedecisions within the RNO column.
026A2.03 4.1/4.4026A2.04 3.9/4.2
e. CRO-258 modified - Start the lB DG and energize the 1 G A, M, 5 64160V Bus.
There has been a Loss of all A/C power. ECP-0.0, Loss of All A/CPower has been entered. 2C DG is Tagged Out. 1 -2A DG hastripped due to an electrical issue. 1C DG is supplying U-2. Thecandidate is to perform ECP-0.0 starting at step 5.2. He will startthe 1 B DG (the only one available to U-i). When the DG isstarted, the output breaker fails to close automatically and actionsare required per the RNO column of ECP-0.0 to close the outputbreaker. Once the output breaker is closed from the EPB, thesequencer will run and start loads. ECP-0.0 will be exited at step5.8.
064A3.06 3.3/3.4064A4.06 3.9/3.9EPE055EA1 .06 4.1/4.5EPE055EA2.03 3.9/4.7
____________ _______
f. CRO-127A - Perform actions of AOP-100 for a Nl-42 failure. D, S 7
UOP-1 .2, 4% power and ramping up, N-42 has just failed.Perform AOP-i00 section 1.12. Terminate JPM at step i2ofsection 1.12 of AOP-100 when the candidate states that he willsubmit a CR at step 12. The simulator does not provide thecapability of tripping bistables for OT deltaT at step 13. Bank JPMis CR0-i 27A.
Allow the candidate to complete actions in the Simulator, and thenfor SRO only have the candidate determine if a Mode change canbe performed. If so, what actions are required to ramp up to 12%power?
015A2.0i 3.5/3.9015A3.02 3.7/3.9015A4.03 3.8/3.9015G2.2.40 SRO 47
g. CRO-091A - Place the Standby CCW Hx on service on the A’ D, 5 8Train.
100% power, swap from the 1 B CCW Hx o/s to the 1 C Hx 0/s.Requires unisolating and throttling open flow to one Hx whilethrottling closed and isolating the other Hx. The 3009 FCV’s arereverse acting valves (100% demand is full closed), requiringincreased attention to detail. This action is performed per SOP23.0 section 4.4.
008A4.01 3.3/3.1008A4.09 3.0/2.9
h. (RO only) CRO-350A - Operate Post LOCA Hydrogen D, F, C 5Recombiner.
A LOCA has occurred with an increase in Containment H2concentration. Step 6.5 RNO of EEP-1 directs performance ofAttachment 3 to place the Post LOCA H2 Recombiners in service.The candidate is directed to place 1A H2 Recombiner in service.The task requires manipulation of control switches on theRecombiner panel and use of Figure 1 of Attachment 3 todetermine the correct setting. Bank JPM is CRO-350A.
This task will be simulated in the actual Control Room, thiseQuipment is not available in the Simulator
028A2.01 3.4/3.6028A4.01 4.0/4.0
In-Plant Systems@ (3 for RO); (3 for S no-I)
SO-430 B and C (combined) - Mechanically align the 1C SW D 4Spump to the B Train and select it for B Train autostart.
Unit 1 has experienced an LOSP. The 1C SW pump is aligned tothe A Train and the 1 D SW pump has tripped. Two SW pumpsare required to support operation of the 1 B DG. Actions havebeen completed to align the 1C SW pump to the B Trainelectrically. The candidate is to align the 1C SW pump to the BTrain mechanically and select it to autostart for the 1 D SW pump.This is per SOP-24.OD (a checklist in the back of SOP-24.0).Candidate will start at step 2.0 and complete the rest of thechecklist. Then Appendix 6 will have to be performed to align theSW pump for autostart.
Discussion: this JPM will be performed at the SWIS which is in an outsidestructure away from the main part of the plant. This JPM has never beendone for any HLT class at FNP due to the location of the JPM. Usingstation keeping methods this should not present too much of a challengeto accomplish.
076A2.01 3.5/3.7076A2.02 2.7/3.1
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j. SO-351A -Start the 1-2A DG from the DLCP in Mode 4. D, E 6
Candidate will perform FNP-0-SOP-38.1 to start the 1-2A DGfrom the Local panel in Mode 4 (section 4.10 performed, not4.11). Voltage and Frequency will have to be adjusted to bring itin spec. Once DC is running with voltage and frequency in spec,control will be shifted to the Control Room EPB operator
Discussion: This JPM will be performed in the Diesel Building and isrelevant to a Loss of ALL AC event similar to Fukashima.
064A2.02 2.7/2.9APEO56AA2.21 3.6/3.8EPEO55EA1 .02 4.3/4.4
k. SO-372B modified - Perform a #2 WMT release.
Start at step 4.4.9 of SOP-50.1, Appendix 2, to open RCV-18. Thecandidate will initiate the release and then a “Water DischargeLine Hi-Rad” alarm will come in on the Liquid Waste Panel.Candidate must perform actions of ARP-13.2, annunciator 14, tostop the release per the ARP. Terminate the JPM when therelease is stopped. Modified from SO-372B to make it analternate path.
The release can be stopped by one of the following methods:1) Closing RCV-182) Closing Vi 143) Closing V1O8A4) Stopping the WMT pump
Discussion: This JPM has never been performed in this manner at FNP.068A2.04 3.3/3.3068A3.02 3.6/3.6
DG starts on the simulator exam -
2C DG started in one scenario, small blackout DG that is started differently than Large DGs.Difference is the flowpath and method for starting and aligning will be different.
A, M, E, R 9
@ All RO and SRO-l control room (and in-plant) systems must be different and serve different safetyfunctions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions mayoverlap those tested in the control room.
* Type Codes Criteria for RO / SRO-l
(A)lternate path 4-6 / 4-6 (5/5)(C)ontrol room (1/0)(D)irect from bank 9 / 8 (6/5)(E)mergency or abnormal in-plant 1 / 1 (2/2)(EN)gineered safety feature - / -
(L)ow-Power/Shutdown 1 / 1 (2/2)(N)ew or (M)odified from bank including 1 (A) 2 / 2 (5/5)(P)revious 2 exams 3 / 3 (randomly selected) 0(R)CA i/i (1/1)(S)imulator (7/7)
