ML15008A196

Draft-Outlines (Folder 2)

ML15008A196
Person / Time
Site:	Millstone  (DPR-065)
Issue date:	01/05/2015
From:	Cote M Dominion Nuclear Connecticut
To:	Peter Presby Operations Branch I
Shared Package
ML14043A009	List: ML14107A421 ML14262A252 ML14303A708 ML15007A395 ML15007A419 ML15007A437 ML15008A062 ML15008A196 ML15008A205 ML15008A229 ML15009A074 ML15156A603
References
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Download: ML15008A196 (33)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Millstone Unit 2 (MP2 Date of Exam:

October 2014 RO K/A Cate~ory Points I\\

SRO-Onlv Points I

Tier Group fl K

K K

K K

K A

A A

A G

G*

1 2

3 4

5 6

1 2

3 4

Total

1.

1 2

3 3

5 2

3 18

\\

v 6 Emergency &

Abnormal 2

2 2

2 N/A 1

1 N/A 1

9 1\\ 7 4

Plant Evolutions Tier Totals 4

5 5

6 3

4 27 y

10 1

2 3

5 3

2 1

3 3

3 1

2 28 I \\

5

2.

11

\\

Plant 2

1 1

0 3

1 2

0 1

0 1

0 10 J

3 Systems Tier Totals 3

4 5

6 3

3 3

4 3

2 2

38 L

\\a

3. Generic Knowledge and Abilities 1

2 3

4 10 1/

2 3

4 \\

Categories 3

3 II 2

2 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-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 KIA stateRlents.

4.

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

5.

Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.*

The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply)'. Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#)

on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-2 ES-40t PWR Examination Outline Form ES-401-2 Emerqenc and Abnormal Plant Evolutions-Tier 11Group 1 (RO I~)

EIAPE #I Name I Safety Function K

K K A A G

KIA Topic(s)

IR 1 2 3 1 2 000007 (BWIE02&E10; CEIE02) Reactor X

EA1.2 Ability to operate and I or monitor 3.3 1

Trip - Stabilization - Recovery 11 the following as they apply to the (Reactor Trip Recovery): Operating behavior characteristics of the facility.

000008 Pressurizer Vapor Space X

AK3.01 Knowledge of the reasons for the 3.7 2

Accident 13 following responses as they apply to the Pressurizer Vapor Space Accident: Why PZR level may come back on scale ifRCS is saturated.

000009 Small Break LOCA I 3 X

EK1.01 Knowledge of the operational 4.2 3

implications of the following concepts as they apply to the small break LOCA:

Natural circulation and cooling, including reflux boiling 000011 Large Break LOCA I 3 X

2.4.9 Knowledge of low power I shutdown 3.8 4

implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

000015117 RCP Malfunctions I 4 X

AA2.01 Ability to determine and interpret 3.0 5

the following as they apply to the Reactor Coolant Pump Malfunctions (Loss ofRC Flow): Cause ofRCP failure 000022 Loss of Rx Coolant Makeup I 2 X

AK3.02 Knowledge of the reasons for the 3.5 6

following responses as they apply to the Loss of Reactor Coolant Makeup: Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging 000025 Loss of RHR System I 4 X

AK2.05 Knowledge of the interrelations between the Loss of Residual Heat 2.6 7

Removal System and the following: Reactor building sump QQQQ2e bess ef GernfleAeAt GeeliA§ Randomly Deselected WateFt 8 QQQQ27 PFessl!Fii!:eF PFeSSl!Fe GeAtFel Randomly Deselected

c.

.~

000029 ATWS 11 X

2.1.23 Ability to perform specific system 4.3 8

and integrated plant procedures during all modes of plant operation.

000038 Steam Gen. Tube Rupture I 3 X

2.1.7 Ability to evaluate plant performance 4.4 9

and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000040 (BWIE05; CEIE05; WIE12)

X EK2.2 Knowledge of the interrelations 3.7 Hl Steam Line Rupture - Excessive Heat between the (Excess Steam Demand) and Transfer I 4 the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 000054 (CEIE06) Loss of Main X

EA1.3 Ability to operate and I or monitor 3.2 11 Feedwater I 4 the following as they apply to the (Loss of Feedwater): Desired operating results during abnormal and emergency situations 000055 Station Blackout I 6 X

EA1.04 Ability to operate and monitor the 3.5 12 following as they apply to a Station Blackout: Reduction of loads on the battery 000056 Loss of Off-site Power I 6 X

AK1.04 Knowledge of the operational 3.1 13 implications of the following concepts as they apply to Loss of Offsite Power:

Definition of saturation conditions, implication for the systems 000057 Loss of Vital AC lnst. Bus I 6 X

AA1.02 Ability to operate and I or monitor 3.8 14 the following as they apply to the Loss of Vital AC Instrument Bus: Manual control ofPZR level 000058 Loss of DC Power I 6 X

AA1.03 Ability to operate and I or monitor 3.1 15 the following as they apply to the Loss of DC Power: Vital and battery bus components 000062 Loss of Nuclear Svc Water I 4 X

AA2.06 Ability to determine and interpret 2.8 16 the following as they apply to the Loss of Nuclear Service Water: The length of time after the loss of SWS flow to a component before that component may be damaged 000065 Loss of Instrument Air I 8 X

AK3.03 Knowledge of the reasons for the following responses as they apply to the 2.9 17 Loss of Instrument Air: Knowing effects on plant operation of isolating certain equipment from instrument air l,0,4le94 bGGA GtoJtsise GeRtaiRmeRt,1 d Removed for CE Plant Wtfi!~ ~ bess ef fi!meF§eRG'f GeelaRt Removed for CE Plant ResiFG. t 4 Bwtfi!94; livtfi!9a IRa8eEjtoJate l=leat Removed for CE Plant

~-

_, C'

. ~*

000077 Generator Voltage and Electric X

AK2.02 Knowledge of the interrelations 3.1 18 Grid Disturbances I 6 between Generator Voltage and Electric Grid Disturbances and the following:

Breakers, relays KIA Category Totals:

2 3

3 5

2 3

Group Point Total:

1816

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 I~)

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 I 1 X 2.4.46 Ability to verify that the 4.2 19 alarms are consistent with the plant conditions.

QQQQQd QFe1313eEl GeRtFel ~eEl/-

~

Randomly Deselected 000005 Inoperable/Stuck Control Rod I 1 X

AKl.Ol Knowledge of the 3.1 20 operational implications of the following concepts as they apply to Inoperable I Stuck Control Rod:

Axial power imbalance QQQQ24 E:meF§9RG'f E!eFatieR 1-

~

Randomly Deselected QQQQ2g F!FeSS~,JFi~eF bevel Malf\\,jRstieR t 2 Randomly Deselected 000032 Loss of Source Range Nl I 7 X

AK3.01 Knowledge of the reasons for the following responses as they 3.2 21 apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss QQQ9dd bess ef IRteFmeEliate ~aR§e ~Ill-7 Randomly Deselected 000036 (BW/A08) Fuel Handling Accident I 8 X

AK3.03 Knowledge of the reasons 3.7 22 for the following responses as they apply to the Fuel Handling Incidents: Guidance contained in EOP for fuel handling incident QQQQd7 ateam GeReFateF +!,!Be beal~,l d Randomly Deselected 000051 Loss of Condenser Vacuum I 4 X

AKl.Ol Knowledge of the 2.4 23 operational implications of the (LER following concepts as they apply to 2010

003, Loss of Condenser Vacuum:

IR 20100 Relationship of condenser vacuum to 05.1R circulating water, 20110

02) flow rate, and temperature QQQQi9 AssiEleRtal bi(11,1iEl ~aEllA!aste ~el. t 9 Randomly Deselected QQQQ6Q AssiEleRtal Gasee~,~s ~aElwaste ~el. 1-9 Randomly Deselected 000061 ARM System Alarms I 7 X

AAl.Ol Ability to operate and I or 3.6 24 monitor the following as they apply to the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation QQQQ67 PlaRt ~iFe GR site 1-g Randomly Deselected QQQQ6g (E!W.~O.Q6) GeRtFSI ~eem E:*,*as. t g Randomly Deselected

000069 (WIE14) Loss of CTMT Integrity I 5 X

AA2.02 Ability to determine and 3.9 25 interpret the following as they apply to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity 000074 (WIE06&E07) lnad. Core Cooling I 4 X

EK2.05 Knowledge of the 3.9 26 interrelations between the and the following Inadequate Core Cooling:

LPipumps QQQQ7e ~i§R ReastsF GsslaAt AG!i>,<ily 1-Q Randomly Deselected lN,leQ~ & eQ2 Re8ia§A9SiS & Sl +eFFAiAa!iSA 1-d Removed for CE Plant l,AJ/-e ~ d SteaFA GeAeFalsF GveF J3Fess~o~Fe 1-4 Removed for CE Plant VWeHi GsAtaiAFAeAt FlssEliA§ 1-9 Removed for CE Plant VWe~e ~i§R GsAtaiAFAeAt RasiatisA t Q Removed for CE Plant BW.'.".Q~ PlaAI R~o~AI3asld ~

Removed for CE Plant Blf\\#,A,Q2&AQd bess et N~ll XI-¥ 1-7 Removed for CE Plant Bl.A.Wl,Q4 +~o~FI3iAe +FiJ:l I-4 Removed for CE Plant BW.~A,Q§ EFA9F§9AGy Qiesel Ast~o~atisA,l e Removed for CE Plant BW,~A,Q7 FleeEliA§ 1-8 Removed for CE Plant BW,leQd IAaEleEJ~o~ate S~o~sseeliA§ MaF§iA,1 4 Removed for CE Plant BW/-eQ8; W,leQd bGGA GssiEls*,*JR QeJ3F9SS./- 4 Removed forCE Plant BWIE09; CEIA13; WIE09&E10 Natural Circ. I 4 X

AK2.1 Knowledge of the 3.0 27 interrelations between the (Natural Circulation Operations) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features BWte~ d&e~ 4 eGI2 R~o~les aAEl eAsles~:JFes Removed for CE Plant Gel-A~~; W/-eQ8 RGS GveFseeliA§ 12+::> 1-4 Randomly Deselected GetM e el!Gess RGS beal~a§e 1-2 Randomly Deselected Ge,leQQ Fl!AG!ieAal Ress'<'eFY Randomly Deselected KIA Category Point Totals:

2 2

2 I

I I

Group Point Total:

914

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems-Tier 2/Group 1 (RO I SRG)

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

K2.02 Knowledge of bus power 2.5 28 (RCPS) supplies to the following: CCW pumps 003 Reactor Coolant Pump X

A3.05 Ability to monitor 2.7 29 (RCPS) automatic operation of the RePS, including: RCP lube oil and bearing lift pumps 004 Chemical and Volume X

A2.22 Ability to (a) predict the 3.2 30 Control (CVCS) impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions: Mismatch of letdown and charging flows.

005 Residual Heat Removal X

K3.07 Knowledge of the effect 3.2 31 (RHRS) that a loss or malfunction of the RHRS will have on the following:

Refueling operations 006 Emergency Core Cooling X

A1.15 Ability to predict and/or 3.3 32 (ECCS) monitor changes in parameters (to prevent exceeding design limits) associated with operating the Eees controls including:

RWST level and temperature 007 Pressurizer Relief/Quench X

K5.02 Knowledge of the 3.1 33 Tank (PRTS) operational implications of the following concepts as the apply to PRTS: Method offorming a steam bubble in the PZR 008 Component Cooling Water X

K3.01 Knowledge of the effect 3.4 34 (CCWS) that a loss or malfunction of the eews will have on the following:

Loads cooled by CCWS 010 Pressurizer Pressure Control X

K6.03 Knowledge of the effect of 3.2 35 (PZR PCS) a loss or malfunction of the following will have on the PZR PeS: PZR sprays and heaters

012 Reactor Protection (RPS)

X A2.07 Ability to (a) predict the 3.2 36 impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of de control power 013 Engineered Safety Features X

K4.03 Knowledge of ESFAS 3.9 37 Actuation (ESFAS) design feature(s) and/or interlock(s) which provide for the following: Main Steam Isolation System 013 Engineered Safety Features X

K4.07 Knowledge of ESF AS 3.7 38 Actuation (ESFAS) design feature(s) and/or interlock(s) which provide for the following: Power Supply Loss 022 Containment Cooling (CCS)

X Kl.Ol Knowledge of the physical 3.5 39 connections and/or cause effect relationships between the CCS and the following systems:

SWS/cooling system 022 Containment Cooling (CCS)

X A1.02 Ability to predict and/or 3.6 40 monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including:

Containment pressure Q~a lse GeREieRseF MP2 does not have system 026 Containment Spray (CSS)

X K4.05 Knowledge of CSS design 2.8 41 feature(s) and/or interlock(s) which provide for the following:

Prevention of material from clogging nozzles during recirculation 039 Main and Reheat Steam X

Kl.Ol Knowledge of the physical 3.1 42 (MRSS) connections and/or cause-effect relationships between the MRSS and the following systems: S/G 059 Main Feedwater (MFW)

X 2.2.44 Ability to interpret control 4.2 43 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

061 Auxiliary/Emergency X

A3.03 Ability to monitor 3.9 44 Feedwater (AFW) automatic operation of the AFW, including: AFW S/G level control on automatic start

062 AC Electrical Distribution X

A4.03 Ability to manually operate 2.8 45 and/or monitor in the control room: Synchroscope, including an understanding of running and incoming voltages 063 DC Electrical Distribution X

K2.01 Knowledge of bus power 2.9 46 supplies to the following: Major DC loads 064 Emergency Diesel Generator X

A2.13 Ability to (a) predict the 2.6 47 (ED/G) impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Consequences of opening auxiliary feeder bus (ED/G sub supply) 064 Emergency Diesel Generator X

K3.03 Knowledge of the effect 3.6 48 (ED/G) that a loss or malfunction of the ED/G system will have on the following: ED/G (manual loads) 073 Process Radiation X

Al.Ol Ability to predict and/or 3.2 49 Monitoring (PRM) monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels 073 Process Radiation X

KS.Ol Knowledge of the 2.5 50 Monitoring (PRM) operational implications as they apply to concepts as they apply to the PRM system: Radiation theory, including sources, types, units, and effects 076 Service Water (SWS)

X K2.01 Knowledge of bus power 2.7 51 supplies to the following: Service water 076 Service Water (SWS)

X 2.2.22 Knowledge of limiting 4.0 52 conditions for operations and safety limits.

078 Instrument Air (lAS)

X K3.01 Knowledge of the effect 3.1 53 that a loss or malfunction of the lAS will have on the following: Containment air system 078 Instrument Air (lAS)

X K3.02 Knowledge of the effect 3.4 54 that a loss or malfunction of the lAS will have on the following:

Systems having pneumatic valves and controls 103 Containment X

A3.01 Ability to monitor 3.9 55 automatic operation of the containment system, including:

Containment isolation KJA Category Point Totals:

2 3

5 3

2 I

3 3

3 I

2 Group Point Total:

28/5

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems -Tier 21Group 2 (RO I SRQ)

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 QQ~ GeRIFSI ~eEl !;lFi..,e Randomly Deselected QQ2 ReasteF GeelaRI Randomly Deselected 011 Pressurizer Level Control X

K6.03 Knowledge of the effect of a 2.9 56 (PZR LCS) loss or malfunction on the following will have on the PZR LCS:

Relationship between PZR level and PZR heater control circuit.

Q14 ReEl PesitieR IRElisatieR X -

K4.06 Knowledge ofRPS design 3.4 59 features and/or interlocks which provide for the following: individual and group misalignment.

015 Nuclear Instrumentation (NIS)

X K6.04 Knowledge of the effect of a 3.1 57 loss or malfunction on the following will have on the NIS: Bistables and logic circuits.

QH) i>JeA R!o!GieaF IASIF!o!RleA!alieA Randomly Deselected Q17 lA seFe +eRl]39Fal~oJFe MeAileF Randomly Deselected 027 Containment Iodine Removal X

KS.Ol Knowledge of the operational 3.1 58 (CIRS) implications of the following concepts as they apply to the CIRS:

Purpose of charcoal filters Q28 19y9Fe~eR ~eGeRlSiAeF Randomly Deselected D,

029 Containment Purge (CPS)

Rejected 033 Spent Fuel Pool Cooling X

K4.01 Knowledge of design 2.9

()0 (SFPCS) feature(s) and/or interlock(s) which provide for the following:

Maintenance of spent fuel level

{"\\':).c.

Randomly Deselected Qda SteaRJ GeReFateF Randomly Deselected 041 Steam Dump System (SDS)

X A2.02 Ability to (a) predict the 3.6 61 and Turbine Bypass Control impacts of the following malfunctions or operations on the SDS; and (b) based on those predictions or mitigate the consequences of those malfunctions or operations: Steam valve stuck open 045 Main Turbine Generator X

K4.11 Knowledge ofMT/G system 3.6 62 (MTIG) design feature(s) and/or interlock(s) which provide for the following: T /G reactor trip

055 Condenser Air Removal X

K1.06 Knowledge of the physical 2.6 63 (CARS) connections and/or cause effect relationships between the CARS and the following systems: PRM system Qae GemJeRsate Randomly Deselected Q98 bifllli9 ~a9waste Randomly Deselected 071 Waste Gas Disposal (WGDS)

X A4.26 Ability to manually operate 3.1 64 and/or monitor in the control room:

Authorized waste gas release, conducted in compliance with radioactive gas discharge permit A7'l 1\\

o.

Randomly Deselected 075 Circulating Water X

K2.03 Knowledge of bus power 2.6 65 supplies to the following:

Emergency/essential SWS pumps Q79 StatieR AiF Randomly Deselected QBe ~iFe I=!FetestieR Randomly Deselected KJA Category Point Totals:

I I

0 3

I 2

0 I

0 I

0 Group Point Total:

10/3

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

Form ES-401-3 Facility:

Millstone Unit 2 Date of Exam:

October 2014 Category KIA#

Topic RO SRO-Only IR IR 2.1.23 Ability to perform specific system and integrated plant 4.3 66 \\

procedures during all modes of plant operation.

1.

Conduct 2.1.37 Knowledge of procedures, guidelines, or limitations 4.3 67 of Operations associated with reactivity management.

Subtotal 2

\\

I 2.2.6 Knowledge of the process for making changes to 3.0 68 I

procedures.

2.

2.2.13 Knowledge of tagging and clearance procedures.

4.1 69 I

Equipment 2.2.22 Knowledge of limiting conditions for operations and 4.0 70 ' I Control safety limits.

\\

Subtotal 3

\\ I 2.3.12 Knowledge of radiological safety principles pertaining to 3.2 71 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to I\\

3.

locked high-radiation areas, alig_ning_filters, etc.

Radiation 2.3. 14 Knowledge of radiation or contamination hazards that 3.4 72

\\

Control may arise during normal, abnormal, or emergency conditions or activities.

Subtotal 2

I \\

2.4.4 Ability to recognize abnormal indications for system 4.5 73

\\

4.

operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Emergency Ability to verify that the alarms are consistent with the

\\

Procedures I 2.4.46 4.2 74 Plan plant conditions.

2.4.18 Knowledge of the specific bases for EOPs.

3.3 75 1 Subtotal 3

~

\\

Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 Facility:

Millstone Unit 2 Date of Exam:

October 20 14

~~

RO KJA Category_ Points

~

SRO-Only.Points Tier Group

/1' v

K K I}

K K

K A

A A

A A2 G*

Total 1

2 N

5 6

1 2

3 /¥"

Total

1.

1

~ v 18 3

3 6

Emergency &

y

/

Abnormal 2

N/A N/A 9

2 2

4 Plant Evolutions Tier Totals L

~

27 5

5 10 1

y 28 3

2 5

2.

v

~

K41 Plant 2

/

10 2

0 3

Systems Tier Totals /

~ lL 5 2

8

3. Generic Knowledge and Abilities

,---1-2---

3

_.-4---:"I 1 I 2 I 3 I 4 I 7 I Categories

~

1-" --

2 2

I 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 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.

7.*

The generic (G) K!As 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 K!As.

8.

On the following pages, enter the KJA 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 KJA catalog, and enter the KJA 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 Outline Form ES-401-2 Emerqencv and Abnormal Plant Evolutions -Tier 11Group 1 (RG I SRO)

EIAPE #I Name I Safety Function 000007 (BWIE02&E10; CEtE02) Roaster To' Ci n

1 000008 Pressurizer Vapor Spase AssiElent I 3 000009 Small Break LOCA I 3 000011 Large Break LOCA I 3 000015117 RCP Malfunctions I 4 000022 boss of Rx Coolant Makeup I 2 000025 boss of RI=IR System I 4 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control C'.

I'*

• on,-,lio

:l 000029 1\\WVS I 1 000038 Steam Gen. Tube Rupture I 3 000040 (BW/E05; CEIE05; VWE12)

Steam Line Rupture Exsessive l=leat Transfer I 4 000054 (CEtE06) boss of Main FeeEiwater I 4 000055 Station Blackout I 6 000056 Loss of Off site Pmver t 6 000057 boss of Vital AC lnst. Bus / 6 000058 Loss of DC Power I 6 000062 Loss of ~Juslear Svs Water / 4 000065 boss of Instrument Air t 8 KKKAA G

1 2 3

1 2

X X

X X

X X

KIA Topic(s)

Randomly Deselected Randomly Deselected EA2.02 Ability to determine or interpret the following as they apply to a small break LOCA: Possible leak paths 2.4.6 Knowledge of EOP Mitigation Strategies AA2.10 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on loss of cooling or seal injection Randomly Deselected Randomly Deselected 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected EA2.06 Ability to determine or interpret the following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses Randomly Deselected Randomly Deselected 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

Randomly Deselected Randomly Deselected IR 3.8 76 4.7 78 3.7 77 4.4 79 4.1 80 4.1 81

WIEQ4 bGGA Gl!!siEie GeR!aiRR18R!,l d Removed for CE Plant IJWE~ ~ bess ef ER18FJBRGY GeelaR!

Removed for CE Plant ResiFG. t 4 BW.£EQ4; 'PJ.£EQ1i IAaEie(Jl!a!e Flea!

Removed for CE Plant Tr~nd,

'~~,f <::.

.~.

c;,;

QQQQ77 GeReFa!eF VellaJe aREI Eles!FiG Randomly Deselected GFiEI Qis!l!FI3aRG9S I e KIA Category Totals:

0 0

0 0

3 3

Group Point Total:

18/6

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 11Group 2 (RG I SRO)

EIAPE #I Name I Safety Function K

K K A A G KIA Topic(s)

IR 1

2 3

1 2 QQQQQ~ GaAtiAl,!Sl,!S Rae IJltitMFawal,l ~

Randomly Deselected QQQQQJ gFa1313ee GaAtFSI Rae t ~

Randomly Deselected QQQQQa IAai:JeFalale,lgtl,!GI~ GaAtFSI Rae,l ~

Randomly Deselected QQQQ24 EFAeF§eAsy BeFatiaA t ~

Randomly Deselected QQQQ2!l 1=1FeSSl,!Fi2'eF bevel Malfl,!AGtiaA,1 2 Randomly Deselected QQQQJ2 bass af gal,!FGe RaA§e ~II t 7 Randomly Deselected QQQQJJ bess af IAteFFAeeiate RaA§e Nl t 7 Randomly Deselected QQQQJe (BW/fi,Q8) ~l,lel l=laAeliA§,o.ssieeAt t g Randomly Deselected 000037 Steam Generator Tube Leak I 3 X

AA2.12 Ability to determine and 4.1 82 interpret the following as they apply to the Steam Generator Tube Leak:

Flow rate of leak QQQQa~ bass af GaREleAseF VaGl,ll,!FA t 4 Randomly Deselected 000059 Accidental Liquid RadWaste Rei. I 9 X 2.2.38 Knowledge of conditions and 3.6 83 limitations in the facility license.

QQQQ9Q AssieeAtal Gaseel,ls Rae*.*.<aste Rei.,1 g Randomly Deselected QQQQ9~,A.RM gysteFA,A,IaFFAS 1-7 Randomly Deselected 000067 Plant Fire On-site I 8 X 2.2.37 Ability to determine 4.6 84 operability and/or availability of safety related equipment.

QQQQe!l (BWtAQe) GaAtFSI RaaFA EliaS. t g Randomly Deselected QQQQ99 PME14) bass ef GTMT IAle§Fity t a

'""""<\\~.0~ Ability ta deteFmine and

.X 44

&4 inteFf)Fet the fallowing as they llflflly ta the bass 9I Gantainment lntegFit~': lieFifieatieH efaHtematie aHd maHHal meaHs sf resteriHg integFity Kl A rejected due to overlap with RO exam.

QQQQ74 (W,lEQe&EQ7) I Rae. GaFe GaaliA§ t 4 Randomly Deselected QQQQ7e l=li§A ReastaF GaalaAt,A,sti¥ity t 9 Randomly Deselected lAifEG~ & E92 Reeia§Aasis & g1 TeFFAiAatiaA 1 J Removed for CE Plant W,lE ~ J gteaFA GeAeFataF G*JeF i:JFSSSl,!Fe t 4 Removed for CE Plant

\\o.lfE01 a GaAtaiAFAeAt ~laaeiA§ t a Removed for CE Plant

\\o.lfEO~e l=li§A GeAtaiAFAeAt RaeiatiaA,l 9 Removed for CE Plant BVVJAQ~ PlaAt RuAbask I~

Removed for CE Plant BlA4AQ2&AQJ bass af ~~~II Xf.¥,1 7 Removed for CE Plant

8W,4A,Q4 =l=llFSiRe =I=Fif3 f. 4 Removed for CE Plant 8\\1\\II,O.Q§ EFReF§eRGy Qiesel AG!lJa!iaR,l e Removed for CE Plant 8W,40.Q7 ~leesiR§ J 8 Removed for CE Plant 8\\IV/E;Qa IRa9eEJlolate SlJI:lseeliR§ MaF§iR I 4 Removed for CE Plant 8l,ll,l/E;Q8; W,lE;Qa bQGA Geelse*.vR Qef3Fess. I 4 Removed for CE Plant 8WJE;Q9; GE;IMa; \\IVIE;Q9&E;~Q ~la!lJFal GiFG.I4 Randomly Deselected 8WIE;~ a&E;~ 4 E;QP Rllles aRB ERGI9SlJFes Removed for CE Plant GE;J,O.~ ~; IJI.I.f.E;QS RGS QveFsealiR§ P+S 14 Randomly Deselected GE;I,O.~ e EliGess RGS beal~a§e I 2 Randomly Deselected CE/E09 Functional Recovery X

EA2.1 Ability to determine and 4.4 85 interpret the following as they apply to the (Functional Recovery): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

KIA Category Point Totals:

0 0

0 0

2 2

Group Point Total:

9/4

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems-Tier 21Group 1 (RG I SRO)

System # I Name K K K K K K A A A A

G KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 003 Reactor Coolant Pump X

A2.01 Ability to (a) predict the 3.9 86 (RCPS) impacts of the following malfunctions or operations on the RePS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Problems with RCP seals, especially rates of seal leak-off 004 Chemical and Volume X

A2.15 Ability to (a) predict the 3.7 87 Control (CVCS) impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High or low PZR level 005 Residual Heat Removal Randomly Deselected

~

006 Emergency Core Cooling Randomly Deselected

~

007 Pressurizer Relief/Quench Randomly Deselected T.

fDDTC'\\

008 Com~onent Cooling lll.tater Randomly Deselected 010 Pressurizer Pressure Control 2.2.25 Knowledge of the bases in 4.2 89 (PZR PCS)

Technical Specifications for limiting conditions for operations and safety limits.

i\\2.02 Ability t9 (a) pFediet the 012 Reactor Protection {RPS)

.,.9 impaets 9f the fali9Wiftg malfufteti9ftS 9F 9penti9ftS 9ft the RI!S; aftd (b) based 9ft th9se pFedieti9ftS, ase f!F9eedaFes t9 e9FFeet, e9fttF91, 9F mitigate the e9ftSefJ

Heftees 9f th9se malfufteti9ftS 9F 9penti9fts

bess ef iRstrumeRt pev;er Kl A rejected due to overlap with RO exam.

01 d Engineered Safety Features Randomly Deselected 1\\ ~*"~.;nn 11:: C' t: 1\\ C' 022 Containment Cooling (CCS)

Questioned rejected due to oversampling ees.

Q::la lee GaREieRser MP2 does not have system 026 Containment Spray (CSS)

X A2.04 Ability to (a) predict the 4.2 88 impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Failure of automatic recirculation transfer Q~9 MaiR aREI Rel=leat ~teaFR Randomly Deselected

~

Qa9 MaiR FeeEiwater (MFiilJ)

Randomly Deselected Qe1 Au*iliar:y,li:OFRer§eRey Randomly Deselected r-.

'1\\t:\\M\\

062 AC Electrical Distribution X

2.2.40 Ability to apply Technical 4.7 90 Specifications for a System.

Qe~ QG i:Oieetrieal QistrieutiaR Randomly Deselected Qe4 i:OFRer§eRG}' Qiesel GeReratar Randomly Deselected fWIGj Q7~ ~raeess RaEiiatiaR Randomly Deselected roo*n~

Q7e ~erviee Water (~l.liJ~)

Randomly Deselected Q78 IRstruFReRt Air (lA~)

Randomly Deselected 1Q:3 GaRtaiRFReRt Randomly Deselected KJA Category Point Totals:

0 0

0 0

0 0

0 3

0 0

2 Grou~ Point Total:

28/5

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlantS stems -Tier 21Group 2 (RG I SRO)

System #I Name K

K K

K K

K A A A A G KIA Topic(s)

IR 1

2 3

4 5

6 1 2 3

4 QQ~ GeRtFel ReEl QFive Randomly Deselected QQ2 ReasteF GeelaRt Randomly Deselected Q~ ~ PFeSSllFii!:eF be*.*el GeRtFel to7o r-e*

Randomly Deselected Q~ 4 ReEl PesitieR IREiisatieR Randomly Deselected 015 Nuclear Instrumentation (NIS)

X A2.05 Ability to (a) predict the 3.8 91 impacts of the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core void formation QHi ~JeR RlJGieaF IRStFlJmeRtatieR Randomly Deselected Q~ 7 lA seFe +emj3eFatlJFe MeRiteF Randomly Deselected Q27 GeRtaiRmeRt leEiiRe Remeval Randomly Deselected fGl.RS}

Q28 l=lyEIFe§eR Reseml:liReF Randomly Deselected

o.

(",

Q29 GeRtaiRmeRt PllF§e (GPS)

Randomly Deselected 033 Spent Fuel Pool Cooling X

A2.03 Ability to (a) predict the 3.5 92 (SFPCS) impacts of the following malfunctions or operations on the SFPCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level K3.01 Knowledge af the effeet that Qd4 rllel l=laREIIiR§ eqllij3meRI

~ -

~ w a lass 9F malfunetian af the Fuel Handling System will ha'!*e an the fallowing: Containment ventilation K/ A rejected due to overlap with RO exam.

034 Fuel Handling Equipment X

K4.02 Knowledge of design 3.3 93 feature(s) and/or interlock(s) which provide for the following:

Fuel movement Qda Steam GeReFaleF Randomly Deselected Q4~ Steam QlJmi3 System (SQS)

Randomly Deselected

'To Do

(",

Q4§ MaiR =l=lJFSiRe GeReFaleF Randomly Deselected fM+fG1 Q§§ GeREleRseF.O.iF Remeval Randomly Deselected fGARS}

Q§e GeREleRsate Randomly Deselected Qe8 biEJ~oJiEl RaElwasle Randomly Deselected Q7~ Waste Gas gisJ3esal p,ll.lGgS)

Randomly Deselected Q+:l.O.Fea RaElialieR MeRileFiR§ Randomly Deselected Q7§ GiFs~oJialiR§ WaleF Randomly Deselected Q7Q StalieR.O.iF Randomly Deselected QSe FiFe j.:2mtestieR Randomly Deselected KJA Category Point Totals:

0 0

0 I

0 0

0 2

0 0

0 Group Point Total:

10/3

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

Form ES-401-3 Facility:

Millstone Unit 2 Date of Exam:

October 2014 Category K/A#

Topic RO SRO-Only IR IR 2.1.5 Ability to use procedures related to shift staffing, such as 1\\

I 3.9 94

1.

minimum crew complement, overtime limitations, etc.

Conduct Ability to perform specific system and

\\ I of Operations 2.1.23 integrated plant procedures during all modes of 4.4 95 plant operation.

Subtotal

\\

I 2

2.2.1 Ability to perform pre-startup procedures for the facility, \\ I 4.4 96

2.

including operating those controls associated with plant Equipment equipment that could affect reactivity.

Control

\\ I 2.2.37 Ability to determine operability and/or availability of 4.6 97 safety related equipment.

Subtotal 2

3.

2.3.4 Knowledge of radiation exposure limits under normal or I \\

3.7 98 Radiation emergency conditions.

Control 2.3.-

Randomly Deselected I \\

Subtotal I

\\

1 2.4.22 Knowledge of the bases for prioritizing safety functions I

\\

4.4 99

4.

during abnormaUemergency operations.

Emergency Knowledge of the lines of authority during I

\\

Procedures I 2.4.37 implementation of the emergency plan.

4.1 100 Plan I

\\

Subtotal 2

Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA SROl/2 069 AA2.02 Kl A was also randomly selected on the RO exam. Res elected (Q#83)

E/ APE 000059 AA 2.03Accidental Liquid Radwaste Release.

SRO 2/1 012 A2.02 A similar KIA was randomly selected on the RO exam: RPS A2.07, (Q#88)

Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of de control power (RO Q#36)

Kl A would test similar concepts. Reselected Plant System 026 Containment Spray, A2.04 SRO 2/2 034 K3.01 Kl A tests similar concept, automatic purge isolation that appears on (Q#93)

RO written exam in question #59 for the Fuel Handling Equipment System. Re-selected K4.02.

R03 G2.4.6 Could not write a good RO question to 2.4.6 EOP mitigation (Q#73) strategies. Randomly selected 2.4.4 entry level conditions for EOP and abnormal procedures.

R03 G2.4.13 Could not write a good RO question to 2.4.13 Knowledge of crew (Q#74) responsibilities. Randomly selected 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

SRO 1/2 2.2.37 Could not write a discriminating SRO question for entry conditions (Q#84) for KA 2.4.4 AOPs, EOPs for Plant Fire system. Randomly selected 2.2.37.

RO 211 013 K4.16 Could not find write a discriminating question for ESF AS "to avoid (Q#38)

PTS". Randomly selected K4.07, Power supply loss.

R02/2 015 A4.01 Could not find write a discriminating question for NIS "Selection of (Q#57) controlling channel." Randomly selected K6.04, Bistables and logic circuit.

R03 G2.1.13 This Kl A is performed by Security personnel at Millstone and not (Q#66) relevant for Reactor Operators. Randomly selected G 2.1.23.

R0111 029 G2.1.25 Could not write an ATWS question that was discriminating using (Q#8) the ability to interpret reference material. Randomly selected 2.1.23.

RO 111 038 G2.1.31 Could not write a SGTR question that was discriminating using the (Q#9) ability to locate control room switches. Randomly selected 2.1. 7.

R0211 006 A1.14 Could not write a discriminating question for monitoring controls (Q#32) for reactor level. Randomly selected A1.15.

ES-401 Record of Rejected K/ As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA SR0111 011 G2.2.39 Knowledge ofless than one hour TS is RO knowledge. Could not (Q#78) write a SRO only question. Re-selected 2.4.6.

SRO 211 062 G2.2.42 Knowledge of entry level TS conditions is RO knowledge. Could (Q#90) not write a SRO only question. Re-selected 2.2.40.

RO 2/1 004 Al.ll Could not write question to 004 A1.11. Re-selected 004 A2.22 (Q#30)

Predict impact of mismatch of charging I letdown and mitigate.

R02/2 045 K5.18 Could not find write a discriminating question for MT/G K5.18.

(Q#62)

Reselected 045 K4.11.

R03 G2.2.35 Could not find write a discriminating question for G2.2.35.

(Q#70)

Reselected G2.2.22.

SRO G2.1.23 Could not find write a discriminating SRO question for G2.1.29.

(Q95)

Reselected G2.1.23.

SRO System 022 Rejected question based on oversampling system. Reselected (Q89)

System 01 0 Pressurizer Pressure control.

ROQ59 System 022 Rejected question based on oversampling system. Reselected System 014 Rod Position Indications.

SRO 83 M2.03 KA changed due to could not write sro level question to ka.

Selected generic.2.2.38 which was more appropriate for ODCM question.

~

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: October 2014 Examination Level: RO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note)

Code*

R,M 2.1.20 Ability to execute procedure steps. (4.3)

Conduct of Operations JPM: Calculate Time to Boil. Modify JPM-A2-R (RO-ADMIN-1)

Conduct of Operations R, D KIA System 001, A4.1 0: Determination of an ECP (RO-ADMIN-2)

(3.9)

JPM: Manually calculate ECP use JPM 216 or create NEW JPM where RO reviews flawed ECP calculation. Determine impact (KIA 001 A2.12 Erroneous ECP calculation (4.1)).

R,N 2.2.12 Knowledge of surveillance procedures (3.0)

Equipment Control JPM: Perform monthly borated water sources (RO-ADMIN-3) verification surveillance, SP 2601A. Document on SP 2601A-009.

R,M 2.3. 7 Ability to comply with radiation work permit Radiation Control requirements during normal or abnormal (RO-ADMIN-4) conditions. (3.5)

JPM: Modify JPM 238 or A3R or make a new one:

Determin~ protective clothing and limits associated with performance of a task in the RCA 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: Millstone Unit 2 Date of Examination: October 2014 Examination Level: SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note)

Code*

KIA System 001, A4.1 0: Determination of an ECP Conduct of Operations (3.9)

R,D JPM: Manually calculate ECP use JPM 216 or SRO-ADMIN-1 create NEW JPM where SRO reviews flawed ECP calculation. Determine impact (KIA 001 A2.12 Erroneous ECP calculation (4.1)).

2.1.36 Knowledge of procedures and limitations involved in core alterations. (4.1)

Conduct of Operations R,D JPM: At the completion of this JPM, the examinee will have identified a loss of CTMT closure, entered SRO-ADMIN-2 appropriate TSAS and directed actions to suspend all operations involving movement of irradiated fuel assemblies in the containment_(JPM A-08-02) 2.2.40 Ability to apply Technical Specifications for Equipment Control R,N a system. (4.7)

SRO-ADMIN-3 JPM: Determine Technical Specification applicability and actions. (New-build around Aux Feed Water equipment).

R, P-2.3.6 Ability to approve release permits. (3.8)

Radiation Control 2009, M JPM: Review and approve Liquid Radwaste SRO-ADMIN-4 Discharge Permit-Modify JPM.

2.4.41 Knowledge of the emergency action level Emergency Procedures/Plan R,M thresholds and classifications. (4.6)

SRO-ADMIN-5 JPM: Classify event, Determine PAR, complete Incident Response Form (S/G Tube Leak, Gen Emergency, Modify JPM-182).

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: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

JPM #

System I JPM Title Type Code*

Safety Function S-1 CRDS I Dropped CEA Recovery-Alt Path (JPM-208)

M, S,A 1

S-2 ESFAS I Reset Inadvertent SIAS - Alt Path N,S,EN,A 2

S-3 PCS I PORV Switch Failure On OTCC (JPM 118)

D,S,A 3

S-4 RCS I Start RCP on Heatup-Alt Path (JPM 163).

D,S,L,A 4(P)

S-5 CCS I Shift CAR Units-Alt Path (JPM-160)

D,S,A 5

S-6 AC Distribution I Tie 480 Volt Busses (JPM-053)

D, S,L 6

S-7 PRMS I Adjust SJAE RadMan Setpoints (JPM-120)

D,S 7

S-8 SFPC I Restore SFP Clg Following LOCA-Alt Path N,A,S,L 8

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 Appendix R Actions in Fire Area R-1 N, E RCA 6

P-2 MRSS I Local Operation of ADV (JPM-93)

D, E 4(S)

P-3 CVCS I Local Boration lAW AOP 2551 N,E,RCA 1

All RO and SR0-1 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 Actual Criteria for RO I SR0-1 I SRO-U (A)Iternate path 61613 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 61511 S91S81S4 (E)mergency or abnormal in-plant 31312

<:11<:11<:1 (EN)gineered safety feature 11111

- I -

I <:1 (control room system)

(L)ow-Power I Shutdown 31211

<:11<:11<:1 (N)ew or (M)odified from bank include 1 (A) 51514

<:21<:21<:1 (P)revious 2 exams 01010 s 3 I s 3 I s 2 (randomly selected)

(R)CA 21211

<:11<:11<:1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

JPM #

System I JPM Title Type Code*

Safety Function S-1 CRDS I Dropped CEA Recovery-Alt Path (JPM-208)

M,S,A 1

S-2 ESFAS I Reset Inadvertent SIAS - Alt Path N,S,EN,A 2

S-3 PCS I PORV Switch Failure On OTCC (JPM 118)

D,S,A 3

S-4 RCS I Start RCP on Heatup-Alt Path (JPM 163).

D, S, L,A 4(P)

S-5 CCS I Shift CAR Units-Alt Path (JPM-160)

D,S,A 5

S-7 PRMS I Adjust SJAE Rad Mon Setpoints (JPM-120)

D,S 7

S-8 SFPC I Restore SFP Clg Following LOCA - Alt Path N,A,S, L 8

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P-1 Appendix R Actions in Fire Area R-1 N, E RCA 6

P-2 MRSS I Local Operation of ADV (JPM-93)

D,E 4(S)

P-3 CVCS I Local Boration lAW AOP 2551 N,E,RCA 1

All RO and SR0-1 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 Actual Criteria for RO I SR0-11 SRO-U (A)Iternate path 61613 4-6 I 4-6 12-3 (C)ontrol room (D)irect from bank 61511

'>91:'>81:'>4 (E)mergency or abnormal in-plant 31312

~11~11~1 (EN)gineered safety feature 11111

- I -

I

~1 (control room system)

(L)ow-Power I Shutdown 31211

~11~11~1 (N)ew or (M)odified from bank include 1 (A) 51514

~21~21~1 (P)revious 2 exams 01010

3 I

:; 31 ::; 2 (randomly selected)

(R)CA 21211

~11~11~1 (S)imulator

S-1:

The examinee will perform a CEA recovery following a dropped CEA. During CEA movement, the CEDS TROUBLE alarm comes in during CEA movement. This is modified alternate path JPM from the bank. (KIA: 000-003-AA 1.02, IR 3.6/3.4)

S-2:

The examinee will perform a reset of Safety Injection Actuation Signal (SIAS) following an Inadvertent ESFAS Actuation using AOP 2571 Inadvertent ESFAS Actuation. This is a new JPM under the Engineered Safety Features Actuation System - Reactor Coolant System Inventory Control Safety Function. (KIA 013.A4.02, IR 4.3 I 4.4)

S-3:

Examinee performs opening of the PORVs by the contingency action of EOP 2540D, Success Path HR-3.This is an alternate path JPM directly from the bank. Based on JPM 118 (KIA 010 A4.03, IR 4.0/3.8)

S-4:

The examinee will start the fourth RCP, monitor critical RCP parameters including alarms and secure the RCP per OP 2301 C and/or ARP 2590B-083, "RCP A Upper Oil Reservoir Oil Level Lo". This JPM is performed at shutdown conditions and is an alternate path JPM directly from the bank. Consider modifying type of alarm that comes in requiring RCP trip. (KIA 003 A2.02, IR 3.7/3.9)

S-5:

At the completion of this JPM, the examinee has successfully stopped and restarted an OPERABLE CAR Fan. This JPM is an alternate path. (KIA 022 A4.01, IR 3.6/3.6)

S-6:

The examiner will cross-tie 480 volt busses The examinee will cross-tie 480 volt busses (22A and 22B, with 22B supplying bus 22A) per OP 2344A, 480 Volt Load Centers, in preparation for tagging and replacement of Bus 22A Transformer. This is a shutdown JPM directly from the bank. (KIA 062-A4.01, IR 3.3/3.1)

S-7:

The examinee will change the setpoint of the SJAE Radmonitor (RM5099) a Chemistry approved SP2833-007 "SJAE Radmonitor MR 5099 & PPC Alarm Setpoint Change Request and OP2383C "Radiation Monitor Alarm Setpoint Control" Section 4.1. This JPM is directly from the bank. (KIA 071 A4.25, IR 3.2/3.2)

S-8:

The examinee will restore Spent Fuel Pool Cooling approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following a LOCA in accordance with step 55 of EOP 2532 LOCA and using EOP 2541, Appendix

42. This is a new Plant Systems JPM. It is performed at shutdown conditions and includes an alternate path with failure of pump to start. (KIA 033 A2.02, IR 2.7/3.0)

P-1:

The examinee will transfer control from the Control Room to the Fire Shutdown Panel, C-10 and secure the A Diesel Generator using AOP 2579A, Fire Procedure for Hot Standby Appendix R Fire Area R-1 due to a fire and evacuation of the Control Room.

This is a new JPM that requires access into the RCA. (KIA APE-068-AA1.21, IR 3.9/4.1)

P-2:

The examinee will take local manual control of the "A" Atmospheric Dump Valve and open the valve to 25% using EOP 2541 Appendix 36 during loss of Instrument Air and Reactor trip. This JPM is directly from the bank. (KIA 039-A2.04, IR 3.4/3.7)

P-3:

The examinee will commence a manual boration to the RCS during a shutdown from outside the control room event (not due to fire). The examinee will perform steps in AOP 2551, Shutdown from Outside the Control Room. This is a new JPM in the RCA.(KIA 004-A2.14, IR 3.8/3.9))

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: October 2014 Exam Level: RO SR0-1 SRO-U Operating Test No.: NRC Control Room Systems© (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

JPM#

System I JPM Title Type Code*

Safety Function S-1 CRDS I Dropped CEA Recovery-Alt Path (JPM-208)

M,S,A 1

S-2 ESFAS I Reset Inadvertent SIAS - Alt Path N,S,EN,A 2

S-8 SFPC I Restore SFP Clg Following LOCA-Alt Path N,A,S, L 8

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1 Appendix R Actions in Fire Area R-1 N, E RCA 6

P-2 MRSS I Local Operation of ADV (JPM-93)

D,E 4(S)

All RO and SR0-1 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 Actual Criteria for RO I SR0-1 I SRO-U (A)Iternate path 61613 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 61511

591:581:54 (E)mergency or abnormal in-plant 31312

<!11<!11<!1 (EN)gineered safety feature 11111

- I -

I <!1 (control room system)

(L)ow-Power I Shutdown 31211

<!11<!11<!1 (N)ew or (M)odified from bank include 1 (A) 51514

<!21<!21<!1 (P)revious 2 exams 01010

53 I :5 3 I :52 (randomly selected)

(R)CA 21211

<!11<!11<!1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone Unit 2 Scenario No.: 3 Op-Test No.: NRC 2014 Examiners:

Operators:

SRO ATC BOP Initial Conditions: 100% Power IC, BOL, Equilibrium Xenon, 1105 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C, Channel C Wide Range Containment Pressure safety instrument is OOS.

Turnover: 100% power, equilibrium Xenon, 1105 ppm Boron, blend ratio: 4.32: 1.0, SGBD @ 40gpm per Steam Generator, 24E is aligned to 24C. Channel C Wide Range Containment Pressure (PI 8115) instrument is OOS. Entered TSAS 2 for 3.4.3.4 RPS Instrumentation and 3.4.3.4 ESAS Instrumentation 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago Prerequisites met for SP26060 2-CS-4.1 B Stroke and Timing I ST. Perform 1ST at the start of this shift. High winds reported on Long Island Sound for the entire day.

Critical Tasks:

r

1. Manually Shutdown the reactor. The reactor must be manually tripped using the CEDM output breakers immediately (within 1 minute) when an automatic reactor trip fails and/or the manual push buttons do NOT work. (CT-1/SPTA-5)

2.

Emergency borate following A TWS. Emergency Borate the RCS following Reactor Trip following the failure of more than one full-length CEA to insert on a reactor trip prior to exiting EOP 2525 Standard Post Trip Actions.

3.

Initiate a plant cooldown. A plant cooldown at a rate of greater than 40°F/hr should be initiated within one hour, following an unisolable LOCA, until the condenser steam dump valves or ADVs are full open. (CT-3/LOCA-3)

Event No.

Malf. No.

Event Event Description Type*

Override N {ATC, Perform Surveillance Procedure SP-26060 to stroke test 1

for valve BOP)

Containment Spray Valve CS-4.1 B. Stroke time is out of (0 min) indication specification (overriding one of the position lights on for a few in Control TS (SRO) additional seconds to make it look like the valve took longer to Room.

stroke).

RX01B RX02B Pressurizer Spray Valve Controller Failure, HIC-100F fails causing I {ATC, 2

Override SRO)

Spray Valve 100F to open 25%. During transient, Proportional (1 0 min) proportion TS (SRO)

Pressurizer heater Group 2 breaker trips open. (EN-49779). Must al heater remove RX01 B so operator can close spray valve.

indication 3

C (BOP, (30 min)

SW09A SRO)

Service Water Pump "A" strainer high 0/P (4psid and rising) 1 of42

Op-Test No.: ___,_N_,_,R...!..:C"'--- Scenario No.: ~

Event No.: 1

• l~~

Event

Description:

Raise Power to 100%

Time I Position I Applicant's Actions or Behavior 4

C (BOP, (40 min)

FW39A SRO)

High vibration on "A" SGFP (both HP/LP bearings >3mils, <5mils)

N (ATC) 5 R (ATC)

Rapid power reduction to take "A" SGFP offline (-65% power)

(43 min)

TU02A

RD1401, RD1402,

RD1405, Turbine High Vibration results in manual scram (greater than 12 6

RD1406, M (All) mils sustained, ramp). Reactor Trip manual pushbuttons do not (60 min)

RD1409, work (ATWS). 6 CEAs fail to insert on reactor trip (ATWS).

RD1414 Emergency Boration required.

RP27B RP04B RP04D CH-514, The normal Emergency Boration path is failed. CH-514, boric acid 7

CH-508, C (ATC) isolation valve and CH-508, CH-509 boric acid gravity feed isolation (60min) 509 valves will NOT open. Must perform boration from RWST and overrides charging pumps.

8 RC05A C (ATC)

Pressurizer Safety Valve RC-200 fails to re-seat (25% severity)

(61 min)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 2 of42

Appendix D Scenario Outline Form ES-D-i Facility: Millstone Unit 2 Scenario No.: 4 Op-Test No.: NRC 2014 Examiners:

Operators:

Initial Conditions: (IC 55) 100% Power, MOL, Equilibrium Xenon, 1065 ppm Boron, SGBD @40gpm per Steam Generator, 24E aligned to 24C.

Turnover: 100% Power, BOL, Equilibrium Xenon, 1065 ppm Boron, SGBD@ 40gpm per Steam Generator, 24E aligned to 24C.

Critical Tasks:

1.

Manually trip the turbine or close MSIVs within 1 minute following a reactor trip and failure of automatic turbine trip.

2.

Isolate AFW to the affected SG #2 within 30 minutes following the generation of MSIS during an ESDE.

3.

Manually start "A" HPSI pump prior to reaching pressurizer low level alarm following a failure of "A" HPSI pump to actuate and a degraded of "C" HPSI pump.

Event No.

Malf.

Event Type*

Event Description No.

1 RX04B I (ATC, Channel Y PZR Level transmitter, L T11 OY (selected), fails low

(+10min)

SRO)

(55%, 2 minute ramp).

2 C (BOP, No. 1 Turbine control valve failure. (- 20MWe drop, 20% open total, TC06A SRO)

(+20 min)

R (ATC) 1 min ramp) 3 I (ATC,

(+35 min)

RP09D SRO)

Spurious RPS low flow trip Channel "D" TS (SRO) 4 SG01A C (All),

No. 1 Steam Generator tube leak (75 gpd and rising more than 15

(+40 min)

TS (SRO) gpd/min - 0.12 gpm )

5 R (All)

Rapid power reduction for Steam Generator Tube Leak

(+40 min) 6 SG02A M (ATC, No.1 SGTR exceeds charging pump capacity. Reactor trip required.

(+55 min)

SRO)

(200 gpm) 7 TC10H C (BOP)

Turbine fails to trip on reactor trip

(+55 min)

Excessive Steam Demand Event outside containment on #2 Steam 8

MS02B C (BOP, Generator, upstream of #2 MSIV. (1.5 million lbm/hr, no ramp. need

(+57 min)

SRO)

SIAS to occur, do not want to lose NPSH to RCPs, 2 minute delay from reactor trip) 9 ES031 C (ATC, "A" HPSI pump fails to start on SIAS (failure of ESAS Module AM

(+60 min)

SI05C SRO) 514). C HPSI pump is degraded (50o/~)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.S.d)

Actual

1.

Total malfunctions (5-8) 8

2.

Malfunctions after EOP entry (1-2) 2

3.

Abnormal events (2-4) 4

4.

Major transients (1-2) 1

5.

EOPs entered/requiring substantive actions (1-2) 1

6.

EOP contingencies requiring substantive actions (0-2) 1

7.

Critical tasks (2-3) 3