ML14307B005

Final Outlines (Folder 3)

ML14307B005
Person / Time
Site:	Calvert Cliffs
Issue date:	10/21/2014
From:	Christopher Lally Operations Branch I
To:	Calvert Cliffs
Shared Package
ML14079A469	List: IR 05000317/2014301 ML14092A008 ML14304A680 ML14304A721 ML14304A727 ML14307B005 ML14307B051 ML14307B072 ML14307B104 ML15043A709 ML15146A207
References
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Download: ML14307B005 (27)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Exam: 08/25/2014 RO Category K/ A Points SRO Only Points Tier Group K

K K

K K

K A

A A

A G

Total A2 G

Total l

2 3

4 5

6 I

2 3

4 I. Emergency &

1 3

3 3

3 3

3 18 3

3 6

Abnormal Plant 2

I 2

1 N/A I

2 NIA 2

9 2

2 4

Evolutions Tier Totals 4

5 4

4 5

5 27 5

5 10 1

3 2

3 3

2 2

3 3

2 2

3 28 3

2 5

2. Plant Systems 2

1 I

1 1

1 1

l 0

1 I

1 10 0

2 I

3 Tier Totals 4

3 4

4 3

3 4

3 3

3 4

38 5

3 8

1 2

3 4

1 2

3 4

3. Generic Knowledge & Abilities Categories 10 7

2 3

3 2

2 2

1 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).

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.l.b of ES-40 1 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 a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/ A categories.

7.*

The generic (G) K/ As in Tiers I and 2 shall be selected from Section 2 of the K/ A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-40 I for the applicable K/ 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 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 K/ A catalog, and enter the K/ A numbers, descriptions, IRs, and point totals

(#)on Form ES-40 1-3. Limit SRO selections to K/ As that are linked to I 0 CFR 55.43.

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions-Tier 1 I Group 1 -REACTOR OPERA TOR E/APE #/Name/Safety Function K

K K

A A

G KA Topic Imp Pts 1

2 3

1 2

EK3 - Knowledge of the reasons for the 007 Reactor Trip - Stabilization -

X following as they apply to the reactor trip:

4.0 1

Recovery I 1 EK3.01-Actions contained in EOP for reactor trip AK2 - Knowledge of the interrelations 008 Pressurizer Vapor Space Accident X

between the Pressurizer Vapor Space 2.5 1

13 I

Accident and the following:

AK2.03-Controllers and positioners EA2 - Ability to determine or interpret the 009 Small Break LOCA I 3 X

following as they apply to a Small Break 3.4 I

LOCA:

EA2.13 -Charging pump flow indication EK3 - Knowledge of the reasons for the following responses as they apply to the 011 Large Break LOCA I 3 X

Large Break LOCA:

4.2 1

EK3.09-Maintaining DIG's available to provide standby power AKl-Knowledge of the operational implications of the following concepts as 000015/000017 RCP Malfunctions I 4 they apply to Reactor Coolant Pump X

Malfunctions (Loss of RC Flow):

2.9 I

AK 1.04 - Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow 2.1 -Conduct of Operations 025 Loss ofRHR System I 4 X

2.1.20- Ability to interpret and execute 4.6 1

procedure steps.

AAl-Ability to operate and I or monitor the following as they apply to the Loss of 026 Loss of Component Cooling X

Component Cooling Water:

2.9 1

Water I 8 AA 1.07 - Flow rates to the components and systems that are serviced by the CCWS; interactions among the components.

AKl - Knowledge of the operational implications of the following concepts as 027 Pressurizer Pressure Control X

they apply to Pressurizer Pressure Control 2.8 I

System Malfunction I 3 Malfunctions:

AK 1.02 -Expansion of liquids as temperature increases EK2-Knowledge of the interrelations 029 ATWS I 1 X

between the and the following an A TWS:

2.9*

I EK2.06 - Breakers, relays, and disconnects EA2 - Ability to determine or interpret the 038 Steam Gen. Tube Rupture I 3 X

following as they apply to a SGTR:

3.7*

1 EA2.ll -Local radiation readings on main steam lines

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group I - REACTOR OPERA TOR E/APE #!Name/Safety Function K

K K

A A

G KA Topic Imp Pts 1

2 3

1 2

AK3 - Knowledge of the reasons for the

' following responses as they apply to the 054 Loss of Main Feedwater I 4 X

Loss of Main Feedwater (MFW):

4.6 1

AK3.05 - HPIIPORV cycling upon total

• '~*"'

feedwater loss EA2 - Ability to determine or interpret the following as they apply to a Station 055 Station Blackout I 6 X

Blackout:

3.4 1

EA2.0 1 - Existing valve positioning on a loss of instrument air system 2.2 - Equipment Control 056 Loss of Off-site Power I 6 X

2.2.3 - Knowledge of the design, procedural, 3.8 1

and operational differences between units.

2.1 -Conduct of Operations 057 Loss of Vital AC In st. Bus I 6 X

2.1.28 - Knowledge ofthe purpose and 4.1 I

function of major system components and controls.

AK 1 - Knowledge of the operational implications of the following concepts as 058 Loss of DC Power I 6 X

they apply to Loss of DC Power:

2.8 I

AK 1.01 -Battery charger equipment and instrumentation AAl-Ability to operate and I or monitor 065 Loss of Instrument Air I 8 X

the following as they apply to the Loss of 2.7*

1 Instrument Air:

AA 1.01-Remote Manual Loaders AAl -Ability to operate and/or monitor 077 Generator Voltage and Electric X

the following as they apply to Generator 3.8 1

Grid Disturbances I 6 Voltage and Electric Grid Disturbances:

AA 1.02 - Turbine I generator controls EK2 - Knowledge of the interrelations between the (Excess Steam Demand) and the following:

CEIE05 Steam Line Rupture-X EK2.2 - Facility's heat removal systems, 3.7 1

Excessive Heat Transfer I 4 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.

I KIA Category Totals:

3 3

3 3

3 3

Group Point Total:

1s 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions-Tier 1 I Group 2 - REACTOR OPERA TOR E/APE #/Name/Safety Function K

K K

A A

G KA Topic Imp Pts 1

2 3

1 2

AK2 - Knowledge of the interrelations between the Loss of Source Range 032 Loss of Source Range Nl I 7 X

Nuclear Instrumentation and the following:

2.7*

I AK2.0 I -Power supplies, including proper switch positions AK1 -Knowledge of the operational implications of the following concepts as 036 Fuel Handling Accident I 8 X

they apply to Fuel Handling Incidents :

3.4 1

AKI.02-SDM AA2 - Ability to determine and interpret 060 Accidental Gaseous RadWaste the following as they apply to the Rei. I 9 X

Accidental Gaseous Radwaste:

3.6*

I AA2.06-Valve lineup for release of radioactive gases 2.1 - Conduct of Operations 061 ARM System Alarms I 7 X

2.1.27-Knowledge of system purpose 3.9 I

and/or function AA2 - Ability to determine and interpret the following as they apply to the Plant 067 Plant Fire On-site I 9 X,,,

Fire on Site:

3.1 I

AA2.04-The fire's extent of potential operational damage to plant equipment AK2 - Knowledge of the interrelations 068 Control Room Evac. / 8 between the Control Room Evacuation X

and the following:

3.3 I

• AK2.07-ED/G 2.4-Emergency Procedures I Plan 069 Loss of CTMT Integrity I 5 X

2.4.41-Knowledge of the emergency action 2.9 I

level thresholds and classifications AAl -Ability to operate and I or monitor 076 High Reactor Coolant Activity I 9 X

the following as they apply to the High 3.2 I

Reactor Coolant Activity:

AA I.04-Failed fuel-monitoring equipment AK3 - Knowledge of the reasons for the following responses as they apply to the CEIA II RCS Overcooling-PTS I 4 X

(RCS Overcooling)

AK3.3 - Manipulation of controls required to 3.1 l

obtain desired operating results during abnormal, and emergency situations KIA Category Totals:

1 2

1 1

2 2

Group Point Total:

9 I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 -REACTOR OPERA TOR System/Evolution #/Name K

K K

K K

K A

A A

A G

KATopic Imp Pts 1

2 3

4 5

6 1

2 3

4 K4 - Knowledge of RCPS design feature(s) and/or interlock(s) which provide for 2.8 003 Reactor Coolant Pump X

the following:

I K4.04-Adequate cooling ofRCP

. motor and seals

'. 2.2 - Equipment Control 003 Reactor Coolant Pump x* 2.2.12 - Knowledge of surveillance 3.7 1

procedures K6 - Knowledge of the effect of a loss or malfunction on the 004 Chemical and Volume X

). : following eves components:

3.8 1

Control

'*>: K6.26-Methods of pressure control of solid plant (PZR relief and water inventory)

A4-Ability to manually operate and/or monitor in the 004 Chemical and Volume X

control room:

3.5 1

Control

'; -i A4.09-PZR spray and heater

'i controls I

2.4 1 -Emergency Procedures I 005 Residual Heat Removal Plan

~

3.7 1

2.4.3-Ability to identify F**

!post-accident instrumentation KS - Knowledge of the operational implications of the 005 Residual Heat Removal X

I

. following concepts as they 2.9*

1

apply the RHRS:

K5.03-Reactivity effects ofRHR fill water A2-Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those 006 Emergency Core Cooling X

predictions, use procedures to 3.9 I

correct, control, or mitigate the consequences of those malfunctions or operations:

A2.13 -Inadvertent SIS actuation KS - Knowledge of the operational implications of the 007 Pressurizer Relief/Quench X

following concepts as the apply 3.1 I

Tank to PRTS:

K5.02-Method of forming a steam bubble in the PZR

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 - REACTOR OPERA TOR K

K K

K K

K A

A A

A System/Evolution #/Name 1

2 3

4 5

6 1

2, 3 4

G KA Topic Imp Pts

• • ..

• 2.4-Emergency Procedures I

(")(;

Plan 008 Component Cooling Water 3.7 1

2.4.6-Knowledge of EOP mitigation strategies.

;y Al - Ability to predict and/or

,. ~

,, /

'!\\ monitor changes in parameters 008 Component Cooling Water X

'; :*~~

(to prevent exceeding design 3.1 1

limits) associated with operating 1;::;:

the CCWS controls including:

y I~.. *~

A 1.04-Surge tank level

1' K3 - Knowledge of the effect that a loss or malfunction of the PZR 0 I 0 Pressurizer Pressure Control X

PCS will have on the following:

3.8 1

• *.~ > i K3.01-RCS

• "?'!:

..* iv; A3 -Ability to monitor 01 0 Pressurizer Pressure Control X

1.*.1

>_; automatic operation of the PZR 3.6 1

PCS, including:

~

lj &ji.*. A3.02-PZR pressure

~

K4 - Knowledge of RPS design feature(s) and/or interlock(s) 012 Reactor Protection X

• • • -~

which provide for the following:

2.8*

1 X

l:t~ K4.08 -Logic matrix testing

\\

1.¥ K6 - Knowledge of the effect of a

-~ *;

loss or malfunction on the 013 Engineered Safety Features X

I :,

following will have on the 2.7*

I Actuation (ESF AS)

ESFAS:

K6.0 1 - Sensors and detectors

.:t:~ A3-Ability to monitor automatic 022 Containment Cooling X

operation of the CCS, including:

4.1 I

A3.01-Initiation of safeguards mode of operation

~****.. ";.

IJIT:

AI - Ability to monitor automatic 022 Containment Cooling X

operation of the CCS, including:

3.6 1

.*i A 1.02 - Containment pressure I> ;*

Kl - Knowledge of the physical connections and/or cause-effect 026 Containment Spray X

relationships between the CSS 4.1 I

and the following systems:

K1.02-Cooling water Kl - Knowledge of the physical connections and/or cause-effect 039 Main and Reheat Steam X

relationships between the MRSS 3.3 I

and the following systems:

K 1.02-Atmospheric relief dump valves II System/Evolution #/Name K

K K

K K

K A

A A

A G

KA Topic Imp Pts J

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 -REACTOR OPERA TOR I

I 1 I 2 I 3 I 4 I 5 I 6 I 1 I 2 ! 3 I 4 b I I

I I Al - Ability to predict and/or monitor changes in parameters

':, r (to prevent exceeding design 059 Main Feedwater X

limits) associated with operating 2.7*

I

• • *~,, the MFW controls including:

},~)l' A 1.03 -Power level restrictions for

. X;:

operation ofMFW pumps and i*'

,*!~*: valves t.i;;':

~:~~;

K4 - Knowledge of AFW design feature(s) and/or interlock(s) 061 Auxiliary /Emergency X

d+,'4 which provide for the following:

2.7 I

Feedwater

>,. ~* '

l:j!

I~

K4.13-Initiation of cooling water I~J. and lube oil

. / '.:

l'£z,.n K3-Knowledge of the effect that

~J~tt a loss or malfunction of the ac 1

, t:;.

062 AC Electrical Distribution X

distribution system will have on 4.1 I

c'""'

{ t

~~

the following:

K3.02-ED/G 1;~\\~

2i'~" A3 - Ability to monitor

>

• automatic operation of the DC 063 DC Electrical Distribution X

~g electrical system, including:

2.7 A3.01 -Meters, annunciators, I

d dials, recorders, and indicating

['it::, lights 064 Emergency Diesel

~. {.

\\~'

K2 - Knowledge of bus power X

supplies to the following:

2.8*

I Generator

~: :

! K2.02-Fuel oil pumps Jt~~

A4 - Ability to manually operate 073 Process Radiation and/or monitor in the control Monitoring X

r}~;~ room:

3.9 I

,; \\'

b'.< ): A4.01 -Effluent release

-v,.

A2-Ability to (a) predict the i'q impacts of the following li, 1:,'"' malfunctions or operations on the 073 Process Radiation I:'>. PRM system; and (b) based on Monitoring X

i'Yv those predictions, use procedures 2.7 I

to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02-Detector failure c;:c K1 -Knowledge of the physical connections and/or cause-effect 076 Service Water X

relationships between the SWS 3.8*

I and the following systems:

K1.05-DIG

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 - REACTOR OPERA TOR c

K K

K K

K K

A.A A

A System/Evolution #/Name 1

2 3

4 5

6 1

2 3

4,G KA Topic Imp Pts

~'

K2 - Knowledge bus power 078 Instrument Air X

• .L,, supplies to the following:

3.3*

I K2.02 - Emergency Air compressor

.,::. K3 - Knowledge of the effect that a loss or malfunction of the I 03 Containment X

y *'*

containment system will have on 3.8 I

the following:

I*

K3.02-Loss of containment I*;~ integrity under normal operations I

KIA Category Totals:

3 2

3 3

2 2

3 I

3 2 r}~~F:I Group Point Total:

281

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 2-REACTOR OPERATOR System/Evolution #/Name K

K K

K K

K A A A A

G KA Topic Imp Pts 1

2 3

4 5

6 1.. 2~ 3 4

• ~*..... :

K1 - Knowledge of the physical connections and/or cause-effect 001 Control Rod Drive X

If: ;

. relationships between the CRDS 4.5 I

!1. ;*.

i': ";

and the following systems:

I~* \\

i**~} Kl.05 - NIS and RPS

• • '*}. AI - Ability to predict and/or monitor changes in parameters 002-RCS X f

~-~.

... (to prevent exceeding design 4.0 l

I~

~,N limits) associated with operating

~*~

the RCS controls including:

A 1.05 - RCS flow It*'**

,tj l;;;;s;: K6 - Knowledge of the effect of a

..* loss or malfunction on the 011 Pressurizer Level Control

>S" following will have on the PZR System X

1>;,

LCS:

3.1 I

r\\*~,

1!,:

K6.04-Operation of PZR level controllers r":-

K2 - Knowledge of bus power 027 Containment Iodine X

supplies to the following:

3.1

• I Removal i'* * :.c

.... K2.01-Fans

!i'f KS - Knowledge of the operational implications of the 028 Hydrogen Recombiner and X

I,,

following concepts as they apply 3.4 I

Purge Control

~~i to the HRPS:

!'~i::*

K5.02-Flammable hydrogen concentration

YC~'

A3-Ability to monitor automatic operation of the 029 Containment Purge X

Containment Purge System 3.8 I

f, including:

tc*~<

A3.01-CPS isolation

~,;,.

2.4-Emergency Procedures I Plan 035 Steam Generator System X

2.4.45-Ability to prioritize and 4.1 I

interpret the significance of each annunciator alarm K3 - Knowledge of the effect 041 Steam Dump/Turbine X

that a loss or malfunction of the Bypass Control

~

SDS will have on the following:

3.8 I

K3.02-RCS K4-Knowledge of MT/G system design feature(s) and/or interlock (s) which provide for 045 Main Turbine Generator X

the following:

2.7 1

K4.0 I - Programmed controller for relationship between steam pressure at T/G inlet (impulse, first stage) and plant power level

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 2 - REACTOR OPERA TOR System/Evolution #/Name K

K K

K K

K A

.. :\\*.** A A

G KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 :*. '*

A4 - Ability to manually operate and/or monitor in the control 068 Liquid Radwaste X

>:' K 't room:

3.2*

I A4.02-Remote radwaste release KIA Category Totals:

I I

1 1

1 1

1 t,.:~z::i 1 1

Group Point Total:

10 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions -Tier 1 I Group 1 - Senior Reactor Operator E/ APE #/Name/Safety Function 022 Loss of Rx Coolant Makeup 12 040 Steam Line Rupture -

Excessive Heat Transfer I 4

055 Station Blackout 16 062 Loss of Nuclear Service Water I 4 CE/E02 Reactor Trip -

Stabilization - Recovery I I

CEIE06 Loss of Feedwater I 4 KIA Category Totals:

K K

K A

1 2

3 1

0 0

0 0

KA Topic AA2 - Ability to determine and interpret the following as they apply to the Loss of Imp Pts Reactor Coolant Makeup:

3.6 AA2.03-Failures of flow control valve or controller 2.4 - Emergency Procedures I Plan:

2.4.1 - Knowledge of EOP entry conditions and immediate action steps.

2.1 - Conduct of Operations:

2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

, AA2 - Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:

AA2.03-The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 2.4 - Emergency Procedures I Plan:

2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

EA2 - Ability to determine and interpret the following as they apply to the (Loss of Feedwater):

EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations Group Point Total:

4.8 4.4 2.9 4.1 3.9 6

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group 2 - Senior Reactor Operator E/APE #/Name/Safety Kl K2 K3 AI A2 G

KA Topic Imp Pts Function AA2 -Ability to determine and interpret the following as they apply to 003 Dropped Control x*

' ; the Dropped Control Rod:

3.8 1

Rod I 1 AA2.03 - Dropped rod, using in-core/

I:", ~-

~,,

ex-core instrumentation, in-core or loop I;\\'-

• F r/

temperature measurements.

024 Emergency

. ' 2.2-Equipment Control:

k 4.7 1

Boration I 1 IL*' ;.,I.X; 2.2.40- apply Technical Specifications for a system.

1',....... '

i;.. '" l'i,;,,

AA2 - Ability to determine and i

interpret the following as they apply to 037 Steam Generator

.. 'X

'~ '.; -

the Steam Generator Tube Leak:

4.3 I

Tube Leak I 3

1:

AA2.16 - Pressure at which to maintain

.,... ' y

' RCS during S/G cooldown.

2.4-Emergency Procedures I Plan:

.c.*.

2.4.21 -Knowledge ofthe parameters and CEIE09 Functional tx logic used to assess the status of safety Recovery functions, such as reactivity control, core 4.6 1

' cooling and heat removal, reactor coolant

** X* system integrity, containment conditions, radioactivity release control, etc.

'V ;

KIA Category Totals:

0 0

0 0

• iFz*~,':~

Group Point Total:

4 I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems-Tier 2 I Group 1 - Senior Reactor Operator System/Evolution #/Name K

K K

K K

K A

A A

A G

KA Topic Imp Pts 1

2 3

4 5

6 1,2 3

4 A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those i: -

predictions, use procedures to

',-\\

correct, control, or mitigate the

~-- ----

consequences of those

X malfunctions or operations:

3.9 I

026 Containment Spray A2.07 - Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit.

A2-Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on those 039 Main Steam and Reheat

)(

predictions, use procedures to correct, control, or mitigate the 3.7 I

(MRSS) consequences of those malfunctions or operations:

}:

},',,;

A2.03 - Indications and alarms for

'" \\ *-

main steam and area radiation monitors (during SGTR)

• c 2.4 - Emergency Procedures I 061 Auxiliary/Emergency Plan

x 4.7 I

Feed water 2.4.6-Knowledge of EOP mitigation strategies.

2.4 - Emergency Procedures I 064 Emergency Diesel Plan X

4.6 I

Generator (ED/G) 2.4.41 - Knowledge of the EAL thresholds and classifications.

A2-Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; and (b) based on those 078 Instrument Air (lAS)

X predictions, use procedures to 2.9 1

correct, control, or mitigate the consequences of those malfunctions or operations:

A2.0 I - Air dryer and filter malfunctions KIA Category Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 I Group 2 - Senior Reactor Operator System/Evolution #/Name K

K K

K K

K A

A A

A G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 2.1 -Conduct of Operations 2.1. 7 - Ability to evaluate plant 015 Nuclear Instrumentation X

performance and make operational 4.7 1

(NIS) judgments based on operating i characteristics, reactor behavior, i

and instrument interpretation.

A2-Ability to (a) predict the impacts of the following

' malfunctions or operations on the Condensate System; and (b) 056-Condensate System X

based on those 2.5*

1 predictions or mitigate the consequences of those malfunctions or operations:

A2.05-Condenser Tube Leakage i

A2 -Ability to (a) predict the impacts of the following malfunctions or operations on the 072 Area Radiation Monitoring ARM; and (b) based on those X,

predictions or mitigate the 2.9 I

(ARM) consequences of those malfunctions or operations:

A2.01 -Erratic or failed power supply o I c,

KIA Category Totals:

1 0

0 0

0 0

2 0

0 1

Group Point Total:

3 I

ES-401 PWR Examination Outline Form ES-401-3 Tier 3 Generic Knowledge & Abilities Outline - RO & SRO II Facility: Calvert Cliffs Nuclear Power Plant Date of Exam: 08/25/2014 RO SRO Category KIA#

Topic JR IR 2.1.8 Ability to coordinate personnel activities outside the control room.

3.4 1

2.1.41 Knowledge of the refueling process.

2.8 1

Conduct 2.1.40 Knowledge of refueling administrative requirements.

', 'f \\;, '",-

3.9 1

of Operations Ability to use procedures related to shift staffing, such as minimum

[' L,, ':

2.1.5 3.9 I

crew complement, overtime limitations, etc.

Subtotal f <,

2 2

2.2.12 Knowledge of surveillance procedures.

3.7 I

2.2.13 Knowledge of safety and tagging clearance procedures.

4.1 1

1,:

2.2.14 Knowledge of the process for controlling equipment configuration or 3.9 1

~

status.

Equipment Control Knowledge of the process for managing maintenance activities during 2.2.17 power operations, such as risk assessments, work prioritization, and 3.8 1

coordination with the transmission system operator.

Jc c~"- ' >

2.2.35 Ability to determine Technical Specification Mode of Operation 4.5 1

,~, :;

c Subtotal 3

2 v

2.3.4 Knowledge of radiation exposure limits under normal or emergency 3.2 1

conditions.

2.3.7 Ability to comply with radiation work permit requirements during 3.5 1

normal or abnormal conditions.

Radiation Control 2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.4 I

/.:;

normal, abnormal, or emergency conditions or activities Knowledge of radiation monitoring systems, such as fixed radiation 2.3.15 monitors and alarms, portable survey instruments, personnel monitoring 3.1 1

equipment, etc.

Subtotal 3

1 2.4.11 Knowledge of abnormal condition procedures.

4.0 1

2.4.25 Knowledge of fire protection procedures.

3.3 1

Emergency Knowledge of events related to system operation/status that must be Procedures/Plan 2.4.30 reported to internal organizations or external agencies, such as the State, 4.1 1

the NRC, or the transmission system operator 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation 4.5 1

Subtotal 2

2 I

Tier 3 Total(s)

I I 10 I I 7 I

ES-401 Record of Rejected K/As Form ES-401-4 Tier/Group Randomly Selected Kl A Reason for Rejection 025 - Loss of RHR System ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers ROlli 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.1.2 2.1.20, which was randomly drawn, using numbered poker chips.

056 Loss of Off-site Power ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers ROlli 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with 2.2.3, KIA 2.2.17 which was randomly drawn, using numbered poker chips.

057 Loss of Vital AC Inst. Bus ES-40 I contains guidance, in the form of a list, on generic Kl As for use with Tiers ROlli 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.1.2 2.1.28, which was randomly drawn, using numbered poker chips.

ROl/1 OJ I Large Break LOCA Feedwater isolation not performed on Large Break LOCA at CCNPP. Replaced EK3.02 with EK3.09, which was randomly drawn, using numbered poker chips.

061 ARM System Alarms ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers RO 1/2 1 & 2. The randomly selected Kl A is not on the ES-40 1 list. Replaced with KIA 2.1.14 2.1.27, which was randomly drawn, using numbered poker chips.

RO 112 CEIAll RCS Overcooling NKEG (Westinghouse) Random Sample Generator selected EK3.3 instead of AK3.3 for this APE. Changed K/ A to AK3.3 RO 112 067 Plant Fire On-Site Per discussion with NRC Chief Examiner changed K/ A from AA2.14 to AA2.04 RO 211 003 Reactor Coolant Pump There are no isolation valve interlocks for RCP's at CCNPP. Replaced with K4.11 K4.04, which was randomly drawn, using numbered poker chips.

004 Chemical and Volume CCNPP does not have a Boronometer chart recorder. Replaced with A4.09, RO 211 Control A4.22 which was randomly drawn, using numbered poker chips.

006 Emergency Core Cooling CCNPP ECCS piping is not heat traced due to the low BA concentration in the RO 211 RWT. Replaced with A2.13, which was randomly drawn, using numbered A2.07 poker chips.

008 Component Cooling System There are no setpoints, interlocks, or automatic action associated with EOP entry RO 211 conditions for CCW at CCNPP. Replaced with 2.4.6, which was randomly KIA 2.4.2 drawn, using numbered poker chips.

There are no procedure directed mitigating operator actions for grounds on a DC RO 211 063 DC Electrical Distribution Bus. The remaining A2 has an importance rating of< 2.5. Replaced with A3.01, which was randomly drawn, using numbered poker chips.

RO 211 076 Service Water Per discussion with NRC Chief Examiner changed Kl A from K I.08 to K 1.05 071-Waste Gas Disposal Waste Gas related subject matter already covered by several other KIAs (TJ/G2, R0212 Sys 060 & T2/G I, Sys 73). Replaced with previously unsampled System 002-A1.06 RCS, Al.OS, which was randomly drawn, using numbered poker chips.

001 Control Rod Drive System There is no physical connection between Component Cooling Water and Control RO 212 Rod Drive System at CCNPP. Replaced with Kl.OS which was randomly drawn, Kl.OJ using poker chips.

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/Group Randomly Selected KIA Reason for Rejection 011-Pressurizer Level Control A loss of the function of Pressurizer level gauges as post-accident monitoring RO 212 System instrumentation has no effect on the pressurizer level control system. Replaced K6.05 with K6.04, which was randomly drawn, using numbered poker chips.

040 - Steam Line Rupture-ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 111 Excessive Heat Transfer I & 2. The randomly selected KIA is not on the ES-401 list. Replaced with 2.4.1, KIA2.3.11 which was randomly drawn, using numbered poker chips.

055 -Station Blackout ES-40 I contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 111 I & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.1.34 2.1.23, which was randomly drawn, using numbered poker chips.

CE/E02 - Reactor Trip-ES-40 I contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 111 Stabilization/Recovery 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.3.15 2.4.31, which was randomly drawn, using numbered poker chips.

024 - Emergency Boration ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 112 I & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.2.35 2.2.40, which was randomly drawn, using numbered poker chips.

CEIE09 Functional Recovery ES-40 1 contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 112 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with KIA 2.3.4 2.4.21, which was randomly drawn, using numbered poker chips.

061 Auxiliary/Emergency ES-401 contains guidance, in the form of a list, on generic Kl As for use with Tiers SRO 211 Feed water 1 & 2. The randomly selected KIA is not on the ES-401 list. Replaced with 2.4.6, KIA 2.4.44 which was randomly drawn, using numbered poker chips.

026 Containment Spray There are no consequences to the CSS associated with the potential radiation SRO 211 hazard presented by the RWT. Kept same system and replaced with A2.07, A2.09 which was randomly drawn, using numbered poker chips.

017 In Core Temperature Spent several hours trying to write an SRO Only question for this Kl A and was SRO 2/2 Monitor (ITM) unable to do so. Replaced System with 056 Condensate System and Kl A with A2.05 which were randomly drawn, using numbered poker chips.

SRO Generic 2.1.44 The randomly selected Kl A is specific to RO responsibilities. Replaced with 2.1.5 which was randomly drawn, using numbered poker chips.

The randomly selected K/ A duplicates that previously selected as the basis for one SRO Generic 2.3.6 of the JPMs. Additionally, four of the nine available KIAs in section 2.3 have been sampled elsewhere in the written exam. Replaced with 2.4.30 which was randomly drawn, using numbered poker chips.

Spent several hours trying to write an SRO Only question for this Kl A and was SRO Generic 2.4.18 unable to do so. Replaced with 2.4.40 which was randomly drawn, using numbered poker chips.

ES-401 Record of Rejected K/ As Form ES-401-4 27 total Kl A changes:

10 procedurally driven by ES-40 1

• 2 due to discussion with NRC after NRC review

• 2 due to software sampling errors

• 9 due to not being applicable at CCNPP

• 2 due to inability to write question after hours trying 1 due to oversampling of a system

• 1 due to duplication with selected JPM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8125114 thru 915114 Exam Level: RO I SR0-1 I SRO-U Operating Test#: 2014 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations M,R Ensure adequate shutdown margin exists in Mode 3 (RO Admin-1)

Conduct of Operations P,R Monitor Azimuthal Power Tilt (Tq) using Excore (RO Admin-2)

Nuclear Instrumentation Equipment Control D,R Apply Tech Specs to a relay failure (RO Admin-3)

Radiation Control Determine Radiological Controls associated with (RO Admin-4)

M,R manipulating a valve in the RCA Emergency Procedures I Plan (RO Admin-5)

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: Calvert Cliffs Nuclear Power Plant Date of Examination: 8125114 thru 915114 Exam Level: RO I SR0-1 I SRO-U Operating Test#: 2014 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Conduct of Operations M,R Ensure adequate shutdown margin exists in Mode 3 (SRO-ADMIN-1)

Conduct of Operations D,P,R Ability to implement plant procedures for a Condenser Tube Leak (SRO-ADMIN-2)

Equipment Control D,R Apply Tech Specs to a relay failure (SRO-ADMIN-3)

Radiation Control (SRO-ADMIN-4)

M,R Approve a Liquid Waste Discharge Permit Emergency Procedures I Plan M,R Determine appropriate Emergency Response Actions (SRO-ADMIN-5)

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: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/25/14 thru 9/5/14 Exam Level: RO I SRO-I I SRO-U Operating Test#: 2014 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Conduct of Operations M,R Ensure adequate shutdown margin exists in Mode 3 (SRO-ADMIN-1)

Conduct of Operations D,P,R Ability to implement plant procedures for a Condenser Tube (SRO-ADMIN-2)

Leak Equipment Control D,R Apply Tech Specs to a relay failure (SRO-ADMIN-3)

Radiation Control (SRO-ADMIN-4)

M,R Approve a Liquid Waste Discharge Permit Emergency Procedures I Plan M,R Determine appropriate Emergency Response Actions (SRO-ADMIN-5)

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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/25/14 thru 9/5/14 Exam Level: RO I SR0-1 I SRO-U Operating Test#: 2014 Control Room Systems: (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. SIM-1 Align a LPSI Pump for Core Flush via Hot Leg Injection A,D,EN, S 2

b.SIM-2 Respond to CEA(s) Misaligned by 15 Inches or More A,D,P,S 1

c. SIM-3 Attempt to Correct the Abnormal SDC Condition A,D,L,S 4 (P)

d. SIM-4 Respond to a Failure of a Pump with Reactor Power< 5%

A,D,L,S 4 (S)

e. SIM-5 Bleed and Feed to Cool the Quench Tank D, S 5

f. SIM-6 Verify the Vital Auxiliaries Safety Function is Satisfied A,D,S 6

g.SIM-7 Shifting Component Cooling Heat Exchangers D,S 8

h. SIM-8 Test Gaseous Waste Discharge RMS Channel RI-2191 N,S 9

I In-Plant SystemsC<il (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

a. PLT-1 Align the Reserve Battery to 11 DC Bus N

6 b.PLT-2 Isolate Fire Effects for 11 Cavity Cooling Fan Damper E,N,R 7

c. PLT-3 Instrument Air System Operation Using Fire Main for Compressor Cooling D,L 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all5 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 SR0-1 I SRO-U (A)ltemate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

o;91:o;81:o;4 (E)mergency or abnormal in-plant

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

- I - I

~1 (control room system)

(L)ow-Power I Shutdown

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

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

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

(R)CA

~11~11~1 (S)imulator

ES-301 Control Room/In-Plant Systems OuWne Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/25/14 thru 9/5/14 Exam Level: RO I SR0-1 I SRO-U Operating Test#: 2014 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. SIM-1 Align a LPSI Pump for Core Flush via Hot Leg Injection A,D,EN,S 2

b.SIM-2 Respond to CEA(s) Misaligned by 15 inches or more A,D,P,S 1

c. SIM-3 Attempt to Correct the Abnormal SDC Condition A,D,L,S 4 (P)

d. SIM-4 Respond to a Failure of a Pump with Reactor Power< 5%

A,D,L,S 4 (S)

e. SIM-5 Bleed and feed to cool the Quench Tank D,S 5

f. SIM-6 Verify the Vital Auxiliaries Safety Function is Satisfied A,D,S 6

g.SIM-7 Shifting Component Cooling Heat Exchangers D,S 8

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

a. PLT-1 Align the Reserve Battery to 11 DC Bus N

6 b.PLT-2 Isolate Fire Effects for 11 Cavity Cooling Fan Damper E,N,R 7

c. PLT-3 Instrument Air System operation using Fire Main for Compressor Cooling D,L 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I SR0-1 I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank s91s81s4 (E)mergency or abnormal in-plant

2:11:2:11:2:1 (EN)gineered safety feature

- I - I :2:1 (control room system)

(L)ow-Power I Shutdown

2:1/:2:1/:2:1 (N)ew or (M)odified from bank including 1(A)

2:21:2:21:2:1 (P)revious 2 exams s 3 Is 3 Is 2 (randomly selected)

(R)CA

2:1/:2:11:2:1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/25/14 thru 915114 Exam Level: RO I SRO-I I SRO-U Operating Test#: 2014 Control Room Systems<<~ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. SIM-I Align a LPSI Pump for Core Flush via Hot Leg Injection A,D,EN, S 2

b. SIM-3 Attempt to Correct the Abnormal SDC Condition A,D,L,S 4 (P)

c. SIM-7 Shifting Component Cooling Heat Exchangers D,S 8

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

a. PLT-1 Align the Reserve Battery to 11 DC Bus N

6

a. PLT-2 Isolate Fire Effects for 11 Cavity Cooling Fan Damper & Restore E,N,R 7

Switchgear Room Ventilation All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all5 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)ltemate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

~91~81~4 (E)mergency or abnormal in-plant

?:11?:11?:1 (EN)gineered safety feature

- I - I ?:1 (control room system)

(L)ow-Power I Shutdown

?:11?:1/?:1 (N)ew or (M)odified from bank including l(A)

?:21?:21?:1 (P)revious 2 exams

~ 3 I~ 3 I~ 2 (randomly selected)

(R)CA

?:11?:11?:1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 1 OP-Test#: CCNPP 2014 Examiners:

Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is in Mode 1.

Turnover: 12 MSL and N-16 Monitors, 12 AFW Pump, and the 1B DG are OOS. The OC DG is aligned to 14 4KV Bus per OI-21B. 11 Charging Pump is the lead pump. Instructions for the crew are to maintain power at 100%

Event#

Malfunction #

Event Type*

Event Description 1

152-1206 C-BOP/SRO 11 Heater Drain Pump trip R-ATC 2

rcs026 01 I-ATC 1-LT-110X (selected channel) fails LOW T-SRO 3

srw002 02 C-ALL 12 SRW Header leak in Turbine Bldg 4

fw006 02 C-BOP/SRO 12 MFRV fails as is (mechanical binding) 5 ceds010 19 C-ATC CEAs 19 and 32 fail to insert on Reactor trip. (Boration ceds010 32 using normal path) 6 swyd002 M-ALL Complete Loss of Offsite Power C-BOP/SRO 7

dg002_02 1A DG Start Failure T-SRO (N)ormal (R )eactivity (I)nstrument ( C)omponent (M)ajor (T)ech Spec Critical Tasks: (shaded)

1. Notes two CEAs failed to insert, commences RCS boration before exit ofEOP-0.

2. Notes excessive Feed Flow, secures main feed & initiate auxiliary feed before exit ofEOP-0

3. Reenergizes a 4kV Bus with the OC DIG prior to 125 VDC voltage< 106V.

Page 1 of21

Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 2 OP-Test #: CCNPP 2014 I Examiners:

Operators:

Initial Conditions: Unit-1 is at 100% power, EOC. Unit-2 is in Mode 5.

Turnover: 13 Cond Booster Pump is tagged out for inspection of high vibrations (expect back at end of shift), 12 AFW Pump OOS for governor work (out for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, back in in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) Instructions for the crew are to maintain power at 100%

Event Malfunction #

Event Type*

Event Description R-ATC Call from ESO to reduce load to 800 MWE 1

Rapid Downpower in <15 min N-BOP/SRO C-All 2

120v003 01 Loss of1Y01 T-SRO ms018 04 C-BOP/SRO S/G Level LT-1114-D variable leg leak in 3

ms010 01 T-SRO containment 4

ms010 01 M-All Steam line break in containment I Reactor Trip esfa004 01 CSAS A&B Automatic Failure 5

esfa004 02 I -All SGIS Automatic Actuation Failure esfa012 6

Emergency Airlock T-SRO Containment Integrity breached (N)ormal (R)eactivity (I)nstrument ( C)omponent (M)ajor (T)ech Spec Critical Tasks: (shaded)

1. Trips all RCP's within 10 minutes of CIS actuation (no CC flow to RCP's).

2. Determines CSAS failure and manually actuates CSAS prior to exiting EOP-0.

3. Identifies and isolates 11 S/G prior to RCS subcooling exceeding 140°F.

Appendix D Scenario Outline Form ES-D-1 Facility: Calvert Cliffs Nuclear Power Plant Scenario #: 4 OP-Test #: CCNPP 2014 Examiners:

Operators:

Initial Conditions: Unit-1 is at 100% power, MOC. Unit-2 is at 100% power.

Turnover: 12 CS Pump OOS for last hour for pump coupling Inspection (back in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).

11 BA Pump OOS for last 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (bearing seized) (back in 1 day). 23 Aux Feed Pump is OOS for motor bearing repair and is expected back in 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

Event#

Malfunction #

Event Type*

Event Description 1

480v002 01 C-ALL Loss ofMCC-104 (AOP-7I)

T-SRO C-BOP/SRO 2

ms002 01 R-ATC 11 S/G Tube Leak (AOP-2A)

T-SRO 3

ms010 01 M-ALL 11 S/G MSLB in Cntmt (EOP-8) 4 esfa010 01 C-BOP CIS "A" and "B" Failure esfa010 02 5

1-SI-428@

C-ATC/SRO 11 HPSI Discharge valve 12% open 12%

(N)ormal (R)eactivity (I)nstrument

( C)omponent (M)ajor (T)ech Spec Critical Tasks: (shaded)

1. Recognizes failure of CIS "A" and CIS "B". Manually actuates CIS "A" and CIS "B" (prior to exiting EOP-0).

2. Trips all RCP's after CIS actuates and within 10 minutes of Component Cooling isolation to Containment.

3. Notes insufficient flow from 11 HPSI pump and starts 12 HPSI pump prior to RVLMS 3rd light lit Page 1 of21