ML14246A236

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Final Outlines (Folder 3)
ML14246A236
Person / Time
Site: Beaver Valley
Issue date: 07/01/2014
From:
FirstEnergy Nuclear Operating Co
To: Brian Fuller
Operations Branch I
Shared Package
ML14058A120 List:
References
U01884
Download: ML14246A236 (30)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Fac BVPS UNIT 1 RO Date ofExam 7/7 thru 7/18 2014 RO KIA Category Points Tier Group K

K K K K

K A

A A

A G

TOTAL 1

2 3

4 5

6 1

2 3

4 1

3 4

2 3

18

1.

Emergency 2

1 2

1 1

9 Abnormal Plant Tier 4 6 3 4

27 Evolutions Totals 1

3 2

3 3

2 2

3 3

2 2

3 28

2.

Plant 2

Systems 0

0 1

1 1

1 1

2 1

1 1

10 Tier 3 2 4 4 3

3 4 5

3 3 4 38 Totals 1

2 3

4

3. Generic Knowledge and 10 Abilities Category 3

3 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 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 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.

NUREG-1021, Revision 9 Supplement 1 RO Page 1 of 13 FENOC Facsimile Rev. 1

I ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 1(RO)

EIAPE #I Name I Safety Function K

K K A A G KIA Topic(s)

IR 1

2 3

1 2 000007 Reactor Tripl1 X

EK2 Knowledge of the interrelations between a 2.6 1

reactor trip and the following:

[Question 1]

EK2.02 Breakers, relays and disconnects (CFR 41.7 145.7) 000008 Pressurizer (PZR) Vapor Space

}(

AK2 Knowledge of the interrelations between the 2.7*

1 Accident (Relief Valve Stuck Open)l3 Pressurizer Vapor Space Accident and the following:

[Question 2]

~

AK2.01 Valves (CFR 41.7 145.7) 000011 Large Break LOCA/3

}(

EK3 Knowledge of the reasons for the following 4.2 1

responses as the apply to the Large Break LOCA:

[Question 3]

EK3.09 Maintaining DIGs available to provide I

standby power

. i (CFR 41.5 141.10 145.61 45.13) 0000151000017 Reactor Coolant Pump X

'*" I"'

AK2 Knowledge of the interrelations between the 2.9 1

(RCP) Malfunctionsl4 1.'.,

Reactor Coolant Pump Malfunctions (Loss of RC I ;.. > Flow) and the following:

[Question 4]

I i' AK2.07 RCP seals (CFR 41.7 145.7) 000022 Loss of Reactor Coolant Makeupl2 1*, *.

            • ~

2.4.47 Ability to diagnose and recognize trends in 4.2 1

X an accurate and timely manner utilizing the

.:stion 5]

,.::~

appropriate control room reference material.

(CFR: 41.10 143.5145.12) 000025 Loss of Residual Heat Removal

}(

~'

  • AK2. Knowledge of the interrelations between the 2.6 1

System (RHRS)I4 I*********

Loss of Residual Heat Removal System and the

\\, "*

following:

[Question 6]

AK2.05 Reactor building sump (CFR41.7145.7) 000027 Pressurizer Pressure Control X

I AA 1 Ability to operate and I or monitor the following 3.1*

1 System (PZR PCS) Malfunctionl3 as they apply to the Pressurizer Pressure Control Malfunctions:

[Question 7]

AA 1.02 SCR-controlled heaters in manual mode (CFR 41.7 145.51 45.6) 000029 Anticipated Transient Without

}(

EK1 Knowledge of the operational implications of 2.8 1

Scram (ATWS)I1 the following concepts as they apply to the ATWS:

[Question 8]

EK1.05 definition of negative temperature coefficient as applied to large PWR coolant systems (CFR 41.8 141.10 145.3) 000040 Steam Line Rupturel4 X

AK1 Knowledge of the operational implications of 3.4 1

the following concepts as they apply to Steam Line

[Question 9]

Rupture:

AK1.07 Effects of feedwater introduction on dry SIG (CFR 41.8141.10 145.3)

NUREG-1 021, Revision 9 Supplement 1 RO Page 2 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 1(RO) Continued EIAPE #I Name I Safety Function K K K A A G KIA Topic(s)

IR 1

2 3

1 2

000054 Loss of Main Feedwater (MFW)I4 X

M 1 Ability to operate and I or monitor the following 3.5 1

as they apply to the Loss of Main Feedwater (MFW):

[Question 1 0]

M 1.03 AFW auxiliaries, including oil cooling water supply i

(CFR 41.7 I 45.51 45.6)

I 000056 Loss of Offsite Powerl6

!>' X 2.4.34 Knowledge of RO tasks performed outside 4.2 1

the main control room during an emergency and the

[Question 11]

resultant operational effects.

(CFR: 41.10 143.5145.13) 000057 Loss of Vital AC Electrical

X

,*I AK3 Knowledge of the reasons for the following 4.1 1

Instrument Busl6 responses as they apply to the Loss of Vital AC Instrument Bus:

[Question 12]

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus (CFR 41.5141.10 145.6145.13) 000058 Loss of DC Powerl6

X
  • 1,.*

AK1 Knowledge of the operational implications of 2.8 1

[Question 13]

the following concepts as they apply to Loss of DC I

Power:

AK1.01 Battery charger equipment and

      • r *,

instrumentation i/

  • Gi, (CFR 41.8141.10 145.3) vv..J062 Loss of Nuclear Service Waterl4 I'X M2 Ability to determine and interpret the following 2.8*

1

[Question 14]

as they apply to the Loss of Nuclear Service Water:

i M2.06 The length of time after the loss of SWS

(:2 flow to a component before that component may be damaged (CFR: 43.51 45.13) 000065 Loss of Instrument Airl8 X

M2 Ability to determine and interpret the following 2.6 1

[Question 15]

as they apply to the Loss of Instrument Air:

M2.03 Location and isolation of leaks (CFR: 43.5 I 45.13) 000077 Generator Voltage and Electric Grid

}(

M2 Ability to determine and interpret the following 3.9 1

Disturbancesl6 as they apply to Generator Voltage and Electric

[Question 16]

Grid Disturbances:

M2.09 Operational status of emergency diesel generators (CFR: 41.5 and 43.5145.5, 45.7, and 45.8)

WIE04 LOCA Outside Containment/3 X 2.4.47 Ability to diagnose and recognize trends in 4.2 1

[Question 17]

an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 143.5145.12)

NUREG-1021, Revision 9 Supplement 1 RO Page 3 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1 (RO) Continued EIAPE #I Name I Safety Function K K K A A G

KIA Topic(s)

IR 1

2 3

1 2 WIE11 Loss of Emergency Coolant

)(

1',

EA 1 Ability to operate and I or monitor the following 3.7 1

Recirculationl4 as they apply to the (Loss of Emergency Coolant

[Question 18]

Recirculation)

"I EA 1.3 Desired operating results during abnormal and emergency situations.

I (CFR: 41.7 I 45.5 I 45.6)

I 3

4 2

3 3

3 KIA Category Point Totals:

Group Point Total:

18 NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 2(RO)

E/APE #I Name I Safety Function K

K K A A G

KIA Topic(s)

IR 1

2 3

1 2

000003 Dropped Control Rod/1

)(

AK1 Knowledge of the operational implications of the 2.6 1

[Question 19]

following concepts as they apply to Dropped Control Rod:

AK1.1 0 Definitions of core quadrant power tilt 1******.*

(CFR 41.8 I 41.10 I 45.3) 000005 Inoperable/Stuck Control Rod/1 X

AK2 Knowledge of the interrelations between the 2.5 1

[Question 20]

Inoperable I Stuck Control Rod and the following:

AK2.02 Breakers, relays, disconnects, and control room switches (CFR 41.7 I 45.7) 000028 Pressurizer (PZR) Level Control

)(..

M 1 Ability to operate and I or monitor the following 2.7 1

Malfunction/2 as they apply to the Pressurizer Level Control

[Question 21]

Malfunctions:

M 1.04 Regenerative heat exchanger and temperature limits

..,*.. z.

(CFR 41.7 I 45.5 I 45.6) 000060 Accidental Gaseous Radwaste X li"*;

M2 Ability to determine and interpret the following 2.6 1

Release/9

  • ~

as they apply to the Accidental Gaseous Radwaste:

[Question 22]

M2.04 The effects on the power plant of isolating a given radioactive-gas leak I /.

(CFR: 43.5 I 45.13) 1-161 Area Radiation Monitoring (ARM)

X I >

M 1 Ability to operate and I or monitor the following 3.6 1

~ Aem Alarms/?

as they apply to the Area Radiation Monitoring

[Question 23]

(ARM)System Alarms:

M 1.01 Automatic actuation (CFR 41.7 I 45.5 I 45.6) 000067 Plant fire on site/9

)(

M2 Ability to determine and interpret the following 2.9 1

[Question 24]

as they apply to the Plant Fire on Site:

M2.12 Location of vital equipment within fire zone (CFR: 43.5 I 45.13)

W/E06 Degraded Core Cooling/4 X 2.1.25 Ability to interpret reference materials, such 3.9 1

[Question 25]

as graphs, curves, tables, etc.

(CFR: 41.10 I 43.5 I 45.12)

W/E08 Pressurized Thermal Shock/4

)(

EK3 Knowledge of the reasons for the following 3.4 1

[Question 26]

responses as they apply to the (Pressurized Thermal Shock)

EK3.1 Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

(CFR: 41.5 I 41.10 I 45.6 I 45.13)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 2(RO) Continued EIAPE #I Name I Safety Function K K K A A G

KIA Topic(s)

IR 1 2 3

1 2

WIE13 Steam Generator Overpressurel4 X

EK2 Knowledge of the interrelations between the 3.0 1

[Question 27]

(Steam Generator Overpressure) and the following:

EK2.2 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.

(CFR: 41.7 I 45.7) 1 2

1 2

2 1

KIA Category Point Totals:

Group Point Total:

9 NUREG-1021, Revision 9 Supplement 1 RO Page 6 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 1 (RO)

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 K6 Knowledge of the effect of a loss or 2.6 1

System (RCPS) malfunction on the following will have on the

[Question 28]

RCPS:

K6.14 Starting requirements (CFR: 41.7 I 45.5) 003 Reactor Coolant Pump X

K3 Knowledge of the effect that a loss or 3.5 1

System (RCPS) malfunction of the RCPS will have on the

[Question 29]

following:

K3.02 S/G (CFR: 41.7 I 45.6) 004 Chemical and Volume

X K4 Knowledge of CVCS design feature(s) 2.8 1

Control System (CVCS) and/or interlock(s) which provide for the

[Question 30]

following:

I K4.01 Oxygen control in RCS (CFR: 41.7) 005 Residual Heat Removal X

I<

K5 Knowledge of the operational implications 2.9*

1 System (RHRS)

I.

of the following concepts as they apply the

[Question 31]

RHRS:

K5.03 Reactivity effects of RHR fill water (CFR: 41.5 I 45. 7) 006 Emergency Core Cooling

X
1.

K3 Knowledge of the effect that a loss or 4.2 1

em (ECCS)

/

malfunction of the ECCS will have on the L""..~estion 32]

I following:

K3.03 Containment

y. (CFR: 41.7 I 45.6) 007 Pressurizer Relief
X 2.2.12 Knowledge of surveillance procedures.

3.7 1

Tank/Quench Tank System (PRTS)

(CFR: 41.10 I 45.13)

[Question 33]

007 Pressurizer Relief X

A2 Ability to (a) predict the impacts of the 3.9 1

Tank/Quench Tank System following malfunctions or operations on the (PRTS)

PRTS; and (b) based on those predictions, use

[Question 34]

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

A2.01 Stuck-open PORV or code safety (CFR: 41.5 I 43.5/ 45.3/45.13) 008 Component Cooling Water

X K3 Knowledge of the effect that a loss or 3.4 1

System (CCWS) malfunction of the CCWS will have on the

[Question 35]

following:

K3.01 Loads cooled by CCWS (CFR: 41.7 I 45.6)*

010 Pressurizer Pressure X

A4 Ability to manually operate and/or monitor 4.0 1

Control System (PZR PCS) in the control room:

[flo 1estion 36]

A4.03 PORV and block valves (CFR: 41.7 I 45.5 to 45.8)

NUREG-1 021, Revision 9 Supplement 1 RO Page 7 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

-Tier 2/Group 1 (RO) Continued I

II 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

,I 010 Pressurizer Pressure X

K4 Knowledge of PZR PCS design feature(s) 2.7 1

Control System (PZR PCS) and/or interlock(s) which provide for the

[Question 37]

following:

K4.01 Spray valve warm-up (CFR: 41.7) 012 Reactor Protection System X

K2 Knowledge of bus power supplies to the 3.3 1

[Question 38]

following:

K2.01 RPS channels, components, and I

interconnections I

(CFR: 41.7)

I 012 Reactor Protection System

)(

K6 Knowledge of the effect of a loss or 2.8 1

[Question 39]

malfunction of the following will have on the RPS:

K6.01 Bistables and bistable test equipment (CFR: 41.7 /45.7) 013 Engineered Safety Features X

,. K1 Knowledge of the physical connections 3.8 1

Actuation System (ESF AS) and/or cause effect relationships between the

[Question 40]

't.

ESFAS and the following systems:

K1.03 CCS (CFR: 41.2 to 41.9 I 45.7 to 45.8)

, Containment Cooling X

A3 Ability to monitor automatic operation of the 4.1 1

.em (CCS)

CCS, including:

[Question 41]

A3.01 Initiation of safeguards mode of operation (CFR: 41.7 I 45.5) 026 Containment Spray System X

(

K1 Knowledge of the physical connections 4.2 1

(CSS)

  • ~

and/or cause/effect relationships between the

[Question 42]

CSS and the following systems:

I K1.01 ECCS (CFR: 41.2 to 41.9 I 45.7 to 45.8) 026 Containment Spray System

)(

A4 Ability to manually operate and/or monitor 3.5 1

(CSS) in the control room:

[Question 43]

A4.05 Containment spray reset switches (CFR: 41.7 I 45.5 to 45.8) 039 Main and Reheat Steam X 2.2.39 Knowledge of less than or equal to one 3.9 1

System (MRSS) hour Technical Specification action statements

[Question 44]

for systems.

(CFR: 41.7/41.10 I 43.2 I 45.13)

NUREG-1 021, Revision 9 Supplement 1 RO Page 8 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

-Tier 2/Group 1 (RO) Continued 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

4 039 Main and Reheat Steam X

A 1 Ability to predict and/or monitor changes in 2.5*

1 System (MRSS) parameters (to prevent exceeding design

[Question 45]

limits) associated with operating the MRSS controls including:

A 1.09 Main steam line radiation monitors (CFR: 41.5 I 45.5) 059 Main Feedwater (MFW)

)(

I

~

A2 Ability to (a) predict the impacts of the 3.0*

1 System

~*

following malfunctions or operations on the

[Question 46]

MFW; and (b) based on those predictions, use

~

procedures to correct, control, or mitigate the I';~*

consequences of those malfunctions or operations:

A2.11 Failure of feedwater control system (CFR: 41.5/43.5/ 45.3 I 45.13) 061 Auxiliary I Emergency

)(

~~ ~

K5 Knowledge of the operational implications 2.6 1

Feedwater (AFW) System of the following concepts as the apply to the

[Question 47]

AFW:

K5.03 Pump head effects when control valve is

~..

shut (CFR: 41.5 /45. 7)

I**

062 AC Electrical Distribution X

A 1 Ability to predict and/or monitor changes in 3.4 1

!=:"stem i',

I,

parameters (to prevent exceeding design JStion 48]

I *J I,

limits) associated with operating the ac distribution system controls including:

A 1.01 Significance of DIG load limits I

,* (CFR: 41.5 /45.5) 063 DC Electrical Distribution X

A3 Ability to monitor automatic operation of the 2.7 1

System DC electrical system, including:

[Question 49]

A3.01 Meters, annunciators, dials, recorders, and indicating lights (CFR: 41.7 /45.5) 064 Emergency Diesel X

~ ~.. K1 Knowledge of the physical connections 3.6 1

~

Generator (ED/G) System

/

and/or cause/effect relationships between the

[Question 50]

ED/G system and the following systems:

K1.04 DC distribution system (CFR: 41.2 to 41.9 I 45.7 to 45.8) 073 Process Radiation X

A 1 Ability to predict and/or monitor changes in 3.2 1

Monitoring (PRM) System parameters (to prevent exceeding design

[Question 51]

limits) associated with operating the PRM system controls including:

A 1.01 Radiation levels (CFR: 41.5 I 45. 7)

NUREG-1021, Revision 9 Supplement 1 RO Page 9 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

-Tier 2/Group 1(RO) Continued 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

4 076 Service Water System X

K4 Knowledge of SWS design feature(s) 2.5*

1 (SWS) and/or interlock(s) which provide for the (Question 52]

following:

K4.01 Conditions initiating automatic closure of closed cooling water auxiliary building header supply and return valves (CFR: 41.7) 078 Instrument Air System (lAS)

X K2 Knowledge of bus power supplies to the 2.7 1

[Question 53]

following:

K2.01 Instrument air compressor (CFR: 41.7) 1 03 Containment System X 2.1.19 Ability to use plant computers to 3.9 1

(Question 54]

evaluate system or component status.

,\\'

(CFR: 41.10 I 45.12) 1 03 Containment System X

A2 Ability to (a) predict the impacts of the 3.5*

1 (Question 55) following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.03 Phase A and B isolation (CFR: 41.5 I 43.5 I 45.3 I 45.13) i=

3 2

3 3

2 2

3 3

2 2

3 KIA Category Point Totals:

Group Point Total:

28 NUREG-1021, Revision 9 Supplement 1 RO Page 1 0 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 2(RO)

System# I Name K K K K K K A A A A G KIA Topic(s) 1 2 3

4 5

6 1 2 3

4 IR 001 Control Rod Drive System

X K6 Knowledge of the effect of a loss or 2.8 1

[Question 56]

malfunction on the following CRDS components:

K6.02 Purpose and operation of sensors feeding into the CRDS (CFR: 41.7/45.7) 011 Pressurizer Level Control

X A 1 Ability to predict and/or monitor changes in 3.1 1

System (PZR LCS) parameters (to prevent exceeding design limits)

[Question 57]

associated with operating the PZR LCS controls including:

A1.04 T-ave (CFR: 41.5 I 45.5) 014 Rod Position Indication

X 2.2.37 Ability to determine operability and/or 3.6 1

System (RPIS) availability of safety related equipment.

[Question 58]

(CFR: 41.7 I 43.5 I 45.12) 015 Nuclear Instrumentation

X K3 Knowledge of the effect that a loss or 3.9 1

System (NIS) malfunction of the NIS will have on the

[Question 59]

following:

I K3.01 RPS (CFR: 41.7 I 45.6) 016 Non-Nuclear

X A3 Ability to monitor automatic operation of the 2.9*

1 ln~trumentation System (NNIS)

NNIS, including:

stion 60]

A3.02 Relationship between meter readings and actual parameter value (CFR: 41.7 I 45.5) 034 Fuel Handling Equipment

X K4 Knowledge of design feature(s) and/or 2.6 1

System (FHES) interlock(s) which provide for the following:

[Question 61]

K4.01 Fuel protection from binding and dropping (CFR: 41.7) 041 Steam Dump System

.)(

I*

A2 Ability to (a) predict the impacts of the 2.8 1

(SDS)/Turbine Bypass Control following malfunctions or operations on the I*}

[Question 62]

SDS; and (b) based on those predictions use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

t I

A2.03 Loss of lAS (CFR: 41.5 I 43.5 I 45.3 I 45.13) 056 Condensate System X

A2 Ability to (a) predict the impacts of the 2.6 1

[Question 63]

following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Loss of condensate pumps (CFR: 41.5 I 43.5 I 45.3 I 45.13)

NUREG-1 021, Revision 9 Supplement 1 RO Page 11 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

-Tier 2/Group 2(RO) Continued System # I Name K K K K K K A A A A G

KIA Topic(s) 1 2

3 4

5 6

1 2 3

4 IR 075 Circulating Water System

}(

A4 Ability to manually operate and/or monitor 3.2*

1

[Question 64]

in the control room:

A4.01 Emergency/essential SWS pumps (CFR: 41.7 I 45.5 to 45.8) 086 Fire Protection System X

K5 Knowledge of the operational implication of 3.1 1

(FPS) the following concepts as they apply to the Fire

[Question 65]

Protection System:

K5.03 Effect of water spray on electrical components (CFR: 41.5 I 45.7)

KIA Category Point Totals:

0 0

1 1

1 1

1 2 1

1 1

Group Point Total:

10 NUREG-1021, Revision 9 Supplement 1 RO Page 12 of 13 FENOC Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3

.t "cility: BVPS UNIT 1 RO Date ofExam 7/7 thru 7118 2014 RO Category KIA#

Topic IR

1.

2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

2.9*

Conduct of Operations

2.

I Equipment Control

3.

Radiation Control

4.

Emergency Procedures/

Plan (CFR: 41.10 I 43.5 I 45.12)

[Question 66]

2.1.20 Ability to interpret and execute procedure steps.

(CFR: 41.10 I 43.5 I 45.12)

[Question 67]

2.1.27 Knowledge of system purpose and/or function.

(CFR: 41.7)

[Question 68]

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

(CFR: 41.10 I 43.2 I 45.13)

[Question 69]

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

(CFR: 41.7 I 43.5 I 45.12)

[Question 70]

4.6 3.9 3.6 2.2.42 Ability to recognize system parameters that are entry-level conditions for 3.9 Technical Specifications.

(CFR: 41.7 I 41.10 I 43.2 I 43.3 I 45.3)

[Question 71]

Subtotal 2.3.12 Knowledge of radiolog safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 I 45.9 I 45.10)

[Question 72]

2.3.14 Knowledge of radiation or contamination hazards that may arise during 3.4 normal, abnormal, or emergency conditions or activities.

(CFR: 41.12/43.4/45.10)

[Question 73]

Subtotal 2.4.2 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

(CFR: 41.7 I 45.7 I 45.8)

[Question 74]

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

4.2 (CFR: 41.10 I 45.3)

[Question 75]

Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 RO Page 13 of 13 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Faci SRO ONLY Points Tier Group A2 G*

TOTAL 1

3 3

6

1.

Emergency 2

2 2

4 Abnormal Plant Tier 5

5 10 Evolutions Totals 1

3 2

5

2.

Plant 2

Systems 0 2 1

3 Tier 5

3 8

Totals

3. Generic Knowledge and 1 2 3 4 7

Abilities Category 2 1 2 2 Note:

1.

Ensure that at least two topics from every applicable KJA 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 KJAs 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) KJAs 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 KJAs.

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 KJAs that are linked to 10 CFR 55.43.

NUREG-1 021, Revision 9 Supplement 1 SRO Page 1 of 6 FENOC Facsimile Rev. 2

ES-401 EIAPE #I Name I Safety Function 000009 Small Break LOCA/3

[Question 76]

000026 Loss of Component Cooling Water (CCW)I8

[Question 77]

000038 Steam Generator Tube Rupture (SGTR)I3

[Question 78]

Onsite Power WIE05 Loss of Secondary Heat Sink/4

[Question 80]

.12 Uncontrolled Depressurization of all Steam Generatorsl4

[Question 81]

KIA Category Point Totals:

NUREG-1021, Revision 9 Supplement 1 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions-Tier 1/Group 1(SRO)

K K K A KIA Topic(s)

IR 1

2 3

1 2.4.8 Knowledge of how abnormal operating 4.5 procedures are used in conjunction with EOPs.

(CFR: 41.10 I 43.5 I 45.13)

M2 Ability to determine and interpret the following 3.6 as they apply to the Loss of Component Cooling Water:

M2.02 The cause of possible CCW loss (CFR: 43.5 I 45.13) 2.1.32 Ability to explain and apply system limits and 4.0 precautions.

(CFR: 41.10 I 43.2 I 45.12)

EA2 Ability to determine or interpret the following as 3.7 they apply to a Station Blackout:

EA2.01 Existing valve positioning on a loss of instrument air system (CFR 43.5 I 45.13)

EA2 Ability to determine and interpret the following 4.4 as they apply to the (Loss of Secondary Heat Sink)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 I 45.13) 2.4.47 Ability to diagnose and recognize trends in an 4.2 accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 I 43.5 I 45.12) 3 3

6 Group Point Total:

SRO Page 2 of 6 FENOC Facsimile Rev. 2

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2(SRO)

IF===========================T=9==r=r=

E/APE #I Name I Safety Function 000037 Leak/3

[Question 82]

(S/G) Tube 000059 Accidental Liquid Radwaste Release/9

[Question 83]

000076 High Reactor Coolant Activity/9

[Question 84]

W/E10 Natural Circulation with Steam Void in Vessel with/without RVLIS/4

[Question 85]

KIA Category Point Totals:

NUREG-1021, Revision 9 Supplement 1 K

K K A 1 2 3

1 KIA Topic(s)

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

AA2.09 System status, using independent readings from redundant Condensate air ejector exhaust monitor (CFR: 43.5 I 45.13) 2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10143.5 I 45.11)

AA2 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:

AA2.06 Response of PZR LCS to changes in the letdown flow rate (CFR: 43.5 I 45.13) 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

(CFR: 41.10 I 43.5 145.3)

Group Point Total:

IR 3.4*

4.6 2.5 4.0 SRO Page 3 of 6 FENOC Facsimile Rev. 2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

~===================9=9r=r=T=~9==r=

System # I Name 004 Chemical and Volume Control System

[Question 86]

022 Containment Cooling System (CCS)

[Question 87]

063 DC Electrical Distribution System

[Question 88]

064 Emergency Diesel Generator (ED/G) System

[Question 89]

078 Instrument Air (lAS)

[Question 90]

tegory Point Totals:

NUREG-1 021, Revision 9 Supplement 1 K K 1

2 K K K A 4

5 6

1 SRO Page 4 of 6

-Tier 2/Group 1 (SRO)

KIA Topic(s)

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

A2.14 Emergency Boration (CFR: 41.5143.5 I 45.3 I 45.5) to (a) predict the impacts of the 2.7 following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.01 Fan motor over-current (CFR: 41.5/ 43.5 I 45.3/ 45.13) 2.2.37 Ability to determine operability and/or 4.6 availability of safety related equipment.

(CFR: 41.7 /43.5/45.12)

A2 Ability to (a) predict the impacts of the 2.9 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:

A2.02 Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures (CFR: 41.5/ 43.5 I 45.3 I 45.13) 2.2.44 Ability to interpret control room 4.4 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5/43.5 I 45.12)

Group Point Total:

FENOC Facsimile Rev. 2 5

ES-401 System # I Name 015 Nuclear Instrumentation System (NIS)

[Question 91]

071 Waste Gas Disposal System (WGDS)

[Question 92]

079 Station Air System (SAS)

[Question 93]

KIA Category Point Totals:

NUREG-1 021, Revision 9 Supplement 1 K K K K 1

2 3

4 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 2(SRO)

KIA Topic(s)

IR A2 Ability to (a) predict the impacts of the 3.9 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:

A2.01 Power supply loss or erratic operation (CFR: 41.5 I 43.5 I 45.3 I 45.5)

A2 Ability to (a) predict the impacts of the 3.6 following malfunctions or operations on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.02 Use of waste gas release monitors, radiation, gas flow rate, and totalizer (CFR: 41.5 I 43.5 I 45.3 I 45.13) 2.2.25 Knowledge of the bases in Technical 4.2 Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 I 41.7 I 43.2)

Group Point Total:

3 SRO Page 5 of 6 FENOC Facsimile Rev. 2

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 F':lcility: BVPS UNIT 1 SRO Date ofExam 7/7 thru 7/18 2014 Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation

  • rol
4.

Emergency Procedures/

Plan KIA#

Topic 2.1.39 Knowledge of conservative decision making practices.

(CFR: 41.10 /43.5/45.12)

[Question 94]

2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR:41.10145.12)

[Question 95]

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

(CFR: 41.51 43.5 I 45.12)

[Question 96]

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

(CFR: 41.11 I 41.12 I 43.4 145.9)

[Question 97]

2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12/43.4/45.9)

[Question 98]

Subtotal 2.4.3 Ability to identify post-accident instrumentation.

(CFR: 41.6/ 45.4)

[Question 99]

2.4.44 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10 I 41.12 /43.5 /45.11)

[Question 100]

Subtotal Tier 3 Point Total NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 SRO Only IR 4.3 4.3 2

1 3.1 2

4.4 2

7 FENOC Facsimile Rev. 2

ES 401 R ecor d fR.

0 ejecte d KIA s F

s orm E -401-4 II Facility: BVPS Unit 1 Date of Exam 7/7 thru 7/18 2014 Operating Test No.: BV1LOT14 NRC

~r I Randomly Reason for Rejection

.oup Selected KIA RO OUTLINE 1/2 000067 AA2.06 Question #24; At Beaver Valley the need for pressurizing the control room during a plant fire on site is an SRO decision based on the SRO's judgment of the control room environment. Therefore we are unable to construct a question that will have definitive criteria for the need to pressurize the control room. Randomly selected 000067 AA2.12 as a replacement.

2/1 012 K6.07 Question #39; Beaver Valley does not have a core protection calculator.

Randomly selected 012 K6.01 as a replacement.

2/1 039 2.2.25 Question #44; Knowledge of TS bases is an SRO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev. 1 (3/11/1 0). Randomly selected 039 2.2.39 as a replacement.

2/1 059 A2.07 Question #46; Beaver Valley does not have MFW pump turbines. Randomly selected 059 A2.11 as a replacement.

2/1 103 A2.05 Question #55; Beaver Valley does not have any emergency containment entry procedures. Randomly selected 103 A2.03 as a replacement.

2/2 015 K3.04 Question #59; Beaver Valley does not have ICS. Randomly selected 015 K3.01 as a replacement.

2/2 041 K2.02 Question #62; Beaver Valley does not have ICS. Randomly selected 041 A2.03 as a replacement.

3 2.3.11 Question #71; Ability to control radiation releases has already been addressed in this exam with RO and SRO JPMs as well as Q# 92 of the written exam. In order to maintain exam balance, randomly selected 2.2.42 as a replacement.

1/2 000060 AA2. 04 Question #22; Beaver Valley only has a single ARM that has automatic actions and this is already being addressed in Question #23. Randomly selected 000060 AA2.04 as a replacement.

1/1 000025 AK3.02 Question #6; Beaver Valley no longer isolates RHR low pressure piping on increasing pressure. Rather, this function is accomplished with the low pressure over pressurization protection system. The system employs the PORVs to relieve pressure without isolating the RHR low pressure piping. Therefore the KIA is not applicable to Beaver Valley. Discussed with the chief examiner and the decision was made tore-select a different KIA. Randomly selected 000025 AK3.03 as a replacement.

NUREG-1 021, Revision 9 Supplement 1 Page 1 of 2 FENOC Facsimile Rev. 2

ES-401 R ecor d f R. t d KIA 0

eJec e s

F orm ES-401-4 Facility: BVPS Unit 1 Date of Exam 7/7 thru 7/18 2014 Operating Test No.: BV1LOT14 NRC SRO OUTLINE 1/1 W/E12 2.4.1 Question #81; Knowledge of EOP entry conditions and immediate actions is RO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev.

1 (3/11/1 0). Randomly selected W/E12 2.4.47 as a replacement.

2/2 027 A2.01 Question #91; Beaver Valley has retired the containment iodine removal system and replaced it with a passive sodium tetraborate system. Randomly selected 015 A2.01 as a replacement.

3 2.1.44 Question #95; Knowledge of RO duties in the control room is RO knowledge lAW the NRC Clarification guidance for SRO-only questions Rev. 1 (3/11 /1 0).

Randomly selected 2.1.31 as a replacement.

3 2.4.8 Question #99; Overlap with question 76 identical KIA creates overlap and potential double-jeopardy issues. Randomly selected 2.4.3 as a replacement.

2/1 064 A2.09 Question # 89; Unable to develop a discriminatory question for the second part of the KIA which requires procedure use to address a malfunction regarding an EDG that fails to synchronize. Other than to call maintenance to effect repairs, there is no operational procedural guidance for this condition. Discussed with the chief examiner and the decision was made to re-select a different KIA. Randomly selected 064 A2.02 as a replacement.

211 004A2.14 Question #86, Unable to develop discriminatory question for the second part of the KIA since the procedure guidance for addressing Low VCT Pressure is to just monitor the automatic operation of the makeup valve. Discussed with the chief examiner and the decision was to reselect a different KIA.

Since there are multiple KIAs under the Chemical and Volume Control System and the A2 stem statement, randomly reselected A2.14 as a replacement to match original selected system and topic.

NUREG-1021, Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 2

II ES-301 Facility:

BVPS Unit 1

~amination Level RO IKI Administrative Topic (See Note)

Conduct of Operations (RO A.1.1)

Conduct of Operations (RO A.1.2)

..:JUipment Control (RO A.2)

Radiation Control (RO A.3)

Emergency Procedures/Plan (RO A.4)

Type Code*

M,R M,R N,R D,R Administrative Topics Outline Form ES-301-1 Date of Examination:

7/7 thru 7/18 2014 SROD Operating Test Number BV1LOT14 NRC Describe activity to be performed 2.1.23 (4.3)

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

(1AD-007) Perform an ECP Calculation 2.1.43 (4.1)

Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(1AD-016) Plot and Evaluate 1/M Data 2.2.13 (4.1)

Knowledge of tagging and clearance procedures.

(1AD-047) Prepare a Clearance Tagout for FW-P-38 2.3.11 (3.8)

Ability to control radiation releases.

(1AD-004) Perform Decay Tank Discharge Pre-Release Verification NOT EVALUATED

  • 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 NUREG-1 021, Revision 9 Supplement 1 (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)

FENOC Facsimile Rev. 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

BVPS Unit 1 Date of Examination: 717 thru 7118 2014

<amination Level RO D SRO IXl Operating Test Number BV1LOT14 NRC Administrative Topic Type Describe activity to be performed (See Note)

Conduct of Operations (SRO A.1.1)

Conduct of Operations (SRO A.1.2)

Equipment Control

,.:JRO A.2)

Radiation Control (SRO A.3)

Emergency Procedures/Plan (SRO A.4)

Code*

M, R 2.1.23 (4.4)

N,R N, R N, R N,S Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(1AD-011) Review an ECP Calculation 2.1.3 (3.9)

Knowledge of shift or short-term relief turnover practices.

(1AD-048) Determine Availability for Call-in (3 ROs) 2.2.17 (3.8)

Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

(1AD-041) Perform a Risk Assessment [1 FW-P-3A] Maintenance 2.3.11 (4.3)

Ability to control radiation releases.

(1AD-042) Determine Compensatory Actions for RM-P-1GW-108 and 02A-1 GW-11 0-1 Being OOS 2.4.41 (4.6)

Knowledge of the emergency action level thresholds and classifications.

(1AD-046) Classify an Emergency Event (Scenario Specific) i 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 IL NUREG-1021, Revision 9 Supplement 1 (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)

FENOC Facsimile Rev. 1

ES 301 C

t I R on ro II PI t S t

oom n-an

>>ys ems o tr u me F orm ES 301 2 I Facility:

BVPS Unit 1 Date of Examination:

7171 thru 7/18 2014 1 Exam Level: RO IRI SRO(I) D SRO(U) D Operating Test No.:

BV1LOT14 NRC 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 S1 -Shift From Main F/W Reg. Valves to Bypasses (1 CR-072)

S,D 4S S2-Discharge Laundry and Contaminated Shower Drain Tank- (High S,N,A 9

radiation alarm received - No Auto Actions occur) (1 CR-658)

S3 - Rod Control Assembly Partial Movement Test- (Rods continue to S,D,A 1

move during performance of the test) (1CR-596)

S4 - Drain SIS Accumulator - (Low pressure alarm received during S,N,A,EN 3

draining) (1 CR-659)

S5 - Place Excess Letdown in Service (1CR-056)

S,D 2

S6-Respond to High PRT Temperature- (High PRT level received during S,N,A 5

spray down of PRT) (1 CR-661)

S7 - X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent S,N,A 6

occurs and EDG auto actions fails to occur) (1 CR-660)

S8 - Respond to a Loss of the RHR System (RHR pump trips requiring S, D, A, L, E 4P RCP start) (1 CR-594)

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

P1 -Startup a Rod Drive MG (1 PL-003)

D, L 1

P2-Reset the Terry Turbine Trip Throttle Valve (1 PL-004)

D,R 4S P3-Place the Diesel Air Compressor in Service (1PL-031)

D,E 8

All RO and SRO 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)Iternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant

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

-I-I~ 1 (Control room system)

(L)ow-power I Shutdown

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

~21~21~1 (P)revious 2 exams s 31 s 3 Is 2 (randomly selected)

(R)CA

~11~11~1 11 (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev.2

ES 301 C

t I R on ro II PI t 5 t

oom n-an iys ems o tr u me F orm ES 301 2 Facility:

BVPS Unit 1 Date of Examination:

7171 thru 7/18 2014 Exam Level: RO 0 SRO(I) liD SRO(U) 0 Operating Test No.:

BV1LOT14 NRC 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 51 - Shift From Main FIW Reg. Valves to Bypasses (1 CR-072)

S,D 4S 52-Discharge Laundry and Contaminated Shower Drain Tank- (High S,N,A 9

radiation alarm received - No Auto Actions occur) (1 CR-658) 53 - Rod Control Assembly Partial Movement Test- (Rods continue to S,D,A 1

move during performance of the test) (1CR-596) 54-Drain SIS Accumulator- (Low pressure alarm received during S,N,A,EN 3

draining) (1 CR-659) 56-Respond to High PRT Temperature- (High PRT level received during S,N,A 5

spray down of PRT) (1 CR-661) 57 - X-Fer 4KV Emer Bus from EDG to Normal Feed - (EDG overcurrent S,N,A 6

occurs and EDG auto actions fails to occur) (1 CR-660) 58-Respond to a Loss of the RHR System (RHR pump trips requiring S, D,A,L,E 4P RCP start) (1CR-594)

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

P1 - Startup a Rod Drive MG (1 PL-003)

D, L 1

P2-Reset the Terry Turbine Trip Throttle Valve (1 PL-004)

D,R 4S P3-Place the Diesel Air Compressor in Service (1 PL-031)

D,E 8

All RO and SRO 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)Iternate Path 4-6 14-6 12-3 (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

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

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

~ 31 ~ 3 I~ 2 (randomly selected)

(R)CA

~11~11~1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev.2

A d" D

~ppen IX s

  • o tr cenar.o u me 1L14N1 Facility:

BVPS Unit 1 Scenario No. 1 Op Test No.:

1LOT14 NRC Examiners:

Operators:

SRO ATC BOP Initial IC 68(29): 100% power, EOL, Equ. XE Conditions, CB "D"@ 227 steps, RCS boron-100 Conditions:

ppm.

Turnover:

Maintain 1 00% power.

"A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B.

Critical Tasks:

1. CT -50 (FR-S.l.A) Crew isolates the main turbine
2. CT -3 (E-O.E) Crew manually actuates CIB
3. CT-11 (E-0.0) Crew closes cnmt isolation valves Event Event Type Event Description No.

1 (TS) SRO RCS loop 1, ch III, flow transmitter, FT-1RC-416 fails low.

2 (C) ATC, SRO River water pump, 1 WR-P-1A trips, requiring manual start of (TS) SRO 1WR-P-1B.

3 (C) ATC, SRO "B" RCP thermal barrier leak/ TV -1 CC-1 07B fails to auto close on high flow, requires manual closure.

4 (R) ATC "B" S/G feedwater leak inside CNMT requiring an unplanned (N) BOP, SRO power reduction per AOP 5

"B" feedwater leak increases once power is reduced to 94%.

(M) ALL Reactor fails to trip from the control room, requires entry into FR-S.l.

6 (M) ALL Upon Rx trip, all 3 steam lines fault.

7 (I) BOP, SRO Automatic main steam line isolation failure, requires manual main steam line isolation.

8 Train "B" CIA fails to actuate along with train "A" valve (I) ATC, SRO MOV-1CH-378 failing to automatically close, ATC must manually actuate CIA or close MOV-1CH-378.

9 (I) ATC, SRO Automatic CIB actuation failure, requires manual actuation.

10 (C) BOP, SRO Control room dampers, 1VS-D-40-1A, 1B, 1C and lD fail to automatically close, requires manual closing.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

A d" D 1ppen 1x 5

  • o tr cenar.o u me 1L14N1 Facility:

BVPS Unit 1 Scenario No. 1 Op Test No.:

1LOT14 NRC Examiners:

Operators:

SRO ATC BOP Initial IC 68(29): 100% power, EOL, Equ. XE Conditions, CB "D" @ 227 steps, RCS boron - 100 Conditions:

ppm.

Turnover:

Maintain 100% power.

"A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B.

Critical Tasks:

1. CT -50 (FR-S.l.A) Crew isolates the main turbine
2. CT -3 (E-O.E) Crew manually actuates CIB
3. CT-11 (E-0.0) Crew closes cnmt isolation valves Event Event Type Event Description No.

I 1

(

C:l T~} gR:o RO;; leefl 1, eh IlL -tle'<v tFaRsmiHeF. Fl' I RG,~ l i tail~; lev,z.

2 (C) ATC, SRO River water pump, 1 WR-P-1 A trips, requiring manual start of (TS) SRO 1WR-P-1B.

3 (C) ATC, SRO "B" RCP thermal barrier leak/ TV -1 CC-1 07B fails to auto close on high flow, requires manual closure.

4 (R) ATC "B" S/G feedwater leak inside CNMT requiring an unplanned (N) BOP, SRO power reduction per AOP 5

"B" feedwater leak increases once power is reduced to 94%.

(M) ALL Reactor fails to trip from the control room, requires entry into FR-S.l.

6 (M)ALL Upon Rx trip, all 3 steam lines fault.

7 (I) BOP, SRO Automatic main steam line isolation failure, requires manual main steam line isolation.

8 Train "B" CIA fails to actuate along with train "A" valve (I) ATC, SRO MOV-1CH-378 failing to automatically close, ATC must manually actuate CIA or close MOV-1CH-378.

9 (I) ATC, SRO Automatic CIB actuation failure, requires manual actuation.

10 (C) BOP, SRO Control room dampers, lVS-D-40-lA, lB, lC and ID fail to automatically close, requires manual closing.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

A d" D

~ppen IX s

  • o tr cenano u me 1L14N2 Facility:

FENOC BVPS Unit 1 Scenario No.:

2 Op Test No.:

1LOT14 NRC Examiners:

Operators:

SRO ATC BOP Initial IC 67(17): 65% power, MOL, Equ. XE Conditions, CB "D" @ 177 steps, RCS boron -

Conditions:

1102 ppm.

Turnover:

Maintain current power level.

1FW-P-3B OOS for maintenance, with lFW-P-2 aligned to "B" header IA W TS 3.7.5, Condition B.

Control rods are in manual due to I&C MSP in progress.

Critical Tasks:

1. CT -4 (E-O.F) Establish AFW flow
2. CT-18 (E-3.A) Isolate ruptured SG
3. CT -20 (E-3.C) Crew depressurizes RCS
4. CT -21 (E-3.D) Crew terminates SI Event Malf. No.

Event Type Event Description No.

1 (C) ATC, SRO lA charging pump trip, requires manual starting of lB.

(TS) SRO 2

(C) ATC, SRO 200 gpd "B" steam generator tube leak (TS) SRO 3

(R) ATC Main feed pump, lFW-P-lB trips, requires rapid power (N) BOP, SRO reduction (AOP 1.24.1) 4 (M) ALL "B" Main feed regulating valve, FCV -1 FW -488 fails shut, leads to a Rx trip with a loss of offsite power.

5 Turbine driven aux feed pump, lFW-P-2 trips on overspeed (C) BOP, SRO and motor driven aux feed pump, 1FW-P-3A fails to auto start, requiring manual start of 1FW-P-3A.

6 (M) ALL 500 gpm SGTR in the "B" steam generator.

7 Main steam line isolation valve on the ruptured SG, TV-lMS-(C) BOP, SRO 101 B failed open, requires the crew to perform an alternate MSLI alignment.

8 (C) ATC, SRO PRZR PORV fails open during depressurization requires closing of block valve.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

Appendix D Scenario Outline 1L14N3 Facility:

FENOC BVPS Unit 1 Scenario No.:

3 Op Test No.:

1LOT14 NRC Examiners:

Operators:

SRO ATC BOP Initial IC 211: 5% power, BOL, Equ. XE Conditions, CB "D"@ 114 steps, RCS boron-1851 Conditions:

ppm.

Turnover:

Raise Power to 10-14% to place turbine online.

Critical Tasks:

1. CT-12 (E-O.P), Manually actuate SLI
2. CT -17 (E-2.A), Isolate faulted SG
3. CT -48 (FR-P.l.A), Terminate ECCS flow I challenge to the integrity CSF Event Malf. No.

Event Type Event Description No.

1 (R) ATC Raise Power to 10-14%

(N) SRO 2

(C) BOP, SRO Leak collection exhaust fan, 1 VS-F-4A trips, requiring manual (TS) SRO start of 1 VS-F-4B 3

(C) ATC, SRO Charging flow control valve, FCV-1CH-122 fails shut in AUTO, requires manual control of PRZR level.

4 (I) BOP, SRO Main steam header pressure transmitter, PT-1MS-464 fails low, requiring manual control of condenser steam dumps.

(C) BOP, SRO SG atmospheric relief valve, PCV -1 MS-1 01 B fails open, 5

(TS) SRO requires manual control of condenser steam dumps during failure and local operator isolation.

6 (M) ALL Steam Break inside cnmt on "B" SG 7

(I) BOP, SRO SLI auto actuation failure, requires manual MSLI.

8 (C) BOP, SRO Aux feedwater control valve failed open, requires alternate isolation method.

9 (I) BOP, SRO Control room emergency ventilation system fails to actuate on CIB signal, requiring manual initiation.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev 1

A d" D lppen IX 5

  • o tr cenano u me 1L14N4 Facility:

BVPS Unit 1 Scenario No.:

4 Op Test No.:

1LOT14 NRC Examiners:

Operators:

SRO ATC BOP Initial IC 62(18): 81% power, MOL, Equilibrium Xe, CB "D"@ 206 steps, RCS boron-1012 Conditions:

ppm.

Turnover:

Rx is at 81% power due to isolating the condenser "D" Waterbox for cleaning.

"A" Train Priority, 1FW-P-3B is OOS with 1FW-P-2 aligned to the "B" header lAW TS 3.7.5, Condition B.

Critical Tasks:

1. CT-1 (E-O.A)- Manually Trip Reactor
2. CT -6 (E-0.1) - Establish 1 train of HHSI
3. CT-16 (E-l.C)- Manually trip RCPs Event Malf. No.

Event Type Event Description No.

1 (C) ATC, SRO The 1A boric acid transfer pump trips requiring aligning the (TS) SRO standby train for service.

2 (TS) SRO Ch 2, cnmt pressure transmitter, PT-1LM-100B, fails high.

3 (R) ATC Cooling tower pump, CT-P-1C trips, causing degraded (N) BOP, SRO condenser vacuum, requiring power reduction.

4 (I) ATC, SRO Auto rod insertion fails on load reduction, A TC manually controls Tavg.

5 (M) ALL Condenser Low-Low vacuum causes turbine trip.

6 (I) ATC, SRO Auto Rx trip fails to occur, requires A TC to manually trip the reactor from BB-A.

7 Exciter circuit breaker fails to auto open on Rx trip, requires (C) BOP, SRO BOP to manually trip the exciter circuit breaker.

8 (M) ALL 1500 GPM LOCA one minute after Rx trip.

9 "A" charging pump, 1 CH-P-1A trips, and "B" charging pump, (C) ATC, SRO 1CH-P-1B fails to auto start on Safety Injection, requiring manual start.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 1

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