Text

Final Outlines (Folder 3)
	ML15281A147
Person / Time
Site:	Millstone
Issue date:	08/20/2015
From:	David Silk; Operations Branch I
To:	; Dominion Nuclear Connecticut
Shared Package
ML15072A211	List: IR 05000423/2015301; ML15078A430; ML15243A191; ML15281A139; ML15281A140; ML15281A141; ML15281A142; ML15281A143; ML15281A144; ML15281A146; ML15281A147; ML15281A148; ML15357A489;
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ES-401 PWR Examination Outline Fonn ES-401-2 Facility: Millstone 3 Date of Exam: September 22nd, 2015 RO Kl A Category Points SRO-Only Points Tier Group K

K K

K A A A A G A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

1.

Emergency &

1 5

2 2

4 3

2 18 I

5 6

Abnormal Plant 2

I 2

2 NIA 2

I NIA I

9 I

3 4

Evolutions Tier 6

4 4

6 4

3 27 2

8 10 Totals

2.

1 2

3 3

3 2

2 1

2 3

5 2

28 3

2 5

Plant Systems 2

I 0

0 2

0 I

I 2

0 0

3 10 I

2 3

Tier 3

3 3

5 2

3 2

4 3

5 5

38 4

4 8

Totals

3.

Generic Knowledge and 1

2 3

4 1

2 3

4 Abilities Categories 10 7

4 3

I 2

I 3

I 2

Note: I.

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 KA is allowed ifthe 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 +/- I 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 of ES-40 I for guidance regarding the elimination of inappropriate Kl A statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting as second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers I and 2 from the shaded systems and Kl A categories.

7.

The generic (G) K/As in Tiers I 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. I.b of ES-40 I for the applicable Kl As.

8.

On the following pages, enter the Kl 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 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 #I does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to IOCFR55.43.

G*

Generic Kl As Revision 1

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier I/Group I (RO)

E/APE #I Name I Safety K

K K

A A

G KIA Topic(s)

IR Function I

2 3

I 2

000007 Reactor Trip -

Operate I monitor Nuclear Instrumentation Stabilization - Recovery I I 5

on a reactor trip 4.0/4.1 I

0000008 Pressurizer Vapor Interrelations between vapor space break Space Accident I 3 2

and sensors and detectors 2.7/2.7 2

000009 Small Break LOCA Operational implications of the use of steam 13 2

tables on a small break LOCA 3.5/4.2 3

000011 Large Break LOCA Determine or interpret equipment necessary 13 7

for critical pump water seals during LOCA 3.2/3.4 4

000015/17 RCP Operational Implications of thermodynamic Malfunctions I 4 4

relationship between RCS loops and SGs 2.9/3.1 5

000022 Loss of Rx Coolant Ability to perform without reference actions Makeup I 2 2.4.49 that require immediate operation 4.6/4.4 6

000025 Loss of RHR Determine or interpret limitations on LPI System I 4 5

flow and temperature rates of change 3.1/3.5 7

000027 Pressurizer Pressure Knowledge of EOP entry conditions and Control Malfunction I 3 2.4.1 immediate action steps 4.6/4.8 8

000029 A TWS I I 15 Operate I monitor AFW system 4.1/3.9 9

000038 Steam Gen. Tube Operate I monitor safety injection and Rupture I 3 30 containment isolation systems on SGTR 4.0/3.8 10 000056 Loss of Off-site Operational implications of the principle of Power I 6 1

cooling by natural convection 3.7/4.2 11 000057 Loss of Vital AC Determine or interpret AC instrument bus Elec. Inst. Bus I 6 6

alarms for the inverter and alternate source 3.2/3.7 12 000062 Loss of Nuclear Operate I monitor control of flow rates to Service Water I 4 6

components cooled by the SWS 2.912.9 13 000065 Loss of Instrument Reasons for: Knowing effects on plant Air I 8 3

operation of isolating equipment from air 2.9/3.4 14 W/E04 LOCA Outside Operational implications of annunciators, Containment I 3 3

indicating signals, and remedial actions 3.513.9 15 W /E 11 Loss of Emergency Operational implications of components, Coolant Recirc. I 4 1

capacity, & function of emergency systems 3.7/4.0 16 W/E05 Loss of Secondary Reasons for normal, abnormal and Heat Sink I 4 2

emergency operating procedures 3.7/4.l 17 000077 Generator Voltage Interrelations between Generator Voltage and Electric Grid 1

and Grid Disturbances and motors 3.1/3.2 18 Disturbances I 6 Kl A Category Totals:

5 2

2 4

3 2

Group Point Total:

18

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier I/Group 2 (RO)

E/APE #I Name I Safety K

K K

A A

G KIA Topic(s)

IR Function 1

2 3

1 2

000003 Dropped Control Reasons for reset of demand position counter Rod I 1 6

to zero 2.7/3.0 19 000032 Loss of Source Operate I monitor manual restoration of Range NI I 7 1

power 3.1/3.4 20 000061 ARM System Operational Implications of detector Alarms I 7 I

limitations 2.5/2.9 21 000076 High Reactor Reasons for corrective actions as a result of Coolant Activity I 9 5

high RCS fission-product activity level 2.9/3.6 22 Interrelations between SI Termination and W/E02 SI Termination I 3 2

heat removal systems and relation to proper 3.5/3.9 23 operation of the facility W /E 13 Steam Generator Determine or interpret facility conditions Over-pressure I 4 I

and selection of appropriate procedures 2.9/3.4 24 W /E03 Post LOCA Interrelations between control and safety Cooldown Depress. I 4 1

systems, instruments, signals, interlocks, 3.6/4.0 25 failure modes, auto/manual features W/E09 Natural Circ. I 4 Operate I monitor for desired operating 3

results during natural circulation operations 3.5/3.8 26 W/E08 RCS Overcooling-Ability to recognize abnormal indications for PTS/4 2.4.4 system operating parameters that are entry 4.5/4.7 27 level conditions for EOPs and AOPs KIA Category Point Totals:

I 2

2 2

I 1

Group Point Total:

9

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group I (RO)

System # I Name K

K K

K A

A A

A G

KIA Topic(s)

IR I

2 3

4 5

6 I

2 3

4 003 Reactor Physical connections I cause-effect Coolant Pump 10 relationship between RCPs and RCS 3.0/3.2 28 003 Reactor Manually operate I monitor seal Coolant Pump I

injection in the control room 3.3/3.2 29 004 Chemical Manually operate I monitor boron and Volume I

and control rod reactivity effects in 3.8/3.9 30 Control the control room 005 Residual Effect of a loss of malfunction of Heat Removal 1

RHR on the RCS 3.9/4.0 31 006 Emergency Effect of loss or malfunction of Core Cooling IO valves will have on ECCS 2.6/2.8 32 007 Pressurizer Operational implications of the Relief/Quench 1

method of forming a steam bubble in 2.6/2.9 33 Tank the Pzr 008 Component 2

Knowledge of bus power supplies to Cooling Water the CCW pump, including backup 3.013.2 34 008 Component Design features I interlocks for the Cooling Water 9

standby CCW pumps 2.7/2.9 35 010 Pressurizer Operational implications of constant Pressure Control 2

enthalpy expansion through a valve 2.613.0 36 012 Reactor Knowledge of bus power supplies to Protection I

RPS channels, components, and 3.3/3.7 37 interconnections 012 Reactor Effect of loss or malfunction of Protection 4

bypass-block circuits on RPS 3.3/3.6 38 013 Engineered 2

Predict impact I mitigate excess Safety Features steam demand 4.3/4.5 39 Actuation 022 Containment Knowledge of abnormal condition Cooling 2.4.11 procedures 4.0/4.2 40 026 Containment Effect of a loss of malfunction of Spray 2

CSS will have on recirc spray system 4.2/4.3 41 039 Main and Monitor automatic operation of Reheat Steam 2

isolation of the MRSS 3.1/3.5 42

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group I (RO) Continued System # I Name K

K K

K A

A A

A G

KIA Topic(s)

IR I

2 3

4 5

6 1

2 3

4 059 Main Design features I interlocks which Feedwater 5

control speed of MFW pump turbine 2.5/2.8 43 059 Main Predict I monitor parameters Feedwater 7

associated with operating controls for 2.5/2.6 44 feed pump speed 06 I Auxiliary/

Operational implications of decay Emergency 2

heat sources and magnitude 3.213.6 45 Feedwater 062AC Manually operate I monitor all Electrical 1

breakers (including switchyard) in 3.313.1 46 Distribution the control room 062 AC Predict impact I mitigate improper Electrical 3

sequencing when transferring to or 2.913.4 47 Distribution from an inverter 063 DC Monitor automatic operation of Electrical 1

meters, annunciators, and indicating 2.7/3.1 48 Distribution lights 064 Emergency Monitor automatic operation of:

Diesel Generator 4

number of starts available with an air 3.1/3.5 49 compressor 073 Process Effect of a loss of malfunction of Radiation I

PRMS on radioactive effluent 3.6/4.2 50 Monitoring releases 076 Service Knowledge of bus power supplies to Water I

service water 2.7/2.7 51 076 Service Manually operate I monitor SWS Water 2

valves in the control room 2.6/2.6 52 078 Instrument Knowledge of how AOPs are used in Air 2.4.8 conjunction with EOPs 3.8/4.5 53 078 Instrument Physical connections I cause-effect Air 4

relationship between IAS and cooling 2.6/2.9 54 water to the compressor 103 Containment Manually operate I monitor ESF 3

slave relays in the control room 2.7/2.7 55 KIA Category Point Totals:

2 3

3 3

2 2

I 2

3 5

2 Group Point Total:

28

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

System# I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 016 Non-nuclear Parameters and logic used to assess Instrumentation 2.4.21 the status of safety functions, such as 4.014.6 56 core cooling, heat removal, integrity 017 In-Core Effect of loss or malfunction of ITM Temperature I

sensors and detectors 2.7/3.0 57 Monitor 027 Containment Predict impact I mitigate high Iodine Removal 1

temperature in the filter system 3.013.3 58 029 Containment Design features I interlocks which Purge 2

provides for negative pressure in 2.9/3.1 59 containment 035 Steam Physical connections I cause-effect Generator 13 relationship between SGS and 2.7/2.8 60 condensate system 071 Waste Gas Predict impact I mitigate use of waste Disposal 2

gas release monitors, radiation, gas 3.313.6 61 flow rate, and totalizer 072 Area Predict I monitor parameters Radiation 1

associated with operating ARM 3.413.6 62 Monitoring controls including radiation levels 075 Circulating Design features I interlocks which Water 1

provide for heat sink 2.5/2.8 63 079 Station Air Ability to interpret and execute 2.1.20 procedure steps 4.6/4.6 64 086 Fire Events related to system operation Protection 2.4.30 that must be reported to internal 2.7/4.1 65 organizations, or external agencies Kl A Category Point Totals:

1 0

0 2

0 1

1 2

0 0

3 Group Point Total:

10

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier I/Group I (SRO)

E/APE #/Name I Safety K

K K

A A

G KIA Topic(s)

IR Function I

2 3

I 2

000011 Large Break Recognize abnormal indications that are entry level LOCAi 3 2.4.4 conditions that are entry level for EOPs and AOPs 4.7 76 000015/17 RCP Knowledge of operational implications ofEOP Malfunctions I 4 2.4.20 warnings, cautions, and notes 4.3 77 000029 A TWS I I I

Determine or interpret reactor nuclear instrumentation 4.7 78 000056 Loss of Off-site Knowledge of EOP entry conditions and immediate Power I 6 2.4.1 action steps 4.8 79 000057 Loss of Vital AC Knowledge of operational implications of EOP Elec. Inst. Bus I 6 2.4.20 warnings, cautions, and notes 4.3 80 W /E05 Loss of Ability to prioritize and interpret the significance of Secondary Heat Sink I 4 2.4.45 each annunciator or alarm 4.3 81 KIA Category Totals:

I 5

Group Point Total:

6

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier I/Group 2 (SRO)

El APE # I Name I Safety K

K K

A A

G KIA Topic(s)

IR Function 1

2 3

1 2

Ability to interpret reference materials 000061 ARM System Alarms I 7 2.1.25 such as graphs, curves, tables, etc.

4.2 82 000076 High Reactor Coolant Ability to evaluate plant performance Activity I 9 2.1.7 and make operational judgments 4.7 83 Site Priority: AOP 3571 Selection of or adherence to Instrument Failure Response I

appropriate procedures NA 84 Site Priority: OP 3272 EOP Ability to verify that alarms are User's Guide 2.4.46 consistent with plant conditions 4.2 85 KIA Category Point Totals:

1 3

Group Point Total:

4 Revision 2

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

System# I Name K

K K

K A

A A

A G

KIA Topic(s)

JR I

2 3

4 5

6 1

2 3

4 004 Chemical and Volume Knowledge of specific Control 2.4.18 bases for EOPs 4.0 86 Predict impact and 005 Residual Heat Removal 4

mitigate RHR valve 2.9 87 malfunction 006 Emergency Core Ability to evaluate plant Cooling 2.1.7 performance and make 4.7 88 operational judgments 007 Pressurizer Predict impact and Relief/Quench Tank 2

mitigate abnormal 3.2 89 pressure in the PRT 073 Process Radiation Predict impact and Monitoring I

mitigate erratic or failed 2.9 90 power supply KIA Category Point Totals:

3 2

Group Point Total:

5

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

System# I Name K

K K

K A

A A

A G

KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 Predict impact and mitigate rod 001 Control Rod Drive 17 misalignment alarm 3.8 91 016 Non-nuclear Prioritize and interpret the Instrumentation 2.4.45 significance of each 4.3 92 annunciator or alarm Knowledge of the bases in 035 Steam Generator 2.2.25 Technical Specifications for 4.2 93 LCOs and safety limits 1

2 Group Point Total:

3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Millstone Unit 3 Date of Exam: Sept 23, 2015 Category KIA#

Topic RO SRO-Only IR IR 2.1.28 Knowledge of purpose and function of major system components and 4.1 66 4.1 controls

1.

2.1.30 Ability to locate and operate components, including local controls 4.4 67 4.0 Conduct of 2.1.32 Ability to explain and apply system limits and precautions 3.8 68 4.0 Operations 2.1.25 Ability to interpret reference material, such as graphs, curves, tables, etc.

3.9 69 4.2 2.1.45 Ability to identify and interpret diverse indications to validate the response 4.3 94 of another indication Subtotal 4

1

2.

2.2.2 Ability to manipulate the console controls as required to operate the facility 4.6 70 4.1 between shutdown and designated power levels Equipment 2.2.12 Knowledge of surveillance procedures 3.7 71 4.1 Control 2.2.37 Ability to determine operability and/or availability of safety related 3.6 72 4.6 equipment Knowledge of the process for managing maintenance activates during 2.2.17 power operations, such as risk assessments, work prioritization, and 3.8 95 coordination with the transmission system operator 2.2.20 Knowledge of the process for managing troubleshooting activities 3.8 96 2.2.38 Knowledge of conditions and limits in the facility license 4.5 97 Subtotal 3

3

3.

Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey instruments, personnel monitoring 2.9 73 2.9 equipment, etc.

Radiation Knowledge of radiological safety procedures pertaining to licensed 2.3.13 operator duties, such as rad monitor alarms, Ctmt entry requirements, fuel 3.8 98 handling responsibilities, access to locked high rad areas, etc.

Subtotal 1

1

4.

2.4.13 Knowledge of crew roles and responsibilities during EOP usage 4.0 74 4.6 Emergency 2.4.19 Knowledge of EOP layout, symbols, and icons 3.4 75 4.1 Procedures/

2.4.1 Knowledge of EOP entry conditions and immediate action steps 4.8 99 Plan 2.4.26 Knowledge of facility protection requirements, including fire brigade and 3.6 100 portable firefighting equipment usage Subtotal 2

2 Tier 3 Point Total 10 7

Revision 1

ES-401 Record of Rejected Kl As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected Kl A 1/1 APE.015/017.Kl.l Oversample of natural circulation, with APE.056.Kl.Oland W/E09.Al.03 112 APE.003.AK3.03 NA MP3. No automatic turbine runback to balance primary and secondary power 1/2 APE.076.AK2.01 NA MP3. No failed fuel Radiation Monitor. MP3 relies on manual sampling 2/1 003.A4.07 NA MP3. No RCP Seal Bypass path 211 004.A4.20 NA MP3. MP3 uses manual valves to align the de-borating demineralizer 211 007.K5.02 NA MP3. Rejected per lead examiner direction. MP3 does not discharge to PRT while drawing a bubble in the Pressurizer.

2/1 008.K4.07 Oversample of CCW pump power supply, with 008.K2.02 211 010.K5.0l Oversample of steam table use, with EPE.009.Kl.2 2/1 012.Al.01 NA MP3. Operators do not monitor or adjust RPS trip setpoints 211 064.A3.08 NA MP3. No automatic transfer to auto position after manual EDG stop 2/1 073.K5.0l Oversample of Rad Monitors, with APE.061.Kl.Ol, 073.K3.01, 071.A2.02, 072.Al.OI, SRO 073.A2.01 2/1 078.GEN.2.l.19 Ability to use PPC to evaluate system status; better tested on operating exam.

Information available for instrument air on the PPC is fairly generic. Candidates will be routinely demonstrating PPC use during the operating exam.

2/1 078.GEN.2.2.37 Determine operability of safety related equipment. Instrument air is not safety related 2/1 078.GEN.2.2.39

.::; 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tech Spec LCOs. NA for instrument air 2/1 078.GEN.2.4.18 Basis of EOPs. EOPs assume no IAS available. No significant EOP bases step related to Instrument Air.

212 071.A2.07 NA MP3. No actions required with Gaseous Waste System on loss of Met Tower 212 079.GEN.2.2.37 Determine operability of safety related equipment. Station air is not safety related 3/1 GEN.2.1.42 Rejected per lead examiner direction. Fuel movement procedures are not an RO job function at MP3.

3/4 GEN.2.4.28 Security procedures are not an RO job function SRO 1/1 EPE.011.GEN.2.2.39

< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tech Spec LCOs is RO level knowledge SRO 1/2 APE.061.GEN. 2.2.39

.::; 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Tech Spec LCOs is RO level lmowledge SRO 1/2 Plant Priority Inadvertent CIA Over-sample of Critical Safety Function Status Trees GEN.2.4.21 SRO 112 Plant Priority Rejected per lead examiner direction. Minimal effect of shutdown conditions on Inadvertent CIA actions in the AOP. Randomly selected another El APE due to overlap with GEN.2.4.9 Operating Exam and limited ability to write discriminating SRO level question from this AOP.

SRO 2/2 001.A2.2 Effect of loss of power to reactor trip breakers is RO level knowledge SRO 2/2 001.A2.10 Effect of loss of power to Rod Drive MG Sets is RO level lmowledge ES-401, Page 44of50 Revision 2

Written Exam Question Attributes Bank New Mod HO Mem Bank New Mod HO Mem 1

x x

26 x

x 2

x x

27 x

x 3

x x

.. 28 x

x 4

29 x

x x

x 5

x x

... 30 x

x 6

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.... :: 31 x

x 7

x x

32 x

x 8

x x

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33 x

x 9

x x

34 x

x 10 x

x 1*

35 x

x 11 x

x 36 x

x 12

> 37 x

x x

x 13 x

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- - .* 38 x

x 14 x

x 39 x

x 15 x

x 40 x

x 16 41 x

x x

x 17 x

x

... i'*. 42 x

x 18 x

x

. 43 x

x 19 44 x

x L:/,..

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20 45 x

x x

x 21 x

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- - - 46 x

x 22 x

x 47 x

x 23 x

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x 24 x

x

.o.,:.*.

49 x

x 25 x

x

... 50 x

x 14 8

3 17 8

14 9

2 13 12 Bank New Mod HO Mem Bank New Mod HO Mem

Written Exam Question Attributes Bartle New Mod HO Mem ?'.

Bartle New Mod HO Mem

1\\

SRO 51 x

x

, ;.,,. 76 x

x 52 x

x

,. ' ;.i; 77 x

x 53 x

x

.. +;,,; 78 x

x 54 x

x

..

:: 79 x

x 55 x

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x 56 x

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x 57 x

x 1*>}**** 82 x

x 58 x

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x 61 x

x IP~

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Bank New Mod HO Mem 11 /,' #

Bank New Mod HO Mem RO

S56

s 38-45 30-37 1*r.,,.. <; SRO

Sl9

2

13

Sl2 1-25 14 8

3 17 8

J:s~i 26-50 14 9

2 13 12 1,*

51-75 18 7

0 11 14 i* *.....

Total 46 24 5

41 34

Total 14 9

2 19 6

ES-301 Facility:

Millstone Unit 3 Examination Level:

RO Administrative Topics Outline Date of examination:

0 SRO D Operating Test Number:

Form ES-301-1 Rev 0/2 8/19/15 9/14/15 2K15 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Perform AC electrical source inoperability Conduct of Operations surveillance requirements.

D,S KIA 2.1.31 (Ability to locate control room switches, controls, and RO A.1.1 indications, and to determine that they correctly reflect the desired plant lineup.)

KIA Rating: 4.6 I 4.3 Determine the required boration time and final control Conduct of Operations M, R rod height for a rapid downpower.

RO A.1.2 KIA 2.1.20 (Ability to interpret and execute procedure steps.)

KIA Rating: 4.6 I 4.6 Equipment Control Recommend a clearance boundary for 3CCl*P1 A.

P, D, R KIA 2.2.13 (Knowledge of tagging and clearance procedures.)

ROA.2 KIA Rating: 4.1 I 4.3 Task Preview for Work in RHR Heat Exchanger Radiation Control Room.

N,R KIA 2.3. 7 (Ability to comply with radiation work permit ROA.3 requirements during normal or abnormal conditions.)

KIA Rating: 3.5 I 3.6 Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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, Page 22 of 27

ES-301 Facility:

Millstone Unit 3 Examination Level:

RO D Administrative Topics Outline Date of examination:

SRO [X]

Operating Test Number:

Form ES-301-1 Rev 0/1 7/14/15 9/14/15 2K15 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Loss of containment closure.

Conduct of Operations D,R KIA 2.1.36 (Knowledge of procedures and limitations involved in SRO A1.1 core alterations.)

KIA Rating: 3.0 I 4.1 Review and approve reactivity calculation.

Conduct of Operations P, M, R KIA 2.1.37 (Knowledge of procedures, guidelines, or limitations SRO A1.2 associated with reactivity management.)

KIA Rating: 4.3 I 4.6 Notifications and Reportability associated with a safety limit violation.

Equipment Control D,R KIA 2.2.22 (Knowledge of limiting conditions for operations and SRO A.2 safety limits.)

KIA Rating: 4.0 I 4.7 Review and approve a radioactive liquid waste Radiation Control M,R discharge permit.

SRO A.3 KIA 2.3.6 (Ability to approve release permits.)

KIA Rating: 2.0 I 3.8 Emergency plan classification and protective action recommendation for a general emergency.

Emergency Plan KIA 2.4.41 (Knowledge of the emergency action level thresholds D,R and classifications.)

SRO A.4 KIA Rating: 2.9 I 4.6 KIA 2.4.44 (Knowledge of emergency plan protective action recommendations.)

KIA Rating: 2.4 I 4.4 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 0/2 8/19/15 Facility Millstone Unit 3 Date of Examination:

9/14/15 Exam Level:

RO [KJ SRO-I D SRO-U D Operating Test No.:

2K15 Control Room Systems:

8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a.

Manual Make-up Calculation & Manual Make-up to VCT N,S 1 -004 K/A Number: 004-A4.13; K/A Rating: 3.3 I 2.9

b. Vent Unisolated Accumulators K/A Number: 006-A1.13; K/A Rating: 3.5 I 3.7 M,EN,A,E,S 2-006 K/A Number: 006-A4.07; K/A Ratinq: 4.4 I 4.4

c. Arm COPPS M,S 3-010 K/A Number: 01 O-K4.03; K/A Rating: 3.8 I 4.1

d. Aligning RHR For SDR Inventory Control P,D,L,S 4.1 -005 K/A Number: 005-A4.01; K/A Rating: 3.6 I 3.4

e. Natural Circulation Cooldown Using GA-26 P,D,EN,A,E,S 4.2-039 K/A Number: 039-A 1.05; K/A Rating: 3.2 I 3.3

f.

Respond To An Inadvertent Containment Isolation Phase 'A' P, M, EN, A, E, 5-103 K/A Number: 103-A2.03; K/A Rating: 3.5 I 3.8 s

g. Transferring Bus 340 To Offsite Power M, L, S 6-062 K/A Number: 062-A2.12; K/A Rating: 3.2 I 3.6

h. Stop Auxiliary Building Filtration (Lower Levels)

N,S 9-071 K/A Number: APE 060-AA 1.02; K/A Rating: 2.9 I 3.1 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Local Actions On A Loss Of Instrument Air M,A,E 8-078 K/A Number: APE 065-AA 1.04; K/A Rating: 3.5 I 3.4

j.

Align ESF And Auxiliary Building Sump Pumps, Post LOCA D,A,E,R 6-062 K/A Number: 062-A4.04; K/A Rating: 2.6 I 2.7

k.

Cross-Connect Service Water To East Switchgear Ventilation D, E, L 4.2 -076 K/A Number: 076-K1.19; K/A Rating: 3.6 I 3.7 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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 / SRO-U (A)lternate path 4-6 I 4-61 2-3 (C)ontrol room (D)irect from bank

59/:58/:54 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature 2:1 I :::1 I ;::: 1 (control room system)

(L)ow-Power I Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)revious 2 exams

5 3 / :5 3 / :5 2 (randomly selected)

(R)CA 2:1/2:1/2:1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 0/2 8/19/15 Facility Millstone Unit 3 Date of Examination:

9/14/15 Exam Level:

ROD SRO-I CR]

SRO-U D Operating Test No.:

2K15 Control Room Systems:

8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Perform A Boration At Power D,S 1 -004 K/A Number: 004-A4.03; K/A Rating: 2.7 I 3.2

b. Vent Unisolated Accumulators K/A Number: 006-A 1.13; K/A Rating: 3.5 I 3. 7 M, EN, A, E, S 2-006 K/A Number: 006-A4.07; K/A Ratinq: 4.4 I 4.4

c. Arm COPPS M,S 3-010 K/A Number: 01 O-K4.03; K/A Rating: 3.8 I 4.1

d. Aligning RHR For SOR Inventory Control P, D,L,S 4.1 -005 K/A Number: 005-A4.01; K/A Rating: 3.6 I 3.4

e. Natural Circulation Cooldown Using GA-26 P,D,EN,A,E,S 4.2-039 K/A Number: 039-A1.05; K/A Rating: 3.2* I 3.3

f.

Respond To An Inadvertent Containment Isolation Phase 'A' P, M, EN, A, E, 5-103 K/A Number: 103-A2.03; K/A Rating: 3.5/ 3.8 s

g.

h. Stop Auxiliary Building Filtration (Lower Levels)

N,S 9-071 K/A Number: APE 060-AA 1.02; K/A Rating: 2.9 I 3.1 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

Local Actions On A Loss Of Instrument Air M,A,E 8-078 K/A Number: APE 065-AA 1.04; K/A Rating: 3.5 I 3.4

j.

Align ESF And Auxiliary Building Sump Pumps, Post LOCA D,A,E,R 6-062 K/A Number: 062-A4.04; K/A Rating: 2.6 I 2.7

k.

Cross-connect Service Water To East Switchgear Ventilation D, E,L 4.2-076 K/A Number: 076-K1.19; K/A Rating: 3.6 I 3. 7 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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

9/: :;8/::;4 (E)mergency or abnormal in-plant

~1/~1/~1 (EN)gineered safety feature

~1 I ~1 I~ 1 (control room system)

(L)ow-Power I Shutdown

~1/~1/~1 (N)ew or (M)odified from bank including 1(A)

~2/~2/~1 (P)revious 2 exams

3 I: ::; 3 I:::; 2 (randomly selected)

(R)CA

~1/~1/~1 (S}imulator ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Rev 0/1 Facility: Millstone 3 Scenario No.: 2K15 NRC-01 Op-Test No.: 2K15 Examiners:

Operators:

Initial Conditions: IC-357, 74% Power, Beginning of Life Turnover:

The last shift Qerformed a downQower to 7 4% QOwer due to intake conditions.

AOP 3569, Severe Weather, has been entered for a hurricane watch. Additionally, last shift Qerformed OP 3301 G to induce Qressurizer SQrays. The 'B' Stator Cooling PumQ is out of service for bearing reQlacement. Orders are to maintain QOwer stable as management evaluates hurricane tracking.

Event Malf.

Event Event No.

No Type*

Description 1

RX10A I (RO)

Primary Pressurizer Level control channel TIS (US)

(RCS*L T459) fails high causing level to decrease (AOP 3571 ). (Tech Spec entry) 2 R (RO)

Due to hurricane tracking, Management directs N (BOP) downpower to 60% @ 1 % per minute (AOP 3575).

R (US) 3 RX19 I (BOP) 3FWS-PT508 fails high requiring manual control of the Master Speed Controller (AOP 3571 ).

4 ED04C C (RO)

Loss of emergency bus 34C. Isolate letdown TIS (US)

(AOP 3581 ). Recover from loss of 34C (AOP 3577).

(Tech Spec entry) 5 EG01 M (RO)

A main generator trip occurs, causing a steam line MS02C M (BOP) break outside of containment, upstream of 'C' MSIV.

MS07A M (US)

On the plant trip, the 'C' & 'D' MSIV's fail open and the MS07B

'A' & 'B' low set SG safety valves fail open. All four MS12C SG's are faulted (ECA-2.1 ). Later in event, one SIG MS12D safety reseats (will transition to E-2).

6 FW20C C (BOP)

No Aux Feed Pumps auto start. The Turbine Driven FW18B Aux Feed Pump can be started from MB5.

7 SIR14 C (RO)

Charging injection valve (3SIH*MV8801 B) fails to open below P-19 requiring actions to open.

N)ormal, R )eactivity, {l)nstrument, (C)omponent, (M)ajor D-37

Appendix D Scenario Outline Form ES-D-1 Rev 0/2 Facility: Millstone 3 Scenario No.: 2K15 NRC-02 Op-Test No.:

2K15 Examiners:

Operators:

Initial Conditions: IC-18 100% Power Middle of life Turnover:

The Qlant is at 100% 12ower and at middle of life. The "B" HVK Chiller unit is out of service for 12lanned maintenance.

Event Malf.

Event Event No.

No Type*

Description 1

RC07A C (RO)

'A' PZR PORV (3RCS*PCV455A) leak. Results in TIS (US) closing the PORV block valve. (Annunciator response) (Tech Spec entry) 2 R (US)

ISO-NE directed 300 MWe Emergency Load R (RO)

Reduction. (AOP 3575, Rapid Downpower at 5%/min)

N (BOP) 3 CC04B C (RO)

Respond to a RPCCW leak (AOP 3561, Loss of TIS (US)

RPCCW). Results in taking the 'B' train of RPCCW out of service. (Tech Spec entry) 4 SI06B M (ALL)

RCS to SI LOCA (isolable) outside CTMT. AOP 3555, Reactor Coolant Leak requires a manual Reactor Trip and Safety Injection.

5 CHL00411 C (RO)

SLCRS 'A' HVR EXH FAN/SPL Y DMPR CHL00410 (3HVR*FN 12A) fails to auto start.

CHL00695 CHL00694 CHL00399 CHL00410 ANL01103 6

Transition to ECA-1.2, LOCA Outside CTMT.

7 LOCA determined to be isolable. Transition to E-1, Loss of Reactor or Secondary Coolant.

(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor D-37

Appendix D Scenario Outline Form ES-D-1 Rev 0/2 Facility: Millstone 3 Scenario No.: 2K15 NRC-04 Op-Test No.:

2K15 Examiners:

Operators:

Initial Conditions: 74% Power, Beginning of life, Eguilibrium Xe.

Turnover:

The 12lant is at 7 4% 12ower. The Turbine Driven Auxiliar~ Feedwater Pum12 has been out of service for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for governor maintenance and is ex12ected back in 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months .

Event Malf.

Event Event No.

No Type*

Description 1

RX05 4A I (RO)

Narrow Range Loop 4 Thot instrument (RCS-TE441A)

TIS (US) fails hiqh. (AOP 3581 I 3571) (Tech Spec entrv) 2 FW01 R (US)

Condenser vacuum leak requiring load reduction.

R (RO)

(AOP 3575 at 5%/min)

N (BOP) 3 RX15 I (BOP)

Main Steam header pressure (MSS-PT507) fails low.

(AOP 3571) 4 RX09A I (RO)

Primary channel of Pressurizer Pressure (RCS*PT 455)

TIS (US) fails high. (AOP 3581 I 3571) (Tech Spec entry) 5 RX09A M (ALL)

Pressurizer Pressure (RCS*PT 455) fails low, causing RXR05 214 Reactor Trip on OTDT.

RXR34 6

TC03 C (BOP)

Automatic Turbine Trip failed, turbine will not run back.

TC04 Auto MSI failed, both Manual MSI pushbuttons failed, TC06A/B/C/D MSIVs and steam traps must be closed manually.

TC07 A/B/C/D Results in automatic Safety Injection.

RP08AB RPDI0071 RPDI0140 7

RP07B C (RO)

Train 'B' of auto SI failed.

8 SW01C/D C (RO)

Running Service Water pumps trip on the reactor trip.

SW02A/B Stand-by Service Water Pumps fail to auto start.

ED11E ED12E 9

FW20A The 'A' MDAFW pump fails to start in auto or manual.

FW18A The 'B' MDAFW pump discharge valve is shut with a FW21B stem/disc separation. The TDAFW pump is out of FW19 service for governor maintenance.

10 FW07A C (BOP)

Crew enters FR-H.1. MDFW pump will not start; SG FW37 feedwater flow will be established from the condensate pumps.

(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor D-37

ES-401 PWR Examination Outline Fonn ES-401-2 Facility: Millstone 3 Date of Exam: September 22nd, 2015 RO Kl A Category Points SRO-Only Points Tier Group K

K K

K A A A A G A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

1.

Emergency &

1 5

2 2

4 3

2 18 I

5 6

Abnormal Plant 2

I 2

2 NIA 2

I NIA I

9 I

3 4

Evolutions Tier 6

4 4

6 4

3 27 2

8 10 Totals

2.

1 2

3 3

3 2

2 1

2 3

5 2

28 3

2 5

Plant Systems 2

I 0

0 2

0 I

I 2

0 0

3 10 I

2 3

Tier 3

3 3

5 2

3 2

4 3

5 5

38 4

4 8

Totals

3.

Generic Knowledge and 1

2 3

4 1

2 3

4 Abilities Categories 10 7

4 3

I 2

I 3

I 2

Note: I.

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 KA is allowed ifthe 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 +/- I 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 of ES-40 I for guidance regarding the elimination of inappropriate Kl A statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting as second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers I and 2 from the shaded systems and Kl A categories.

7.

The generic (G) K/As in Tiers I 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. I.b of ES-40 I for the applicable Kl As.