ML16034A138

Final Outlines (Folder 3)

ML16034A138
Person / Time
Site:	Beaver Valley
Issue date:	11/30/2015
From:	Peter Presby Operations Branch I
To:	Ronnenberg D FirstEnergy Nuclear Operating Co
Shared Package
ML15161A011	List: IR 05000412/2016301 ML15194A008 ML15334A437 ML15345A016 ML15355A238 ML15355A239 ML15355A241 ML15355A242 ML15355A243 ML15355A244 ML16034A138 ML16034A193 ML16034A218 ML16034A473 ML16042A442
References
U01906
Download: ML16034A138 (31)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Beaver Valley Unit 2 RO Date of Exam 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 1.

3 3 3 3 18 Emergency 2

& 2 1 2 2 9 Abnormal Plant Tier Evolutions Totals 5 4 5 5 27 1

2.

2 2 3 3 3 2 2 3 2 3 3 28 Plant Systems 2 0 1 1 2 1 1 1 0 1 1 1 10 Tier Totals 2 3 4 5 4 3 3 3 3 4 4 38 1 2 3 4 10

3. Generic Knowledge and Abilities Category 2 3 2 3 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).

(One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-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 with justification; 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 (I Rs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #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.

G* Generic KIAs NUREG-1021, Revision 10 RO Page 1of13 FENOC Facsimile r2

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

E/APE #I Name I Safety Function K K K KIA Topic(s) IR #

1 2 3 000007 Reactor Trip I 1 EK2 Knowledge of the interrelations between a 3.5 reactor trip and the following:

[Question 1]

EK2.03 Reactor trip status panel (CFR 41.7 / 45.7) 000008 Pressurizer (PZR) Vapor Space AK1 Knowledge of the operational implications of 3.2 Accident (Relief Valve Stuck Open) I 3 the following concepts as they apply to a Pressurizer Vapor Space Accident:

[Question 2]

AK1 .01 Thermodynamics and flow characteristics of 1: . . open or leaking Valves

• • .. (CFR 41.8 / 41.10 I 45.3) 000015/000017 Reactor Coolant Pump AK2 Knowledge of the interrelations between the 2.9 (RCP) Malfunctions I 4 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

[Question 3] AK2.07 RCP seals (CFR 41.7 I 45.7) 000022 Loss of Reactor Coolant Makeup I AK1 Knowledge of the operational implications of 3.0 2 the following concepts as they apply to Loss of Reactor Coolant Makeup:

[Question 4] AK1 .03 Relationship between charging flow and PZR level (CFR 41.8 I 41.10 I 45.3)

Otvu25 Loss of Residual Heat Removal AA2 Ability to determine and interpret the following 3.3*

System (RHRS) I 4 as they apply to the Loss of Residual Heat Removal System:

[Question 5] AA2.04 Location and isolability of leaks (CFR: 43.5 I 45.13) 000026 Loss of Component Cooling Water AK3 Knowledge of the reasons for the following 4.0 (CCW) I 8 responses as they apply to the Loss of Component Cooling Water:

[Question 6] AK3.03 Guidance actions contained in EOP for Loss ofCCW (CFR 41.5,41.10 I 45.6 I 45.13) 000027 Pressurizer Pressure Control 2.1.28 Knowledge of the purpose and function of 4.1 System (PZR PCS) Malfunction I 3 major system components and controls.

(CFR: 41. 7)J

[Question 7]

000029 Anticipated Transient Without EK2 Knowledge of the interrelations between the 2.9*

Scram (ATWS) I 1 and the following an ATWS:

EK2.06 Breakers, relays, and disconnects

[Question 8]

(CFR 41.7 I 45.7)

NUREG-1021, Revision 10 RO Page 2of13 FENOC Facsimile r2

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

000038 Steam Generator Tube Rupture EK3 Knowledge of the reasons for the following 3.6*

(SGTR) / 3 responses as the apply to the SGTR:

EK3.03 Automatic actions associated with high

[Question 9] radioactivity in SIG sample lines (CFR 41.5 I 41.10 I 45.6 I 45.13) 000054 Loss of Main Feedwater (MFW) / 4 AA2 Ability to determine and interpret the following 4.1 as they apply to the Loss of Main Feedwater (MFW):

[Question 1OJ AA2.02 Differentiation between loss of all MFW and trip of one MFW pump (CFR: 43.5 I 45.13) 000055 Loss of Offsite and Onsite Power 2.4.18 Knowledge of the specific bases for EOPs. 3.3 (Station Blackout) 16 (CFR: 41.10/43.1 /45.13)

[Question 11]

000056 Loss of Offsite Power 16 AK1 Knowledge of the operational implications of 3.7 the following concepts as they apply to Loss of Offsite Power:

[Question 12]

AK1 .01 Principle of cooling by natural convection (CFR 41.8 I 41.10 I 45.3) 57 Loss of Vital AC Electrical AA2 Ability to determine and interpret the following 3.7 Instrument Bus/ 6 as they apply to the Loss of Vital AC Instrument Bus:

[Question 13]

AA2.03 RPS panel alarm annunciators and trip indicators (CFR: 43.5 I 45.13) 000062 Loss of Nuclear Service Water/ 4 AK3. Knowledge of the reasons for the following 3.5 responses as they apply to the Loss of Nuclear

[Question 14] Service Water:

AK3.04 Effect on the nuclear service water discharge flow header of a loss of CCW (CFR 41.4, 41.8 I 45.7) 000065 Loss of Instrument Air I 8 2.4.4 Ability to recognize abnormal indications for 4.5 system operating parameters that are entry-level conditions for emergency and abnormal operating

[Question 15] procedures.

(CFR: 41.10 I 43.2 I 45.6) 000077 Generator Voltage and Electric Grid AA 1 Ability to operate and/or monitor the following 4.1 Disturbances/ 6 as they apply to Generator Voltage and Electric Grid Disturbances:

[C' --stion 16] AA 1.04 Reactor controls (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8)

NUREG-1021, Revision 10 RO Page 3of13 FENOC Facsimile r2

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

W/E11 Loss of Emergency Coolant X i~~l~ )r; EA 1 Ability to operate and I or monitor the following 3.7

~ i;,4 ,;~

Recirculation I 4 1 :: as they apply to the (Loss of Emergency Coolant Recirculation)

[Question 17] EA1 .3 Desired operating results during abnormal and emergency situations (CFR: 41. 7 / 45.5 / 45.6)

W/E12 Uncontrolled Depressurization of all EA 1 Ability to operate and I or monitor the following 3.6 Steam Generators /4. as they apply to the (Uncontrolled Depressurization of all Steam Generators)

[Question 18] EA 1.2 Operating behavior characteristics of the facility.

(CFR: 41. 7 I 45.5 / 45.6) 3 3 3 3 3 3 KIA Category Point Totals: Group Point Total: 18 NUREG-1021, Revision 10 RO Page 4of13 FENOC Facsimile r2

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 KIA Topic(s) IR #

000033 Loss of Intermediate Range AK1 Knowledge of the operational implications of the 2.7 Nuclear Instrumentation I 7 following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:

AK1 .01 Effects of voltage changes on performance

[Question 19]

(CFR 41.8 I 41.10 I 45.3) 000059 Accidental Liquid Radwaste AA2 Ability to determine and interpret the following 2.9 Release /9 as they apply to the Accidental Liquid Radwaste Release:

[Question 20] AA2.02 The permit for liquid radioactive-waste release (CFR: 43.5 / 45.13) 000067 Plant fire on site I 9 AK3 Knowledge of the reasons for the following 3.3 responses as they apply to the Plant Fire on Site:

AK3.04 Actions contained in EOP for plant fire on

[Question 21]

site (CFR 41.5,41.10 / 45.6 / 45.13) 000068 Control Room Evacuation I 8 AK2 Knowledge of the interrelations between the 3.7 Control Room Evacuation and the following:

[Question 22]

AK2.02 Reactor trip system (CFR 41.7 / 45.7) 000069 Loss of Containment Integrity I 5 AK3 Knowledge of the reasons for the following 3.8*

responses as they apply to the Loss of Containment

[Question 23] Integrity:

AK3.01 Guidance contained in EOP for loss of containment integrity (CFR 41.5,41.10 I 45.6 / 45.13)

W/E02 SI Termination/ 3 2.2.44 Ability to interpret control room indications to 4.2 verify the status and operation of a system, and

[Question 24] understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 I 45.12)

W/E03 LOCA Cooldown and EK1 Knowledge of the operational implications of the 3.6 Depressurization I 4 following concepts as they apply to the (LOCA Cooldown and Depressurization)

[Question 25] EK1 .2 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).

(CFR: 41.8 / 41.10 / 45.3)

NUREG-1021, Revision 10 RO Page 5of13 FENOC Facsimile r2

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

1 2 3 W/E07 Saturated Core Cooling / 4 EA 1 Ability to operate and I or monitor the following 3.6 as they apply to the (Saturated Core Cooling)

[Question 26]

EA 1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41. 7 / 45.5 / 45.6)

W/E13 Steam Generator Overpressure/ 4 2.1.23 Ability to perform specific system and 4.3 integrated plant procedures during all modes of plant

[Question 27] operation.

(CFR: 41.10 I 43.5 / 45.2 / 45.6) 2 1 2 1 1 2 KIA Category Point Totals: Group Point Total: 9 NUREG-1021, Revision 10 RO Page 6of13 FENOC Facsimile r2

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 Al~~ KIA Topic(s) JR #

1 2 3 4 5 6 1 .' 3 41:*~;.

003 Reactor Coolant Pump K2 Knowledge of bus power supplies to the 3.1 System (RCPS) following:

[Question 28] K2.01 RCPS Ir*: (CFR: 41.7) 004 Chemical and Volume K5 Knowledge of the operational implications 2.5 Control System of the following concepts as they apply to the

[Question 29] eves:

K5.14 Reduction process of gas concentration in RCS: vent accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)

(CFR: 41.5/45. 7) 005 Residual Heat Removal K2 Knowledge of bus power supplies to the 2.7*

System (RHRS) following:

[Question 30] K2.03 RCS pressure boundary motor-operated valves (CFR: 41.7) 006 Emergency Core Cooling A3 Ability to monitor automatic operation of the 3.6*

System (ECCS) ECCS, including:

r- 'Stion 31]

. A3.07 RHR pumps I.*.* . (CFR: 41.7 / 45.5) h.

006 Emergency Core Cooling K4 Knowledge of ECCS design feature(s) 2.6 System (ECCS) and/or interlock(s) which provide for the

[Question 32] following:

K4.01 Cooling of centrifugal pump bearings (CFR: 41.7) 007 Pressurizer Relief K4 Knowledge of PRTS design feature(s) 2.6 Tank/Quench Tank System and/or interlock(s) which provide for the (PRTS) following:

[Question 33]

.*r. K4.01 Quench tank cooling

<CFR: 41.7) 008 Component Cooling Water 1 2.2.38 Knowledge of conditions and limitations 3.6 System (CCWS) ~~**~ in the facility license.

[Question 34]

1::~1.:.

I;~~ (CFR:41.7/41.10/43.1/45.13) f:~\C 008 Component Cooling Water ) K3 Knowledge of the effect that a loss or 4.1 System (CCWS) malfunction of the CCWS will have

[Question 35] on the following:

~)

010 Pressurizer Pressure 1  :~:1 A3 Ability to monitor automatic operation of the 3.6 Cnntrol System (PZR PCS) l**~i~:. PZR PCS, including:

stion 36]

1.:*. F:* A3.02 PZR pressure

\*' (CFR: 41. 7 I 45.5)

NUREG-1021, Revision 10 RO Page 7of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued System # I Name K 1

K 2

K 3

K 4

K K A 5 6 1 ~1~

~:; A 3

A 4

1:,'.J~ KIA Topic(s) IR #

012 Reactor Protection System Ji!1\ K6 Knowledge of the effect of a loss or 1

~ 2.9

/~~.:

(RPS) malfunction of the following will have on the

[Question 37) f)'\': RPS:

~;t

~-i K6.02 Redundant channels

,) (CFR: 41. 7 I 4517)

K5 Knowledge of the operational implications i~it I

013 Engineered Safety Features ~ 2.9 1 Actuation System (ESFAS) of the following concepts as they apply to the ESFAS:

[Question 38)  !;),:! 111

• 111 K5.02 Safety system logic and reliability i~*:;)~:  !,\::

c:;;,. (CFR: 41.5 / 45.7) 1~

.~

022 Containment Cooling A2 Ability to (a) predict the impacts of the 2.9* 1 System (CCS) IJ0 following malfunctions or operations on the

.: CCS; and (b) based on those predictions, use

[Question 39) procedures to correct, control, or mitigate the f'J~

i .

J 1,'11'1 J , ** ,

consequences of those malfunctions or operations:

A2.04 Loss of service water l~:i '  :~:1,;~1 (CFR: 41.5 / 43.5 / 45.3 / 45.13) r ~.'~Lf:

022 Containment Cooling J:fC ~

A4 Ability to manually operate and/or monitor 3.8 1 System (CCS) 1:1,' in the control room:

J

[Question 40] (1:,

• ,.. *~ A4.05 Containment readings of temperature, I pressure, and humidity system.

... i

,1

, .. J (CFR: 41. 7 I 45.5 to 45.8) 026 Containment Spray System

~

J '*; f;'.; ~:, A 1 Ability to predict and/or monitor changes in 3.9 1 (CSS) 1:1' parameters (to prevent exceeding design

~

limits) associated with operating the CSS 1:~~1

[Question 41]

controls including:

l~~t A 1.01 Containment pressure

• ,:.;/ (CFR: 41.5 / 45.5) 026 Containment Spray System 2.1.23 Ability to perform specific system and (CSS)

!,f,:, ,;~ integrated plant procedures during all modes 4.3 1

~'.~

[Question 42) of plant operation.

i;2i; (CFR

41.10 I 43.5 / 45.2 / 45.6) 039 Main and Reheat Steam 1;1  ;: K3 Knowledge of the effect that a loss or

~ 3.2* 1 System (MRSS)

J  ;

i',~ malfunction of the MRSS will have on the following:

[Question 43) 111

/ K3.03 AFW pumps.

'. J

~~;;;, (CFR: 41. 7 I 45.6) 039 Main and Reheat Steam System (MRSS)

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

4.6 1

[1  ;

[Question 44) .:' '°\ (CFR: 41.10 / 43.5 / 45.13)

NUREG-1021, Revision 10 RO Page 8of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1{RO) Continued

"",~

System # I Name K 1

K 2

K 3

K K 4 5 K

6 A

1 i~~

A 3 ~11~~ KIA Topic(s) IR #

~{

059 Main Feedwater (MFW) ~,\~ ) A4 Ability to manually operate and monitor in 3.1* 1 System the control room:

(Question 45]

• • ~~ A4.01 MFW turbine trip indication (CFR: 41. 7 / 45.5 to 45.8)

~ ~

_~

059 Main Feedwater (MFW) A2 Ability to (a) predict the impacts of the 3.4* 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 consequences of those malfunctions or i~* ~\: operations:

1'r;J;

',* *~:~ A2.01 Feedwater actuation of AFW system

• : (CFR: 41.5 / 43.5 I 45.3 / 45.13) x

• ~

061 Auxiliary I Emergency 1: :: KS Knowledge of the operational implications 3.2 1 Feedwater (AFW) System

~:~;,: of the following concepts as the apply to the AFW:

1,*r~

(Question 47]

f~;~

K5.02 Decay heat sources and magnitude

,'i :;; (CFR: 41.5 / 45.7) 062 AC Electrical Distribution System ~~~ 1,~~t: A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ac 2.7 1

[Question 48] I~,~~ J~ distribution system; and (b) based on those predictions, use procedures to correct, control,

0~~

1: .  ::;;,: or mitigate the consequences of those I'::*.* malfunctions or operations:

,. i'.1~*~

A2.08 Consequences of exceeding voltage

.. '~,

I\~

limitations

'I .i (CFR: 41.5 / 43.5 / 45.3 / 45.13) 063 DC Electrical Distribution ) i;:~'; fj:~. K1 Knowledge of the physical connections 2.7 1 System  :;;[; and/or cause effect relationships between the (Question 49]  ;;~ ,,*

i

~~;i DC electrical system and the following systems:

~~~i K1 .02 AC electrical system (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 064 Emergency Diesel ~.;c: K6 Knowledge of the effect of a loss or

) .. 2.7 1 Generator (ED/G) System malfunction of the following will have on the

iS' ~~

:,, ED/G system:

(Question 50] *:*. :

,:,.:: i :j

'S,,.'

K6.07 Air receivers

\:~;  ::£~ (CFR: 41.7 / 45.7)

[i~

073 Process Radiation ) ;in:;: K3 Knowledge of the effect that a loss or 3.6 1 Monitoring (PRM) System malfunction of the PRM system will have on

• ~~

[Question 51] the following:

I~ K3.01 Radioactive effluent releases (CFR: 41.7 / 45.6)

NUREG-1021, Revision 10 RO Page 9of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued I,/\ \!,:;,

System #I Name 076 Service Water System K

1 K

2 K

3 K

4 K

5 K

6 ~b~

A 3

A 4 re KIA Topic(s)

A 1 Ability to predict and/or monitor changes in IR #

)( 2.6* 1 (SWS) parameters (to prevent exceeding design

[Question 52] limits) associated with operating the SWS controls including:

,, A 1.02 Reactor and turbine building closed

'~}

cooling water temperatures.

(CFR: 41.5 / 45.5) 078 Instrument Air System (IAS) K1 Knowledge of the physical connections

~Rt

• ~

)( 3.3* 1

[Question 53] and/or cause-effect relationships between the IAS and the following systems:

,G' I K1 .03 Containment air

(

',,:',i .,t~: '1 (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 103 Containment System *.:*':,, . :,~ K4 Knowledge of containment system design

)( 3.0* 1 feature(s) and/or interlock(s) which provide for

~~

[Question 54]

.\ the following:

Y,'

K4.01 Vacuum breaker protection (CFR: 41.7)

~r rn:i

~{:

103 Containment System )( it:~ A4 Ability to manually operate and/or monitor 3.1* 1

[Question 55] in the control room:

~

A4.09 Containment vacuum system

,~?.

(CFR: 41. 7 / 45.5 to 45,8) 2 2 3 3 3 2 2 3 2 3 3 KIA Category Point Totals: Group Point Total: 28 NUREG-1021, Revision 10 RO Page 10of13 FENOC Facsimile r2

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 :i'A, A A I~(~ KIA Topic(s) 1 2 3 4 5 6 1 j~~f 3 4 l!)f IR i==:=:=~c=======;:====c:======:========;====i=====T====il 001 Control Rod Drive System vi~"'~ A 1 Ability to predict and/or monitor changes in 3.7

[Question 56] "l~t~ parameters (to prevent exceeding design limits)

(* associated with operating the CRDS controls IJ\

~  :~,;~ including:

l~~~t~~ 'E:~,;.;; A 1.04 PZR level and pressures

';*. i'1:,1 (CFR: 41.5 / 45.5) 002 Reactor Coolant System A3 Ability to monitor automatic operation of the 4.4 (RCS) RCS, including:

[Question 57]

A3.03 Pressure, temperatures, and flows (CFR: 41.7 / 45.5) 011 Pressurizer Level Control K6 Knowledge of the effect of a loss or 3.1 System (PZR LCS) malfunction on the following will have on the

[Question 58] PZR LCS:

K6.05 Function of PZR level gauges as post accident monitors (CFR: 41.7 / 45.7) 028 Hydrogen Recombiner and }( K5 Knowledge of the operational implications of 3.4 Purge Control System (HRPS) the following concepts as they apply to the

[Question 59] HRPS:

K5.01 Explosive hydrogen concentration (CFR: 41.5 / 45. 7) r ";ontainment Purge System }( l'i; ;, K3 Knowledge of the effect that a loss or 2.9 (1... . .:i) I £ *~ malfunction of the Containment Purge System

[Question 60] *'* will have on the following:

K3.01 Containment parameters (CFR: 41. 7 / 45.6) 034 Fuel Handling Equipment  :(,/ ~ K4 Knowledge of design feature(s) and/or 2.6 System (FHES) ,... '1} interlock(s) which provide for the following:

[Question 61] I: * ,

f'.( 'i~~* K4.03 Overload protection (CFR: 41.7)

I If-------+--+--+--+--+---+--+---+

035 Steam Generator System }( t*

~--~-----+---+---ll K4 Knowledge of S/GS design feature(s) and/or 2.9 (S/GS) ~- interlock(s) which provide for the following:

[Question 62]

K4.05 Amount of reserve water in S/G (CFR: 41.7) 045 Main Turbine Generator A4 Ability to manually operate and/or monitor in 3.1 (MT/G) System the control room:

[Question 63]

A4.01 Turbine valve indicators (throttle, governor, control, stop, intercept), alarms, and annunciators (CFR: 41.7 / 45.5 to 45.8)

NUREG-1021, Revision 10 RO Page 11 of 13 FENOC Facsimile r2

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 KIA Topic(s)

IR #

1 2 3 4 5 6 1 072 Area Radiation Monitoring 2.4.46 Ability to verify that the alarms are 4.2 (ARM) System consistent with the plant conditions.

[Question 64) (CFR: 41.10 I 43.5 I 45.3 I 45.12) 075 Circulating Water System K2 Knowledge of bus power supplies to the 2.6*

[Question 65] following:

K2.03 Emergency/essential SWS pumps (CFR: 41.7)

KIA Category Point Totals: 0 1 1 2 1 1 1 0 1 1 1 Group PointTotal: 10 NUREG-1021, Revision 10 RO Page 12of13 FENOC Facsimile r2

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

ility

Beaver Valley Unit 2 RO Date of Exam 12/7 thru 12/18 2015 RO Category KIA# Topic IR #

1. 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, 4.1 Conduct switches, etc.

of Operations (CFR: 41.10 / 45.1 / 45.12)

[Question 66]

2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 1 response of another indication.

(CFR: 41.7 / 43.5 / 45.4)

[Question 67]

Subtotal

2. 2.2.6 Knowledge of the process for making changes to procedures.

Equipment (CFR: 41.10 / 43.3 / 45.13)

Control [Question 68]

2.2.15 Ability to determine the expected plant configuration using design and 3 .9 configuration control documentation, such as drawings, line-ups, tag-outs, etc.

(CFR: 41.10 / 43.3 / 45.13)

[Question 69]

2.2.39 Knowledge of less than or equal to one hour Technical Specification 3 .9 action statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

Question 70 Subtotal

3. 2.3.7 Ability to comply with radiation work permit requirements during normal Radiation or abnormal conditions.

Control (CFR: 41.12 / 45.10)

[Question 71]

2.3.13 Knowledge of radiological safety procedures pertaining to licensed 3 .4 operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

[Question 72]

Subtotal

4. 2.4.6 Knowledge of EOP mitigation strategies.

Emergency (CFR: 41.10 / 43.5 / 45.13)

Procedures/ [Question 73]

Plan 2.4.25 Knowledge of fire protection procedures. 3.3 (CFR: 41.10 / 43.5 / 45.13)

[Question 74]

2.4.39 Knowledge of RO responsibilities in emergency plan implementation. 3.9 (CFR:41.10/45.11)

Question 75 Subtotal 11~r 3 Point Total NUREG-1021, Revision 10 RO Page 13of13 FENOC Facsimile r2

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

SRO ONLY Points Tier Group A2 G* TOTAL 1

3 3 6 1.

Emergency 2

& 2 2 4 Abnormal Plant Tier Totals 5 5 10 Evolutions 1

2. 3 2 5 Plant Systems 2 0 2 1 3 Tier Totals 5 3 8 1 2 3 4

3. Generic Knowledge and 7 Abilities Category 2 1 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).

(One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-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 with justification; 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 (I Rs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #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, !Rs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

G* Generic KIAs NUREG-1021, Revision 10 SRO Page 1 of 6 FENOC Facsimile Rev. r2

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

~

E/APE #I Name I Safety Function K K K A KIA Topic(s) IR #

1 2 3 1 000009 Small Break LOCA / 3 4 EA2 Ability to determine or interpret the following as 3.9 1

[Question 76)  :.:'*; they apply to a small break LOCA:

t  :~

EA2.05 The time available for action before PZR is I I~

empty, given the rate of decrease of PZR level (CFR 43.5 / 45.13)

.:'.'.~

~ I~

000011 Large Break LOCA I 3 2.4.41 Knowledge of the emergency action level 4.6 1

[Question 77) thresholds and classifications.

(CFR: 41.10 I 43.5 / 45.11) 000040 Steam Line Rupture I 4 AA2 Ability to determine and interpret the following 4.5 1

"* 10

[Question 78) as they apply to the Steam Line Rupture:

ij ~

?i:Fi  :~,

AA2.05 When ESFAS systems may be secured (CFR: 43.5 / 45.13)

'~

.0~ ;,~.,

• ,::;:;rt 000058 Loss of DC Power / 6 Ji~ 2.2.25 Knowledge of the bases in Technical

'<%:" 4.2 1

[Question 79) "' Specifications for limiting conditions for operations

~', ";,

,:  :;, and safety limits.

d  :~;

1*~:':: :; (CFR: 41.5 / 41.7 / 43.2)

-v ii' :~;~~

4 LOCA Outside Containment I 3 I'~*:: *it)( 2.4.11 Knowledge of abnormal condition procedures. 4.2 1

[Question 80) (CFR: 41.10 / 43.5 / 45.13)

'r!. ~1 ill t~

~'~

W/E05 Loss of Secondary Heat Sink I 4 EA2 Ability to determine and interpret the following i

4.4 1

[Question 81) as they apply to the (Loss of Secondary Heat Sink)

,,~

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and I~

emergency operations.

i,4:r i~!t (CFR: 43.5 / 45.13)

'.~:;*1 '~~

3 3 6 KIA Category Point Totals: Group Point Total:

NUREG-1021, Revision 10 SRO Page 2 of 6 FENOC Facsimile Rev. r2

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

'=/APE #I Name I Safety Function K K K A

"'i*'

KIA Topic(s) IR #

1 2 3 1 ~t. !'.

000003 Dropped Control Rod / 1 2.2.36 Ability to analyze the effect of maintenance 4.2 1

[Question 82] activities, such as degraded power sources, on the status of limiting conditions for operations.

(CFR: 41.10 / 43.2 / 45.13)

i 000024 Emergency Boration / 1 "' 2.1.23 Ability to perform specific system and 4.4 1

[Question 83]  ;~~ I::~~ integrated plant procedures during all modes of plant operation.

~}r,;,,,, 11\ (CFR: 41.10 / 43.5 / 45.2 / 45.6)

W/E06 Degraded Core Cooling I 4 ~i;i\j ii EA2 Ability to determine and interpret the following 4.2 1

[Question 84] c.'.'.'f'cJ as they apply to the (Degraded Core Cooling) l.~t, ir~~; EA2.1 Facility conditions and selection of appropriate procedures during abnormal and I~~~J: ,\~~ { emergency operations.

(CFR: 43.5 / 45.13)

I' W/E09 Natural Circulation Operations I 4 EA2 Ability to determine and interpret the following

I I~

3.8 1 as they apply to the (Natural Circulation Operations)

[Question 85]

EA2.2 Adherence to appropriate procedures and I;1: operation within the limitations in the facility's license

and amendments.

[,:r (CFR: 43.5 / 45.13)

~; ~ ;~~

KIA Category Point Totals: 0 0 0 0 2 2 Group Point Total: 4 NUREG-1021, Revision 10 SRO Page 3 of 6 FENOC Facsimile Rev. r2

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

System # I Name K K K K K K Ail'.~ A A KIA Topic(s) IR #

1 2 3 4 5 6 1 >2 3 4

~i~

003 Reactor Coolant Pump i~j!j A2 Ability to (a) predict the impacts of the 3.9 1 System (RCPS) following malfunctions or operations on the

[Question 86] RCPS; and (b) based on those predictions,

~r; use procedures to correct, control, or mitigate li:/;, the consequences of those malfunctions or operations:

~

~ 11 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a

'~ I* t 1~i:

normal shutdown of an RCP (CFR: 41.5 / 43.5/ 45.3 / 45/13)

I /i:~;:

~~. ~~

004 Chemical and Volume A2 Ability to (a) predict the impacts of the 3.3 1 Control System following malfunctions or operations on the

[Question 87] eves; and (b) based on those predictions, use procedures to correct, control, or mitigate 111,i~f the consequences of those malfunctions or

~

, operations:

It ~.

A2.33 Fact that isolating cation demineralizer 11 stops boron dilution and enables restoration of if normal boron concentration

~~)

(CFR: 41.5/ 43/5 / 45/3 / 45/5)

I: ~

h }

013 Engineered Safety Features I' tion System (ESFAS) ii:~*t; I~!~ 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, 4.3 1 rl~:*;

[Question 88] and notes.

'I ..

(CFR: 41.10143.5 I 45.13) 1,1~*1* ~:;l Ii *:r, I~)'

076 Service Water System (SWS) i: A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 3.1 1

[Question 89] *fi~'.\: SWS; and (b) based on those predictions, use Ii GI

(.i procedures to correct, control, or mitigate the consequences of those malfunctions or 1.f;

~ operations:

I~~: 1!

~~

A2.02 Service water header pressure

[t:1~ (CFR: 41.5 / 43.5 / 45/3 / 45/13) f '.f 078 Instrument Air System (IAS) h '**1, 2.4.34 Knowledge of RO tasks performed 4.1 1

[Question 90] I* ":' outside the main control room during an

!l\~:.I emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13) lr'.:*:1: '/

3 2 KIA Category Point Totals: Group Point Total: 5 NUREG-1021, Revision 10 SRO Page 4 of 6 FENOC Facsimile Rev. r2

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

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

'~'.~ KIA Topic(s) 033 Spent Fuel Pool Cooling 1 2 3 4 5 6 1 ;*

le 3 4 A2 Ability to (a) predict the impacts of the IR #

i7~ 1 3.5 1 System (SFPCS) following malfunctions or operations on the

[Question 91] 1+t Spent Fuel Pool Cooling System; and (b)

~;I~ based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations

1it

• ~~

A2.01 Inadequate SOM (CFR: 41.5 I 43.5 I 45.3 I 45.13)

~;

[.;i~

041 Steam Dump System 2.4.50 Ability to verify system alarm setpoints 4.0 1 (SDS)/Turbine Bypass Control  ;; ' and operate controls identified in the alarm

[Question 92] .-...;, response manual.

lC

':{:';  ; *J (CFR: 41.10 I 43.5 I 45.3)

1"*

lwi:' *.~th 079 Station Air System (SAS) 1;;; A2 Ability to (a) predict the impacts of the

[Question 93]  :*~* II following malfunctions or operations on the SAS; and (b) based on those predictions, use 3.2 1 1;~ procedures to correct, control, or mitigate the

• consequences of those malfunctions or

.,. ~

tti£ It c.

• ~v' operations:

h. ,, A2.01 Cross-connection with IAS

• . (CFR: 41.5 I 43.5 I 45.3 I 45.13) 11:*i

==

l.t.:

Kt!-. Category Point Totals: 2 1 Group Point Total: 3 NUREG-1021, Revision 10 SRO Page 5 of 6 FENOC Facsimile Rev. r2

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 lity: Beaver Valley Unit 2 SRO Date of Exam SRO Only Category KIA# Topic IR #

1. 2.1.4 Knowledge of individual licensed operator responsibilities related to shift 3.8 Conduct staffing, such as medical requirements, "no-solo" operation, maintenance of Operations of active license status, 10CFR55, etc.

(CFR: 41.10/43.2)

[Question 94]

2.1.36 Knowledge of procedures and limitations involved in core alterations. 4.1 (CFR: 41.10 / 43.6 / 45.7)

[Question 95)

Subtotal 2

2. 2.2.42 Ability to recognize system parameters that are entry-level conditions for Equipment Technical Specifications.

Control (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

[Question 96)

Subtotal 1

3. 2.3.4 Knowledge of radiation exposure limits under normal or emergency Radiation conditions.

Control (CFR: 41.12 / 43.4 / 45.10)

[Question 97) 2.3.11 Ability to control radiation releases. 4.3 (CFR: 41.11 / 43.4 / 45.10)

[Question 98)

Subtotal 2

4. 2.4.29 Knowledge of the emergency plan.

Emergency (CFR: 41.10 / 43.5 / 45.11)

Procedures/

[Question 99)

Plan 2.4.44 Knowledge of emergency plan protective action recommendations. 4.4 (CFR: 41.10 / 41.12 / 43.5 / 45.11)

[Question 100)

Subtotal 2 Tier 3 Point Total 7 NUREG-1021, Revision 10 SRO Page 6 of6 FENOC Facsimile Rev. r2

ES-401 Record of Rejected K/As Form ES-401-4 I Facility: Beaver Valle~ Unit 2 Date of Exam 12n thru 12/18 2015 Operating Test No.: BV2LOT15 NRC I

Tier I Randomly Reason for Rejection Group Selected KIA 1/1 000025 AA2.05 Question #5; Beaver Valley does not use Residual Heat Removal (RHRS) for Low Pressure Injection (LPI). Randomly selected 025 AA2.04 as a replacement.

1/1 057 AA2.11 Question #13; There is no interface between the MFP running indicator and controller, and the Vital AC busses at Beaver Valley. Reselect due to lack of applicability. Discussed with Chief Examiner. Randomly selected 057 AA2.03 as a replacement.

2/1 026 A1 .02 Question #41; Beaver Valley does not operate the CNMT Spray Sytem based on CNMT temperature. Procedurally the EOPs use CNMT pressure. The procedures do not refer to CNMT Temp for any control functions of CSS. Randomly selected 026A1.01 as a replacement.

2/1 059 A2.07 Question #46; Beaver Valley does not have MFW pump turbines.

Randomly selected 059 A2.01 as a replacement.

2/2 041 G2.4.41 Question #92; 041 Steam Dump System (SDS)/Turbine Bypass Control 2.4.41 Knowledge of the emergency action level thresholds and classifications. Reselected due to oversampling. Similar to Q77 (011 G2.4.41 ). Randomly selected 041 G2.4.50 as a replacement.

2/1 013 G2.4.1 Question #88; G2.4.1, Knowledge of EOP entry conditions and immediate action steps. Unable to write a discriminatory SRO level question. The KIA is RO level knowledge. Randomly selected 013 G2.4.20 as a replacement.

2/2 034 K1.04 Question #61; K1 Knowledge of the physical connections and/or cause effect relationships between the Fuel Handling System and the following systems: NIS. Unable to write a discriminatory question. Randomly selected 034 K4.03 as a replacement.

1/2 WE02 G2.4.21 Question #24; 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Unable to write a discriminatory question. Randomly selected WE02 G2.2.44 as a replacement.

2/1 026 G2.2.12 Question #42; 2.2.12 Knowledge of surveillance procedures.

Unable to write a discriminatory question with the limited opportunities available with Cnmt Cooling surveillances. Randomly selected 026 G2.1.23 as a replacement.

NUREG-1021, Revision 10 FENOC Facsimile r2

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments Administrative JPMs

• Modify the Task Standard to match the direction given in the procedure, remove the statement to recommend no further rod withdrawal, add statement to insert all control rods.

RO A1.1

• Modify the Initial Conditions to add that the plant tripped from 100% power, clarify that this is not a startup following a refueling outage.

• Modify step 4.1 to remove recommended action then made step 4.2 critical.

Added procedure 20M-50.4.D as reference

• Modify the initial conditions to remove the statements related to turnover at beginning and end of shifts.

RO A1.2

• Modify the directions to document the reasons for determining if the license is active or inactive. (Note these comments were from the outline submittal, not walkthrough week)

RO

• Modify step 4 to address potential question and local operator action for A2 recirculation valves.

RO

• No comments .

A3

• Modify the Task Standard to match the direction given in the procedure, remove the statement to recommend no further rod withdrawal.

SRO

• Modify the Initial Conditions to add that the plant tripped from 100% power, clarify A1.1 that this is not a startup following a refueling outage.

• Modify step 4.1 to remove recommended action. Added procedure 20M-50.4.D as reference SRO

• No comments .

A1.2

• Add numbering to the Initiating Cue to define what the candidate is expected to perform and report. Modify step 4 note to include the possibility that the candidate may direct field manipulations of the recirculation valves. Modify step 8.3 to include the Shift manager may be one of the two approving SROs.

SRO A2

• Modify step 4 to address potential question and local operator action for recirculation valves.

• Modify Step 8 to note that the Shift Manager may be one of the two approving SR Os.

• Modify initial conditions to clarify that the worker (add name) has no previous accident or emergency exposure.

SRO A3

• Split initiating cue into two numbered parts.

1

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• Modify the Answer Key to identify the critical items on the form.

• Modify the initiating cue to include a statement that the General Announcement mas been made to the crew at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

SRO

• Add note to step 5 that refers to the critical items that are highlighted on the A4 answer key.

• The selection of "Drill" or "Actual Emergency" is not critical since this evaluation is performed in a classroom setting.

Simulator JPMs

• JPM is Alternate Path due to actions to align alternate flow path in the procedure .

S1 ES-301-2 (RO/SRO) modified.

• No changes to JPM .

• Added PAB Operator is stationed at 2SGC-RQl100 Radiation Monitor skid to the Initial conditions.

• Added cue for initial ORMS point 1065 being cyan due to expected RP actions .

• Added Booth Operator cue for annunciator A4-5H when venting sample lines .

• Added procedure steps to evaluator cues to help follow along with work direction .

Modified flowrates in JPM step 8 & 10 as requested.

S2

• Added evaluator note stating the completion of step 19.2 or 20.1 will meet the task standard.

• Removed critical step to verify position indication lights of 2SGC-HCV100 since the valve controller is actually the critical step.

• Made minor place keeping correction to procedure step IV.A.8.d of plant procedure.

• Corrected procedure step number on candidate direction sheet.

S3

• No changes to JPM .

S4

• Minor change of moving Booth Operator cue to precede step 15 .

• Corrected JPM steps 8 and 22 to state correct Data sheet 3 .

SS

• Changed Task Standard to "Annunciator A4-5H, "POWER RANGE HIGH/LOW SP FLUX DEVIATION/AUTO DEFEAT" verified by performing QPTR Alarm check with setpoints determined to be +/-10 µA of the answer key".

2

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• JPM is not alternate path, alarm is already in at the start of the JPM. ES-301-2 (RO/SRO) modified.

S6

• Removed pictures from JPM Word document and modified picture #1 to show high vibration values on the meters.

• Limited JPM picture use to 2 pictures, and modified appropriate Evaluator Cues .

• Separated JPM step 2 into two separate steps .

S7

• Changed old JPM step 3 to match procedure step.

• Clarified switches to be operated, and phases to be monitored when candidate is monitoring voltages SB

• Added bullet for 'CNMT is not accessible' in the Initial Conditions to prevent role play for an Operator in containment during the RCP startup.

Plant JPMs P1

• Added procedure steps 3 & 4 to JPM for ease of evaluating candidate .

P2

• No changes to JPM .

P3

• No changes to JPM .

Scenarios

• Page 2, Scenario outline, corrected SG pressure transmitter as channel 4 not channel 3.

• Throughout - added procedure titles to scripting .

Sc1

• Page 8, Added NOTE with information that crew is required to place alternate channel in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Page 9, Enhanced ROLE PLAYS for tripping of bistables .

• Throughout - added procedure titles to scripting .

• Page 11, Modified scripting to state that the crew may initially attempt to stabilize Sc2 SG level using manual control of the main feed regulating valve.

• Page 21, Added a NOTE and emphasis to components required to be verified/manipulated to meet requirements of CT-17, Isolation of a faulted SG.

3

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• Throughout - added procedure titles to scripting .

• Page 6, Enhanced ROLE PLAY for field operator identification of Safeguards Sc3 leak.

• Page 14, Enhanced ROLE PLAY for status of the turbine driven aux feedwater pump.

• Swapped events 1 and 2, added additional turnover information (oil leak) as a reason to swap Component cooling water pumps.

• Throughout - added procedure titles to scripting .

• Added additional CIA actuation individual component failure, 2HVP*MOD22B Sc4 failed to auto close, to event 10.

• Page 17, Added a NOTE and emphasis to components required to be verified/manipulated to meet requirements of CT-18, Isolation of a ruptured SG.

• Page 18, Scripted actions for cooldown if the main condenser is isolated due to a MSLI occurrence.

• Why does the MFRV need to be returned to Automatic Control?

General Per 20M-24.4.IF procedure, if not desired to trip Bistables for the Level Questions Channel (for example if another channel was already tripped), then the MFRV may be operated in Manual as long as a Basis For Continued Operation is generated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• How does the Brass coupling operate on the Trip Throttle valve .

The brass split coupling will move up and down with the stem of the valve.

General When the valve trips, the coupling will lower with the shaft and the valve Questions seats. When the handle is turned clockwise to raise the sliding nut to the latch position, the brass coupling will remain in the down position. After latching, when the handwheel is turned counter clockwise, the stem rises as does the brass coupling 4

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: 12/7 thru 12/18 2015 amination Level RO IXl SROD Operating Test Number BV2LOT15 NRC Administrative Type Describe activity to be performed Topic Code*

(See Note)

Conduct of D,R 2.1.43 (4.1)

Operations Ability to use procedures to determine the effects on reactivity of plant (RO A 1.1) changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

JPM 2AD-016 Plot and Evaluate 1/M Data Conduct of N,R 2.1.4 (3.3)

Operations Knowledge of individual licensed operator responsibilities related to (RO A 1.2) shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

JPM 3AD-023 Determine if License Status is Maintained Active (RO)

Equipment N,R 2.2.41 (3.5) 1trol Ability to obtain and interpret station electrical and mechanical (RO A 2) drawings.

JPM 2AD-048 Determine Isolation Boundary Points and Mark on PlantVOND Radiation Control D, R 2.3.11 (3.8)

(RO A 3) Ability to control radiation releases.

JPM 2AD-010 Determine GW Storage Tank Discharge Bleed Flow Rate Emergency Plan NOT EVALUATED (RO A 4)

• ,:, ::. *.:: :;~ 11S (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items).

• Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank <.::. 3 for ROs; .'.5. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.'.5. 1; randomly selected)

NUREG-1021, Revision 10 FENOC Facsimile rO

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: 12/7 thru 12/18 2015 r "lmination Level RO D SRO 00 Operating Test Number BV2LOT15 NRC Administrative Type Describe activity to be performed Topic (See Note) Code*

Conduct of D,R 2.1.43 (4.3)

Operations Ability to use procedures to determine the effects on reactivity of (SRO A 1.1) plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

JPM 2AD-019 Plot and Evaluate 1/M Data and Determine Required Actions Conduct of N,R 2.1.4 (3.8)

Operations Knowledge of individual licensed operator responsibilities related to (SRO A 1.2) shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

JPM 3AD-024 Evaluate Operators Work History to Determine if License Status is Active (SRO)

Equipment Control N, R 2.2.41 (3.9)

, <0 A 2) Ability to obtain and interpret station electrical and mechanical drawings.

JPM 2AD-049 Identify Isolation Boundary Points and Mark on Plant VOND then Identify Method of Plant Configuration Control Radiation Control M,R 2.3.4 (3.7)

(SRO A 3) Knowledge of radiation exposure limits under normal or emergency conditions.

JPM 2AD-038 Determine Emergency Exposure Authorization Limits Emergency Plan D,R 2.4.44 (4.4)

(SRO A 4) Knowledge of emergency plan protective action recommendations.

JPM 2AD-037 Determine Protective Action Recommendations (Part 1) 11 1\jv 1 E: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items).

• -**pe 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 (~ 1)

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

NUREG-1021, Revision 10 FENOC Facsimile rO

ES 301 C on t ro IRoom /I n-Pl an t S;ystems o utrme - -

Form ES 301 2 I Facility: Beaver Valle)£ Unit 2 Date of Examination: 12/7/ thru 12/18 201~ 11

~;::.,, Level: RO 00 SRO(I) D SRO(U) D Operating Test No.: BV2LOT15 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System I JPM Title Type Code* Safety Function S1 - Transfer to Hot Leg Recirculation (2CR-570) S,D,EN,A 3 S2 - Discharge Steam Generator Slowdown Evaporator Test Tank [2SGC- S,N,A 9 TK23A] to Unit 2 Cooling Tower Slowdown. (2CR-660)

S3 - Rod Control Assembly Partial Movement Test - (Rods continue to S,N,A 1 move during performance of the test) (2CR-747)

S4 - Batch to the Refuel Water Storage Tank (2CR-537) S,D 2 SS - Perform QPTR Alarm Test (2CR-144) S,D 7 S6 - Respond to Containment Air Recirculation Fan High Vibration Alarm S,N 5 (2CR-661)

S? - Perform a Hot Bus Transfer (2CR-523) S,D,A 6 SB - Start A Reactor Coolant Pump (2CR-513) S, D,A, L 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - Uninterruptible Power Supply [UPS*VITBS2-3(4)] Shutdown (2PL-021) D 6 P2 - Reset the Terry Turbine Trip Throttle Valve (2PL-004) D,R 4S P3 - Place the Diesel Air Compressor in Service (2PL-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 SRO-I 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  ::::11::::11::::1 (EN)gineered safety feature  :::: 1 I:::: 1 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 3/ s 3 Is 2 (randomly selected)

11::::11::::1 II (R)CA (S)imulator NUREG-1021, Revision 10 FENOC Facsimile r2

ES 301 C on t ro IRoom /I n-Pl an t SiYStems o utrme Form ES 301 2 - -

Facility: Beaver Valle~ Unit 2 Date of Examination: 12/7/ thru 12/18 2015 11 Exam Level: RO D SRO(I) !RI SRO(U) D Operating Test No.: BV2LOT15 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System I JPM Title Type Code* Safety Function S 1 - Transfer to Hot Leg Recirculation (2CR-570) S,D,EN,A 3 S2 - Discharge Steam Generator Slowdown Evaporator Test Tank [2SGC- S,N,A 9 TK23A] to Unit 2 Cooling Tower Slowdown. (2CR-660)

S3 - Rod Control Assembly Partial Movement Test - (Rods continue to S,N,A 1 move during performance of the test) (2CR-747)

S4 - Batch to the Refuel Water Storage Tank (2CR-537) S,D 2 S6 - Respond to Containment Air Recirculation Fan High Vibration Alarm S,N 5 (2CR-661)

S7 - Perform a Hot Bus Transfer (2CR-523) S,D,A 6 SS - Start A Reactor Coolant Pump (2CR-513) S, D,A, L 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - Uninterruptible Power Supply [UPS*VITBS2-3(4)] Shutdown (2PL-021) D 6 P2 - Reset the Terry Turbine Trip Throttle Valve (2PL-004) D,R 4S P3 - Place the Diesel Air Compressor in Service (2PL-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 SRO-I 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 ~1/~1/~1 (EN)gineered safety feature ~ 1 I~ 1 I.:::. 1 (control room system)

(L)ow-power I Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 3/ s 3 Is 2 (randomly selected)

(R)CA ~1/~1/~1 11 (S)imulator NUREG-1021, Revision 10 FENOC Facsimile r2

A,ppen d"1x D s cenano

. 0 utrme 2L15N1 Facility: BVPS Unit 2 Scenario No. 1 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO ATC BOP Initial IC-142(15): 48% power, MOL, Equ. XE Conditions, CB "D"@ 158 steps, RCS boron -

Conditions: 558 ppm.

Turnover: Maintain 48% power.

Critical Tasks: 1. CT-10 (E-0.M) Crew closes PORV block MOV

2. CT-13 (E-0.Q) Crew manually trips turbine

3. CT-43 (FR-H.1.A) Crew establishes feedwater flow Event Malf. No. Event Type Event Description No.

1 XMT-RCS019A (I,A) ATC, SRO Pressurizer level transmitter, 2RCS*LT459 drifts low.

(TS) SRO 2 XMT-MSS053A (I,A) BOP, SRO 2MSS*PT496 fails low over 30 sec, requires manual control of (TS) SRO 2FWS*FCV498.

3 RCS02A (C,A) ATC, SRO 30 gpm RCS leak (unisolable)

(TS) SRO 4 (R) ATC (N) BOP, SRO Ops management directed Emergency Shutdown, AOP 2.51.1.

5 RCS02A (M)ALL 400 gpm loop A LOCA , requires manual Rx trip 6 EHC08A (C) BOP, SRO Auto main Turbine trip failure 7 VLV-RCS034A 2RCS*PCV456 lifts/fails to reseat on Rx trip, requires manual (C)ATC, SRO closure ofMOV block valve, 2RCS*MOV536.

8 PMP-AFWOO 1, 2, Loss of all feed, Entry into FR-H.1, success path- main feed LOA-AFW022 (M)ALL 9 VLV- 2SSR-AOV117 A, B, C, SG BD sample line auto isolation MSC 104, 105, 106 (C) ATC, SRO failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ---+ FR-H.1 ---+ E-0 ---+ E-1 NUREG-1021, Revision 10 FENOC Facsimile r2

A endix D Scenario Outline 2L 15N2 Facility: BVPS Unit 2 Scenario No. 2 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO ATC BOP Initial IC-143 (10): 100% power, BOL, Equ. XE Conditions, CB "D"@ 227 steps, RCS boron -

Conditions: 1100 ppm.

Turnover: Maintain current plant conditions Critical Tasks: 1. CT-6 (E-0.1) Crew establishes SIS Flow

2. CT-52 (FR-S.1.C) Crew inserts negative reactivity

3. CT-17 (E-2.A) Crew isolates the faulted SG Event Event Type Event Description No.

1 XMT-MSS043A (R) ATC Load rejection - VPL failure, (N) BOP/SRO 20M-26.4.X 2 GEN02 (C,A) BOP/SRO MUG Voltage regulator overexcitation failure.

3 XMT-RCS030A (I,A) ATC/SRO 2RCS*PT444 drifts HIGH, PRZR pressure decreases, manual SROT.S. control of PRZR pressure required.

4 XMT-RCS002A SROT.S. "A" RCS loop flow transmitter, 2RCS*FT415, fails low.

5 FLX-CFW33 (M) ALL 2800 gpm Feedwater leak inside CNMT on "C" SG with an PPLOlA A TWS - Failure of auto/manual Rx trip on manual Rx trip PPLOlB attempt.

6 VLV-SIS069 2SIS*MOV867A and 2SIS*MOV867B auto open failure.

(C) ATC, SRO VLV-SIS070 7 VLV-MSC021, (C) BOP/SRO "B" Train Hydrogen Analyzer fails to automatically start on 023,024,025 SIS signal.

8 VLV-AFW014 (C) BOP/SRO AFW valve, 2FWE*HCV100B, fails to close from the CR.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ~ FR-S. l ~ E-0 ~ E-2 NUREG-1021, Revision 10 FENOC Facsimile r2

Appen d"1x D s cenario outme r 2L 15N4 II Facility: BVPS Unit 2 Scenario No. 4 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO I ATC BOP Initial IC 145: 4.8% power, MOL, Rx SIU in progress, CB "D" @ 105 steps, RCS bordn - 1349 Conditions: ppm.

Turnover: Due to an oil leak, SIU 2CCS-P21B and S/D 2CCS-P21A IAW 20M-28.4.H Raise power to 15% to SIU main turbine IAW 20M-52.4.A.

Critical Tasks: 1. CT-11 (E-0.0) CNMT isolation

2. CT-18 (E-3.A) Crew isolates ruptured SG

3. CT-19 (E-3.B) Crew establishes/maintains RCS temperature

4. CT-20 (E-3.C) Crew depressurizes RCS to meet SI termination criteria Event Malf. No. Event Type Event Description No.

1 (N) BOP/SRO Due to oil leak, S/U 2CCS-P21B & S/D 2CCS-P21A.

2 (R) ATC Normal power increase to 15% IAW 20M-52.4.A (N) SRO 3 CNH"'.CFWll (C,A) BOP/SRO 2FWS*FCV479, Bypass Feedwater valve controller fails as is in AUTO, requires manual operation.

4 PMP-CHS002 (C,A) ATC/SRO 2CHS*P21B, Charging/ HHSI pump shaft seizure.

SRO (TS) 5 (N) ATC/SRO Restore normal charging and letdown.

6 XMT-MSC038A SRO (TS) 2LMS*PT952, CNMT pressure transmitter fails high.

7 PPL02A (M)ALL Spurious Rx trip.

8 RCS04B (M)ALL 21B SG 520 gpm tube rupture.

9 PPL07B (C) ATC/SRO 2CHS*P21C, Charging I HHSI auto start failure.

10 VLV-SEA015 (C) BOP/SRO Train B CIA failure with 2CHS*MOV378 and 2HVP*MOD22B auto close failures.

11 VLV- (C) ATC/SRO PRZR PORV fails to close when opened for RCS RCS032,33,34 depressurization in E-3, requires isolation.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (A)bnormal E ES-0.1 - E E-3 NUREG-1021, Revision 10 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Facility: Beaver Valley Unit 2 RO Date of Exam 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 1.

3 3 3 3 18 Emergency 2

& 2 1 2 2 9 Abnormal Plant Tier Evolutions Totals 5 4 5 5 27 1

2.

2 2 3 3 3 2 2 3 2 3 3 28 Plant Systems 2 0 1 1 2 1 1 1 0 1 1 1 10 Tier Totals 2 3 4 5 4 3 3 3 3 4 4 38 1 2 3 4 10

3. Generic Knowledge and Abilities Category 2 3 2 3 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).

(One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-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 with justification; 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 (I Rs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #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.

G* Generic KIAs NUREG-1021, Revision 10 RO Page 1of13 FENOC Facsimile r2

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

E/APE #I Name I Safety Function K K K KIA Topic(s) IR #

1 2 3 000007 Reactor Trip I 1 EK2 Knowledge of the interrelations between a 3.5 reactor trip and the following:

[Question 1]

EK2.03 Reactor trip status panel (CFR 41.7 / 45.7) 000008 Pressurizer (PZR) Vapor Space AK1 Knowledge of the operational implications of 3.2 Accident (Relief Valve Stuck Open) I 3 the following concepts as they apply to a Pressurizer Vapor Space Accident:

[Question 2]

AK1 .01 Thermodynamics and flow characteristics of 1: . . open or leaking Valves

• • .. (CFR 41.8 / 41.10 I 45.3) 000015/000017 Reactor Coolant Pump AK2 Knowledge of the interrelations between the 2.9 (RCP) Malfunctions I 4 Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:

[Question 3] AK2.07 RCP seals (CFR 41.7 I 45.7) 000022 Loss of Reactor Coolant Makeup I AK1 Knowledge of the operational implications of 3.0 2 the following concepts as they apply to Loss of Reactor Coolant Makeup:

[Question 4] AK1 .03 Relationship between charging flow and PZR level (CFR 41.8 I 41.10 I 45.3)

Otvu25 Loss of Residual Heat Removal AA2 Ability to determine and interpret the following 3.3*

System (RHRS) I 4 as they apply to the Loss of Residual Heat Removal System:

[Question 5] AA2.04 Location and isolability of leaks (CFR: 43.5 I 45.13) 000026 Loss of Component Cooling Water AK3 Knowledge of the reasons for the following 4.0 (CCW) I 8 responses as they apply to the Loss of Component Cooling Water:

[Question 6] AK3.03 Guidance actions contained in EOP for Loss ofCCW (CFR 41.5,41.10 I 45.6 I 45.13) 000027 Pressurizer Pressure Control 2.1.28 Knowledge of the purpose and function of 4.1 System (PZR PCS) Malfunction I 3 major system components and controls.

(CFR: 41. 7)J

[Question 7]

000029 Anticipated Transient Without EK2 Knowledge of the interrelations between the 2.9*

Scram (ATWS) I 1 and the following an ATWS:

EK2.06 Breakers, relays, and disconnects

[Question 8]

(CFR 41.7 I 45.7)

NUREG-1021, Revision 10 RO Page 2of13 FENOC Facsimile r2

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

000038 Steam Generator Tube Rupture EK3 Knowledge of the reasons for the following 3.6*

(SGTR) / 3 responses as the apply to the SGTR:

EK3.03 Automatic actions associated with high

[Question 9] radioactivity in SIG sample lines (CFR 41.5 I 41.10 I 45.6 I 45.13) 000054 Loss of Main Feedwater (MFW) / 4 AA2 Ability to determine and interpret the following 4.1 as they apply to the Loss of Main Feedwater (MFW):

[Question 1OJ AA2.02 Differentiation between loss of all MFW and trip of one MFW pump (CFR: 43.5 I 45.13) 000055 Loss of Offsite and Onsite Power 2.4.18 Knowledge of the specific bases for EOPs. 3.3 (Station Blackout) 16 (CFR: 41.10/43.1 /45.13)

[Question 11]

000056 Loss of Offsite Power 16 AK1 Knowledge of the operational implications of 3.7 the following concepts as they apply to Loss of Offsite Power:

[Question 12]

AK1 .01 Principle of cooling by natural convection (CFR 41.8 I 41.10 I 45.3) 57 Loss of Vital AC Electrical AA2 Ability to determine and interpret the following 3.7 Instrument Bus/ 6 as they apply to the Loss of Vital AC Instrument Bus:

[Question 13]

AA2.03 RPS panel alarm annunciators and trip indicators (CFR: 43.5 I 45.13) 000062 Loss of Nuclear Service Water/ 4 AK3. Knowledge of the reasons for the following 3.5 responses as they apply to the Loss of Nuclear

[Question 14] Service Water:

AK3.04 Effect on the nuclear service water discharge flow header of a loss of CCW (CFR 41.4, 41.8 I 45.7) 000065 Loss of Instrument Air I 8 2.4.4 Ability to recognize abnormal indications for 4.5 system operating parameters that are entry-level conditions for emergency and abnormal operating

[Question 15] procedures.

(CFR: 41.10 I 43.2 I 45.6) 000077 Generator Voltage and Electric Grid AA 1 Ability to operate and/or monitor the following 4.1 Disturbances/ 6 as they apply to Generator Voltage and Electric Grid Disturbances:

[C' --stion 16] AA 1.04 Reactor controls (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8)

NUREG-1021, Revision 10 RO Page 3of13 FENOC Facsimile r2

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

W/E11 Loss of Emergency Coolant X i~~l~ )r; EA 1 Ability to operate and I or monitor the following 3.7

~ i;,4 ,;~

Recirculation I 4 1 :: as they apply to the (Loss of Emergency Coolant Recirculation)

[Question 17] EA1 .3 Desired operating results during abnormal and emergency situations (CFR: 41. 7 / 45.5 / 45.6)

W/E12 Uncontrolled Depressurization of all EA 1 Ability to operate and I or monitor the following 3.6 Steam Generators /4. as they apply to the (Uncontrolled Depressurization of all Steam Generators)

[Question 18] EA 1.2 Operating behavior characteristics of the facility.

(CFR: 41. 7 I 45.5 / 45.6) 3 3 3 3 3 3 KIA Category Point Totals: Group Point Total: 18 NUREG-1021, Revision 10 RO Page 4of13 FENOC Facsimile r2

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 KIA Topic(s) IR #

000033 Loss of Intermediate Range AK1 Knowledge of the operational implications of the 2.7 Nuclear Instrumentation I 7 following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:

AK1 .01 Effects of voltage changes on performance

[Question 19]

(CFR 41.8 I 41.10 I 45.3) 000059 Accidental Liquid Radwaste AA2 Ability to determine and interpret the following 2.9 Release /9 as they apply to the Accidental Liquid Radwaste Release:

[Question 20] AA2.02 The permit for liquid radioactive-waste release (CFR: 43.5 / 45.13) 000067 Plant fire on site I 9 AK3 Knowledge of the reasons for the following 3.3 responses as they apply to the Plant Fire on Site:

AK3.04 Actions contained in EOP for plant fire on

[Question 21]

site (CFR 41.5,41.10 / 45.6 / 45.13) 000068 Control Room Evacuation I 8 AK2 Knowledge of the interrelations between the 3.7 Control Room Evacuation and the following:

[Question 22]

AK2.02 Reactor trip system (CFR 41.7 / 45.7) 000069 Loss of Containment Integrity I 5 AK3 Knowledge of the reasons for the following 3.8*

responses as they apply to the Loss of Containment

[Question 23] Integrity:

AK3.01 Guidance contained in EOP for loss of containment integrity (CFR 41.5,41.10 I 45.6 / 45.13)

W/E02 SI Termination/ 3 2.2.44 Ability to interpret control room indications to 4.2 verify the status and operation of a system, and

[Question 24] understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 I 45.12)

W/E03 LOCA Cooldown and EK1 Knowledge of the operational implications of the 3.6 Depressurization I 4 following concepts as they apply to the (LOCA Cooldown and Depressurization)

[Question 25] EK1 .2 Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).

(CFR: 41.8 / 41.10 / 45.3)

NUREG-1021, Revision 10 RO Page 5of13 FENOC Facsimile r2

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

1 2 3 W/E07 Saturated Core Cooling / 4 EA 1 Ability to operate and I or monitor the following 3.6 as they apply to the (Saturated Core Cooling)

[Question 26]

EA 1.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41. 7 / 45.5 / 45.6)

W/E13 Steam Generator Overpressure/ 4 2.1.23 Ability to perform specific system and 4.3 integrated plant procedures during all modes of plant

[Question 27] operation.

(CFR: 41.10 I 43.5 / 45.2 / 45.6) 2 1 2 1 1 2 KIA Category Point Totals: Group Point Total: 9 NUREG-1021, Revision 10 RO Page 6of13 FENOC Facsimile r2

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 Al~~ KIA Topic(s) JR #

1 2 3 4 5 6 1 .' 3 41:*~;.

003 Reactor Coolant Pump K2 Knowledge of bus power supplies to the 3.1 System (RCPS) following:

[Question 28] K2.01 RCPS Ir*: (CFR: 41.7) 004 Chemical and Volume K5 Knowledge of the operational implications 2.5 Control System of the following concepts as they apply to the

[Question 29] eves:

K5.14 Reduction process of gas concentration in RCS: vent accumulated non-condensable gases from PZR bubble space, depressurized during cooldown or by alternately heating and cooling (spray) within allowed pressure band (drive more gas out of solution)

(CFR: 41.5/45. 7) 005 Residual Heat Removal K2 Knowledge of bus power supplies to the 2.7*

System (RHRS) following:

[Question 30] K2.03 RCS pressure boundary motor-operated valves (CFR: 41.7) 006 Emergency Core Cooling A3 Ability to monitor automatic operation of the 3.6*

System (ECCS) ECCS, including:

r- 'Stion 31]

. A3.07 RHR pumps I.*.* . (CFR: 41.7 / 45.5) h.

006 Emergency Core Cooling K4 Knowledge of ECCS design feature(s) 2.6 System (ECCS) and/or interlock(s) which provide for the

[Question 32] following:

K4.01 Cooling of centrifugal pump bearings (CFR: 41.7) 007 Pressurizer Relief K4 Knowledge of PRTS design feature(s) 2.6 Tank/Quench Tank System and/or interlock(s) which provide for the (PRTS) following:

[Question 33]

.*r. K4.01 Quench tank cooling

<CFR: 41.7) 008 Component Cooling Water 1 2.2.38 Knowledge of conditions and limitations 3.6 System (CCWS) ~~**~ in the facility license.

[Question 34]

1::~1.:.

I;~~ (CFR:41.7/41.10/43.1/45.13) f:~\C 008 Component Cooling Water ) K3 Knowledge of the effect that a loss or 4.1 System (CCWS) malfunction of the CCWS will have

[Question 35] on the following:

~)

010 Pressurizer Pressure 1  :~:1 A3 Ability to monitor automatic operation of the 3.6 Cnntrol System (PZR PCS) l**~i~:. PZR PCS, including:

stion 36]

1.:*. F:* A3.02 PZR pressure

\*' (CFR: 41. 7 I 45.5)

NUREG-1021, Revision 10 RO Page 7of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued System # I Name K 1

K 2

K 3

K 4

K K A 5 6 1 ~1~

~:; A 3

A 4

1:,'.J~ KIA Topic(s) IR #

012 Reactor Protection System Ji!1\ K6 Knowledge of the effect of a loss or 1

~ 2.9

/~~.:

(RPS) malfunction of the following will have on the

[Question 37) f)'\': RPS:

~;t

~-i K6.02 Redundant channels

,) (CFR: 41. 7 I 4517)

K5 Knowledge of the operational implications i~it I

013 Engineered Safety Features ~ 2.9 1 Actuation System (ESFAS) of the following concepts as they apply to the ESFAS:

[Question 38)  !;),:! 111

• 111 K5.02 Safety system logic and reliability i~*:;)~:  !,\::

c:;;,. (CFR: 41.5 / 45.7) 1~

.~

022 Containment Cooling A2 Ability to (a) predict the impacts of the 2.9* 1 System (CCS) IJ0 following malfunctions or operations on the

.: CCS; and (b) based on those predictions, use

[Question 39) procedures to correct, control, or mitigate the f'J~

i .

J 1,'11'1 J , ** ,

consequences of those malfunctions or operations:

A2.04 Loss of service water l~:i '  :~:1,;~1 (CFR: 41.5 / 43.5 / 45.3 / 45.13) r ~.'~Lf:

022 Containment Cooling J:fC ~

A4 Ability to manually operate and/or monitor 3.8 1 System (CCS) 1:1,' in the control room:

J

[Question 40] (1:,

• ,.. *~ A4.05 Containment readings of temperature, I pressure, and humidity system.

... i

,1

, .. J (CFR: 41. 7 I 45.5 to 45.8) 026 Containment Spray System

~

J '*; f;'.; ~:, A 1 Ability to predict and/or monitor changes in 3.9 1 (CSS) 1:1' parameters (to prevent exceeding design

~

limits) associated with operating the CSS 1:~~1

[Question 41]

controls including:

l~~t A 1.01 Containment pressure

• ,:.;/ (CFR: 41.5 / 45.5) 026 Containment Spray System 2.1.23 Ability to perform specific system and (CSS)

!,f,:, ,;~ integrated plant procedures during all modes 4.3 1

~'.~

[Question 42) of plant operation.

i;2i; (CFR

41.10 I 43.5 / 45.2 / 45.6) 039 Main and Reheat Steam 1;1  ;: K3 Knowledge of the effect that a loss or

~ 3.2* 1 System (MRSS)

J  ;

i',~ malfunction of the MRSS will have on the following:

[Question 43) 111

/ K3.03 AFW pumps.

'. J

~~;;;, (CFR: 41. 7 I 45.6) 039 Main and Reheat Steam System (MRSS)

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

4.6 1

[1  ;

[Question 44) .:' '°\ (CFR: 41.10 / 43.5 / 45.13)

NUREG-1021, Revision 10 RO Page 8of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1{RO) Continued

"",~

System # I Name K 1

K 2

K 3

K K 4 5 K

6 A

1 i~~

A 3 ~11~~ KIA Topic(s) IR #

~{

059 Main Feedwater (MFW) ~,\~ ) A4 Ability to manually operate and monitor in 3.1* 1 System the control room:

(Question 45]

• • ~~ A4.01 MFW turbine trip indication (CFR: 41. 7 / 45.5 to 45.8)

~ ~

_~

059 Main Feedwater (MFW) A2 Ability to (a) predict the impacts of the 3.4* 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 consequences of those malfunctions or i~* ~\: operations:

1'r;J;

',* *~:~ A2.01 Feedwater actuation of AFW system

• : (CFR: 41.5 / 43.5 I 45.3 / 45.13) x

• ~

061 Auxiliary I Emergency 1: :: KS Knowledge of the operational implications 3.2 1 Feedwater (AFW) System

~:~;,: of the following concepts as the apply to the AFW:

1,*r~

(Question 47]

f~;~

K5.02 Decay heat sources and magnitude

,'i :;; (CFR: 41.5 / 45.7) 062 AC Electrical Distribution System ~~~ 1,~~t: A2 Ability to (a) predict the impacts of the following malfunctions or operations on the ac 2.7 1

[Question 48] I~,~~ J~ distribution system; and (b) based on those predictions, use procedures to correct, control,

0~~

1: .  ::;;,: or mitigate the consequences of those I'::*.* malfunctions or operations:

,. i'.1~*~

A2.08 Consequences of exceeding voltage

.. '~,

I\~

limitations

'I .i (CFR: 41.5 / 43.5 / 45.3 / 45.13) 063 DC Electrical Distribution ) i;:~'; fj:~. K1 Knowledge of the physical connections 2.7 1 System  :;;[; and/or cause effect relationships between the (Question 49]  ;;~ ,,*

i

~~;i DC electrical system and the following systems:

~~~i K1 .02 AC electrical system (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 064 Emergency Diesel ~.;c: K6 Knowledge of the effect of a loss or

) .. 2.7 1 Generator (ED/G) System malfunction of the following will have on the

iS' ~~

:,, ED/G system:

(Question 50] *:*. :

,:,.:: i :j

'S,,.'

K6.07 Air receivers

\:~;  ::£~ (CFR: 41.7 / 45.7)

[i~

073 Process Radiation ) ;in:;: K3 Knowledge of the effect that a loss or 3.6 1 Monitoring (PRM) System malfunction of the PRM system will have on

• ~~

[Question 51] the following:

I~ K3.01 Radioactive effluent releases (CFR: 41.7 / 45.6)

NUREG-1021, Revision 10 RO Page 9of13 FENOC Facsimile r2

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1(RO) Continued I,/\ \!,:;,

System #I Name 076 Service Water System K

1 K

2 K

3 K

4 K

5 K

6 ~b~

A 3

A 4 re KIA Topic(s)

A 1 Ability to predict and/or monitor changes in IR #

)( 2.6* 1 (SWS) parameters (to prevent exceeding design

[Question 52] limits) associated with operating the SWS controls including:

,, A 1.02 Reactor and turbine building closed

'~}

cooling water temperatures.

(CFR: 41.5 / 45.5) 078 Instrument Air System (IAS) K1 Knowledge of the physical connections

~Rt

• ~

)( 3.3* 1

[Question 53] and/or cause-effect relationships between the IAS and the following systems:

,G' I K1 .03 Containment air

(

',,:',i .,t~: '1 (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 103 Containment System *.:*':,, . :,~ K4 Knowledge of containment system design

)( 3.0* 1 feature(s) and/or interlock(s) which provide for

~~

[Question 54]

.\ the following:

Y,'

K4.01 Vacuum breaker protection (CFR: 41.7)

~r rn:i

~{:

103 Containment System )( it:~ A4 Ability to manually operate and/or monitor 3.1* 1

[Question 55] in the control room:

~

A4.09 Containment vacuum system

,~?.

(CFR: 41. 7 / 45.5 to 45,8) 2 2 3 3 3 2 2 3 2 3 3 KIA Category Point Totals: Group Point Total: 28 NUREG-1021, Revision 10 RO Page 10of13 FENOC Facsimile r2

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 :i'A, A A I~(~ KIA Topic(s) 1 2 3 4 5 6 1 j~~f 3 4 l!)f IR i==:=:=~c=======;:====c:======:========;====i=====T====il 001 Control Rod Drive System vi~"'~ A 1 Ability to predict and/or monitor changes in 3.7

[Question 56] "l~t~ parameters (to prevent exceeding design limits)

(* associated with operating the CRDS controls IJ\

~  :~,;~ including:

l~~~t~~ 'E:~,;.;; A 1.04 PZR level and pressures

';*. i'1:,1 (CFR: 41.5 / 45.5) 002 Reactor Coolant System A3 Ability to monitor automatic operation of the 4.4 (RCS) RCS, including:

[Question 57]

A3.03 Pressure, temperatures, and flows (CFR: 41.7 / 45.5) 011 Pressurizer Level Control K6 Knowledge of the effect of a loss or 3.1 System (PZR LCS) malfunction on the following will have on the

[Question 58] PZR LCS:

K6.05 Function of PZR level gauges as post accident monitors (CFR: 41.7 / 45.7) 028 Hydrogen Recombiner and }( K5 Knowledge of the operational implications of 3.4 Purge Control System (HRPS) the following concepts as they apply to the

[Question 59] HRPS:

K5.01 Explosive hydrogen concentration (CFR: 41.5 / 45. 7) r ";ontainment Purge System }( l'i; ;, K3 Knowledge of the effect that a loss or 2.9 (1... . .:i) I £ *~ malfunction of the Containment Purge System

[Question 60] *'* will have on the following:

K3.01 Containment parameters (CFR: 41. 7 / 45.6) 034 Fuel Handling Equipment  :(,/ ~ K4 Knowledge of design feature(s) and/or 2.6 System (FHES) ,... '1} interlock(s) which provide for the following:

[Question 61] I: * ,

f'.( 'i~~* K4.03 Overload protection (CFR: 41.7)

I If-------+--+--+--+--+---+--+---+

035 Steam Generator System }( t*

~--~-----+---+---ll K4 Knowledge of S/GS design feature(s) and/or 2.9 (S/GS) ~- interlock(s) which provide for the following:

[Question 62]

K4.05 Amount of reserve water in S/G (CFR: 41.7) 045 Main Turbine Generator A4 Ability to manually operate and/or monitor in 3.1 (MT/G) System the control room:

[Question 63]

A4.01 Turbine valve indicators (throttle, governor, control, stop, intercept), alarms, and annunciators (CFR: 41.7 / 45.5 to 45.8)

NUREG-1021, Revision 10 RO Page 11 of 13 FENOC Facsimile r2

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 KIA Topic(s)

IR #

1 2 3 4 5 6 1 072 Area Radiation Monitoring 2.4.46 Ability to verify that the alarms are 4.2 (ARM) System consistent with the plant conditions.

[Question 64) (CFR: 41.10 I 43.5 I 45.3 I 45.12) 075 Circulating Water System K2 Knowledge of bus power supplies to the 2.6*

[Question 65] following:

K2.03 Emergency/essential SWS pumps (CFR: 41.7)

KIA Category Point Totals: 0 1 1 2 1 1 1 0 1 1 1 Group PointTotal: 10 NUREG-1021, Revision 10 RO Page 12of13 FENOC Facsimile r2

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

ility

Beaver Valley Unit 2 RO Date of Exam 12/7 thru 12/18 2015 RO Category KIA# Topic IR #

1. 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, 4.1 Conduct switches, etc.

of Operations (CFR: 41.10 / 45.1 / 45.12)

[Question 66]

2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 1 response of another indication.

(CFR: 41.7 / 43.5 / 45.4)

[Question 67]

Subtotal

2. 2.2.6 Knowledge of the process for making changes to procedures.

Equipment (CFR: 41.10 / 43.3 / 45.13)

Control [Question 68]

2.2.15 Ability to determine the expected plant configuration using design and 3 .9 configuration control documentation, such as drawings, line-ups, tag-outs, etc.

(CFR: 41.10 / 43.3 / 45.13)

[Question 69]

2.2.39 Knowledge of less than or equal to one hour Technical Specification 3 .9 action statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

Question 70 Subtotal

3. 2.3.7 Ability to comply with radiation work permit requirements during normal Radiation or abnormal conditions.

Control (CFR: 41.12 / 45.10)

[Question 71]

2.3.13 Knowledge of radiological safety procedures pertaining to licensed 3 .4 operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 43.4 / 45.9 / 45.10)

[Question 72]

Subtotal

4. 2.4.6 Knowledge of EOP mitigation strategies.

Emergency (CFR: 41.10 / 43.5 / 45.13)

Procedures/ [Question 73]

Plan 2.4.25 Knowledge of fire protection procedures. 3.3 (CFR: 41.10 / 43.5 / 45.13)

[Question 74]

2.4.39 Knowledge of RO responsibilities in emergency plan implementation. 3.9 (CFR:41.10/45.11)

Question 75 Subtotal 11~r 3 Point Total NUREG-1021, Revision 10 RO Page 13of13 FENOC Facsimile r2

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

SRO ONLY Points Tier Group A2 G* TOTAL 1

3 3 6 1.

Emergency 2

& 2 2 4 Abnormal Plant Tier Totals 5 5 10 Evolutions 1

2. 3 2 5 Plant Systems 2 0 2 1 3 Tier Totals 5 3 8 1 2 3 4

3. Generic Knowledge and 7 Abilities Category 2 1 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).

(One Tier 3 Radiation Control KIA is allowed if the KIA is replaced by a KIA from another Tier 3 Category).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-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 with justification; 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 (I Rs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #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, !Rs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

G* Generic KIAs NUREG-1021, Revision 10 SRO Page 1 of 6 FENOC Facsimile Rev. r2

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

~

E/APE #I Name I Safety Function K K K A KIA Topic(s) IR #

1 2 3 1 000009 Small Break LOCA / 3 4 EA2 Ability to determine or interpret the following as 3.9 1

[Question 76)  :.:'*; they apply to a small break LOCA:

t  :~

EA2.05 The time available for action before PZR is I I~

empty, given the rate of decrease of PZR level (CFR 43.5 / 45.13)

.:'.'.~

~ I~

000011 Large Break LOCA I 3 2.4.41 Knowledge of the emergency action level 4.6 1

[Question 77) thresholds and classifications.

(CFR: 41.10 I 43.5 / 45.11) 000040 Steam Line Rupture I 4 AA2 Ability to determine and interpret the following 4.5 1

"* 10

[Question 78) as they apply to the Steam Line Rupture:

ij ~

?i:Fi  :~,

AA2.05 When ESFAS systems may be secured (CFR: 43.5 / 45.13)

'~

.0~ ;,~.,

• ,::;:;rt 000058 Loss of DC Power / 6 Ji~ 2.2.25 Knowledge of the bases in Technical

'<%:" 4.2 1

[Question 79) "' Specifications for limiting conditions for operations

~', ";,

,:  :;, and safety limits.

d  :~;

1*~:':: :; (CFR: 41.5 / 41.7 / 43.2)

-v ii' :~;~~

4 LOCA Outside Containment I 3 I'~*:: *it)( 2.4.11 Knowledge of abnormal condition procedures. 4.2 1

[Question 80) (CFR: 41.10 / 43.5 / 45.13)

'r!. ~1 ill t~

~'~

W/E05 Loss of Secondary Heat Sink I 4 EA2 Ability to determine and interpret the following i

4.4 1

[Question 81) as they apply to the (Loss of Secondary Heat Sink)

,,~

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and I~

emergency operations.

i,4:r i~!t (CFR: 43.5 / 45.13)

'.~:;*1 '~~

3 3 6 KIA Category Point Totals: Group Point Total:

NUREG-1021, Revision 10 SRO Page 2 of 6 FENOC Facsimile Rev. r2

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

'=/APE #I Name I Safety Function K K K A

"'i*'

KIA Topic(s) IR #

1 2 3 1 ~t. !'.

000003 Dropped Control Rod / 1 2.2.36 Ability to analyze the effect of maintenance 4.2 1

[Question 82] activities, such as degraded power sources, on the status of limiting conditions for operations.

(CFR: 41.10 / 43.2 / 45.13)

i 000024 Emergency Boration / 1 "' 2.1.23 Ability to perform specific system and 4.4 1

[Question 83]  ;~~ I::~~ integrated plant procedures during all modes of plant operation.

~}r,;,,,, 11\ (CFR: 41.10 / 43.5 / 45.2 / 45.6)

W/E06 Degraded Core Cooling I 4 ~i;i\j ii EA2 Ability to determine and interpret the following 4.2 1

[Question 84] c.'.'.'f'cJ as they apply to the (Degraded Core Cooling) l.~t, ir~~; EA2.1 Facility conditions and selection of appropriate procedures during abnormal and I~~~J: ,\~~ { emergency operations.

(CFR: 43.5 / 45.13)

I' W/E09 Natural Circulation Operations I 4 EA2 Ability to determine and interpret the following

I I~

3.8 1 as they apply to the (Natural Circulation Operations)

[Question 85]

EA2.2 Adherence to appropriate procedures and I;1: operation within the limitations in the facility's license

and amendments.

[,:r (CFR: 43.5 / 45.13)

~; ~ ;~~

KIA Category Point Totals: 0 0 0 0 2 2 Group Point Total: 4 NUREG-1021, Revision 10 SRO Page 3 of 6 FENOC Facsimile Rev. r2

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

System # I Name K K K K K K Ail'.~ A A KIA Topic(s) IR #

1 2 3 4 5 6 1 >2 3 4

~i~

003 Reactor Coolant Pump i~j!j A2 Ability to (a) predict the impacts of the 3.9 1 System (RCPS) following malfunctions or operations on the

[Question 86] RCPS; and (b) based on those predictions,

~r; use procedures to correct, control, or mitigate li:/;, the consequences of those malfunctions or operations:

~

~ 11 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a

'~ I* t 1~i:

normal shutdown of an RCP (CFR: 41.5 / 43.5/ 45.3 / 45/13)

I /i:~;:

~~. ~~

004 Chemical and Volume A2 Ability to (a) predict the impacts of the 3.3 1 Control System following malfunctions or operations on the

[Question 87] eves; and (b) based on those predictions, use procedures to correct, control, or mitigate 111,i~f the consequences of those malfunctions or

~

, operations:

It ~.

A2.33 Fact that isolating cation demineralizer 11 stops boron dilution and enables restoration of if normal boron concentration

~~)

(CFR: 41.5/ 43/5 / 45/3 / 45/5)

I: ~

h }

013 Engineered Safety Features I' tion System (ESFAS) ii:~*t; I~!~ 2.4.20 Knowledge of the operational implications of EOP warnings, cautions, 4.3 1 rl~:*;

[Question 88] and notes.

'I ..

(CFR: 41.10143.5 I 45.13) 1,1~*1* ~:;l Ii *:r, I~)'

076 Service Water System (SWS) i: A2 Ability to (a) predict the impacts of the following malfunctions or operations on the 3.1 1

[Question 89] *fi~'.\: SWS; and (b) based on those predictions, use Ii GI

(.i procedures to correct, control, or mitigate the consequences of those malfunctions or 1.f;

~ operations:

I~~: 1!

~~

A2.02 Service water header pressure

[t:1~ (CFR: 41.5 / 43.5 / 45/3 / 45/13) f '.f 078 Instrument Air System (IAS) h '**1, 2.4.34 Knowledge of RO tasks performed 4.1 1

[Question 90] I* ":' outside the main control room during an

!l\~:.I emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13) lr'.:*:1: '/

3 2 KIA Category Point Totals: Group Point Total: 5 NUREG-1021, Revision 10 SRO Page 4 of 6 FENOC Facsimile Rev. r2

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

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

'~'.~ KIA Topic(s) 033 Spent Fuel Pool Cooling 1 2 3 4 5 6 1 ;*

le 3 4 A2 Ability to (a) predict the impacts of the IR #

i7~ 1 3.5 1 System (SFPCS) following malfunctions or operations on the

[Question 91] 1+t Spent Fuel Pool Cooling System; and (b)

~;I~ based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations

1it

• ~~

A2.01 Inadequate SOM (CFR: 41.5 I 43.5 I 45.3 I 45.13)

~;

[.;i~

041 Steam Dump System 2.4.50 Ability to verify system alarm setpoints 4.0 1 (SDS)/Turbine Bypass Control  ;; ' and operate controls identified in the alarm

[Question 92] .-...;, response manual.

lC

':{:';  ; *J (CFR: 41.10 I 43.5 I 45.3)

1"*

lwi:' *.~th 079 Station Air System (SAS) 1;;; A2 Ability to (a) predict the impacts of the

[Question 93]  :*~* II following malfunctions or operations on the SAS; and (b) based on those predictions, use 3.2 1 1;~ procedures to correct, control, or mitigate the

• consequences of those malfunctions or

.,. ~

tti£ It c.

• ~v' operations:

h. ,, A2.01 Cross-connection with IAS

• . (CFR: 41.5 I 43.5 I 45.3 I 45.13) 11:*i

==

l.t.:

Kt!-. Category Point Totals: 2 1 Group Point Total: 3 NUREG-1021, Revision 10 SRO Page 5 of 6 FENOC Facsimile Rev. r2

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 lity: Beaver Valley Unit 2 SRO Date of Exam SRO Only Category KIA# Topic IR #

1. 2.1.4 Knowledge of individual licensed operator responsibilities related to shift 3.8 Conduct staffing, such as medical requirements, "no-solo" operation, maintenance of Operations of active license status, 10CFR55, etc.

(CFR: 41.10/43.2)

[Question 94]

2.1.36 Knowledge of procedures and limitations involved in core alterations. 4.1 (CFR: 41.10 / 43.6 / 45.7)

[Question 95)

Subtotal 2

2. 2.2.42 Ability to recognize system parameters that are entry-level conditions for Equipment Technical Specifications.

Control (CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

[Question 96)

Subtotal 1

3. 2.3.4 Knowledge of radiation exposure limits under normal or emergency Radiation conditions.

Control (CFR: 41.12 / 43.4 / 45.10)

[Question 97) 2.3.11 Ability to control radiation releases. 4.3 (CFR: 41.11 / 43.4 / 45.10)

[Question 98)

Subtotal 2

4. 2.4.29 Knowledge of the emergency plan.

Emergency (CFR: 41.10 / 43.5 / 45.11)

Procedures/

[Question 99)

Plan 2.4.44 Knowledge of emergency plan protective action recommendations. 4.4 (CFR: 41.10 / 41.12 / 43.5 / 45.11)

[Question 100)

Subtotal 2 Tier 3 Point Total 7 NUREG-1021, Revision 10 SRO Page 6 of6 FENOC Facsimile Rev. r2

ES-401 Record of Rejected K/As Form ES-401-4 I Facility: Beaver Valle~ Unit 2 Date of Exam 12n thru 12/18 2015 Operating Test No.: BV2LOT15 NRC I

Tier I Randomly Reason for Rejection Group Selected KIA 1/1 000025 AA2.05 Question #5; Beaver Valley does not use Residual Heat Removal (RHRS) for Low Pressure Injection (LPI). Randomly selected 025 AA2.04 as a replacement.

1/1 057 AA2.11 Question #13; There is no interface between the MFP running indicator and controller, and the Vital AC busses at Beaver Valley. Reselect due to lack of applicability. Discussed with Chief Examiner. Randomly selected 057 AA2.03 as a replacement.

2/1 026 A1 .02 Question #41; Beaver Valley does not operate the CNMT Spray Sytem based on CNMT temperature. Procedurally the EOPs use CNMT pressure. The procedures do not refer to CNMT Temp for any control functions of CSS. Randomly selected 026A1.01 as a replacement.

2/1 059 A2.07 Question #46; Beaver Valley does not have MFW pump turbines.

Randomly selected 059 A2.01 as a replacement.

2/2 041 G2.4.41 Question #92; 041 Steam Dump System (SDS)/Turbine Bypass Control 2.4.41 Knowledge of the emergency action level thresholds and classifications. Reselected due to oversampling. Similar to Q77 (011 G2.4.41 ). Randomly selected 041 G2.4.50 as a replacement.

2/1 013 G2.4.1 Question #88; G2.4.1, Knowledge of EOP entry conditions and immediate action steps. Unable to write a discriminatory SRO level question. The KIA is RO level knowledge. Randomly selected 013 G2.4.20 as a replacement.

2/2 034 K1.04 Question #61; K1 Knowledge of the physical connections and/or cause effect relationships between the Fuel Handling System and the following systems: NIS. Unable to write a discriminatory question. Randomly selected 034 K4.03 as a replacement.

1/2 WE02 G2.4.21 Question #24; 2.4.21 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Unable to write a discriminatory question. Randomly selected WE02 G2.2.44 as a replacement.

2/1 026 G2.2.12 Question #42; 2.2.12 Knowledge of surveillance procedures.

Unable to write a discriminatory question with the limited opportunities available with Cnmt Cooling surveillances. Randomly selected 026 G2.1.23 as a replacement.

NUREG-1021, Revision 10 FENOC Facsimile r2

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments Administrative JPMs

• Modify the Task Standard to match the direction given in the procedure, remove the statement to recommend no further rod withdrawal, add statement to insert all control rods.

RO A1.1

• Modify the Initial Conditions to add that the plant tripped from 100% power, clarify that this is not a startup following a refueling outage.

• Modify step 4.1 to remove recommended action then made step 4.2 critical.

Added procedure 20M-50.4.D as reference

• Modify the initial conditions to remove the statements related to turnover at beginning and end of shifts.

RO A1.2

• Modify the directions to document the reasons for determining if the license is active or inactive. (Note these comments were from the outline submittal, not walkthrough week)

RO

• Modify step 4 to address potential question and local operator action for A2 recirculation valves.

RO

• No comments .

A3

• Modify the Task Standard to match the direction given in the procedure, remove the statement to recommend no further rod withdrawal.

SRO

• Modify the Initial Conditions to add that the plant tripped from 100% power, clarify A1.1 that this is not a startup following a refueling outage.

• Modify step 4.1 to remove recommended action. Added procedure 20M-50.4.D as reference SRO

• No comments .

A1.2

• Add numbering to the Initiating Cue to define what the candidate is expected to perform and report. Modify step 4 note to include the possibility that the candidate may direct field manipulations of the recirculation valves. Modify step 8.3 to include the Shift manager may be one of the two approving SROs.

SRO A2

• Modify step 4 to address potential question and local operator action for recirculation valves.

• Modify Step 8 to note that the Shift Manager may be one of the two approving SR Os.

• Modify initial conditions to clarify that the worker (add name) has no previous accident or emergency exposure.

SRO A3

• Split initiating cue into two numbered parts.

1

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• Modify the Answer Key to identify the critical items on the form.

• Modify the initiating cue to include a statement that the General Announcement mas been made to the crew at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

SRO

• Add note to step 5 that refers to the critical items that are highlighted on the A4 answer key.

• The selection of "Drill" or "Actual Emergency" is not critical since this evaluation is performed in a classroom setting.

Simulator JPMs

• JPM is Alternate Path due to actions to align alternate flow path in the procedure .

S1 ES-301-2 (RO/SRO) modified.

• No changes to JPM .

• Added PAB Operator is stationed at 2SGC-RQl100 Radiation Monitor skid to the Initial conditions.

• Added cue for initial ORMS point 1065 being cyan due to expected RP actions .

• Added Booth Operator cue for annunciator A4-5H when venting sample lines .

• Added procedure steps to evaluator cues to help follow along with work direction .

Modified flowrates in JPM step 8 & 10 as requested.

S2

• Added evaluator note stating the completion of step 19.2 or 20.1 will meet the task standard.

• Removed critical step to verify position indication lights of 2SGC-HCV100 since the valve controller is actually the critical step.

• Made minor place keeping correction to procedure step IV.A.8.d of plant procedure.

• Corrected procedure step number on candidate direction sheet.

S3

• No changes to JPM .

S4

• Minor change of moving Booth Operator cue to precede step 15 .

• Corrected JPM steps 8 and 22 to state correct Data sheet 3 .

SS

• Changed Task Standard to "Annunciator A4-5H, "POWER RANGE HIGH/LOW SP FLUX DEVIATION/AUTO DEFEAT" verified by performing QPTR Alarm check with setpoints determined to be +/-10 µA of the answer key".

2

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• JPM is not alternate path, alarm is already in at the start of the JPM. ES-301-2 (RO/SRO) modified.

S6

• Removed pictures from JPM Word document and modified picture #1 to show high vibration values on the meters.

• Limited JPM picture use to 2 pictures, and modified appropriate Evaluator Cues .

• Separated JPM step 2 into two separate steps .

S7

• Changed old JPM step 3 to match procedure step.

• Clarified switches to be operated, and phases to be monitored when candidate is monitoring voltages SB

• Added bullet for 'CNMT is not accessible' in the Initial Conditions to prevent role play for an Operator in containment during the RCP startup.

Plant JPMs P1

• Added procedure steps 3 & 4 to JPM for ease of evaluating candidate .

P2

• No changes to JPM .

P3

• No changes to JPM .

Scenarios

• Page 2, Scenario outline, corrected SG pressure transmitter as channel 4 not channel 3.

• Throughout - added procedure titles to scripting .

Sc1

• Page 8, Added NOTE with information that crew is required to place alternate channel in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• Page 9, Enhanced ROLE PLAYS for tripping of bistables .

• Throughout - added procedure titles to scripting .

• Page 11, Modified scripting to state that the crew may initially attempt to stabilize Sc2 SG level using manual control of the main feed regulating valve.

• Page 21, Added a NOTE and emphasis to components required to be verified/manipulated to meet requirements of CT-17, Isolation of a faulted SG.

3

December 2015 Beaver Valley Unit 2 Operating Exam NRC Review Comments

• Throughout - added procedure titles to scripting .

• Page 6, Enhanced ROLE PLAY for field operator identification of Safeguards Sc3 leak.

• Page 14, Enhanced ROLE PLAY for status of the turbine driven aux feedwater pump.

• Swapped events 1 and 2, added additional turnover information (oil leak) as a reason to swap Component cooling water pumps.

• Throughout - added procedure titles to scripting .

• Added additional CIA actuation individual component failure, 2HVP*MOD22B Sc4 failed to auto close, to event 10.

• Page 17, Added a NOTE and emphasis to components required to be verified/manipulated to meet requirements of CT-18, Isolation of a ruptured SG.

• Page 18, Scripted actions for cooldown if the main condenser is isolated due to a MSLI occurrence.

• Why does the MFRV need to be returned to Automatic Control?

General Per 20M-24.4.IF procedure, if not desired to trip Bistables for the Level Questions Channel (for example if another channel was already tripped), then the MFRV may be operated in Manual as long as a Basis For Continued Operation is generated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• How does the Brass coupling operate on the Trip Throttle valve .

The brass split coupling will move up and down with the stem of the valve.

General When the valve trips, the coupling will lower with the shaft and the valve Questions seats. When the handle is turned clockwise to raise the sliding nut to the latch position, the brass coupling will remain in the down position. After latching, when the handwheel is turned counter clockwise, the stem rises as does the brass coupling 4

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: 12/7 thru 12/18 2015 amination Level RO IXl SROD Operating Test Number BV2LOT15 NRC Administrative Type Describe activity to be performed Topic Code*

(See Note)

Conduct of D,R 2.1.43 (4.1)

Operations Ability to use procedures to determine the effects on reactivity of plant (RO A 1.1) changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

JPM 2AD-016 Plot and Evaluate 1/M Data Conduct of N,R 2.1.4 (3.3)

Operations Knowledge of individual licensed operator responsibilities related to (RO A 1.2) shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

JPM 3AD-023 Determine if License Status is Maintained Active (RO)

Equipment N,R 2.2.41 (3.5) 1trol Ability to obtain and interpret station electrical and mechanical (RO A 2) drawings.

JPM 2AD-048 Determine Isolation Boundary Points and Mark on PlantVOND Radiation Control D, R 2.3.11 (3.8)

(RO A 3) Ability to control radiation releases.

JPM 2AD-010 Determine GW Storage Tank Discharge Bleed Flow Rate Emergency Plan NOT EVALUATED (RO A 4)

• ,:, ::. *.:: :;~ 11S (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items).

• Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank <.::. 3 for ROs; .'.5. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

(P)revious 2 exams (.'.5. 1; randomly selected)

NUREG-1021, Revision 10 FENOC Facsimile rO

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: 12/7 thru 12/18 2015 r "lmination Level RO D SRO 00 Operating Test Number BV2LOT15 NRC Administrative Type Describe activity to be performed Topic (See Note) Code*

Conduct of D,R 2.1.43 (4.3)

Operations Ability to use procedures to determine the effects on reactivity of (SRO A 1.1) plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

JPM 2AD-019 Plot and Evaluate 1/M Data and Determine Required Actions Conduct of N,R 2.1.4 (3.8)

Operations Knowledge of individual licensed operator responsibilities related to (SRO A 1.2) shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

JPM 3AD-024 Evaluate Operators Work History to Determine if License Status is Active (SRO)

Equipment Control N, R 2.2.41 (3.9)

, <0 A 2) Ability to obtain and interpret station electrical and mechanical drawings.

JPM 2AD-049 Identify Isolation Boundary Points and Mark on Plant VOND then Identify Method of Plant Configuration Control Radiation Control M,R 2.3.4 (3.7)

(SRO A 3) Knowledge of radiation exposure limits under normal or emergency conditions.

JPM 2AD-038 Determine Emergency Exposure Authorization Limits Emergency Plan D,R 2.4.44 (4.4)

(SRO A 4) Knowledge of emergency plan protective action recommendations.

JPM 2AD-037 Determine Protective Action Recommendations (Part 1) 11 1\jv 1 E: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all 5 items).

• -**pe 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 (~ 1)

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

NUREG-1021, Revision 10 FENOC Facsimile rO

ES 301 C on t ro IRoom /I n-Pl an t S;ystems o utrme - -

Form ES 301 2 I Facility: Beaver Valle)£ Unit 2 Date of Examination: 12/7/ thru 12/18 201~ 11

~;::.,, Level: RO 00 SRO(I) D SRO(U) D Operating Test No.: BV2LOT15 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System I JPM Title Type Code* Safety Function S1 - Transfer to Hot Leg Recirculation (2CR-570) S,D,EN,A 3 S2 - Discharge Steam Generator Slowdown Evaporator Test Tank [2SGC- S,N,A 9 TK23A] to Unit 2 Cooling Tower Slowdown. (2CR-660)

S3 - Rod Control Assembly Partial Movement Test - (Rods continue to S,N,A 1 move during performance of the test) (2CR-747)

S4 - Batch to the Refuel Water Storage Tank (2CR-537) S,D 2 SS - Perform QPTR Alarm Test (2CR-144) S,D 7 S6 - Respond to Containment Air Recirculation Fan High Vibration Alarm S,N 5 (2CR-661)

S? - Perform a Hot Bus Transfer (2CR-523) S,D,A 6 SB - Start A Reactor Coolant Pump (2CR-513) S, D,A, L 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - Uninterruptible Power Supply [UPS*VITBS2-3(4)] Shutdown (2PL-021) D 6 P2 - Reset the Terry Turbine Trip Throttle Valve (2PL-004) D,R 4S P3 - Place the Diesel Air Compressor in Service (2PL-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 SRO-I 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  ::::11::::11::::1 (EN)gineered safety feature  :::: 1 I:::: 1 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 3/ s 3 Is 2 (randomly selected)

11::::11::::1 II (R)CA (S)imulator NUREG-1021, Revision 10 FENOC Facsimile r2

ES 301 C on t ro IRoom /I n-Pl an t SiYStems o utrme Form ES 301 2 - -

Facility: Beaver Valle~ Unit 2 Date of Examination: 12/7/ thru 12/18 2015 11 Exam Level: RO D SRO(I) !RI SRO(U) D Operating Test No.: BV2LOT15 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System I JPM Title Type Code* Safety Function S 1 - Transfer to Hot Leg Recirculation (2CR-570) S,D,EN,A 3 S2 - Discharge Steam Generator Slowdown Evaporator Test Tank [2SGC- S,N,A 9 TK23A] to Unit 2 Cooling Tower Slowdown. (2CR-660)

S3 - Rod Control Assembly Partial Movement Test - (Rods continue to S,N,A 1 move during performance of the test) (2CR-747)

S4 - Batch to the Refuel Water Storage Tank (2CR-537) S,D 2 S6 - Respond to Containment Air Recirculation Fan High Vibration Alarm S,N 5 (2CR-661)

S7 - Perform a Hot Bus Transfer (2CR-523) S,D,A 6 SS - Start A Reactor Coolant Pump (2CR-513) S, D,A, L 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 - Uninterruptible Power Supply [UPS*VITBS2-3(4)] Shutdown (2PL-021) D 6 P2 - Reset the Terry Turbine Trip Throttle Valve (2PL-004) D,R 4S P3 - Place the Diesel Air Compressor in Service (2PL-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 SRO-I 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 ~1/~1/~1 (EN)gineered safety feature ~ 1 I~ 1 I.:::. 1 (control room system)

(L)ow-power I Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 3/ s 3 Is 2 (randomly selected)

(R)CA ~1/~1/~1 11 (S)imulator NUREG-1021, Revision 10 FENOC Facsimile r2

A,ppen d"1x D s cenano

. 0 utrme 2L15N1 Facility: BVPS Unit 2 Scenario No. 1 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO ATC BOP Initial IC-142(15): 48% power, MOL, Equ. XE Conditions, CB "D"@ 158 steps, RCS boron -

Conditions: 558 ppm.

Turnover: Maintain 48% power.

Critical Tasks: 1. CT-10 (E-0.M) Crew closes PORV block MOV

2. CT-13 (E-0.Q) Crew manually trips turbine

3. CT-43 (FR-H.1.A) Crew establishes feedwater flow Event Malf. No. Event Type Event Description No.

1 XMT-RCS019A (I,A) ATC, SRO Pressurizer level transmitter, 2RCS*LT459 drifts low.

(TS) SRO 2 XMT-MSS053A (I,A) BOP, SRO 2MSS*PT496 fails low over 30 sec, requires manual control of (TS) SRO 2FWS*FCV498.

3 RCS02A (C,A) ATC, SRO 30 gpm RCS leak (unisolable)

(TS) SRO 4 (R) ATC (N) BOP, SRO Ops management directed Emergency Shutdown, AOP 2.51.1.

5 RCS02A (M)ALL 400 gpm loop A LOCA , requires manual Rx trip 6 EHC08A (C) BOP, SRO Auto main Turbine trip failure 7 VLV-RCS034A 2RCS*PCV456 lifts/fails to reseat on Rx trip, requires manual (C)ATC, SRO closure ofMOV block valve, 2RCS*MOV536.

8 PMP-AFWOO 1, 2, Loss of all feed, Entry into FR-H.1, success path- main feed LOA-AFW022 (M)ALL 9 VLV- 2SSR-AOV117 A, B, C, SG BD sample line auto isolation MSC 104, 105, 106 (C) ATC, SRO failure (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ---+ FR-H.1 ---+ E-0 ---+ E-1 NUREG-1021, Revision 10 FENOC Facsimile r2

A endix D Scenario Outline 2L 15N2 Facility: BVPS Unit 2 Scenario No. 2 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO ATC BOP Initial IC-143 (10): 100% power, BOL, Equ. XE Conditions, CB "D"@ 227 steps, RCS boron -

Conditions: 1100 ppm.

Turnover: Maintain current plant conditions Critical Tasks: 1. CT-6 (E-0.1) Crew establishes SIS Flow

2. CT-52 (FR-S.1.C) Crew inserts negative reactivity

3. CT-17 (E-2.A) Crew isolates the faulted SG Event Event Type Event Description No.

1 XMT-MSS043A (R) ATC Load rejection - VPL failure, (N) BOP/SRO 20M-26.4.X 2 GEN02 (C,A) BOP/SRO MUG Voltage regulator overexcitation failure.

3 XMT-RCS030A (I,A) ATC/SRO 2RCS*PT444 drifts HIGH, PRZR pressure decreases, manual SROT.S. control of PRZR pressure required.

4 XMT-RCS002A SROT.S. "A" RCS loop flow transmitter, 2RCS*FT415, fails low.

5 FLX-CFW33 (M) ALL 2800 gpm Feedwater leak inside CNMT on "C" SG with an PPLOlA A TWS - Failure of auto/manual Rx trip on manual Rx trip PPLOlB attempt.

6 VLV-SIS069 2SIS*MOV867A and 2SIS*MOV867B auto open failure.

(C) ATC, SRO VLV-SIS070 7 VLV-MSC021, (C) BOP/SRO "B" Train Hydrogen Analyzer fails to automatically start on 023,024,025 SIS signal.

8 VLV-AFW014 (C) BOP/SRO AFW valve, 2FWE*HCV100B, fails to close from the CR.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ~ FR-S. l ~ E-0 ~ E-2 NUREG-1021, Revision 10 FENOC Facsimile r2

Appen d"1x D s cenario outme r 2L 15N4 II Facility: BVPS Unit 2 Scenario No. 4 Op Test No.: BV2LOT15 NRC Examiners: Candidates: SRO I ATC BOP Initial IC 145: 4.8% power, MOL, Rx SIU in progress, CB "D" @ 105 steps, RCS bordn - 1349 Conditions: ppm.

Turnover: Due to an oil leak, SIU 2CCS-P21B and S/D 2CCS-P21A IAW 20M-28.4.H Raise power to 15% to SIU main turbine IAW 20M-52.4.A.

Critical Tasks: 1. CT-11 (E-0.0) CNMT isolation

2. CT-18 (E-3.A) Crew isolates ruptured SG

3. CT-19 (E-3.B) Crew establishes/maintains RCS temperature

4. CT-20 (E-3.C) Crew depressurizes RCS to meet SI termination criteria Event Malf. No. Event Type Event Description No.

1 (N) BOP/SRO Due to oil leak, S/U 2CCS-P21B & S/D 2CCS-P21A.

2 (R) ATC Normal power increase to 15% IAW 20M-52.4.A (N) SRO 3 CNH"'.CFWll (C,A) BOP/SRO 2FWS*FCV479, Bypass Feedwater valve controller fails as is in AUTO, requires manual operation.

4 PMP-CHS002 (C,A) ATC/SRO 2CHS*P21B, Charging/ HHSI pump shaft seizure.

SRO (TS) 5 (N) ATC/SRO Restore normal charging and letdown.

6 XMT-MSC038A SRO (TS) 2LMS*PT952, CNMT pressure transmitter fails high.

7 PPL02A (M)ALL Spurious Rx trip.

8 RCS04B (M)ALL 21B SG 520 gpm tube rupture.

9 PPL07B (C) ATC/SRO 2CHS*P21C, Charging I HHSI auto start failure.

10 VLV-SEA015 (C) BOP/SRO Train B CIA failure with 2CHS*MOV378 and 2HVP*MOD22B auto close failures.

11 VLV- (C) ATC/SRO PRZR PORV fails to close when opened for RCS RCS032,33,34 depressurization in E-3, requires isolation.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (A)bnormal E ES-0.1 - E E-3 NUREG-1021, Revision 10 FENOC Facsimile r2