ML102670392

Draft - Outlines (Folder 2)

ML102670392
Person / Time
Site:	Calvert Cliffs
Issue date:	05/06/2010
From:	Mark Draxton Constellation Energy Nuclear Group
To:	Peter Presby Operations Branch I
Hansell S
Shared Package
ML100560028	List: IR 05000317/2010301 ML102070208 ML102670378 ML102670380 ML102670391 ML102670392 ML102670396 ML102670401 ML102670495 ML102670496 ML102670508 ML102670524 ML111670753
References
TAC U01770
Download: ML102670392 (28)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Exam: 08/0212010 RO Category KIA Points SRO Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G

Total

1. Emergency &

1 3 3 3 3

3 3

18 3

3 6

Abnormal Plant 2

1 2 1

N/A 1 2 N/A 2

I 9

2 2

4 Evolutions Tier Totals 4

5 4

4 5

5 I 27 5

5 10 1

2 2 3 3 28 3

2 5

2. Plant Systems 2

1 1 1 1 o 1 1 10 2

1 3

Tier Totals 3 3 4 I

4 4

38 5

3 8

3 filiiilif 3

3. Generic Knowledge & Abilities 1

2 3

4 1

2 3

4 10 7

Categories 3

2 2

3 2

2 2

1 Note:

l.

Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (Le., except for one category in Tier 3 ofthe 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 ofES-401 for guidance regarding the elimination of inappropriate KIA 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 KlAs having an importance rating (IR) of2.5 or higher shall be selected. Use the RO and SRO

(

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

6.

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

7.*

The generic (G) KlAs in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.I.b of ES-40 1 for the applicable KlAs.

S.

On the following pages, enter the KIA numbers, a brief description ofeach 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; jf fuel handling equipment is sampled in other than Category A2 or G* on the SH.o-only exam, enter it on the left side ofColumn 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 ofthe KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401*3.

Limit SRO selections to KlAs t11at are linked to 10 CFR 55.43.

ES-401 PWR Examination Outline Form ES-40l-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group 1 - REACTOR OPERATOR K

K K

A A lid E/APE #iName/Safety Function KA Topic Imp Pts 1

2 3

1 rit

!t~~~

Knowledge of the interrelations between 007 Reactor Trip - Stabilization

"',~

X a reactor trip and the following:

2.6 1

Recovery /1

~..~.

EK2.02 - Breakers, relays and disconnects 1 o; Ability to operate and lor monitor the 008 Pressurizer Vapor Space 1/:*: following as they apply to X

3.6 I

Accident/2 the Pressurizer Vapor Space Accident:

1 AAl.06 - Control ofPZR level I

I i

Ability to determine or interpret the I

-L; following as they apply to a I*:

009 Small Break LOCA / 3 X

small break LOCA:

3.2 1

EA2.29 - CVCS pump indicating lights for determining pump status I

_cc:

r4l Knowledge of the interrelations between I the and the following Large Break 011 Large Break LOCA / 3 X

2.6 1

LOCA:

~ EK2.02 - Pwnos Knowledge of the operational implications of the following concepts as

!~ -'

they apply to Reactor Coolant Pump fif-E!!k: Malfunctions (Loss of RC Flow):

015/017 RCP Malfunction / 4 X

2.9 1

AKl.04 - Basic steady state thermodynamic relationship between Res loops and SIGs resulting from unbalanced RCS flow I

,f',_. '

f:~~.

Ability to determine and interpret the

,",f, 022 Loss ofReactor Coolant following as they apply to the Loss of X

3.2 I

Makeup/2 Reactor Coolant Makeup:

I:

AA2.0 1-Whether charging line leak exists r";,: Ii,::' Ability to operate and I or monitor the

""ff following as they apply to the Loss of 025 Loss ofRHR System / 4 X

Residual Heat Removal System:

2.9 I

I;>

AAl.08 - RHR cooler inlet and outlet ff" temperature indicators r;,;; Ability to operate and I or monitor the following as they apply to the Loss of 026 Loss ofComponent Cooling Component Cooling Water:

X

.J -

3.1 I

Water /8 AAl.05 - The CCWS surge tank, including level control and level alarms, and radiation alarm I

I I

Knowledge of the interrelations between 027 Pressurizer Pressure Control the Pressurizer Pressure Control k

f X

2.6 1

f System Malfunction I 3 Malfunctions and the following:

I

-ii' 1!1~~ AK2.03 - Controllers and positioners I

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 / Group 1 REACTOR OPERATOR K

K K

A A E/APE #/Name/Safety Function

• .*G KA Topic Imp Pts 1

2 3

1 k 2*.*

I l'. Knowledge of the reasons for the V~> following responses as the apply to the 029 ATWS 11 X

4.2 1

ATWS:

EK3.01-Verifying a reactor trip; methods 2.1.14 - Knowledge of criteria or 038 Steam Generator Tube Rupture conditions that require plant-wide 3.1 1

13 announcements, such as pump starts, reactor trips, mode changes, etc.

Knowledge of the operational 040 Steam Line Rupture -

implications of the following concepts as X

3.2 1

Excessive Heat Transfer I 4 I

they apply to Steam Line Rupture:

r;'*.: AKI.04 - Nil ductility temperature I

I

'-1 Knowledge of the reasons for the

. following responses as they apply to the 054 (CEIE06) Loss of Main (Loss of Feedwater)

X 3.2 1

Feedwater 14

";'.:]-Ixi EK3.2 - Normal, abnormal and emergency

~;iY operating procedures associated with (Loss of Feedwater).

Ability to determine or interpret the I

following as they apply to a Station Blackout:

055 Station Blackout 16 I,>;.;

3.7 1

Xi Fi EA2.04 - Instruments and controls operable with only dc battery power

.-. available 2.1.25 - Ability to interpret reference 056 Loss of Offsite Power I 6 materials, such as graphs, curves, tables, 3.9 1

etc.

Knowledge of the reasons for the 1t following responses as they apply to the 057 Loss of Vital AC Inst. Bus / 6 Loss of Vital AC Instrument Bus:

4.1 1

IX AK3.01-Actions contained in EOP for loss of vital ac electrical instrument bus d.2..

Knowledge of the operational I

implications of the following concepts as 058 Loss of DC Power / 6 X

they apply to Loss of DC Power:

2.8 I

AKl.Ol - Battery charger equipment and

~~lItr instrumentation

-':':'.:\\'.

. ~.f.1 2.4.45 - Ability to prioritize and interpret 065 Loss of Instrument Air / 8 x:; the significance ofeach annunciator or 4.1 1

alarm.

KIA Category Totals:

3 3

3 3 3;

• • -t~1 Group Point Total:

18

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions Tier 1 / Group 2 - REACTOR OPERATOR K

K K A

E/APE #/Name/Safety Function KA Topic Imp Pts rc~; ~G 1

2 3

1 fr Knowledge of the reasons for the following responses as they apply to 024 Emergency Boration / 1 X

Emergency Boration:

4.1 1

i ~~

AK3.01 - When emergency boration is I'

required 028 Pressurizer (PZR) Level 2.4.6 - Knowledge ofEOP Mitigation 3.7 1

Control Malfunction / 2 Strategies Knowledge of the interrelations between 1 7 the Loss of Source Range Nuclear 032 Loss of Source Range Nuclear X

1 i; Instrumentation and the following:

2.7 1

Instrumentation / 7 I:;

AK2.01 - Power supplies, including proper switch positions Ii Ability to operate and / or monitor the following as they apply to the Fuel 036 Fuel Handling Incidents / 8 X

Handling Incidents:

3.3 1

~~ :'

AA 1.0 1 - Reactor building containment

~;

purge ventilation system I~

2.2.40 - Ability to apply Technical 037 Steam Generator Tube Leak 13 3.4 1

Specifications for a system Ability to determine and interpret the following as they apply to the Loss of 051 Loss ofCondenser Vacuum / 4 Condenser Vacuum:

3.9 1

AA2.02 - Conditions requiring reactor

~~

I: "I) and/or turbine trip IF""

Knowledge of the operational "i implications of the following concepts as 061 Area Radiation Monitoring 1

X ill" they apply to Area Radiation 2.5 1

(ARM) System Alarms 17 Monitoring (ARM) System Alarms:

AKl.Ol-Detector limitations r

Ability to determine and interpret the following as they apply to the High 076 High Reactor Coolant Activity

'Xl'I :"", Reactor Coolant Activity:

2.8 1

19 AA2.02 - Corrective actions required for

~ii: Ii high fission product activity in RCS

~;;t Knowledge of the interrelations between the (Excess RCS Leakage) and the it following:

CE/A16 Excess RCS Leakage 12 X

AK2.1 - Components, and functions of 3.2 1

1';1~ control and safety systems, including instrumentation, signals, interlocks, failure li4 modes, and automatic and manual features.

KIA Category Totals:

1 2

1 1.. Group Point Total:

9 I

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 21 Group 1 - REACTOR OPERATOR K

K K

K K

K A

AmA SystemlEvolution #/Name G

KA Topic Imp Pts 1

2 3

4 5

6 1

3 4

2.1.30 - Ability to locate and 003 Reactor Coolant Pump Ii;

!~~&

operate components, including 4.4 1

System local controls.

2

. Knowledge of the physical connections and/or cause-effect relationships between the 003 Reactor Coolant Pump X

3.3 1

RepS and the following System systems:

."!, Kl.03 - RCP seal system

.*i ***.

1 Knowledge of the effect that a loss or malfunction of the eves will have on the 004 Chemical and Volume X

,.~*

3.4 I

following:

Control System e'!

If K3.06 - RCS temperature and pressure Ability to manually operate i!;i~;Y~

and/or monitor in the control 004 Chemical and Volume X

3.6 1

room:

Control System A4.10 - Boric acid pumps I

I Knowledge of the operational implications of the following concepts as they apply the 005 Residual Heat Removal X

3.2 I

RHRS:

System (RHRS)

K5.09 - Dilution and boration

.'~~;;

considerations

. Ability to (a) predict the impacts of the following I

malfunctions or operations on the ECCS; and (b) based on those predictions, use 006 Emergency Core Cooling X

3.9 I

procedures to correct, control, System

• .... or mitigate the consequences of I~~~.!.!

those malfunctions or operations:

A2.02 - Loss of flow path I

I" l

I, Knowledge of the operational implications of the following 007 Pressurizer Relief concepts as the apply to PRTS:

X 3.1 1

Tank/Quench Tank System K5.02 - Method offorming a

....';.E I

steam bubble in the PZR I

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

K K

K K

K A

SystemlEvolution #/Name A r~x~~J A G

KA Topic Imp Pts 1

2 3

4 5

6 1

3 4

[xxii Ability to (a) predict the 1~~0,x~~

I impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, 008 Component Cooling or mitigate the consequences of 3.3 1

Water System those malfunctions or operations:

A2.05 - Effect of loss of instrument and control air on the

.'~/ position ofthe CCW valves that I,,) are air operated Knowledge of bus power supplies to the fOllowing:

010 Pressurizer Pressure X

2.5 1

Control System K2.02 - Controller for PZR spray

.x valve

• • • x 2.2.2 - Ability to manipulate the

!i<

console controls as required to 010 Pressurizer Pressure c;c.

X operate the facility between 4.6

]

Control System shutdown and designated power levels.

Knowledge of the effect that a loss or malfunction of the RPS 012 Reactor Protection X

///

3.2 1

will have on the following:

System

.?

K3.02 - T/G

x.

Ability to monitor automatic

,x. operation of the RPS, 012 Reactor Protection X

3.8 1

including:

System A3.01-Individual channel Ix,"

/£'.

Knowledge of the effect of a loss or malfunction on the following 013 Engineered Safety X

~

2.7 1

will have on the ESFAS:

Features Actuation System K6.01 - Sensors and detectors Ability to monitor automatic operation of the CCS, 022 Containment Cooling 1::1 X including:

4.1 1

System (CCS)

A3.01 - Initiation of safeguards mode ofoperation I

..../,

I SystemlEvolution #/Name K

K K

K K

K A 1~1~!1 A I A 1;~0[1 KA Topic Imp Pts

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 21 Group 1 - REACTOR OPERATOR I

I 1 I 2 I 3 I 4 I 5 I 6 I 1 I 2 I 3 I 4 I

~

I I I 1

I Knowledge of CSS design I

1:;;7 feature(s) and/or interlock(s) which provide for the 026 Containment Spray X

t\\

following:

3.8 1

System (CSS)

K4.07 - Adequate level in containment sump for suction (interlock)

Knowledge of the operational implications of the following I';.....

039 Main and Reheat Steam concepts as they apply to the X

2.7 1

(MRSS)System MRSS:

K5.05 - Bases for RCS cooldown limits I

• Knowledge of MRSS design I\\~~*;*

feature(s) and/or interlock(s) jx.'

which provide for the following:

039 Main and Reheat Steam X

K4.02 - Utilization of Tave.

3.l 1

(MRSS)System

'\\ program control when steam dumping through atmospheric relief/dump valves, including T ave. limits Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 059 Main Feedwater System X

operating the MFW controls 2.7 1

(MFW) including:

I~!;JI A 1.03 - Power level restrictions for operation of MFW pumps and valves.

.'7'; Knowledge of the effect that a I

061 Auxiliary I Emergency loss or malfunction of the AFW X

4.2 1

Feedwater System (AFW) will have on the following:

.i K3.02-S/G Knowledge of bus power 062 A.C. Electrical X

supplies to the following:

3.3 1

Distribution K2.0 1 - Major system loads 1;:;5°1 I*'*nil Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and 063 D.C. Electrical (b) based on those predictions, 2.5 1

Distribution IxX use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 - Grounds I

i I

i

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 1 _. REACTOR OPERATOR K

K K

K K

K A A A

A SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 Ability to manually operate and/or monitor in the control 064 Emergency Diesel room:

X 3.9 I

Generators A4.06 - Manual start, loading, and stopping ofthe ED/G Knowledge of the effect of a loss 064 Emergency Diesel or malfunction of the following X

2.7 1

Generators will have on the ED/G system:

K6.07 - Air receivers 073 Process Radiation 2.4.18 - Knowledge ofthe X

3.3 1

Monitoring System specific bases for EOPs.

Knowledge of SWS design feature(s) and/or interlock(s) which provide for the 076 Service Water System X

following:

2.9 1

(SWS)

K4.02 - Automatic start features associated with SWS pump controls Knowledge of the physical connections and/or cause-effect 078 Instrument Air System relationships between the lAS X

2.6 1

(lAS) and the following systems:

Kl.04 - Cooling water to compressor Ability to predict and/or

. monitor changes in parameters (to prevent exceeding design limits) associated with 103 Containment System X

3.7 1

operating the containment system controls including:

Al.Ol - Containment pressure, temperature, and humidity Ability to manually operate and/or monitor in the control room:

103 Containment System X

2.7 1

A4.06 - Operation ofthe containment personnel airlock door IKIA Category Totals:

2 2

3 3

3 2

2

~

2 3

3 Group Point Total:

28

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 - REACTOR OPERATOR K

K K

K K

K A A A A

SystemlEvolution #lName

~'

KA Topic Imp Pts 1

2 3

4 5

6 3

4 1

bJ~***

~=

11;1 Knowledge of RCS design feature(s) and/or interlock(s)

~'z' X" which provide for the Following:

002 Reactor Coolant System X

3.1 1

K4.07 - Contraction and expansion during heatup and cooldown

'x Ability to (a) predict the

>~;

impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use oII Pressurizer Level Control 3.0 I

procedures to correct, control, System or mitigate the consequences I/~~~;I of those malfunctions or operations:

• A2.07 - Isolation of letdown X

Knowledge of the effect of a loss or malfunction of the 015 Nuclear Instrumentation 2.9 1

X.z following will have on the NIS:

.x*

.,~,

K6.0 1 - Sensors and detectors

.~[~

X K2 Knowledge of bus power 027 Containment Iodine supplies to the following:

3.1 1

Removal System K2.01 - Fans

c-:

• .Zj X

~/

Knowledge of the effect that a loss or malfunction of the 033 Spent Fuel Pool Cooling Spent Fuel Pool Cooling 2.6 1

System will have on the System following:

K3.01 - Area ventilation systems X

Ability to monitor automatic operation of the S/G including:

035 Steam Generator System 4.0 1

11'.:*\\<

A3.0J - SIG water level control

,.. ?0,,;;/

X Ability to predict and/or monitor changes in parameters

. (to prevent exceeding design T limits) associated with 045 Main Turbine Generator operating the MT/G system 3.3 1

System controls including:

Al.06 - Expected response of 1\\1 secondary plant parameters

(.,;

following TIG trip I

i I

I

',;1" K

K K

K K

K A

A A

A SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1 2 3

4 Ability to manually operate I

and/or monitor in the coutrol I

068 Liquid Radwaste System

(',

f, 3.8 1

X room:

r>:)~~

A4.04 - Automatic isolation

,,' Knowledge of the physical connections and/or cause effect relationships between the SAS 079 Station Air System X

3.

.:,1;;

0 1

and the following systems:

Kl.OI - lAS 2.4.31-Knowledge of I

I',,,

086 Fire Protection System annunciator alarms, indications, 4.2 1

\\

or response procedures.

KIA Category Totals:

1 1

1 1

0 1

1 1

1 1

t~~:r Group Point Total:

10

ES-401 PWR Examination Outline Form E8-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 I Group 1 - SENIOR REACTOR OPERATOR E/APE #/Name/Safety K

K K

A.A G KA Topic Imp Pts Function 1

2 3

1 ".2 2.2.44 - Ability to interpret control room indications to verify the status and 011 Large Break LOCA I 3

-*f~ operation of a system, and understand how 4.4 1

operator actions and directives affect plant and system conditions.

054 Loss of Main Feedwater 2.2.38 - Knowledge of conditions and

.. *X 4.5 1

14 limitations in the facility license.

2.4.40 - Knowledge of SRO 055 Station Blackout I 6 X responsibilities in emergency plan 4.5 I

implementation.

>~~,tt, Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water:

062 Loss ofNuclear Service i.

X 2.9 1

Water I 4 AA2.04 - The normal values and upper limits for the temperatures of the components cooled by SWS i,

I"'"

Ability to determine and interpret the

,'n following as they apply to the (Reactor Trip Recovery)

CElE02 Reactor Trip X

3.7 I

Recovery / 1 EA2.l - Facility conditions and selection I.

of appropriate procedures during abnormal I'"

and emergency operations.

11.

...~..;

Ability to determine and interpret the

,", following as they apply to the (Excess Steam Demand):

CE/E05 Excess Steam 4.0 I

Demand 14 EA2.l - Facility conditions and selection of appropriate procedures during abnormal Iru:l:

and emergency operations.

i II KIA Category Totals:

0 0

0 0

3 3't Group Point Total:

6

1 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency & Abnormal Plant Evolutions - Tier 1 / Group 2 - SENIOR REACTOR OPERATOR EIAPE #/Name/Safety K

K K

KA Topic Imp Pts 1

G A~;

Function 1

2 3

I-~j 2.2.23 - Ability to track Technical 003 Dropped Control Rod /

x Specification limiting conditions for 4.6 I>

operations.

I';'

2.2.39 - Knowledge of less than or equal to 069 Loss of Containment X

one hour Technical Specification action 4.5 1

Integrity I 5 statements for systems.

Ability to determine and interpret the I~..

following as they apply to the (Natural

• .';~

Circulation Operations):

CE/Al3 Natural Circulation X

3.7 I

Operations 14 AA2.1 - Facility conditions and selection

,

of appropriate procedures during abnormal and emergency operations.

I I

Ability to determine and interpret the following as they apply to the 1;;:/

(Functional Recovery):

CElE09 Functional X

4.0 1

EA2.2 - Adherence to appropriate Recovery procedures and operation within the limitations in the facility's license and 1,- ;;~

anlendments.

I 1-.

!I KIA Category Totals:

0 0

0 0 )i;;~< 2 Group Point Total:

4

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 21 Group 1 SENIOR REACTOR OPERATOR K

K K

K K

K A A A A

System/Evolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1 12 3

4

.e; I

Ie 2.1.23 - Ability to perform 005 Residual Heat Removal I I specific system and integrated X

4.4 I

System plant procedures during all modes of plant operation..

i I

2.2.22 - Knowledge of limiting 006 Emergency Core Cooling X

conditions for operations and 4.7 I

safety limits.

i Ability to (a) predict the

" impacts of the following

< malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to 039 Main and Reheat Steam T~

3.2 1

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

A2.01 - Flow paths of steam during a LOCA 1

Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use 061 Auxiliary I Emergency 3.5 1

procedures to correct, control, Feedwater System c~r or mitigate the consequences of those malfunctions or operations:

A2.07 - Air or MOV failure

.*~it.!

Ability to (a) predict the impacts of the following malfunctions or operations on the lAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the 062 AC Electrical Distribution X

3.9 1

consequences of those malfunctions or operations:

F A2.0 1 - Types of loads that, if de-energized, would degrade or t!1 hinder plant operation IKIA Category Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

i I

5

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2 / Group 2 - SENIOR REACTOR OPERATOR A l'iX' KIK K K

K K

A A

SystemlEvolution #lName G

KA Topic Imp Pts 1

2 3

4 5

6 1

2 3

4 i

r c

, 2.4.30 - Knowledge ofevents related to system operation/status that must be reported to internal 014 Rod Position Indication I,;)~I X

organizations or external 4.1 1

System agencies, such as the State, the NRC, or the transmission system I";;

operator.

i Ability to (a) predict the impacts of the following IY'

,.. malfunctions or operations on the SDS; and (b) based on those 041 Steam Dump System and 3.1 1

predictions or mitigate the Turbine Bypass Control I'~:

consequences of those I'*, *'C malfunctions or operations:

.);,,:

A2.03 - Loss oflAS

]

Ic*

Ability to (a) predict the impacts of the following malfunctions or operations on I~i*;i the Waste Gas Disposal System

and (b) based on those 07 I Waste Gas Disposal X

3.5 1

predictions, use procedures to System (WGDS) j};;

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

A2.09 - Stuck-open relief valve lit IKIA Category Totals:

0 0

0 0

0 0

0 1*2~ 0 0

1 Group Point Total:

3

ES-401 PWR Examination Outline Form ES-401-3 Tier 3 Generic Knowledge & Abilities Outline - RO & SRO Facility: Calvert Cliffs Nuclear Power Plant Date ofExam: 08/02/2010 Category KJA#

Topic RO IR SRO IR 2.1.20 Ability to interpret and execute procedure steps.

4.6 1

2.1.21 Ability to verity the controlled procedure copy.

3.5 1

Conduct of 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 1

Operations 2.1.32 Ability to explain and apply system limits and precautions.

4.0 1

2.1.42 Knowledge of new and spent fuel movement procedures.

3.4 1

Subtotal 3

2 2.2.13 Knowledge oftagging and clearance procedures.

4.1 1

2.2.37 Ability to determine operability and/or availability of safety related equipment.

3.6 1

Equipment Control 2.2.5 Knowledge of the process for making design or operating changes to the facility.

3.2 1

2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

4.2 1

Subtotal 2

2 2.3.11 Ability to control radiation releases.

3.8 1

2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, i access to locked high-radiation areas, aligning filters, etc.

3.4 1

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

2.9 1

2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.8 ! 1 Subtotal 2

2 2.4.4 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.5 I

Emergency ProcedureslPlan 2.4.14 2.4.23 Knowledge of general guidelines for EOP usage.

Knowledge ofthe bases for prioritizing emergency procedure implementation during emergency operations.

3.8 3.4 1

I 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable frrefighting equipment usage.

3.6 I

Subtotal 3

1 II Tier 3 Total

"+ 10 7

I ES-401 Record ofRejected KJAs Form ES-401-4 Tier I Group Randomly Selected KIA RO - 111 System 029, EK3.03 RO - III System 056, Generic 2.3.4 RO - 111 System 077,£K2.07 RO - 112 System 001, AK3.01 RO-1I2 System 033, AA2.02 RO -112 System 059, 2.2.40 RO -112 System 060, AK2.01 RO...211 System OlQ,2k2.1.

RO-211 System 064, A4.07 Reason for Rejection Not applicable at CCNPP. There is no link between ATWS and the operation ofBIT inlet or outlet valves. Replaced with randomly drawn (using numbered poker chips) 029 EK3.01 KIA mismatch for E/APE. Radiation exposure limits with respect to LOOP? Replaced with randomly drawn (using numbered poker chips) Generic K/A 2.1.25 Could not.generate a suitable question. First attempt was rejectedhy'validatots. Replaced with randomly drawn system # 0II and K/A EK.2 (using numbered poker chips).

Used K/A # EK2.02 (only K/A with RO importance rating of

>2.5)

CCNPP procedural direction is to trip the reactor if placing CEDS in off does not terminate the event. Replaced with randomly drawn system # 024 (using numbered poker chips).

Used same KIA #.

CCNPP does not have an Intermediate Range NI System.

Replaced with randomly drawn system # 076 (using numbered poker chips). Used same KlA#.

Could not generate a question after several hours effort.

Replaced with randomly drawn system # 037 (using numbered poker chips). Used same KIA #.

Radiation release/detection oversampled throughout outline.

Replaced with randomly drawn CEIA 16, AK2.1. Other items sampled for this exam include:

061, AK1.01 (RO) 073,2.4.18 (RO) 068, A4.04 (RO) 2.3.11 (RO) 2.3.13 (RO) 071, A2.09 (SRO) 2.3.5 (SRO) 2.3.14 (SRO)

.~t:!fJl.gOfldmatch for the system selected. Replaced with ly drawn KIA 2.2.2 A JPM was previously selected that covered the exact same subject matter. Replaced with randomly drawn (using numbered poker chips) KIA, A4.06

ES-401 Record ofRejt~cted KJAs Form ES-40 1-4

!I Tier I Group Randomly Selected KIA Reason for Rejection RO-21I i System 073, K4.02 Not applicable at CCNPP. Replaced with randomly drawn system 039 (using numbered poker chips) using same KIA (K4.02). Selected new system because the remaining System 073, K4 essentially mirrors the Tier 2 I Group 2 System 068 KIA that was sampled.

RO - 2/1

• System 076, K4.03 Not applicable at CCNPP. There are no automatic opening features associated with the SWS isolation valves to CCW.

Replaced with randomly drawn (using numbered poker chips)

K4.02 RO 212 I***.

I*

Sy&tem()I 7,.K6,Q 1 cc COgl,Q5not generate a suitable question. First attempt was rejected by validators. Replaced with randomly drawn system # O\\? (using numbered poker chips). Used original KlA#.

RO 2/2 Syst~m 028, K2.01 H2 Recombiners no longer SR @ CCNPP. Replaced with randomly drawn system # 027 (using numbered poker chips).

Used original KIA #.

RO - 2/2 System 035, A3.02 Selected new KIA. This KIA essentially mirrors the Tier 2 I Group 1 System 039 KIA that was sampled. Replaced with remaining System 35 KIA, A3.01, having an importance rating of~ 2.5.

RO - 2/2 System 086, G 2.4.49 KIA Not applicable at CCNPP. There are no from memory "immediate actions" associated with the Fire Protection System. Replaced with randomly drawn (using numbered poker chips) KIA G 2.4.31 SRO-1I1 System 065, 2.4.40 Discussed with Peter Presby. KIA mismatch for E/APE.

Replaced with randomly drawn System (using numbered i poker chips) 055, using original KIA.

SRO-1I2 System 068, 2.2.23 Discussed with Peter Presby. KIA mismatch for E/APE.

Replaced with randomly drawn System 003 (using numbered poker chips), using original KIA.

SRO 112 CE/A13, AA2.2 C9~ldn()tgenera~~ asuitable question. First attempt was rejected by validators. Replaced with remaining AA2 KIA, AA2.L SRO-2/1 System 005, G2.1.39 KIA not one of group specified for random sampling in ES 401. Replaced with randomly drawn (using numbered poker chips) KIA G2.1.23.

ES-401 Record of Rejected KJAs Form ES-40 1-4 Tier / Group Randomly Selected KIA Reason for Rejection Discussed with Peter Presby. KIA Not applicable at CCNPP.

Open cooling water system has no chemistry limits. Replaced SRO 211 System 076, G2.1.3.4 with randomly drawn (using numbered poker chips) System I 006, and KIA G 2.2.22.

I Sampled in last exam written for CCNPP. Malfunctions of SRO 211 System 078, A2.0 1 this component are limited in scope. Randomly sampled new system (using numbered poker chips) 062, kept same KIA 2.1.9 is SRO responsibility. Replaced with randomly drawn RO - Generic KIA 2.1.9 (using numbered poker chips) G2.1.20.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/211 0 - 8/11110 Exam Level: RO / SRO-I Operating Test No.: 2010 Type Administrative Topic (see Note)

Describe activity to be performed Code*

Estimate Time to Boiling and Core Uncovery Conduct ofOperations N,S (RO-Admin-l) 2.1.20 - Ability to interpret and execute procedure steps.

Monitor Azimuthal Power Tilt (Tq) using Excore NIs.

(RO-Admin-2)

Conduct ofOperations M,R 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(3.9,4.2)

Verify CCW System valve operability (RO-Admin-3)

Equipment Control N,R 2.2.21 - Knowledge ofpre-and post-maintenance operability requirements.

(2.9,4.1)

Radiation Control Recall the Emergency Response Organization lAW ERPIP 3.0.

(RO-Admin-4)

Emergency Procedures / Plan D,S 2.4.39 - Knowledge ofRO responsibilities in emergency plan implementation. (3.9,3.8)

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 (:s 3 for ROs; :s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank I)

(P)revious 2 exams (:S 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/2110 8/11/10 Exam Level: RO / SRO-I 1SRO-U Operating Test No.: 2010 I Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1JPM Title Type Code*

Function 01 Respond to multiple misaligned CEAs A,N,S 1

(Sim-I) 2 - Use procedures to correct Loss of Forced Circulation D,S,L 4 (primary)

(Sim-2)

c.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes 1 and 2 A,D,S 2

(Sim-4)

d.

013 - Monitor RCS Depressurization A,EN,M, S 3

(Sim-3)

e.

022 - Verify the Containment Environment Safety Function is satisfied D,S 5

(Sim-5)

f.

029 - Respond to a Containment Fuel Handling Incident N,S 8

(Sim-6)

g.

059 - Recover from Automatic Feedwater Isolation A,S,D (Sim-7) ransfer 4KV Bus Loads from DG to Offsite Power Source D,S 6

(Sim-8)

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

i.

022 - Start 11 & 12 Containment Air Coolers P,R 5

(Plant-l)

j.

041 - Initialize and Align the ADV Controllers to 1(2)C43 D,E 4 (secondary)

(Plant-2)

k.

062 - Align the OC DG to 11 4 KV Bus 6

(Plant-3)

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

• Type Codes Criteria for RO I SRO-I 1SRO-U (A)ltemate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank 5:9/:;8/:;4 (E)mergency or abnormal in-plant

~1/2:l/2:1 (EN)gineered safety feature 1 (control room system)

(L)ow-Power 1Shutdown

~1/2:l/~1 (N)ew or (M)odified from bank including leA)

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

3 1

; 3 I:; 2 (randomly selected)

(R)CA

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

I ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date ofExamination: 8/2/10 8/11/10 Exam Level: RO / SRO-U Operating Test No.: 2010 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Ability to Implement Plant procedures for Condenser tube leak.

Conduct ofOperations N,R (SRO-Admin-l) 2.1.34 - Knowledge of primary and secondary plant chemistry limits. (2.7, 3.5)

Verify an Estimated Critical Condition calculation.

Conduct of Operations M,R (SRO-Admin-2) 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)

Monitor Azimuthal Power Tilt (Tq) using Excore Nls.

Equipment Control D,R (SRO-Admin-3) 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (3.9,4.6)

Approve a Liquid Waste Discharge Permit.

Radiation Control M,R (SRO-Admin-4) 2.3.6 - Ability to approve release permits. (2.0, 3.8)

Determine the appropriate emergency response act~ons Emergency Procedures /

Plan D,R per the ERPIP while maintaining an overview of plant conditions.

(SRO-Admin-5) 2.4.41 - Knowledge ofthe emergency action level thresholds and classifications.(2.9, 4.6)

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 (::s 3 for ROs;::S 4 for SROs & RO retakes)

(N)ew or (M)odified from bank I)

(P)revious 2 exams (::S I; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/2/10 - SI11110 Exam Level: RO / SRO-J 1SRO-U Operating Test No.: 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function procedures to correct Loss of Forced Circulation (Sim-2)

D, S, L 4 (primary)

b.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes 1 and 2 (Sim-4)

A,D,S 2

c.

013 - Monitor RCS Depressurization (Sim-3)

I A,EN,M,S 3

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

d.

022 - Start 11 & 12 Containment Air Coolers (Plant-I)

E,P, R 5

e.

041 - Initialize and Align the ADV Controllers to 1(2)C43 (Plant-2)

D,E 4 (secondary)

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

S9/:S8/:S4 (E)mergency or abnormal in-plant 2:: 11 2:: 11 2:: 1 (EN)gineered safety feature

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

(L)ow-Power / Shutdown 2:112::112::1 (N)ew or (M)odified from bank including I(A) 2:2/2::2/2::1 (P)revious 2 exams

S 3 /:S 3 I:S 2 (randomly selected)

(R)CA 2: 11 2: 11 2:: 1 (S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: 8/2/10 - 8/11110 Exam Level: RO / SRO-I Operating Test No.: 2010 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Ability to Implement Plant procedures for Condenser tube leak.

Conduct of Operations N,R (SRO-Adrnin-l) 2.1.34 - Knowledge ofprimary and secondary plant chemistry limits. (2.7, 3.5)

Verify an Estimated Critical Condition calculation.

Conduct ofOperations M,R (SRO-Admin-2) 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9,4.2)

Monitor Azimuthal Power Tilt (Tq) using Excore Nls.

Equipment Control D,R (SRO-Admin-3) 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications. (3.9, 4.6)

Approve a Liquid Waste Discharge Permit.

Radiation Control M,R (SRO-Adrnin-4) 2.3.6 - Ability to approve release permits. (2.0, 3.8)

Determine the appropriate emergency response actions per the ERPIP while maintaining an overview ofplant conditions.

Emergency Procedures I Plan D,R (SRO-Admin-5) 2.4.41 - Knowledge ofthe emergency action level thresholds and classifications.(2.9,4.6)

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 ofExamination: 8/2/10 - 8/1l/IO Exam Level: RO / SRO-I / SRO-U Operating Test No.: 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code'"

Function

a.

001 - Respond to multiple misaligned CEAs A,N,S I

(Sim-l)

b.

002 - Use procedures to correct Loss of Forced Circulation D,S,L 4 (primary)

(Sim-2)

c.

004 - Respond to RCS leakage exceeding one Chg Pp, Modes I and 2 A,D,S 2

(Sim-4)

d.

013 - Monitor RCS Depressurization A, EN, M, S 3

(Sim-3)

e.

022 - VerifY the Containment Environment Safety Function is satisfied D,S 5

(Sim-5)

f.

029 - Respond to a Containment Fuel Handling Incident N,S 8

(Sim-6) 059 - Recover from Automatic Feedwater Isolation A,S,D 4 (secondary)

(Sim-7)

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

h.

022 - Start 11 & 12 Containment Air Coolers E,P,R 5

(Plant-I)

i.

041 - Initialize and Align the ADV Controllers to 1(2)C43 D,E 4 (secondary)

(Plant-2) he OC DO to 11 4 KV Bus D,E 6

(Plant-3)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; a115 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 / SRO-I I SRO-U (A)ltemate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank

9/

::;8/::;4 (E)mergency or abnormal in-plant 2:112:1/2:1 (EN)gineered safety feature 1 2:1 (control room system)

(L)ow-Power 1Shutdown 2:112:1/2:1 (N)ew or (M)odified from bank including I(A) 2:2/2:2/2:1 (P)revious 2 exams

3 /

:; 3 / ::; 2 (randomly selected)

(R)CA 2:112:1/2:1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility:

CCNPP Scenario No.:

1 Op-Test No.:

2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% gower MOC 10,885 MWD/MTU with long term stead![ state gower histolY. U-2 at 100% power BOC.

Turnover:

1A DIG removed from service and tagged out for scheduled maintenance (return in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />), with OC DIG aligned to 11 4kv bus (disconnect 189-1106 shutl.

13 CBP is in PTL and is considered emergenc![ use onl![ due to high vibrations. Instructions for the shift are to maintain 120wer @ 100%.

Event Event Malf. No.

Event Type*

No.

Description RCS023_02 PZR Press Xmtr 100Y fails low RCS024_03 I (ATCIBOP)

PZR Press Xmtr 102C fails low 1

RCS025 02 TS (SRO)

PZR Press Xmtr 103-1 fails low RCS026 02 PZR level XMTR 11OY fails high C(ALL) 2 RCSOO3 20 gpm RCS leak TS (SRO)

R(ATC/SRO) 3 Expeditious Downpower N (BOP) 4 HDV005 02 C(BOP/SRO) 12 Condensate Booster Pump Failure w/o auto start of standby I

5 SWYD002 M (ALL)

Loss ofoffsite power I

6 CEDSOIO C (ATC) 2 Stuck CEA's 7

DG002 02 C (BOP) lB DIG Auto Start Failure C (ALL) 8 4KVOOI 02 11 4kv bus electrical fault TS (SRO)

(N)ormal (R)eactivity.

(I)nstrument.

(C)omponent (M)ajor Critical Tasks: (bold)

Commence boration due to 2 stuck CEA's Restore 4kv vital bus power with OC DIG

Appendix 0 Scenario Outline Form ES-O-1 Facility:

CCNPP Scenario No.:

2 Op-Test No.: 2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% ~ower EOe, 15,500 MWD/MTU with long term stead~ state ~ower histo['y'. U-2 at 100% ~ower MOe Turnover:

11 HPSI Pumg is removed from service for scheduled maintenance (return in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />). 13 CCW ~um~

is OOS for work on 3ro ~umg disconnect. 13 eBP is for mergenc~ use onl~ due to high vibrations.

Instructions for the shift is to remain at 100% gower.

Event Event Malf. No.

Event Type" No.

Description 1

CNTMOOI 04 TS (SRO) 14 Containment Air Cooler failure C (BOP/SRO) 2 TG017 Turbine vibration on bearing 4 ReATC) 3 Various C (ATC) l-CVC-514-MOV breaker failure 4

TGOOI M(ALL)

Turbine trip

RPSOO5, C (ATC) 5 RPS006 &

RPS & Manual Trip Pushbutton failure DSS failure TS (SRO) 6 CCW002 01 C(BOP) 11 Component Cooling Pump failure 7

RCS022 M (ALL)

Pressurizer Safety Valve fails to reseatfleak on top ofPZR) 8 ESFAOOI 02 I (BOP)

SIAS B failure (N)ormal, (R)eactivity, (l)nstrument, (C}omponent,

{M}ajor II Critical Tasks:

Trip Reactor from electrical panels due to A TWS Trip all RCP's due to no cooling Manually actuate SIAS B

Appendix D Scenario Outline Facility:

CCNPP Scenario No.:

4 Op-Test No.:

2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 100% power MOC 10,885 MWD/MTU long term steady state, U-2 is at 100% power EOC.

Turnover:

13 4kv bus aligned to alternate feed while normal feed breaker 152-1311 is OOS for scheduled maintenance.

I~

Event Mall. No.

Event Type*

Description C(SROIBOP) 1 MS009 01 TBV 3940 fails open R(ATC) 2 480vOOI 04 C(SROIBOP) 12B 480V bus failure 3

CVCS003 01 C{ATC) 11 Charging Pump coupling failure I (BOP) 4 ESFA009 02 Spurious CIS B Actuation TS (SRO) 5 CVCS009 I (ATC)

VCT level transmitter fails high 6

CCW003 C (All)

Component Cooling leak in the containment M (All)

I 7

MS00202 12 S/G tube rupture TS (SRO)

I II *

~N)ormall

~Rleactivit:i' 1llnstrument,

\\ C lom~onent, {Mlajor II Critical Tasks:

Secure RCP's prior to exceeding temp limits.

Isolate S/G in EOP-6 Depressurize RCS to minimize leakage

Appendix 0 Scenario Oytline Form ES-P-1 Facility:

CCNPP Scenario No.:

3 Op-Test No.:

2010 Examiners:

Operators:

Initial Conditions:

U-1 is at 65% Qower due to emergent leak reQair to 11 SGFP. Leak reQair is comQlete and 11 SGFP has been returned to service in Qarallel with 12 SGFP. Two hour confidence run is comQlete for 12 SGFP and return to 100% Qower is ready to commence. U-1 is MOC at 10,885 MWD/MTU and U-2 is at 100% BOC.

Turnover:

U-1 is aligned for Pressurizer boron egualization and CVCS is aligned for direct injection to charging l2umQ suction. 23 AFW PumQ OOS for emergent work following failure of STP-0-5A. Instructions for the shift is to increase Qower back to 100% lAW OP-3.

Event Event Malf. No.

Event Type*

No.

Description N (SROIBOP) 1 Raise power from 65% to 100%

R(ATC)

C (BOP/ATC) 2 RCS027 Small leak on PORV 402 TS (SRO) 3 CVCS023 01 C(SROIATC) 11 Charging pump failure I (ATCIBOP) 4 NIOOL02 NI Channel B Upper Detector Fail TS (SRO)

C (SROIBOP) 5 480V003_04 Loss ofMCC-116, down power to <8000 gpm condensate flow R(ATC)

Panel 6

M (ALL)

Breaker 252-1102 trips open (U-4000-11 supply)

Override 7

Various C (ALL)

Suction path failure to U-lsteam driven AFW pumps II (N)ormal.

(R)eactivity, (I)nstrument.

(C)omponent.

(M)ajor Critical Tasks:

Trip all RCP's upon entry into EOP-3 Initiate OTCC to keep core cool