ML19302E287

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Final Written Examination and Operating Test Outlines (Folder 3)
ML19302E287
Person / Time
Site: Beaver Valley
Issue date: 09/13/2019
From: David Silk
NRC Region 1
To:
Shared Package
ML18296A422 List:
References
CAC 000500
Download: ML19302E287 (27)
v • d • e


Text

ES 301 C t IR on ro

/1 Pl t S t

oom n-an

,ys ems Otl" u me F orm ES 301 2 Facility: Beaver Valle)£ Unit 2 Date of Examination: 10/7 thru 10/181 2019 Exam Level: RO lZl SRO(I) D SRO(U) D Operating Test No.: BV2LOT19 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System I J PM Title Type Code*

Safety Function I

S1 2CR-747, Rod Control Partial Movement Test- (Rods continue to S,A,D,P 1

move during performance of the test) (2CR-747)

I S2 2CR-056, Place Excess Letdown in Service S,D 2

S3 2CR-760, Transfer from Hot Leg to Cold ~eg Recirculation S, A, EN, M, 3

L S4 2CR-713, Start the "A" Reactor Coolant Pump:

S,A,D,L 4P S5 2CR-020, Transferfrom Bypass to Main Feed Regulating Valve S,D 4S S6 2CR-800, Respond to a Loss of Vital Bus 2 S,N 6

"57 2CR-622, Respond to Radiation Monitor Alarm (Leak Collect Vent)

S,A,D 7

S8 2CR-801, Respond to Acts of Nature - Severe Weather S,N 9

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

P1 2PL-016, Transferring Power Supplies for 2HVR-FN201C D

5 P2 2PL-052, AMSAC System Trouble - PT Failure D,E 7

P3 2PL-150, Locally Throttle Open AFW Valve During ECA-0.0 D,E,R 4S 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 / SRO-I / SRO-U (A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant

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

~ 1 / ~ 1 /.::: 1 (control room system)

(L)ow-power / 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 / s 2 (randomly selected)

(R)CA

~1,~1,~1 (S)imulator NUREG-1021, Revision 11 FENOC Facsimile Rev 1

ES 301 C

t IR on ro

/I Pl t S t oom n-an iYS ems 0 tr u me F orm ES 301 2 Facility:

  • Beaver Valle3t Unit 2 Date of Examination: 10/7 thru 10/181 2019 Exam Level: ROD SRO(I.) [8]

SRO(U) D Operating Test No.: BV2LOT19 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U) *

\\

System/ JPM Title Type Code*

Safety I

Function S1 2CR-747, Rod Control Partial Movement Test- (Rods continue to S,A,D,P 1

move during performance of the test) (2CR-747)

S2 2CR-056, Place Excess Letdown in Service S,D 2

S3 2CR-760, Transfer from Hot Leg to Cold Leg Recirculation S, A, EN, M, 3

L 2CR-713, Start the "A" Reactor Coolant Pump I

S,A,D,L 4P S4

(

L SS 2CR-020, Transfer from Bypass to Main Feed Regulating Valve S,D 4S S6 2CR-800, Respond to a Loss of Vital Bus 2 S,N I

6 I

S7 2CR-622,'Respond to Radiation Monitor Alarm (Leak Collect Vent)

S,A,D 7

S8 In-Plant Systems @ (3 for RO); (2for SRO-I); (3 or 2 for SRO-U)

I P1 2PL-016, Transferring Power Supplies for 2HVR-FN201 C D

5 P2 2PL-052, AMSAC System Trouble - PT Failure D,E 7

P3 2PL-150, Locally Throttle Open AFW Valve During ECA-0.0 D,E,R 4S 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 / SRO-I / SRO-U )

(A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank S9/S8/S4

{E)mergency or abnormal in-plant

1/;;;
11;;;
1 (EN)gineered safety feature
1 /;;;
1 /?. 1 (control room system)

(L)ow-power / Shutdown I

I

1/;;;
1/;;;
1 (N)ew or (M)odified from bank including 1 (A)
21;;;
21;;;
1 (P)revious 2 exams S3/S3/S2 (randomly selected)

\\

(R)CA

1/;;;
11;;;
1 (S)imulator NUREG-1021, Revision 11 FENOC Facsimile Rev 1

ES 301 C

t IR on ro

/I Pl t S t oom n-an iys ems 0 tr u me F orm ES 301 2 Facility: Beaver Valle~ Unit 2 Date of Examination: 10/7 thru 10/181 2019 Exam Level: ROD SRO(l) D SRO(U) l2s:l Operating Test No.: BV2LOT19 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/ JPM Title Type Code*

Safety Function S1 S2 S3 2CR-760, Transfer from Hot Leg to Cold Leg Recirculation S, A, EN, M, 3

L-S4 2CR-713, Start the "A" Reactor Coolant Pump S, A, D, L 4P S5 S6 2CR-800, Respond to a Loss of Vital Bus 2 S,N 6

S7 S8 In-Plant Systems @ (3 for RO); (2for SRO-I); (3 or 2 for SRO-U)

P1 P2' 2PL-052, AMSAC System Trouble - PT Failure D,E 7

P3 2PL-150, Locally Thr?ttle Open AFW Valve During ECA-0.0 D,E,R 4S 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 / SRO-I / SRO-U (A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant
.
1/;.:1/;.:1 (EN)gineered safety feature
.
1 / ;.: 1 / ~ 1 ( control room system)

{L)ow-power / Shutdown

.
11;.:11;.:1 (N)ew or (M)odified from bank including 1 (A)
.
21;.:21;.:1 (P)revious 2 exams S3/S3/S2 (randomly se,lected)

(R)CA

.
11;.:11;.:1 (S)imulator NUREG-1021, Revision 11 FENOC Facsimile Rev 1

A d" D

,ppen 1x s

. 0 I'

cenario utme Facility:

BVPS Unit2 Scenario N9. 1 OpTestN9.:

  • 2LOT19NRC Examiners:

Candidates:

SRO ATC BOP Initial IC 173 (17): 75% power, MOL, Equ. XE Conditions, CB "D"@ 185 steps, RCS boron-Conditions:

980ppm.

I Turnover:

Maintain 75% power.

I Critical Tasks:

1. CT-13 (E-0.Q) Manually trip the turbine.
2. CT-43 (FR-H.l.A) Establish Feedwater flow into at least one SG.

Event Malf. No.

Event Type Event Description No*.

1 CNH-PCS09B

{C,A)ATC, SRQ 2RCS-LK459Fdemand drifts to 0% in automatic, reducing chanring flow, requires manual PRZR level *control.

2 XMT-MSS055A

{C,A) BOP, SRO 21C steam generator Feed flow transmitter 2FWS*FT496 (TS) SRO drifts low.

3 FLX-LDS04 (C,A)ATC, SRO 25 gpm RCS letdown line le¥. (isolable)

I (TS) SRO 4

NIA

(

(R) ATC Management directed Emergency SID at 2%/inin, IA W AOP,

(N) BOP, SRO 2.51.1 5

RCS02B (M)ALL 520 gpm LOCA on RCS loop B

6 EHC08A (C) BOP, SRO Automatic turbine trip failure, manual trip su~cessful.

PMP-AFWOOl, 2, Terry turbine and 23A motor driven AFW pumps trip on start.

7 LOA-AFW022 (M)ALL 23B motor driven AFW pump shaft sheared. Crew enters FR-H.1 to restore feedwater via a main feed pump.

CNH-PCS10B After re-entry into E-0, MPC fails high, PORV 455C opens 8

VLV-RCS034A (C) ATC, SRO and sticks, requires manual closure of block valve and spray valves.

9 PMP-MSCOll (C) BOP, SRO EDG 2-1 ventilation fan fa1ls to autq start on SI/EDG start.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0-FR-H.1 -E-O-E-1

/

NUREG-1021, Revision 11

../

FENOC Facsimile Rev. AG

A d' D 1ppen 1x s

. 0 tr cenario u me 2L19N2 Facility:

BVPS Unit2 Scenario No. 2 Op Test No.:

2LOT19NRC Examiners:

Candidates:

SRO ATC BOP Initial IC-59 (18): 100% power, MOL, Equ. XE Conditions, CB "D" @230 steps, RCS boron -

Conditions:

890ppm.

Turnover:

Maintain 100% power.

Critical Tasks:

1. CT-2 (E-0.D) Actuate SIS.
2. CT-12 (E-0.P) Actuate Main steam line isolation.
3. CT-17 (E-2.A) Isolate Faulted SG.

Event Malf. No.

Event Type Event Description No.

1 XMT-LDS003A (C,A) _ATC, SRO VCT level transmitter, 2CHS-LT115 fails low.

2 NIS07B

.(C,A) BOP, SRO N-36, Instrument p*ower fuse blows, requires removal from (TS) SRO service and compensatory actions.

3 CRF03-F6 (C,A)ALL Control Bank D, Rod F06 drops.

(TS) SRO 4

FLX-CFW33 (M)ALL C SG feedwater leak inside Containment.

5 VLV-MSS013 (C) BOP, SRO Condenser steam dump valve 2MSS-PCV106A *stuck open, manual main steamline isolation required.

6 PPLOSA, PPLOSB (C)ATC, SRO Automatic safety injection actuation failure.

7 PPL07A (C)ATC, SRO Charging/HHS! pump, 2CHS*P21A auto start failure upon SI actuation.

I 8

. CNH-AFW02A (C) BOP, SRO 2FWE*HCV100B fails to 100%, requires securing AFW pump.

  • PMP-MSC036 Leak Collection Filtered Exhaust Fans, 2HVS*FN204A and 9

PMP~MSC037 (C) BOP, SRO _ l3, trip on Rx trip, requires manual starting of

\\

2HVS*FN204B.

10 11 I

\\

,~,

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (A)bnormal E-0 ~ E-2 ~ ES-1.1 NUREG-1021, Revision 11 FENOC Facsimile Rev. AG

A d' D 1PPen,x s

  • o tr cenario u me Facility:

BVPS Unit2 Scenario No. 3 Op Test No.:

2LOT19NRC

(

Examiners:

Candidates:

SRO ATC BOP Initial IC-87 (29): 100% power, EOL, Equ. XE Conditions, CB "D" @230 steps, RCS boron-Conditions:

lOOppm.

Turnover:

Maintain 100% power.

l

~

Critical Tasks:

1. CT-11 (E-0.0) Close CNMT isolation valves.
2. CT-18. (E-3.A) Isolate ruptured SG.
3. CT-19 (E-3.B) Establish/maintain RCS temperature.

Event Malf. No.

Event Type Event Description No.

(C1A) ATC, SRO 1

XMT-RCS019A (TS) SRO Pressurizer Level Channel, 2RCS*LT459 drifts high.

2 XMT-MSS04~A (C,A)ALL Load rejection-VPL failure, Auto Rod insertion failure -

(TS)'SRO requires manual rod insertion 20M-26.4.X 3

CNH-CFW12 (C,A) BOP, SRO 2FWS*FCV488 fails ASIS in Auto during Load rejection-requires manual control.

Pressurizer pressure transmitter 2RCS*PT445 fails high in 4

XMT-RCS031A (C,A) ATC, SRO auto~atic, 2 PORV~ open. 2RCS*PCV455D requires manual (TS) SRO

. closure, 2RCS*PCV456 sticks open, PORV block valve 2RCS*MOV536 fails to close.

5 RCS04A (M)ALL Reactor trip causes a 650 gpi:n 21A SG tube rupture.

6 VLV-MSSOll (C) BOP, SRO Reheat steam fails to auto isolate on trip -* requires closing VLV-MSS012 2MSS-MOV1 OOA and B.

7 PPL08A, PPL08B (C)ATC, SRO Automatic CIA actuation does not occur; manual initiation is required.

8 CNH-PCS07 (C) BOP, SRO Condenser steam dump controller failed to 0%, ASDVs required for RCS cooldown.

9 10 11 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent,. (M)ajor, (A)bnormal E-0---+ E-1--+ E-3--+ ECA-3.1 NUREG-1021, Revision 11 FENOC Facsimile Rev. AG i

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

BVPS Unit2 2LOT19 RO-Date of Exam 10/7/19 - 10/18/19 RO KIA Category Points SRC> ()NL Y" Points.

I Tier Group K

K K K K

K A A A A G TOTAL A2 **

G**

TOTAL..

1 2

3 4

5 6

1 2

3 4

1 3

3 3

3 3

3 18

1.

Emergency 2

le' 1

1 2

2 2

1 9

Abnormal

,~..

Tier I

Plant 4 4 5 5 5 41 27 Evolutions Totals 1

3 2

3 3

2 3

3 2

2 3

2 28

2.

Plant 2

Systems 0

1 1

1 1

1 1

1 1

1 1

10 Tier 3 3 4 4 3 4 4 3 3 4 3 38 Totals

'J 1

2 3

4 10

3. Generic Knowledge and Abilities Category 3

2 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals'1 in each KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it 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 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 Kl As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, !espectively.

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 Kl As.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' 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, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the KIA catalog.

    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA cataloQ is used to develop the sample plan.

.NUREG-1021, Revision 11 RO Page 1 of 13 FENOC Facsimile Rev. 0

ES-401 PWR Examination Outline Form ES-401-2 I

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

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

IR 1

2 3

1 2'

000007 (EPE 7; BW E02&E10; CE E02)

)(

EK1 Knowledge of the operational implications of 3.6 Reactor Trip, Stabilization, Recovery / 1 the following concepts as they apply to the reactor

[Question 1]

trip:

EK1.04 Decrease in reactor power following reactor T

trip (prompt drop and subsequent decay)

(CFR41.8 / 41.10 / 45.3) 000008 (APE 8) Pressurizer Vapor Space X

AK2. Knowledge of the interrelations between the 2.7 Accident/ 3 Pressurizer Vapor Space Accident and the following:

[Question 2]

AK2.01 Valves

,7 (CFR 41.7 / 45.7) 000009 (EPE 9) Small Break LOCA / 3 X

EK1 Knowledge of the operational implications of 4.2

[Question 3]

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

EK1.01 Natural circulation and cooling, including

)

reflux boiling (CFR 41.8 / 41.10 / 45.3) 000011 (EPE 11) Large Break LOCA / 3

)( 2.4.46 Ability to verify that the alarms are consistent 4.2

[Question 4]

with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 000015 (APE 15) Reactor Coolant Pump x 2.1.27 Knowledge of system purpose and/or 3.9 Malfunctions / 4 function.

[Question 5]

(CFR: 41.7) 000022 (APE 22) Loss of Reactor Coolant X

AK3. Knowledge of the reasons for the following 3.2 Makeup/ 2 responses as they apply to the Loss of Reactor

[Question 6]

Coolant Makeup:

i I

AK3.05 Need to avoid plant transients (CFR 41.5, 41.10 / 45.6 / 45.13) 000025 (APE 25) Loss of Residual Heat

)(

AK2. Knowledge of the interrelations between the 2.6 Removal System / 4 Loss of Residual Heat Removal System and the

[Question 7]

following:

J AK2.05 Reactor building sump l

(CFR 41.7 / 45.7)

\\

000026 (APE 26) Loss of Component X

a:;

AA 1. Ability to operate and / or monitor the 3.1 Cooling Water/ 8 following as they apply to the Loss of Component Cooling Water:

[Question 8]

AA 1.01 CCW temperature indications (CFR 41. 7 / 45.5. / 45.6)

NUREG-1021, Revision 11 RO Page 2 of 13 FENOC Facsimile Rev. 0

ES-401

~

PWR Examination Outline

)

Form ES-401-2 Emergency and Abnormal Plant Evolutions -Tier 1/Group 1(RO) Continued E/APE # / Name I Safety Function K

K K A-~* G.

KIA Topic(s),

IR 1

2 3

1 2

000029 (EPE 29) Anticipated Transient EA 1 Ability to operate and monitor the following as

)(

4.1 Without Scram / 1 they apply to an ATWS:

[Question 9]

EA 1.15 AFW system

. (CFR 41. 7 / 45.5 / 45.6) i:. '*

000040 (APE 40; BW E05; CE E05; W E12)

.x**

AA2. Ability to determine and interpret the following 4.6 Steam Line Rupture-Excessive Heat as they apply to the Steam Line Rupture:

Transfer 14 AA2.02 Conditions requiring a reactor trip

[Question 1 OJ (CFR: 43.5 / 45.13) 000054 (APE 54; CE EQ6) Loss of Main

)

AK 1. Knowledge of the operational implications of 3.6 the following concepts as they apply to Loss of Feedwater /4 Main Feedwater (MFW):

[Question 11]

AK 1.02 Effects of feedwater introduction on dry SIG (CFR 41.8 / 41.10 / 45.3) 000056 (APE 56) Loss of Offsite Power/ 6 J(, 2.2.39 Knowledge of less than or equal to one hour 3.9 Technical Specification action statements for

[Question 12]

systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13) 056AG2.2.39 000062 (APE 62) Loss of Nuclear Service

)( '

AA2. Ability to determine and interpret the following 2.9 Water/ 4 as they apply to the Loss of Nuclear Service Water:

[Question 13]

AA2.01 Location of a leak in the SWS (CFR: 43.5 / 4~.13) 000065 (APE65) Loss of Instrument Air/ 8

)(

AK3. Knowledge of the reasons for the following 3.0

[Question 14]

J responses as they apply to the Loss of Instrument Air:

I AK3.04 Cross-over to backup air supplies (CFR 41.5,41.10 / 45.6 / 45.13) 000077 (APE 77) Generator Voltage and

)

AA 1. Ability to operate and/or monitor the following 3.8 Electric Grid Disturbances / 6 as they apply to Generator Voltage and Electric

[Question 15]

Grid Disturbances:

I AA 1.03 Voltage regulator controls (CFR: 41.5 and 41.10 / 45.5, 45.7, and 45.8)

(W E04) LOCA Outside Containment / 3

)(

EA2. Ability to determine and interpret the following 3.6

[Question 16]

as they apply to the {LOCA Outside Containment)

EA2.2 Adherence to appropriate procedures and operation within the limitations in the facility's

.. license and amendments.

(CFR: 43.5 / 45.13)

NUREG-1021, Revision 11 RO Page 3 of 13 FENOC Facsimile Rev. 0

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

K K A A. G KIA Topic(s)

IR 1

2 3

1 2 (BW E04; W E05) Inadequate Heat

)(

EK2. Knowledge of the interrelations between the 3.9 Transfer-Loss of Secondary Heat Sink/ 4

{Loss of Secondary Heat Sink) and the following:

EK2.2 Facility's heat removal systems, including

[Question 17]

primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7 / 45.7)

(W E11) Loss of Emergency Coolant

)(

EK3. Knowledge of the reasons for the following 3.6 Recirculation / 4 responses as they apply to the {Loss of Emergency

[Question 18]

Coolant Recirculation)

EK3.4 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

(CFR: 41.5 / 41.10, 45.6, 45.13) 3 3 3 3 3 3 KIA Category Point Totals:

Group Point Total:

18 NUREG-1021, Revision 11 RO Page 4 of 13 FENOC Facsimile Rev. 0

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

E/APE # / Name I Safety Function K K K A 'A* G KIA Topic(s)

IR 1

2 3

1 2,,

000036 (APE 36; BW/A08) Fuel-Handling

  • x 2.1.32 Ability to explain and apply system limits and 3.8 Incidents/ 8 precautions.

[Question 19]

(CFR: 41.10 / 43.2 / 45.12) 000037 (APE 37) Steam Generator Tube

)

AK3. Knowledge of the reasons for the following 3.6 Leak/ 3 responses as they apply to the Steam Generator Tube Leak:

[Question 20]

' AK3.06 Normal operating precautions to preclude or minimize SGTR (CFR 41.5,41.10 / 45.6 / 45.13) 000051 (APE 51) Loss of Condenser

>C AA2. Ability to determine and interpret the following 3.9 Vacuum/ 4 as they apply to the L9ss of Condenser Vacuum:

[Question 21]

  • AA2.02 Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 000059 (APE 59) Accidental Liquid

~

AK2. Knowledge of the interrelations between the 2.7 Radwaste Release / 9 Accidental Liquid Radwaste Release and the

[Question 22]

following:

AK2.01 Radioactive-liquid monitors I

(CFR41.7/45.7) 000069 (APE 69; W E14) Loss of

~

,., AA2. Ability to determine and interpret the following 3.7 Containment Integrity/ 5 as they apply to the Loss of Containment Integrity: *

[Question 23]

AA2.01 Loss of containment integrity (CFR: 43.5 / 45.13)

(W E01 & E02) Rediagnosis & SI

~

EK3. Knowledge of the reasons for the following 3.3 Termination/ 3 responses as they apply to the (SI Termination)

[Question 24]

,, EK3.2 Normal, abnormal and emergency operating procedures associated with (SI Termination).

(CFR: 41.5 / 41.10, 45.6, 45.13)

,,_)

(BW E08; W E03) LOCA Cooldown-

)

EA 1. Ability to operate and I or monitor the following 3.7 Depressurization / 4 as they apply to the (LOCA Cooldown and Depressurization)

[Question 25]

EA 1.2 Operating behavior characteristics of the facility.

(CFR: 41. 7 / 45.5 / 45.6)

NUREG-1021, Revision 11 RO Page 5 of 13 FENOC Facsimile Rev. 0

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

K K A A,G KIA Topic(s)

IR 1,2 3

1 2'

000074 (EPE 74; W E06 & E07) Inadequate

)

EK 1. Knowledge of the operational implications of 3.5

, Core Cooling I 4 the following concepts as they, apply to the

i.

(Degraded Core Cooling)

[Question 26]

EK1.2 Normal, abnormal and emergency operating procedures associated with (Degraded Core Cooling).

(CFR: 41_.8 / 41.10, 45.3)

(W E16) High Containment Radiation /9

)

EA 1. Ability to operate and / or monitor the following 2.9 as they apply to the (High Containment Radiation)

[Question 27]

EA 1.2 Operating behavior characteristics of the I

,* facility.

(CFR: 41. 7 / 45.5 / 4,5.6)

)

1 1 2 2 2 1

\\

1.~,; Cc:1Lt:1gory Point Totals:

Group Point Total:

9 NUREG-1021, Revision 11 RO Page 6 of 13 FENOC Facsimile Rev. 0

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

- Tier 2/Group 1 (RO)

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

IR 1

2 3

4 5

6 1

2 3

4 003 (SF4P RCP) Reactor

)(

K2 Knowledge of bus power supplies to the 2.5 Coolant Pump following:

[Question 28]

K2.02 CCW pumps (CFR: 41.7) 004 (SF1; SF2 CVCS) Chemical

)(

K4 Knowledge of eves design feature(s) and/or 3.3 and Volume Control interlock(s) which provide for the following:

[Question 29]

K4.05 Interrelationships and design basis, including

.fluid flow splits in branching networks (e.g., charging and seal injection flow)

(CFR: 41.7) 005 (SF4P RHR) Residual Heat

)(

A2 Ability to (a) predict the impacts of the following 3.5 Removal malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to

[Question 30]

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

_/

A2.02 Pressure transient protection during cold shutdown (CFR: 41.5 / 43.5 / 45.3 / 45.13) 006 (SF2; SF3 ECCS)

)(

K6 Knowledge of the effect of a loss or malfunction 3.4 Emergency Core Cooling C

on the following will have on the ECCS:

[Question 31]

K6.01 BIT/borated water sources (CFR: 41.7 / 45.7) 007 (SF5 PRTS) Pressurizer

)(

A1 Ability to predict and/or monitor changes in 2.6 Relief/Quench Tank parameters (to prevent exceeding design limits) associated with operating the PRTS controls

[Question 32]

including:

A 1.03 Monitoring quench tank temperature (CFR: 41.5 / 45.5) 007 (SF5 PRTS} Pressurizer X

K3 Knowledge of the effect that a loss or malfunction 3.3 Relief/Quench Tank of the PRTS will have on the following:

[Question 33]

K3.01 Containment (CFR: 41. 7 / 45.6) 008 (SF8 CCW) Component

)(

A4 Ability to manually operate and/or monitor in the 2.9 Cooling Water control room:

[Question 34]

A4.07 Control of minimum level in the CCWS surge tank (CFR: 41. 7 / 45.5) 010 (SF3 PZR PCS) Pressurizer

)(

K1 Knowledge of the physical connections and/or 3.2 Pressure Control cause-effect relationships between the PZR PCS and the following systems:

[Question 35]

K1.08 PZR LCS (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 010 (SF3 PZR PCS) Pressurizer

)(

K6 Knowledge of the effect of a loss or malfunction 3.2 Pressure Control of the following will have on the PZR PCS:

[Question 36]

K6.03 PZR sprays and heaters (CFR: 41.7 / 45.7)

NUREG-1021, Revision 11 RO Page 7 of 13 FENOC Facsimile Rev. 0

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

- Tier 2/Group 1 (RO) Continued I

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

IR 1

2 3

4 5

6 1

2 3

4 012 (SF? RPS) Reactor

)

K1 Knowledge of the physical connections 3.1 Protection and/or cause effect relationships between the

[Question 37]

RPS and the following systems:

K1.06 T/G (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 012 (SF? RPS) Reactor

)

K4 Knowledge of RPS design feature(s) and/or 2.8 Protection interlock(s) which provide for the following:

[Question 38]

K4.09 Separation of control and protection circuits (CFR:41.7) 013 (SF2 ESFAS) Engineered

}(

K5 Knowledge of the operational implications 2.8 Safety Features Actuation of the following concepts as they apply to the ESFAS:

[Question 39]

K5.01 Definitions of safety train and ESF channel (CFR: 41.5 / 45. 7) 013 (SF2 ESFAS) Engineered

)

K6 Knowledge of the effect of a loss or 2.7 Safety Features Actuation malfunction on the following will have on the ESFAS:

[Question 40]

K6.01 Sensors and detectors (CFR: 41. 7 / 45.5 to 45.8)

,022 (SF5 CCS) Containment

}(

K1 Knowledge of the physical connections 2.9 Cooling and/or cause-effect relationships between the

[Question 41]

CCS and the following systems:

K1.04 Chilled water (CFR: 41.2 to 41.9 / 45. 7 to 45.8) 026 (SF5 CSS) Containment

}(

A2 Ability to (a) predict the impacts of the 3.6 Spray following malfunctions or operations on the

[Question 42]

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

A2.07 Loss of containment spray pump suction

(

when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit (CFR: 41.5 / 43.5 / 45.3 / 45.13) 026 (SF5 CSS) Containment

}(

A4 Ability to manually operate and/or monitor 4.5 Spray in the control room:

[Question 43]

A4.01 CSS controls (CFR: 41. 7 / 45.5 to 45.8) 039 (SF4S MSS) Main and

}(

A1 Ability to predict and/or monitor changes in 2.9 Reheat Steam parameters (to prevent exceeding design I

limits) associated with operating the MRSS

[Question 44]

controls including:

A 1.10 Air ejector PRM 1,

(CFR: 41.5 / 45.5)

NUREG-1021, Revision 11 RO Page 8 of 13 FENOC Facsimile Rev. 0

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

- Tier 2/Group 1 (RO) Continued System # I Name K

K K K K K A A A A

G KIA Topic(s)

IR 1

2 3

4 5

6 1

2 3

4 039 (SF4S MSS) Main and

)(

A3 Ability to monitor automatic operation of the 3.1 Reheat Steam MRSS, including:

[Question 45]

A3.02 Isolation of the MRSS (CFR: 41.5 / 45.5) 059 (SF4S MFW) Main

)(

A4 Ability to manually operate and monitor in 2.9 Feedwater

)

the control room:

[Question 46]

A4.03 Feedwater control during power increase and decrease (CFR: 41.7 / 45.5 to 45.8) 061 (SF4S AFW)

X KS Knowledge of the operational implications 3.6 Auxiliary/Emergency Feedwater of the following concepts as the apply to the

[Question 47]

AFW:

KS.01 Relationship between AFW flow and RCS heat transfer (CFR: 41.5 / 45.7).

062 (SF6 ED AC) AC Electrical

)(

K4 Knowledge of ac distribution system design 2.7 Distribution

feature(s) and/or interlock(s) which provide for

[Question 48]

the following:

K4.07 One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power (CFR: 41.7) 063 (SF6 ED DC) DC El~ctrical

)(

K2 Knowledge of bus power supplies to the 2.9 Distribution following:

[Question 49]

K2.01 Major DC loads (CFR: 41.7) 064 (SF6 EOG) Emergency

)(

I*,

A3 Ability to monitor automatic operation of the 2.8 Diesel Generator ED/G system, including:

[Question 50]

A3.05 Operation of the governor control of frequency and voltage control in parallel operation (CFR: 41.7 / 45.5)

A 1 Ability to predict and/or monitor changes in 073 (SF7 PRM) Process

)(

3.2 Radiation Monitoring parameters (to prevent exceeding design

[Question 51]

limits) associated with operating the PRM system controls including:

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

NUREG-1021, Revision 11 RO Page 9 of 13 FENOC Facsimile Rev. 0

ES-401 PWR Examination Outline Form ES-401-2 i

Plant Systems

- Tier 2/Group 1 (RO) Continued System # I Name K K K K K K A.. A A A G KIA Topic(s)

IR I

1 2

3 4

5 6

1,2 3 4' i

)

2.4.31 Knowledge of annunciator alarms, 076 (SF4S SW) Service Water indications, or response procedures.

4.2

[Question 52]

(CFR: 41.10 / 45.3) 078 (SF8 IAS) Instrument Air

}(

/

K3 Knowledge of the effect that*a loss or 3.4 i

malfunction of the IAS will have on the

[Question 53]

following:

K3.02 Systems having pneumatic valves and controls (CFR: 41. 7 / 45.6) 103 (SF5 CNT) Containment

)

2.1.25 Ability to interpret reference materials, 3.9

[Question 54]

such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12) 103 (SF5 CNT) Containment

}(

K3 Knowledge of the effect that a loss or 3.8 malfunction of the containment system will

[Question 55]

have on the following:

K3.02 Loss of containment integrity under normal operations (CFR: 41. 7 / 45.6) 3 2 3 3 2 3 3 2 2 3 2 KIA Category Point Totals:

Gro_up Point Total:

28 NUREG-1021, Revision 11 RO Page 10 of 13 FENOC Facsimile Rev. 0

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

- Tier 2/Group 2(RO)

System # / Name K

K K K K K A A A A G KIA Topic(s) 1 2

3 4

5 6

1 '2 3 4

IR 002 (SF2; SF4P RCS) Reactor

}(

K5 Knowledge of the operational implications of 4.0 Coolant the following concepts as they apply to the

[Question 56]

RCS:

a*

K5.11 Relationship between effects of the primary coolant system and the secondary coolant system

~

(CFR: 41.5 / 45.7) 011 (SF2 PZR LCS) Pressurizer

}(

K2 Knowledge of bus power supplies to the 3.1 l:,evel Control following:

[Question 57]

K2.02 PZR heaters (CFR: 41.7) 015 (SF7 NI) Nuclear

}(

A 1 Ability to predict and/or monitor changes in 3.5 Instrumentation parameters to prevent exceeding design limits)

[Question 58]

associated with operating the NIS controls including:

A1.02SUR (CFR: 41.5 / 45.5) 016 (SF7 NNI) Nonnuclear Instrumentation X

A3 Ability to monitor automatic operation of the NNIS, including:

2.9

[Question 59]

A3.01 Automatic selection of NNIS inputs to control systems (CFR: 41.7 / 45.5) 033 (SF8 SFPCS) Spent Fuel

~

A2 Ability to (a) predict the impacts of the 3.1 Pool Cooling following malfunctions or operations on the

[Question 60]

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

A2.03 Abnormal spent fuel pool water level or loss of water level (CFR: 41.5 / 43.5 / 45.3 / 45.13) 034 (SF8 FHS) Fuel-Handling

)

K6 Knowledge of the effect of a loss or 2.6 Equipment malfunction on the following will have on the

[Question 61]

Fuel Handling System:

- K6.02 Radiation monitoring systems (CFR: 41.7 / 45.7) 071 (SF9 WGS) Waste Gas

)

K3 Knowledge of the effect that a loss or 3.2 Disposal malfunction of the Waste Gas Disposal System

[Question 62]

, will have on the following:

K3.05 ARM and PRM systems (CFR: 41. 7 / 45.6) 072 (SF7 ARM) Area Radiation

)

A4 Ability to manually operate and/or monitor in 3.0 Monitoring the control room:

[Question 63]

A4.01 Alarm and interlock setpoint checks and adjustments (CFR: 41.7 / 45.5 to 45.8)

NUREG-1021, Revision 11 RO Page 11 of 13 FENOC Facsimile Rev. 0

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

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

KIA Topic(s) 1 2

3 4

5 6

1 2

3 4

IR 079 (SF8 SAS**) Station Air

)(

K4 Knowledge of SAS design feature(s) and/or 2.9 interlock(s) which provide for the following:

[Question 64]

K4.01 Cross-connect with IAS 1

(CFR: 41.7) 086 Fire Protection

)

2.1.31 Ability to locate control room switches, 4.6

[Question 65]

controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12)

KIA Category Point Totals:

0 1 1 1 1 1 1 1 1 1 1 Group Point Total:

10 NUREG-1021, Revision 11 RO Page 12 of 13 FENOC Facsimile Rev. 0

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

BVPS Unit 2 2LOT19 RO Date of Exam 10/7/19-10/18/19 RO SR() Qnly Category KIA#

Topic IR IR

1.

G2.1.29 2.1.29 Knowledge of how to conduct system lineups, such as valves, 4.1 Conduct breakers, switches, etc.

of Operations (CFR: 41.10 / 45.1 I 45.12)

[Question 66]

G2.1.5 2.1.5 Ability to use procedures related to shift staffing, such as minimum 2.9 crew complement, overtime limitations,, etc.

(CFR: 41.10 / 43.5 / 45.12)

I

[Question 67]

G2.1.6 2.1.6 Ability to manage the control room crew during plant transients.

3.8 (CFR: 41.10 / 43.5 / 45.12./ 45.13)

I

[Question 68]

Subtotal

  • y*,

C

2.

G2.2.13 2.2.13 Knowledge of tagging and clearance procedures.

4.1 Equipment (CFR: 41.10 / 45.13)*

Control

[Question 69]

G2.2.6 2.2:6 Knowledge of the process for making changes to procedures.

3.0 (CFR: 41.10 / 43.3 / 45.13)

[Question 70]

Subtotal

3.

G2.3.5 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation 2.9 Radiation I monitors and alarms, portable survey instruments, personnel monitoring

\\

Control equipment, etc.'

(CFR: 41.11 / 41.12 / 4;3.4 / 45.9)

[Question 71]

G2.3.7 2.3.7 Ability to comply with radiation work permit requirements during 3.5 normal or abnormal conditions.

(CFR: 41.12 / 45.10)

I

[Question 72]

Subtotal

4.

G2.4.1 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.6 Emergency (CFR: 41.10 / 43.5 / 45.13)

Procedures/

[Question 73]

Plan I

G2.4.22 2.4.22 Knowledge of the bases for prioritizing safety functions during 3.6 abnormal/emergency operations.

(CFR: 41. 7 / 41.10 / 43.5 / 45.12)

[Question 74]

G.2.4.3 2.4.3 Ability to identify post-accident instrumentation.

3.7

)

(CFR: 41.6 / 45.4)

[Question 75]

Subtotal Tier 3 Point Total 10 NUREG-1021, Revision 11 RO Page 13 of 13 FENOC Facsimile Rev. 0

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

BVPS Unit 2 2LOT19 SRO Date of Exam 10/7/19-10/18/19 1

,SR01c KIA'. Category Points SRO ONLY Points Tier Group K

K, K.K K KI.A A

,A A, G TOTAL A2 G*

TOTAL

.1 2

3, 4 5

-6 1

2 3.4 r *',

1

1.

3 3

6 I

Emergency 2

2 2

4 Abnormal Plant Tier 5

5 10 Totals f.'

Evolutions

---~*-**--.'

'"-~---*

  • --. ----,~-

1

~

3 2

5

2.

Plant

. ~--.

2 Systems 2

1 3

Tier 5

3 8

Tqtals

-**m**- *-*

3..Generic,Knowledge and 1 2 *J3 4

,7 Abilities Category 1 2 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 outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA from another Tier 3 category.)

1

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 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 Kl As having an importance rating (IR) of 2.5 or higher shall be seleyted. Use the RO and SRO ratings for the RO ar:id 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' 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, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43:

G* Generic KIAs

\\

These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the KIA catalog.

    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA cataloa is used to develop the sample plan.

NUREG-1021, Revision 11

\\

SRO Page 1 of 7 Rev. AG

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

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

IR 1

2 3

1 2

000027 (APE 27) Pressurizer Pressure

)

M2. Ability to determine and interpret the following 3.9 Control System Malfunction / 3 as they apply to the Pressurizer Pressure Control

[Question 76]

Malfunctions:

M2.06 Conditions requiring plant shutdown (CFR: 43.5 / 45:13) 000040 (APE 40; BW E05; CE E05; W E12)

,: ;) 2.1.32 Ability to explain and apply system limits and 4.0 Steam Line Rupture-Excessive Heat precautions.

Transfer/ 4

[Question 77]

(CFR: 41.10 / 43.2 / 45.12) 000055 (EPE 55) Station Blackout/ 6

,X EA2 Ability to determine or interpret the following as 4.1

[Question 78]

they apply to a Station Blackout:

EA2.04 Instruments and controls operable with only de battery power available (CFR 43.5 / 45.13) 000057 (APE 57) Loss of Vital AC

)

2.2.37 Ability to determine operability and/or 4.6 Instrument Bus/ 6 availability of safety related equipment.

[Question 79]

(CFR: 41.7 / 43.5 / 45.12) 000058 (APE 58) Loss of DC Power I 6 X

AA2. Ability to determine and interpret the following 4.1

[Question 80]

as they apply to, the Loss of DC Power:

M2.01 That a loss of de power has occurred; verification that substitute power sources have come on line (CFR: 43.5 / 45.13)

(BW E04; W E05) Inadequate Heat

)

2.1.20 Ability to interpret and execute procedure 4.6 Transfer-Loss of Secondary Heat Sink/ 4 steps.

[Question 81]

(CFR: 41.10 / 43.5 / 45.12) 3 3 6

KIA Category Point Totals:

Group Point Total:

NUREG-1021, Revision 11 SRO Page 2 of 7 Rev.AG

ES-401 E/APE # / Name/ Safety Function 000001 (APE 1) Continuous Rod Withdrawal / 1

[Question 82]

000060 (APE 60) Accidental Gaseous Radwaste Release / 9

[Question 83]

000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7

[Question 84]

(W E15) Containment Flooding/ 5

[Question 85]

KIA Category Point Totals:

I\\

)

NUREG-1021*, Revision 11 PWR Examination Outline Forrri ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(SRO)

K K

K A A G KIA Topic(s)

IR 1

2 3

1 *. 2.

  • ~

AA2. Ability to determine and interpret the following 4.6 I

as they apply to the Continuous Rod Withdrawal AA2.05 Uncontrolled rod Withdrawal, from available indications (CFR: 43.5 / 45.13)

I

~. 2.2.37 Ability to determine operability and/or 4.6 availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12)

(

.. }(

AA2. Ability to determine and interpret the following 2.9 as they apply to the Loss of Source Range Nuclear Instrumentation:

AA2.01 Normal/abnormal power supply operation (CFR: 43.5 / 45.13)

.}( 2.1.23 Ability to perform specific system and 4.4 integrated plant procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 2 2 Group Point Total:

4 SRO Page 3 of 7 Rev.AG

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

  • Tier 2/Group 1 (SRO)

System # I Name K K K K K K A A A A.G KIA Topic(s)

IR 1

2 3

4 5

6 1 i 3

4 003 (SF4P RCP) Reactor

)( 2.1.20 Ability to interpret and execute 4.6 Coolant Pump procedure steps.

[Question 86]

(CFR: 41.10 / 43.5 / 45.12) 061 (SF4S AFW)

)

2.4.50 Ability to verify system alarm setpoints 4.0 Auxiliary/Emergency Feedwater and operate controls identified in the alarm response manual.

[Question 87]

(CFR: 41.10 / 43.5 / 45.3)

(

063 (SF6 ED DC) DC Electrical

)(

A2 Ability to (a) predict the impacts of the 3.2 Distribution following malfunctions or operations on the DC electrical systems; and (b) based on those

[Question 88]

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

A2.01 Grounds (CFR: 41.5 / 43.5 / 45.3 / 45.13)

I I*

076 (SF4S SW) Service Water

)(

A2 Ability to (a) predict the impacts of the

  • 3.7

[Question 89]

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

)

operations:

A2.01 Loss of SWS (CFR: 41.5 / 43.5 I 45/3 / 45/13) 078 (SF8 IAS) Instrument Air

, )(

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

[Question 90]

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

A2.01 Air dryer and filter malfunctions (CFR: ~ 1.5 / 43.5 / 45.3 / 45.13) 3 2

5 KIA Category Point Totals:

Group Point Total:

NUREG-1021, Revision 11 SRO Page 4 of 7 Rev. AG

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 A G KIA Topic(s) 1 2

3 4

,5 6

1 '2, 3 4, '-,

IR 014 (SF1 RPI) Rod Position

}(

A2 Ability to (aj' predict the impacts of the 3.3 Indication i following malfunctions or operations on the

[Question 91]

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

~

A2.01 Loss of offsite power I'

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 035 (SF 4P SG) Steam

  • .*j(

A2 Ability to (a) predict the impacts of the 3.8 Generator following malfunctions or operations.on the SG;

[Question 92]

and (b} based on th9se predictions, use r

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

A2.04 Steam flow/feed mismatch (CFR: 41.5 / 43.5 / 45.3 / 45.5) 001 (SF1 CRDS) Control Rod

.JC 2.4.46 Ability to verify that the alarms are 4.2 Drive.

.consistent with the plant conditions.

[Question 93]

,'/

,* (CFR: 41.10 / 43.5 / 45.3 / 45.12)

KIA Category Point Totals:

2 1 Group Point Total:

3

\\,

NUREG-1021, Revision 11 SRO Page 5 of 7 Rev. AG

ES 401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

BVPS Unit 2 2LOT19 SRO Date of Exam 10/7/19-10/18/19 RO SRO Only Category KIA#

Topic IR IR

1.

G2.1.35 2.1.35 Knowledge of the fuel-handling responsibilities of SROs.

3.9 Conduct (CFR: 41.10 / 43.7) of Operations

[Question 94]

i Subtotal l?~\\1??**

2.

G2.2.19 2.2.19 Knowledge of maintenance work order requirements.

3.4 Equipment (CFR: 41.10 / 43.5 / 45.13)

Control

[Question 95]

G2.2.35 2.2.35 Ability to determine Technical Specification Mode of Operation.

4.5 (CFR: 41. 7 / 41.10 / 43.2 / 45.13)

[Question 96]

Subtotal 1~:;f~2*}

3.

G2.3.6 2.3.6 Ability to approve release permits.

3.8 Radiation (CFR: 41.13 / 43.4 / 45.10)

Control

[Question 97]

G2.3.12 2.3.12 Knowledge of radiological safety principles pertaining to licensed 3.7 operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12 / 45.9 / 45.10)

[Question 98]

Subtotal

/'

J

4.

G2.4.11 2.4.11 Knowledge of abnormal condition procedures.

4.2 Emergency (CFR: 41.10 / 43.5 / 45.13)

Procedures/

[Question 99]

Plan G2.4.42 2.4.42 Knowledge of emergency response facilities.

3.8 (CFR: 41.10 / 45.11)

[Question 100]

Subtotal

}'\\

Tier 3 Point Total

    • q:

7 NUREG-1021, Revision 11 SRO Page 7 of 7 Rev.AG

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

eJec e s

F orm ES 401 4 Facility: Beaver Valley Unit 2 2LOT19 Date of Exam: 10/7 through 10/18/2019 Tier/

Randomly Group Selected KIA Reason for Rejection 1/1 000026 Question 8; There is no CROM high temperature monitoring system, or ability to monitor CROM temperatures available at Beaver Valley, therefore there is no tie AA1.04 between Loss of Component Cooling Water and CROM system high temperature. NRC Chief Examiner randomly selected 000026 AA1.01 as a replacement.

2/1 078 Question 53; Beaver Valley 1 & 2 do not have cross tied air systems. NRC Chief Examiner randomly selected 078 K3.02 as a replacement.

K3.03 2/1 103 Question 54; Knowledge of events related to system oper~tion/status that must be reported to internal organizations or external agencies, such as the State, the 2.4.30 NRC, or the transmission system operator is not a RO Task at Beaver Valley.

NRC Chief Examiner randomly selected 103 G2.1.25 as a replacement.

2/1 103 Question 55; Loss of containment integrity under refueling operations overlaps with question 23, KIA 069 AA2.01 Loss of containment integrity. Also, Tech K3.03 Spec 3.6.1 require that Containment be operable in modes 1-4, and Tech Spec 3.9.3 for Containment Penetrations is only required to be operable when moving recently irradiated fuel. BV procedures do not authorize movement of recently irradiated fuel. NRC Chief Examiner randomly selected 103 K3.02 as a replacement.

2/2 086 Question 65; There are no physical connections and/or cause-effect relationships between Fire Protection system and the AFW system at Beaver Valley. NRC K1.03 Chief Examiner randomly selected 086 K1.02 as a replacement.

1 /1 000057 Question 79; Loss of Vital AC Instrument Bus has no immediate actions required and the KIA is RO required knowledge. NRC Chief Examiner randomly selected 2.4.49 000057 G2.2.37 as a replacement.

1/2 000061 Question 84; Area Radiation Monitoring System - Normal radiation intensity for each ARM system channel overlaps with questions 51 and 63 due to AA2.02 oversampling. NRC Chief Examiner randomly selected new system 000032 AA2.03 as a replacement.

2/2 068 Question 92; Liquid Radwaste - Failure of automatic isolation overlaps with question 22 for the auto isolation of a liquid discharge, and question 83 for A2.04 correcting the problem and maintaining the question at an SRO level. Due to oversampling, the NRC Chief Examiner randomly selected new system 035 A2.04 as a replacement.

2/2 086 Question 65; The only physical connections and/or cause-effect relationships between Fire Protection system and the Service Water system was installed for a K1.02 beyond design bases accident and,is not referenced within our normal operating or emergency operating procedures at Beaver Valley. NRC Chief Examiner randomly selected 086 G2.1.31 as a replacement.

1/2 000032 Question 84; Loss of Source Range Nuclear Instrumentation-A question testing expected values of source range indication when high voltage is automatically AA2.03 removed could only be written by violating the plant startup procedure. NRC Chief Examiner randomly selected 000032 AA2.01 as a replacement.

3 2.3.15 Question 97, Knowledge of radiation monitoring systems. Reselect due to oversampling. A question testing E plan classification levels did not address the KIA. NRC Chief Examiner reselected KIA 2.3.6 as a replacement.

NUREG-1021, Revision 11 Rev AG

Facility: Beaver Valley Unit 2 2LOT19 Date of Exam: 10/7 through 10/18/2019 Tier/

Randomly Group Selected KIA Reason for Rejection 2/1 00063 Question 88, Ability to diagnose and use procedures to mitigate the effects of a loss of ventilation during battery charging. Reselect due to inability to write a A2.02 SRO level question for the KIA. Reselected KIA A2.01 as a replacement, this was the only other KIA in this section.

NUREG-1021, Revision 11 Rev AG

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