ML19086A201

From kanterella
Jump to navigation Jump to search

Final Written Examination and Operating Test Outlines (Folder 3)
ML19086A201
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/15/2019
From: Jenkins T
Entergy Nuclear Indian Point 2
To:
Operations Branch I
Shared Package
ML18130A647 List:
References
CAC 00500, EPID L-2019-OLL-0012
Download: ML19086A201 (38)
v • d • e


Text

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

IPEC Unit 2 Date of Examination:

2/4/2019 Examination Level: RO

~ SRO D Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations RM NAROs Prepare Reactivity Balance Load Change Conduct of Operations RN 1940012125 RO 3.9 Use A Flow Diagram to Determine Leak Equipment Control RN Isolation Boundaries 1940012241 RO - 3.9 Prepare a Gaseous Waste Release Permit Radiation Control RM 1940012311 RO - 3.8 Perform initial NUE Notifications Emergency Plan MS 1940012443 RO - 3.2 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; :,; 4 for SROs and RO retakes)

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

(P)revious 2 exams (s 1, randomly selected)

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

IPEC Unit 2 Date of Examination:

2/4/2019 Examination Level: RO D SRO

~

Operating Test Number:

1 Administrative Topic (see Note)

Type Describe activity to be performed Code*

Spent Fuel Pit Loading Conduct of Operations RM 1940012142 RO - 2.5 SRO - 3.4 Review Reactivity Balance Load Change Conduct of Operations RN 1940012125 RO 3.9 SRO 4.2 Review a Check Off List Equipment Control RN 1940012214 RO - 3.9 SRO - 4.3 Review a Gaseous Waste Release Permit Radiation Control RM 1940012311 RO - 3.8 SRO - 4.3 Classify Event and Complete Form EP-1, Part 1 Emergency Plan RM 1940012441 RO - 2.9 SRO - 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:s; 3 for ROs; :s; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (;:: 1)

(P)revious 2 exams (:s; 1, randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

IPEC Unit 2 Date of Examination:

2-4-2019 Exam Level: RO

~ SRO-I D SRO-U D Operating Test Number:

1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. Retrieve A Dropped Rod SAN 1

001000A408 RO - 3.7 SRO - 3.4

b. Place Excess Letdown In Service SD 2

004000A406 RO - 3.6 SRO - 3.1

c. Depressurize the RCS to Refill the Pressurizer SA 3

006000A409 RO - 4.1 SRO - 4.2

d. Start RCP FR-C.1 SD 4P 003000A402 RO - 2.9 SRO - 2.9
e. Manually Actuate Containment Spray SAD EN 5

026000A401 RO - 4.5 SRO - 4.3

f. Swap 6.9 Bus 6 from 138kV to 13.8 kV SN 6

062000A401 RO - 3.3 SRO - 3.1

g. Controlling Pressurizer Pressure Channel Failure SLM 7

000027A215 RO-3.7 SRO-3.4

h. Terminate Containment Pressure Relief SMA 8

029000A301 RO - 3.8 SRO - 4.0 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Locally Start 22 AFW Pump ED 4S 0610002130 RO - 4.4 SRO - 4.0
j. Lineup Backup Cooling to Charging Pumps RED 8

0080002130 RO - 4.4 SRO - 4.0

k. Swap Gas Decay Tanks NR 9

071 OOOA405 RO - 2.6 SRO - 2.6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

  • Type Codes I

Criteria for R /SR0-1/SRO-U

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3

5 9/:5 8/:5 4

~1/~1/~1

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

~1/~1/~1

~ 2/~ 2/~ 1

5 3/:5 3/:5 2 (randomly selected)

~1/~1/~1

II ES-301 Control Room/In-Plant systems Outline Form ES-301-2 Facility:

IPEC Unit 2 Date of Examination:

2-4-2019 Exam Level: RO D SRO-I

[Zl SRO-U D Operating Test Number:

1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. Retrieve A Dropped Rod SAN 1

001 OOOA408 RO - 3.7 SRO - 3.4 b.NA SRO

c. Depressurize the RCS to Refill the Pressurizer SA 3

006000A409 RO - 4.1 SRO - 4.2

d. Start RCP FR-C.1 SD 4P 003000A402 RO - 2.9 SRO - 2.9
e. Manually Actuate Containment Spray SADEN 5

026000A401 RO - 4.5 SRO - 4.3

f. Swap 6.9 Bus 6 from 138kV to 13.8 kV SN 6

062000A401 RO - 3.3 SRO - 3.1

g. Controlling Pressurizer Pressure Channel Failure SLM 7

000027A215 RO - 3.7 SRO - 3.4

h. Terminate Containment Pressure Relief SN 8

029000A301 RO - 3.8 SRO - 4.0 In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Locally Start 22 AFW Pump ED 48 0610002130 RO - 4.4 SRO - 4.0
j. Lineup Backup Cooling to Charging Pumps RED 8

0080002130 RO - 4.4 SRO - 4.0

k. Swap Gas Decay Tanks NR 9

071 OOOA405 RO - 2.6 SRO - 2.6 All RO and SRO-I control room (and in-plant) systems must be different and seNe different safety functions, all five SRO-U systems must seNe different safety functions, and in-plant systems and functions may overlap those tested in the control room.

  • Type Codes I

Criteria for R /SR0-1/SRO-U

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3

5 9/S 8/S 4

~ 1/~ 1/~ 1

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

~1/~1/~1

~ 2/~ 2/~ 1 s 3/S 3/S 2 (randomly selected)

~ 1/~ 1/~ 1

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: 1 Op-Test No.: _1 Examiners:

Operat~rs:

Initial Conditions: Reset simulator to 100% % power, 22 AFP OOS, 21 and 23 protected; 22 Circulator OOS, 21 Circulator is protected Turnover: # 22 ABFP has been out-of-service for bearing oil line repair for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. It is expected back within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (ITS 3.7.5 - 72 hr AOT). 21 and 23 ABFP are protected equipment. 22 Circulator is out of service for motor replacement (Day 2), not expected to return this shift Critical Tasks:

Insert negative reactivity into the core by at least 1 of the following methods before step 4 steps of FR-S.1 is complete:

De-energize the Control Rod Drives / MG sets Manually insert the rods Establish Emergency Boration Manually actuate Main Steam isolation before transition out of E-0 Manually start SI system pumps before transition out of ES-1.1 Event Malf. No.

Event Event No.

Type*

Description I (ATC) 1 XMT-I (BOP)

RCS Loop 24 Cold Leg temperature failure (TE-441 B)

RCS048A I (CRS) fails low TS(CRS)

R (ATC) 2 MAL-N (CRS)

Nl-41 fails High which results in a Tech Spec Shutdown NIS004A N (BOP)

TS (CRS)

RLY-M (ATC) 3 GEN007 M (CRS)

Main Generator output breakers trip M (BOP)

BKR-4 PPL003 C (ATC)

Reactor Trip Failure BKR-PPL004 MAL-M (ATC)

Steam Break in Turbine Hall, Auto closure MSIVs 5

SGNOOS M (CRS) blocked M (BOP) 6 SWI-C (CRS)

Phase A reset failure SGS002 C (BOP) 7 AOV-C (BOP)

PRZR PORV Fails open RCS003A C (CRS)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 10

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: g Op-Test No.: _j_

Examiners:

Operators:

Initial Conditions: 100% power. 21 Charging Pump and 21 CCW Pump are out of service.

Turnover: 21 Charging Pump (Day 3) and 21 CCW Pump (Day 3) out of service, none are expected to return this shift.

Critical Tasks:

Manually actuate at least one train of SIS-actuated safeguards before any of the following: Transition to any E-1 series, E-2 series, or E-3 series procedure or transition to any FRP.

Isolate the faulted SG before transition out of E-2 Event Malf. No.

Event Event No.

Type*

Description I (ATC) 1 XMT-I (BOP)

L T-460 (Pressurizer Level) fails low.

RCS020A I (CRS)

TS (CRS)

N (CRS) 2 N (BOP)

Downpower R (ATC)

MAL-C (CRS) 3 CRF002AV C (ATC)

Rod F-14 does not move when rods demanded.

TS(CRS)

MAL-M (ATC) 4 SGN004A M (BOP)

Steam line rupture upstream 23 MSIV M (CRS) 5 RLY-C (ATC)

Failure of SI to actuate automatically.

PPL487/488 C (CRS) 6 MOC-C (ATC)

Failure of 21 AFW pump to autostart AFW001 C (CRS) 7 MOC-C (BOP)

Failure of 21 SW pump to autostart.

SWS005 MAL-M (ATC) 8 RCS014C M (BOP) 23 SGTR M /CRS)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 11

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.:

~

Op-Test No.: _J_

Examiners:

Operators:

Initial Conditions: 100% power, 22 Circulator is OOS for motor replacement (Day 2) ), 21 Circulator is protected Turnover: 22 Circulator is OOS for motor replacement (Day 2 Critical Tasks:

Manually trip the main turbine before a severe (orange-path) challenge develops to either the sub-criticality or the integrity CSF or before transition to ECA-2.1, whichever happens first Establish RCS bleed and feed prior to all SG levels reaching 14% WR.

Event Malf. No.

Event Event No.

Type*

Description l(ATC) 1 XMT-l(CRS) 218 SG Feed Flow Controlling Channel (FT-4188) fails CFW005A l(BOP) low TS(CRS)

R(ATC) 2 XMT-N(BOP) 21 and 22 Heater Drain Pumps trip, Power reduction FHW015A N(CRS)

TS(CRS)

FLX-M(ATC) 3 CFW038 M(BOP)

Feed line break in the ABFP Building (Effects ALL SG)

M(CRS)

MAL-4 TCA004 C (ATC)

Turbine fails to trip MAL-TCA005 MOC-5 AFW001 C(ATC) 21 and 23 Motor driven AFW pumps fail to operate, 22 MOC-AFP is started AFW002 CVH-M(ATC) 22 AFW pump trips on overspeed after flow is 6

M(BOP)

ATS0198 M(CRS) established MOC-7 SIS002 C(BOP) 21 and 22 SIP fail to auto start MOC-C(CRS)

SIS003 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 9

Appendix D Scenario Outline Form ES-D-1 Facility: Indian Point 2 Scenario No.: §_

Op-Test No.: _l Examiners:

Operators:

Initial Conditions: Initialize to 100% power IC Turnover 21 EDG OOS LCO 3.8.1.b governor issues (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago), will return next shift, 21 Containment spray pump Out of service LCO 3.6.6 a (6 Hours ago)., 21 Containment Spray pump protected Critical Tasks:

Establish at least 400 gpm AFW flow to the SGs before SG WR level decreases below 14%.

Manually start ESW pump(s) such that the EOG does not fail due to engine overheating.

Event Malf. No.

Event Event No.

Type*

Description I (ATC) 1 XMT-I (BOP)

Turbine First Stage Pressure (PT-412A) fails low MSS053A I (CRS)

TS (CRS) 2 MOT-C (BOP) 25 FCU Trip CNM012A TS(CRS) 3 CNH-C (ATC)

LC-4590 (Pressurizer Level Controller) fails low PCS019B R (ATC) 4 MAL-N (CRS) 21 Steam Generator Tube Leak (120 GPO), Tech RCS014A N (BOP)

Spec shutdown TS (CRS)

XMT-M (ATC) 5 CFW037A M (BOP)

PT-408B (MBFP Suction pressure) fails low M (CRS)

MAL-M (ATC) 6.9kv bus 5 faults when the Unit trips, 22 EOG trips 6

EPS006E M (BOP) on overcrank, 23 EOGs output breaker does not M (CRS) automatically close 7

MOC-C (BOP) 23 Service Water pump does not autostart SWS008 (N)ormal,

( R )eactivity, (l)nstrument, (C)omponent, (M)ajor Page 1 of 9

2;,i cJ ( ckf.fc,eµ i fd.znia,t} Cerf i trf tJu.:i-1, ~

L,sfr"J ~tL <1)1¢ 1s ~

'~f/';..,j ~laced 1-</As ES-401, Rev. 11 PWR Examination Outline Form ES-401-2 Facility: Indian Point Unit 2 Date of Exam: February 2019 RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

1.

1 3

3 3

3 3

3 18 3

3 6

Emergency&

2 1

1 2

2 2

1 9

2 2

4 Abnormal Plant N/A N/A Evolutions Tier Totals 4

4 5

5 5

4 27 5

5 10 I

I I

I 1

3 2

3 3

2 3

3 2

2 3

2 28 3

2 5

2.

I I

I I

I Plant 2

1 1

1 1

1 1

1 1

1 1

0 10 2

1 3

Systems I

I I

I I

Tier Totals 4

3 4

4 3

4 4

3 3

4 2

38 3

8

3. Generic Knowledge and Abilities 1

2 3

4 10 1 I 2 3 I 4 7

Categories I

I 2

2 3

3 1

2 2

2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only, the "Tier Totals" in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the KIA is replaced by a K/A 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section 0.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (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 K/A categories.
7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1.b of ES-401 for the applicable KAs.
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; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note# 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

ES-401, REV 11 RO T1G1 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G 007EA2.01 Q(

008AK1.01 QL RO SRO Reactor Trip - Stabilization - Recovery 4.1 4.3 D D D D D D D ~ D D D

/ 1 Pressurizer Vapor Space Accident/ 3 3.2

3. 7

~ D D D D D D D D D D r.;:o, a l!i;iall Q~aak 1..0 6

QQQiQ:l.iU:l Re,~~. 009~.,.'

a.1 4.1 D D D D D D D D D D ~

(.,,'Ir '1 011EA1.15 Large Break LOCA I 3 4.2 4.2 D D D D D D ~ D D D D 022AA2.01 Loss of Rx Coolant Makeup / 2 3.2 3.8 D D D D D D D ~ D D D

&S-025AK1.01 Loss of RHR System I 4 3.9 4.3

~ D D D D D D D D D D 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 D~DDDDDDDDD Malfunction / 3 G7 029EK3.06 ATWS / 1 4.2 4.3 DD~DDDDDDDD

<<Q~

038EK3.08 Steam Gen. Tube Rupture / 3 4.1 4.2 DD~DDDDDDDD 040AK2.01 Steam Line Rupture - Excessive Heat 2.6 2.5 D ~ D DODD Transfer/ 4 0

054AG2.4.18 Loss of Main Feedwater / 4 3.3 4.o D D D D D D D D D D ~

QI{

Page 1 of 13 FORM ES-401-2 TOPIC:

Decreasing power level from available indications Thermodynamics and flow characteristics of open or leak-ing valves l(flevi4eeJae ef SlifYeille.Aee ereeeeh:1res.

RCS temperature and pressure Whether charging line leak exists Loss of RHRS during all modes of operation Controllers and positioners Verifying a main turbine trip; methods Criteria for securing RCP Valves Knowledge of the specific bases for EOPs.

IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 KA NAME / SAFETY FUNCTION:

055EA1.02 Q12.

056AK3.01 Q(~

057AA2.06 Q14 Station Blackout / 6 Loss of Off-site Power / 6 Loss of Vital AC Inst. Bus / 6 058AG2.4.20 Loss of DC Power/ 6 QI~

WE04EK1.1 LOCA Outside Containment I 3

~t&,

WE05EA1.3 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Ql1 RO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.3 4.4 D D D D D D ~ D D D D 3.5 3.9 D D ~ D D D D D D D 3.2 3.7 D D D D D D D ~ D D D 3.8 4.3 D D D D D D D D D D ~

3.5 3.9

~ D D D D D D D D D D 3.8 4.2 D D D D D D ~ D D D D WE11 EK2.2 Loss of Emergency Coolant Recirc. / 4 3.9 4.3 D ~ D D D D D D D D D Page 2 of 13 FORM ES-401-2 TOPIC:

Manual ED/G start Order and time to initiation of power for the load sequencer AC instrument bus alarms for the inverter and alternate power source Knowledge of operational implications of EOP warnings, cautions and notes.

Components, capacity, and function of emergency systems.

Desired operating results during abnormal and emergency situations.

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

IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 RO T1G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 005AK3.05 Inoperable/Stuck Control Rod/ 1 3.4 4.2 D D ~ D D D D D D D D Q 1'1 028AK3.03 Pressurizer Level Malfunction / 2 3.5 4.1 D D ~ D D D D D D D D G)Zo 032AG2.4.2 Loss of Source Range NI / 7 4.5 4.6 D D D D D DODD~

060AA1.01 Accidental Gaseous Radwaste Rel./ 9 2.8 3

DDDDDD~DDDD

~

068AA2.05 Control Room Evac. / 8 4.2 4.3 D D D D D D D ~ D D D 076AK2.01 High Reactor Coolant Activity / 9 2.6 3

D ~ D D D D D D D D D WE08EK1.2 RCS Overcooling - PTS / 4 3.4 4.o

~ D D D D D D D D D D

~2$"

WE10EA2.2 Natural Circ. With Seam Void/ 4 3.4 3.9 D D D D D D D ~ D D D WE 15EA 1.3 Containment Flooding / 5 2.8 3.o D D D D D D ~ D D D D G27 Page 3 of 13 FORM ES-401-2 TOPIC:

Power limits on rod misalignment False indication of PZR level when PORV or spray valve is open and RCS saturated Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

Area radiation monitors Availability of heat sink Process radiation monitors Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

Desired operating results during abnormal and emergency situations.

IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 RO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G TOPIC:

RO SRO 003K5.05 Reactor Coolant Pump 2.8 3.0 DDDD~DDDDDD The dependency of RCS flow rates upon the number of operating RCPs Q2..f 004K3.04 Chemical and Volume Control 3.7 3.9 DD~DDDDDDDD RCPS G>3o Ref ltU.ec:l QQ41o,6.4Q St=leFMieel BREI l.tel~FRB ~BRIF91 ti.Q ti 4 DDDD~DDDDDD

~lilili,lQRillil gt: i;!~+ dWFiR!j bwbbl& tQ!:FRii&igR iR 12,Z~* iR uid-"

oo'-fl<S-.o-t crease in quench tank pressure when cycling PORV shows that complete steam bubble does not exist, that Q2.q significant noncondensable gas is still present 005K4.12 Residual Heat Removal 3.1 3.7 DDD~DDDDDDD Lineup for piggyback mode with CSS

<031 0061<2.02 Emergency Core Cooling 2.5 2.9 D~DDDDDDDDn Valve operators for accumulators

~32-007K4.01 Pressurizer Relief/Quench Tank 2.6 2.9 DDD~DDDDDDD Quench tank cooling Q33 008A1.02 Component Cooling Water 2.9 3.1 DDDDDD~DDDD CCW temperature Q3Lf 0101<2.02 Pressurizer Pressure Control 2.5 2.7 D~DDDDDDDDD Controller for PZR spray valve Q3!f 012K3.01 Reactor Protection 3.9 4.0 DD~DDDDDDDD CRDS

Q3C, 013K6.01 Engineered Safety Features Actuation 2.7 3.1 DDDDD~DDDDD Sensors and detectors 037 022A1.02 Containment Cooling 3.6 3.8 DDDDDD~DDDD Containment pressure Q3Ct Page4 of 13 IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 RO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/ SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G TOPIC:

RO SRO R~lc,ucL 9221(1.94 GeRte.iAFReRt Geeli~

2.9 2.9 ~DDDDDDDDDD 01,illed netc.1 tl.Jtt:h 02.""Ll<.fof Q,38 026A4.05 Containment Spray 3.5 3.5 DDDDDDDDD~D Containment spray reset switches 0

039A3.02 Main and Reheat Steam 3.1 3.5 DDDDDDDD~DD Isolation of the MRSS Qy.

059A3.02 Main Feedwater 2.9 3.1 DDDDDDDD~DD Programmed levels of the SIG 2...

059G2.1.23 Main Feedwater 4.3 4.4 DDDDDDDDDD~

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

061K6.01 Auxiliary/Emergency Feedwater 2.5 2.8 DDDDD~DDDDD Controllers and positioners Qi..f.5 061K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 DDDDD~DDDDD Pumps QJ.f 062G2.4.47 AC Electrical Distribution 4.2 4.2 DDDDDDDDDD~

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room QL+l, reference material.

063K1.03 DC Electrical Distribution 2.9 3.5 ~DDDDDDDDDD Battery charger and battery Qt.J.'8 063K4.02 DC Electrical Distribution 2.9 3.2 DDD~DDDDDDD Breaker interlocks, permissives, bypasses and cross-ties.

QL/7 064K1.02 Emergency Diesel Generator 3.1 3.6 ~DDDDDDDDDD DIG cooling water system (j)o/j Page 5 of 13 IP2 Feb 2019 Exam, Rev O

R "-fl.o.c eA WL-b, Repftu..eJ_

IA.Ji:..~

ES-401, REV 11 RO T2G1 PWR EXAMINATION OUTLINE KA NAME/ SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 073A2..02 Process Radiation Monitoring 2.1 3.2 D D D D D D D ~ D D D G.>5/

073A4.01 Process Radiation Monitoring 3.9 3.9 D D D D D D D D D ~ D 5-o 076A1.02 Service Water 2.6 2.6 D D D D D D ~ D D D D Q?-eKa.QA

~8Pci&8 \\A(at&r 07(o K'5,.07 H

a D D ~ D D D D D D D D

~3 078A4.01 Instrument Air 3.1 3.1 D D D D D D D D D ~ D 1Q~:~.Q~

C9RtaiRR-18Rt 10~~2.o:3 J 5 a DDDDDDD~DDD Qss-Page 6 of 13 FORM ES-401-2 TOPIC:

Detector failure Effluent release Reactor and turbine building closed cooling water temperatures.

S&&QR'aiPJ &1988Q S991iRg u,atsr Pressure gauges IP2 Feb 2019 Exam, Rev O

Re,, (ac.,ed wcJ-t,.,

Rf lru.eA wi.J*t.,

ES-401, REV 11 RO T2G2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 001K4.07 Control Rod Drive 3.7 3.8 DD D ~DD DD DD D Q!.?{,o 011K6.03 Pressurizer Level Control 2.9 3.3 D D D D D ~ D D D D D Gbl 017A1.01 In-core Temperature Monitor 3.7 3.9 D D D D D D ~ D D D D

~~

Q2SKe.Q4 MyeFe!jeR ReseFReiReF aRe P1:1F!je 2 i

i 2 0 0 0 o.as J<!i".o a. control D ~ D D D D D D

}

029A4.04 Containment Purge 3.s 3.6 D D D D D D D D D ~ D (v$i 2

SteaFR Q1:1FRJ3/T1:1F8iAe 0'/f)8S8 GeRtrel Q41K2.Q D'ff K 2.,o r Q~L-2.8 2.8 D ~ D D D D D D D D D 045K3.01 Main Turbine Generator 2.9 3.2 D D ~ D D D D D D D D Q~3 055A3.03 Condenser Air Removal 2.s 2.1 D D D D D D D D ~ D D q>(o'f 056A2.04 Condensate 2.6 2.8 D D D D D D D ~ D D D Q~S' 033K1.05 Spent Fuel Pool Cooling 2.1 2.8

~ D D D D D D D D D D Q"'o Page 7 of 13 FORM ES-401-2 TOPIC:

Rod stops Relationship between PZR level and PZR heater control circuit Core exit temperature

+Re &elesti',e Fei:;Re* *al ef Rv~FeaeR Containment evacuation signal IGe iR11er:teF 13FealteF8 Remainder of the plant Automatic diversion of CARS exhaust Loss of condensate pumps Connection with RWST IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 RO T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.1.13 Conduct of operations 2.5 3.2 D D D D D D D D D D ~

Qf.e(p P-¥.4-~

":u..i;z

(;;1 wi.ft, G:-2.(,"to

~~7 1Rswst ef 81il8Fat1eR&

~ II 4

D D D D D D D D D D ~

G2.2.35 Equipment Control 3.6 4.5 D D D D D D D D D D ~

Q~

G2.2.41 Equipment Control 3.5 3.9 D D D D D D D D D D ~

Git, G2.3.14 Radiation Control 3.4 3.8 D D D D D D D D D D ~

~($)11_

G2.3.15 Radiation Control 2.9 3.1 D D D D D D D D D D ~

07Z G2.3.7 Radiation Control 3.5 3.6 D D D D D D D D D D ~

-~ 0 G2.4.28 Emergency Procedures/Plans 3.2 4.1 D D D D D D D D D

~

G72>

G2.4.42 Emergency Procedures/Plans 2.6 3.8 D D D D D D D D D D ~

Q74 G2.4.49 Emergency Procedures/Plans 4.6 4.4 D D D D D D D D D D ~

Q7~

Page 8 of 13 FORM ES-401-3 TOPIC:

Knowledge of facility requirements for controlling vital /

controlled access.

KoQlod&dge of sy&biJ:R pr 1cpose aRd or t, mctioo Ability to determine Technical Specification Mode of Operation Ability to obtain and interpret station electrical and mechanical drawings Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of radiation monitoring systems Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of procedures relating to emergency response to sabotage.

Knowledge of emergency response facilities.

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 KA NAME/ SAFETY FUNCTION:

015AG2.1.20 Nuclear Instrumentation 17

~7?:,

026G2.1.19 Loss of Component Cooling Water I 8 G77 056AA2..45 Loss of Off-site Po.ver / 6 7g 065AA2..06 Loss of Instrument Air / 8 Qfso 062AA2..04 Loss of Nuclear Service Water I 4

©71 077G2.4.1 Generator Voltage and Electric Grid Disturbances / 6 Qg(

SRO T1G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2. A3 A4 G RO SRO 4.6 4.6 D D D D D D D D D D ~

3.9 3.8 DDDDDDDDDD~

3.6 3.9 DDDDDDD~DDD 3.6 4.2 DDDDDDD~DDD 2.5 2.9 DDDDDDD~DDD 4.6 4.8 DDDDDDDDDD~

Page 9 of 13 FORM ES-401-2 TOPIC:

Ability to interpret and execute procedure steps Ability to use plant computers to evaluate system or component status Indicators to assess status of ESF breakers (tripped/ not-tripped) and validity of alarms (false/not-false)

When to trip reactor if instrument air pressure is de-creasing The nonnal values and upper limits for the temperatures of the components cooled by SWS Knowledge of EOP entry conditions and immediate action steps IP2 Feb 2019 Exam, Rev O

R~l~

wi.,ft-,

Re.fLtU.ec:L w~

ES-401, REV 11 KA NAME / SAFETY FUNCTION:

001AA2.02 Continuous Rod Withdrawal/ 1 4ov/£(J2 A-I\\ 2.. 02

¢iLf WE13G2.4.35 Steam Generator Overpressure 14 4)~s-061AA2.03 ARM System Alarms 17 03lc,AA-2,0 2..

G1i>2..

069AG2.2.36 Loss of CTMT Integrity I 5 Q!3 SRO T1G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.2 4.2 D D D D D D D ~ D D D 3.8 4.o D D D D D D D D D D ~

3 3.3 D D D D D D D ~ D D D 3.1 4.2 D D D D D D D D D D ~

Page 10 of 13 FORM ES-401-2 TOPIC:

Position of emergency boration valve Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Setpoints for alert and high alarms Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions of operations IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 KA NAME / SAFETY FUNCTION:

012A2.01 Reactor Protection

<v~7 039A2.03 Main and Reheat Steam 6)fg 062A2.12 AC Electrical Distribution QE'j 006G2.4.45 Emergency Core Cooling Q 9/.p 103G2.2.44 Containment GC,o SRO T2G1 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.1 3.6 D D D D D D D ~ D D D 3.4 3.7 D D D D D D D ~ D D D 3.2 3.6 D D D D D D D ~ D D D 4.1 4.3 D D D D D D D D D D ~

4.2 4.4 D D D D D D D D D D ~

Page 11 of 13 FORM ES-401-2 TOPIC:

Faulty bistable operation Indications and alarms for main steam and area radiation monitors (during SGTR)

Restoration of power to a system with a fault on ii Ability to prioritize and interpret the significance of each annunciator or alarm.

Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions IP2 Feb 2019 Exam, Rev O

ES-401, REV 11 KA NAME / SAFETY FUNCTION:

034A2.01 Fuel Handling Equipment

~qr 068A2.04 Liquid Radwaste

~qz_

071G2.2.38 Waste Gas Disposal

~q-3 SRO T2G2 PWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 3.6 4.4 D D D D D D D ~ D D D 3.3 3.3 D D D D D D D ~ D D D 3.6 4.s D D D D D D D D D D ~

Page 12 of 13 FORM ES-401-2 TOPIC:

Dropped fuel element Failure of automatic isolation Knowledge of conditions and limitations in the facility license.

IP2 Feb 2019 Exam, Rev O

Rqoltu..e.L lPi H,..

ES-401, REV 11 SRO T3 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO G2.1.41 Conduct of operations 2.8 3.7 DD DD DD DD DD~

~4-G2.2.13 Equipment Control 4.1 4.3 D D D D D D D D D D ~

&'15 G2.2.40 Equipment Control 3.4 4.7 DD DD DD DD DD~

rv:J G2.3.12 Radiation Control 3.2 3.7 DD DD DD DD DD~

  • Ci!.3.14 RaEliatieR GeRtrel

<;-:2..~.II

~A u D D D D D D D D D D ~

Qq G2.4.30 Emergency Procedures/Plans 2.7 4.1 D D D D D D D D D D ~

Q1 G2.4.8 Emergency Procedures/Plans 3.8 4.5 D D D D D D D D D D ~

GfiCJ Page 13 of 13 FORM ES-401-3 TOPIC:

Knowledge of the refueling processes Knowledge of tagging and clearance procedures.

Ability to apply technical specifications for a system.

Knowledge of radiological safety principles pertaining to licensed operator duties K;R9t14eEl!je ef raEtiatieR er seRtaFRiRalieR l:lai!arEls tl:lal FRay arise SWRR!j RBrFRal, al:lRerFRal, er e1t1er!jeA~

eeRElilieAs er aeliYilies Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

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

IP2 Feb 2019 Exam, Rev O

ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:

IPEC Printed: 11/20/2018 Date Of Exam:

02/04/2019 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G*

Total

1.

1 3

3 3

3 3

3 18 0

0 0

Emergency 2

I I

2 2

2 I

9 0

0 0

NIA N/A Abnormal Tier Plant Evolutions Totals 4

4 5

5 5

4 27 0

0 0

2.

1 3

2 3

3 2

3 3

2 2

3 2

28 0

0 0

Plant 2

1 1

1 1

1 1

1 1

1 1

0 10 0 I 0 0

0 Systems Tier 4

3 4

4 3

4 Totals 4

3 3

4 2

38 0

0 0

3. Generic Knowledge And 1

2 3

4 1

2 3

4 10 0

Abilities Categories 2

2 3

3 0

0 0

0 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRG revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those 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, 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 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.

11/20/2018 12:34:51 pm

PWR RO Examination Outline Printed: I I /20/2018 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G

KA Topic Imp.

Points 000007 Reactor Trip - Stabilization -

X EA2.01-Decreasing power level, from 4.1 I

Recovery I I available indications 000008 Pressurizer Vapor Space Accident/

X AK 1.01 - Thermodynamics and flow 3.2 1

3 characteristics of open or leaking valves 000009 Small Break LOCA / 3 X 2.1.7 - Ability to evaluate plant 4.4 1

performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

0000 I I Large Break LOCA / 3 X

EA 1.15 - RCS temperature and pressure 4.2 1

000022 Loss of Rx Coolant Makeup/ 2 X

AA2.0 I - Whether charging line leak 3.2 I

exists 000025 Loss of RHR System I 4 X

AK 1.0 I - Loss of RHRS during all 3.9 I

modes of operation 000027 Pressurizer Pressure Control System X

AK2.03 - Controllers and positioners 2.6 I

Malfunction / 3 000029 A TWS / I X

EK3.06 - Verifying a main turbine trip; 4.2 I

methods 000038 Steam Gen. Tube Rupture/ 3 X

EK3.08 - Criteria for securing RCP 4.1 1

000040 Steam Line Rupture - Excessive X

AK2.01 - Valves 2.6*

I Heat Transfer/ 4 000054 Loss of Main Feedwater / 4 X 2.4.18 - Knowledge of the specific 3.3 I

bases for EOPs.

000055 Station Blackout/ 6 X

EA 1.02 - Manual ED/G start 4.3 I

000056 Loss of Off-site Power/ 6 X

AK3.0 I - Order and time to initiation of 3.5 1

power for the load sequencer 000057 Loss of Vital AC Inst. Bus / 6 X

AA2.06 - AC instrument bus alarms for 3.2 I

the inverter and alternate power source 000058 Loss of DC Power/ 6 X 2.4.20 - Knowledge of operational 3.8 I

implications ofEOP warnings, cautions, and notes.

W /E04 LOCA Outside Containment I 3 X

EKI.I - Components, capacity, and 3.5 I

function of emergency systems W /E05 Inadequate Heat Transfer - Loss of X

EA 1.3 - Desired operating results 3.8 I

Secondary Heat Sink / 4 during abnormal and emergency situations W/EI I Loss of Emergency Coolant Recirc. I X

EK2.2 - Facility's heat removal systems, 3.9 1

4 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 11/20/2018 12:34:22 pm

PWR RO Examination Outline Facility:

IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G

KA Topic Kl A Category Totals:

3 3

3 3

3 3

11/20/2018 12:34:22 pm Printed: 11/20/2018 Form ES-401-2 Imp.

Points Group Point Total:

18 2

PWR RO Examination Outline Printed: 11/20/2018 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE #/Name/Safety Function Kt K2 K3 At A2 G

KA Topic Imp.

Points 000005 Inoperable/Stuck Control Rod/ 1 X

AK3.05 - Power limits on rod 3.4 I

misalignment 000028 Pressurizer Level Malfunction / 2 X

AK3.03 - False indication of PZR level 3.5 1

when PORV or spray valve is open and RCS saturated 000032 Loss of Source Range NI / 7 X

2.4.2 - Knowledge of system set points, 4.5 I

interlocks and automatic actions associated with EOP entry conditions.

000060 Accidental Gaseous Radwaste Rel. /

X AA 1.0 I - Area radiation monitors 2.8 I

9 000068 Control Room Evac. / 8 X

AA2.05 - Availability of heat sink 4.2 I

000076 High Reactor Coolant Activity/ 9 X

AK2.01 - Process radiation monitors 2.6 I

W /E08 RCS Overcooling - PTS / 4 X

EK 1.2 - Normal, abnormal and 3.4 I

emergency operating procedures associated with Pressurized Thermal Shock W/EIO Natural Circ. / 4 X

EA2.2 - Adherence to appropriate 3.4 I

procedures and operation within the limitations in the facility's license and amendments W /E 15 Containment Flooding I 5 X

EA 1.3 - Desired operating results 2.8 I

during abnormal and emergency situations KIA Category Totals:

1 1

2 2

2 1

Group Point Total:

9 11/20/2018 12:34:28 pm

Facility:

IPEC ES-401 Sys/Evol #/Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief /Quench Tank 008 Component Cooling Water 0 IO Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 022 Containment Cooling 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 059 Main Feedwater 061 Auxiliary/Emergency Feed water 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 11/20/2018 12:34:34 pm Kl X

PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 K2 K3 K4 KS K6 Al A2 A3 A4 G X

X X

X X

X X

X X

X X

X X

X X

X X

X X

Printed:

11/20/2018 Form ES-401-2 KA Topic Imp.

Points K5.05 - The dependency of 2.8*

1 RCS flow rates upon the number of operating RCPs K5.09 - Thermal shock:

3.7 1

high component stress due to rapid temperature change K3.04 - RCPS 3.7 I

K4.12 - Lineup for 3.1 1

piggyback mode with CSS K2.02 - Valve operators for 2.5*

I accumulators K4.0 I - Quench tank 2.6 I

cooling Al.02 - CCW temperature 2.9 I

K2.02 - Controller for PZR 2.5 I

spray valve K3.01 - CRDS 3.9 I

K6.0 I - Sensors and 2.7*

1 detectors Kl.OJ - SWS/cooling 3.5 I

system A 1.02 - Containment 3.6 I

pressure A4.05 - Containment spray 3.5 I

reset switches A3.02 - Isolation of the 3.1 I

MRSS A3.02 - Programmed levels 2.9 I

of the S/G 2.1.23 - Ability to perform 4.3 I

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

K6.02 - Pumps 2.6 1

K6.0 I - Controllers and 2.5 I

positioners 2.4.47 - Ability to diagnose 4.2 I

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

K4.02 - Breaker interlocks, 2.9*

I permissives, bypasses and cross-ties

Facility:

IPEC ES - 401 Sys/Evol #/Name 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 073 Process Radiation Monitoring 076 Service Water 076 Service Water 078 Instrument Air I 03 Containment Kl A Category Totals:

11/20/2018 12:34:34 pm Kl X

X 3

PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 K2 K3 K4 KS K6 Al A2 A3 A4 X

X X

X X

X 2

3 3

2 3

3 2

2 3

Printed:

11/20/2018 Form ES-401-2 G KA Topic Imp.

Points K 1.03 - Battery charger and 2.9 I

battery K 1.02 - ED/G cooling water 3.1 1

system A4.0 I - Effluent release 3.9 I

A2.02 - Detector failure 2.7 I

A 1.02 - Reactor and turbine 2.6*

1 building closed cooling water temperatures K3.07 - ESF loads 3.7 I

A4.0 I - Pressure gauges 3.1 I

A2.03 - Phase A and B 3.5 I

isolation 2

Group Point Total:

28 2

Facility:

IPEC ES-401 Sys/Evol #/Name 001 Control Rod Drive 011 Pressurizer Level Control 017 In-core Temperature Monitor 029 Containment Purge 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate Kl A Category Totals:

11/20/2018 12:34:40 pm Kl X

1 PWR RO Examination Outline Plant Systems - Tier 2 I Group 2 K2 K3 K4 KS K6 Al A2 A3 A4 X

X X

X X

X X

X X

1 1

1 1

1 1

1 1

1 Printed:

1 1/20/2018 Form ES-401-2 G KA Topic Imp.

Points K4.07 - Rod stops 3.7 1

K6.03 - Relationship 2.9 1

between PZR level and PZR heater control circuit A 1.01 - Core exit 3.7 1

temperature A4.04 - Containment 3.5 1

evacuation signal Kl.05 - RWST 2.7*

I K5.03 - Shrink and swell 2.8 I

concept

.. '""" ~- ---.

~ 1 a~.

  • ~~,~ ~t"ter x.2.. 01 Q~z..

v, *-*

K3.0l - Remainder of the 2.9 1

plant A3.03 - Automatic diversion 2.5*

1 of CARS exhaust A2.04 - Loss of condensate 2.6 1

pumps 0

Group Point Total:

10

Facility:

IPEC Generic Category Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan 11/20/2018 12:34:45 pm Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline KA Topic 2.1.13 Knowledge of facility requirements for controlling vital / controlled access.

~.I.~ *fll'lwlsQ~lil et: s~*ste~ f*l~QS8 a11d,'"1 ft11,e~il'lt1.

2..i.'/-c Category Total:

2.2.35 Ability to determine Technical Specification Mode of Operation.

2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

Category Total:

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

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

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

Category Total:

2.4.28 Knowledge of procedures relating to a security event (non-safeguards information).

2.4.42 Knowledge of emergency response facilities.

2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

Category Total:

Generic Total:

Printed:

11/20/2018 Form ES-401-3 2.5 I

~

I qs4,7 2

3.6 I

3.5 I

2 3.5 1

3.4 I

2.9 I

3 3.2 I

2.6 I

4.6 I

3 10

ES-401 PWR Examination Outline Form ES-401-2 Facilit)l:

IPEC Printed: 11/20/2018 Date Of Exam:

02/04/2019 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* Total A2 G*

Total

1.

1 0

0 0

0 0

0 0

3 3

6 Emergency 2

0 0

0 0

0 0

0 2

2 4

N/A N/A Abnormal Tier Plant Totals 0

0 0

0 0

0 0

5 5

10 Evolutions

2.

1 0

0 0

0 0

0 0

0 0

0 0

0 3

2 5

2 0

0 0

0 0

0 0

0 0

0 0

0 0 I 2

I 3

Plant Systems Tier Totals 0

0 0

0 0

0 0

0 0

0 0

0 5

3 8

3. Generic Knowledge And 1

2 3

4 1

2 3

4 0

7 Abilities Categories 0

0 0

0 I

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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2.

The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4.

Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant-specific priority, only those K/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, respectively.

6.

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

7.
  • The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
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 handHng equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3.

Limit SRO selections to K/As that are linked to 10 CFR 55.43.

11/20/2018 1:05:46 pm

PWR SRO Examination Outline Printed: l l /20/2018 Facility:

IPEC ES-401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 E/APE #/Name/Safety Function Kl K2 K3 Al A2 G

KA Topic Imp.

Points 000015/000017 RCP Malfunctions / 4 X 2.1.20 - Ability to interpret and execute 4.6 1

procedure steps.

000026 Loss of Component Cooling Water I X 2.1.19 - Ability to use plant computers 3.9 1

8 to evaluate system or component status.

000056 Loss of Off-site Power I 6 X

AA2.45 - Indicators to assess status of 3.9 1

ESF breakers (tripped/not-tripped) and validity of alarms (false/not-false) 000062 Loss of Nuclear Svc Water/ 4 X

AA2.04 - The normal values and upper 2.9*

I limits for the temperatures of the components cooled by SWS 000065 Loss of Instrument Air/ 8 X

AA2.06 - When to trip reactor if 4.2 1

instrument air pressure is decreasing 000077 Generator Voltage and Electric Grid X 2.4.1 - Knowledge of EOP entry 4.8 1

Disturbances I 6 conditions and immediate action steps.

KIA Category Totals:

0 0

0 0

3 3

Group Point Total:

6 11/20/2018 1:05:20 pm

PWR SRO Examination Outline Printed: 11/20/2018 Facility:

IPEC ES - 401 Emergency and Abnormal Plant Evolutions - Tier I / Group 2 Form ES-401-2 E/APE #/Name/Safety Function Kt K2 K3 At A2 G

KA Topic Imp.

Points 000036 Fuel Handling Accident/ 8 X

AA2.02 - Occurrence of a fuel handling 4.1 1

incident 000069 Loss of CTMT Integrity / 5 X 2.2.36 - Ability to analyze the effect of 4.2 1

maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

W /E02 SI Termination / 3 X

EA2.2 - Adherence to appropriate 4.0 1

procedures and operation within the limitations in the facility's license and amendments W IE 13 Steam Generator Over-pressure / 4 X 2.4.35 - Knowledge of local auxiliary 4.0 1

operator tasks during an emergency and the resultant operational effects.

Kl A Category Totals:

0 0

0 0

2 2

Group Point Total:

4 11/20/2018 1:05:26 pm

Facility:

IPEC ES-401 Sys/Evol #/Name 006 Emergency Core Cooling 012 Reactor Protection 039 Main and Reheat Steam 062 AC Electrical Distribution I 03 Containment Kl A Category Totals:

11/20/2018 1:05:31 pm Kl 0

PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 K2 K3 K4 KS K6 At A2 A3 A4 X

X X

0 0

0 0

0 0

3 0

0 Printed:

I I /20/2018 Form ES-401-2 G KA Topic Imp.

Points X 2.4.45 - Ability to prioritize 4.3 I

and interpret the significance of each annunciator or alarm.

A2.0 I - Faulty bistable 3.6 I

operation A2.03 - Indications and 3.7 I

alarms for main steam and area radiation monitors (during SGTR)

A2. l 2 - Restoration of 3.6 I

power to a system with a fault on it X 2.2.44 - Ability to interpret 4.4 I

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

2 Group Point Total:

5

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/

Randomly Reason for Rejection Group Selected K/ A RO 1/1 009 2.2.12 Knowledge of surveillance testing NA to SBLOCA. Replaced with 000009 2.1.07 RO 2/1 022 K1.04 Chilled water is not used for Containment Cooling. Replaced with 022000 K1.01 RO 2/1 076 K3.02 076 A 1.02 Service Water - Reactor and Turbine Building Closed Cooling Water Temperature 076 K3.02 Service Water Secondary Closed Cooling Water Oversample topic with 076000A 1.02. Replaced with 076000 K3.07 RO 2/1 103 A2.04 029 A4.04 Containment Purge - Containment Evacuation Alarm 103 A2.04 Containment - Containment Evacuation (including recognition of the alarm)

Oversample topic with 029000 A4.04. Replaced with 103000 A2.03 RO 2/1 004 KS.40 IPEC does not use this method to draw a bubble in the PRT.

Replaced with 004000 KS.09 RO 2/2 028 KS.04 IPEC Unit 2 has passive Hydrogen Recombiners. There are no procedure actions associated with Hydrogen Recombiners. Replaced with 035000 KS.03 SRO 1/ 2 001 EA2.02 Cannot write an SRO question; the procedure is too simple (place rods in manual or trip the reactor). Replaced with OOWE02 AA2.02 SR03 2.3.14 Oversample KA. Exact same KA is on RO Tier 3 outline.

Replaced with 2.3.11.

SRO 1/ 2 061 AA2.03 Outline oversamples Radiation Monitor topics.

Replaced with 000036 AA2.02.

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/

Randomly Reason for Rejection Group Selected K/ A RO 1/1 009 2.2.12 Knowledge of surveillance testing NA to SBLOCA. Replaced with (t)?,

000009 2.1.07 RO 2/1 004 K5.40 IPEC does not use this method to draw a bubble in the PRT.

Q2.9 Replaced with 004000 K5.09 RO 2/1 022 K1.04 Chilled water is not used for Containment Cooling. Replaced with Cl38 022000 K1.01 RO 2/1 076 K3.02 076 K3.02 Knowledge of the effect that a loss or malfunction of the SWS will have on the following: - Secondary closed cooling water REJECTED oversample topic with 076000A 1.02. Replaced with 076000 K3.07 G53 RO 2/1 103 A2.04 103 A2.04 Containment - Containment Evacuation (including Q5"S-recognition of the alarm) REJECTED oversample topic with 029000 A4.04. Replaced with 103000 A2.03 RO 2/2 028 K5.04 IPEC Unit 2 has passive Hydrogen Recombiners. There are no

~lei procedure actions associated with Hydrogen Recombiners.

Replaced with 035000 K5.03 RO 2/2 041 K2.02 041 K2.02 rejected ICS Inverter does not exist at IPEC.

r;,~ 2.

Replaced with 041 K2.01 R03 2.1.27 Per Chief Examiners recommendation, this KA does not lend itself t;) (p 7 to a Plant Wide Generic question. Replaced with 2.1.40 SRO 1/ 2 001 EA2.02 Cannot write an SRO question; the procedure is too simple (place Qg4 rods in manual or trip the reactor). Replaced with OOWE02 AA2.02 SRO 1/ 2 061 AA2.03 Outline oversamples Radiation Monitor topics.

(.)~2, Replaced with 000036 AA2.02.

SR03 2.3.14 Oversample KA. Exact same KA is on RO Tier 3 outline. Replaced 00,7 with 2.3.11.

Retrieved from "https://kanterella.com/w/index.php?title=ML19086A201&oldid=4934418"