ML17230A316

Draft Outlines (Folder 2)

ML17230A316
Person / Time
Site:	Crane
Issue date:	07/03/2017
From:	Exelon Generation Co
To:	D'Antonio J Operations Branch I
Shared Package
ML16210A446	List: IR 05000289/2017301 ML17230A294 ML17230A316 ML17230A327 ML17233A133 ML17233A134 ML17233A135 ML18081A807 ML18081A808 ML18081A811
References
CAC U01944
Download: ML17230A316 (33)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Three Mile Island Date of Examination: 06/26/17 Examination Level: RO~ SRO D Operating Test Number: TMl-2017-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Conduct of Operations R,N Shutdown Margin for Low Temperature Conditions 2.1.43 Perform a Transient Leak Rate Calculation Conduct of Operations R, D 2.1.23 Equipment Control S,D Perform the "Shiftly Checks" IAW 1301-1, DATA SHEET 1 2.2.12 Radiation Control ERO Notification Emergency Plan S, P, D 2.4.39 From 12-01 NRC Exam NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

RA1 The examinee will have to calculate shutdown margin(SDM)for a low temperature situation and will determine that SDM is NOT more negative than -1 o/otlk/k.

RA1 The examinee will use OS-24 to calculate a transient leakrate.

RA2 - The examinee will be in the simulator to perform a portion of the shift and daily log set.

The examinee will have to identify all out of specification readings.

RA4 - The examinee will have to make all ERO notifications as shift communicator.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Three Mile Island Date of Examination: 6/26/17 Examination Level: ROD SRO ~

Operating Test Number: TMl-2017-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Maintain Minimum Shift Manning with Overtime Conduct of Operations R,P, D 2.1.5 From 14-01 NRC Exam Conduct of Operations R,D Perform an estimated critical rod position calculation 2.1.43 Use Station Drawing to Predict Impact of Component Equipment Control R,D Failure and Evaluate Technical Specification Implications 2.2.41 Radiation Control R,D Revew RB Entry Survey Log 2.3.12 EAL and PAR Emergency Plan S,M 2.4.44 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

SA1 The examinee will have to identify the required actions to restore minimum staffing and then select personnel to control overtime.

SA1 The examinee will have to independently perform, and approve an estimated critical position.

SA2 - The examinee will have to use station drawings to determine that the Emergency Diesel Generator is inoperable and declare the correct technical specification time clock.

SA3 - The examinee will have to identify all the faults in the RP Entry Survey Log.

SA4 - The examinee will have to determine the EAL and make a PAR in accordance with the facility Emergency Plan.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Three Mile Island Date of Examination: 06/26/17 Exam Level: RO D SRO-I r8l SRO-U D Operating Test No.: TMl-2017-1 Control Room Systems: *8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Makeup System I Emergency Borate Using the RBAT as the Source -

A,D,S 1

Alternate Path - 004 A2.14

b. Reactor Coolant System I Restoration of letdown flow following high D,S 2

temperature closure of MU-V 002 A1.02

c. Emergency Core Cooling System I Respond to inadvertant ES actuation A,EN,M,S 3

- Alternate Path - 006 A2.13

d. Residual Heat Removal System I Transfer of Reactor Building Sump A, D, L, S 4S Recirculation - Alternate Path - 005 A2.04

e. Containment Cooling System I Perform Emergency Operations of A,M,S 5

Reactor Building Emergency Cooling water - Alternate Path - 022 A4.04

f. A.C Electrical Distribution I Transfer BOP Susses from 1 B to 1 A Aux M,S 6

Transformer - 062 A4.01

g. N/A for SRO's N/A N/A

h. Radiation Monitoring System I Respond IAW OP-TM-MAP-C0101 Alarm A, D, P,S 7

Response with failure -Alternate Path - 072 A3.01 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Main Steam System I Locally I Manually Operate the Turbine Bypass D

4S Valves (MS-V-3A-F) 041 A4.08

j. Nuclear Service Closed Cooling Water I Emergency Makeup to Nuclear D,E 8

Service Closed Cooling Surge Tank (NS-T-1) - 008A4.07

k. Waste Gas System I Take Corrective Action for an Unauthorized Waste N,R 9

Gas Release - 071 G2.1.30 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; in-plant systems and functions mav overlap those tested in the control room.

• Type Codes I

Criteria for RO I SRO-I I SRO-U

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

~9/ ~8 I ~ 4 (E)mergency or abnormal in-plant

~ 1 I

~1 I ~ 1 (EN)gineered safety feature

~ 1 I

~ 1 I

~ 1 (control room system)

(L)ow-Power I Shutdown

~ 1 I

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

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

~ 31

~3 I ~ 2 (randomly selected)

(R)CA

~ 1 I

~1 I ~ 1 (S)imulator ES-301, Page 23 of 27 JPM A: Emergency Borate Using the RBAT as the Source -Alternate Path - In this JPM the examinee will be directed to perform OP-TM-EOP-010, Rule 5 for emergency boration. Due to malfunctions, the examinee will have to initiate emergency boration using Guide 1.

JPM B: Restoration of Letdown Flow Following Temperature Closure of MU-V In this JPM the examinee will show the ability to restore letdown while maintaining normal pressurizer level and makeup tank bands.

JPM C: Respond to an Inadvertent ESAS Actuation-Alternate Path - In this JPM the examinee will show the ability to perform the IMA's of OP-TM-AOP-046, INADVERTENT ESAS ACTUATION. The 'B' 500 psig ES signal will not be able to be cleared so the examinee will end up having to throttle open MU-V-16B to ensure proper makeup pump flow.

JPM D: Transfer of Reactor Building Sump Recirculation - Alternate Path - In this JPM the examinee will demonstrate the ability to throttle LPI to within limits after a sump recirculation suction valve fails to open after a LOCA.

JPM E: Perform Emergency Operations of Reactor Building Emergency Cooling Water -

Alternate Path - In this JPM the examinee will be directed to initiate Reactor Building Emergency Cooling. This JPM is modified so that RR-V-1 B does not open and RR-P-1 B must be secured.

JPM F: Transfer BOP Busses from 1Bto1A Aux Transformer-In this JPM the examinee will demonstrate the ability to transfer the 1 C 4160V Bus from the 1 B Aux Transformer to the 1 A Aux Transformer.

JPM H: Respond IAW OP-TM-MAP-C0101 Alarm Response with Failure - Alternate Path - In this JPM, the examinee will have to put the control tower on emergency recirculation. AH-E-18B will trip so the examinee will have to start the opposite train.

JPM I: Manually/Locally operate the turbine bypass valves (MS-V-3A-F) - In this JPM the examinee will take local manual control of MS-V-3C.

JPM J: Emergency Makeup to Nuclear Service Closed Cooling Surge Tank (NS-T-1 )- In this JPM the examinee will have to do an emergency fill of the nuclear closed cooling water surge tank.

JPM K: Take Corrective Action for an Unauthorized Waste Gas release - lnplant-In this JPM the examinee will have to identify what a waste gas tank is releasing and take action to stop the release.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Three Mile Island Date of Examination: 06/26/17 Exam Level: RO ~ SRO-I D SRO-U D Operating Test No.: TMl-2017-1 Control Room Systems: *8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code*

Safety Function

a. Makeup System I Emergency Borate Using the RBAT as the Source -

A,D,S 1

Alternate Path - 004 A2.14

b. Reactor Coolant System I Restoration of letdown flow following high D,S 2

temperature closure of MU-V 002 A1.02

c. Emergency Core Cooling System I Respond to inadvertant ES actuation A,EN,M,S 3

- Alternate Path - 006 A2.13

d. Residual Heat Removal System I Transfer of Reactor Building Sump A, D, L, S 4P Recirculation - Alternate Path - 005 A2.04

e. Containment Cooling System I Perform Emergency Operations of A,M,S 5

Reactor Buildinq Emerqency Cooling water -Alternate Path - 022 A4.04

f. A.C Electrical Distribution I Transfer BOP Susses from 1 B to 1 A Aux M,S 6

Transformer - 062 A4.01

g. Component Cooling Water System I Cross Connect the Secondary River M,S 8

Water System to the Nuclear River Water System - 026 AA2.02

h. Radiation Monitoring System I Respond IAW OP-TM-MAP-C0101 Alarm A,D,P,S 7

Response with failure -Alternate Path - 072 A3.01 In-Plant Systems* (3 for RO); (3 for SRO-I}; (3 or 2 for SRO-U)

i. Main Steam System I Locally I Manually Operate the Turbine Bypass D

4S Valves (MS-V-3A-F) 041 A4.08

j. Nuclear Service Closed Cooling Water I Emergency Makeup to Nuclear D, E 8

Service Closed Cooling Surge Tank (NS-T-1) - 008A4.07

k. Waste Gas System I Take Corrective Action for an Unauthorized Waste N,R 9

Gas release- 071G2.1.30 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; in-plant systems and functions may overlap those tested in the control room.

• Type Codes I

Criteria for RO I SRO-I I SRO-U

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

~9/ ~8 I ~ 4 (E)mergency or abnormal in-plant

~ 1 I

~1 I ~ 1 (EN)gineered safety feature

~ 1 I

~ 1 I

~ 1 (control room system)

(L)ow-Power I Shutdown

~ 1 I

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

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

~ 3 I

~3 I ~ 2 (randomly selected)

(R)CA

~ 1 I

~1 I ~ 1 (S)imulator ES-301, Page 23 of 27 JPM A: Emergency Borate Using the RBAT as the Source -Alternate Path - In this JPM the examinee will be directed to perform OP-TM-EOP-010, Rule 5 for emergency boration. Due to malfunctions, the examinee will have to initiate emergency boration using Guide 1.

JPM B: Restoration of Letdown Flow Following Temperature Closure of MU-V In this JPM the examinee will show the ability to restore letdown while maintaining normal pressurizer level and makeup tank bands.

JPM C: Respond to an Inadvertent ESAS Actuation-Alternate Path - In this JPM the examinee will show the ability to perform the IMA's of OP-TM-AOP-046, INADVERTENT ESAS ACTUATION. The 'B' 500 psig ES signal will not be able to be cleared so the examinee will end up having to throttle open MU-V-16B to ensure proper makeup pump flow.

JPM D: Transfer of Reactor Building Sump Recirculation - Alternate Path - In this JPM the examinee will demonstrate the ability to throttle LPI to within limits after a sump recirculation suction valve fails to open after a LOCA.

JPM E: Perform Emergency Operations of Reactor Building Emergency Cooling Water -

Alternate Path - In this JPM the examinee will be directed to initiate Reactor Building Emergency Cooling. This JPM is modified so that RR-V-1 B does not open and RR-P-1 B must be secured.

JPM F: Transfer BOP Susses from 1Bto1A Aux Transformer - In this JPM the examinee will demonstrate the ability to transfer the 1 C 4160V Bus from the 1 B Aux Transformer to the 1 A Aux Transformer.

JPM G: Cross Connect the Secondary River Water System to the Nuclear River Water System

- In this JPM the examinee will have to cross connect Secondary River with Nuclear River water.

JPM H: Respond IAW OP-TM-MAP-C0101 Alarm Response with Failure -Alternate Path - In this JPM, the examinee will have to put the control tower on emergency recirculation. AH-E-18B will trip so the examinee will have to start the opposite train.

JPM I: Manually/Locally operate the turbine bypass valves (MS-V-3A-F) - In this JPM the examinee will take local manual control of MS-V-3C.

JPM J: Emergency Makeup to Nuclear Service Closed Cooling Surge Tank (NS-T-1) - In this JPM the examinee will have to do an emergency fill of the nuclear closed cooling water surge tank.

JPM K: Take Corrective Action for an Unauthorized Waste Gas release - lnplant - In this JPM the examinee will have to identify what a waste gas tank is releasing and take action to stop the release.

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

Three Mile Island Scenario No.:

Op Test No.:

TMl-2017-1 Examiners:

Operators:

Initial Conditions:

100% power, MOL i

EG-Y-1A "A" Diesel Generator Out of Service Turnover:

EG-Y-1A 7 day LCO has expired. Plant is beginning a shutdown. Directed rate of change of reactor power is 1 %/minute I

Critical Tasks:

Electrical Power Alignment (CT-8)

I I

Natural Circulation RCS Flow (CT-12) i Event No.

Malf. No.

Event Type*

Event Description 1

RCRS Shutdown reactor in 1102-4 (Allow power to lower >10%)

RURO (ICS in Auto, ULD in Hand)

I 2

TSCRS EF-P-1 oil bubbler empty, EF-P-1 inoperable 3

TSCRS NR-P-1A Trips, NR-P-18 Fails to Auto-Start, entry into OP-TM-RW02A CARO MAP-80105, and OP-TM-MAP-80205 (ARO: Starts NR-P-18 from CR) 4 IC09 I CRS ICS Malfunction, entry into OP-TM-AOP-070 IC53 IURO (Main Generator Megawatts fails to 50%, SASS fails to actuate) i IARO i

5 I CRS Loss of ICS AUTO Subfeed Power (MU), entry into OP-TM-MAP-I ED22C IURO H0108 I

IARO (URO: Operate MU-V-32 in HAND, ARO: Restore letdown)

I 6

MCRS Loss of Offsite power with one Emergency Diesel available, Entry I

I ED01 MURO into OP-TM-AOP-020 MARO I

7 FW62C CCRS EF-P-28 trips, Entry into OP-TM-EOP-004, Lack of Heat Tranfer CARO I

8 CCRS Places the S80 diesel on the 1 D 4KV bus, starts EF-P-2A I

CARO (N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor Appendix D Scenario Outline Form ES-D-1 Facility:

Three Mile Island Scenario No.:

2 Op Test No.:

TMl-2017-1 Examiners:

Operators:

Initial Conditions:

85% power, MOL, load following I

EG-Y-1A is 2 days into a 6 day system outage I

i

\\ I I

Turnover:

Maintain 85% power Critical Tasks:

Limit Uncontrolled Radiation Release (CT-21)

Reduce Steaming/Isolate Affected SGs (CT-22)

Event No.

Malf. No.

Event Type*

Event Description

~

1 ES08A TSCRS Inadvertent 4# ES actuation, "A" train, entry into OP-TM-AOP-046 IURO IARO (URO: AOP-046 IMA's, ARO: Restores Letdown) 2 TH17A TSCRS

'A' OTSG Tube Leak, TS call, Reactivity manipulation I

RURO (URO: Lowers power) i I

3 TH13C CCRS RC-P-1C High Vibrations I

CARO (ARO: Secures RCP) 4 IC63 I CRS Feedwater fails to re-ratio on loss of RCP IURO IARO I

5 TH16A MCRS

'A' OTSG tube rupture, requiring HPI initiation, entry into OP-TM-i MURO EOP-001 MARO I

6 MU23A CCRS MU-P-1 A fails to start on ES I

CURO (URO: Starts MU-P-1A) i 7

CCRS Loss of SCM, entry into OP-TM-EOP-002, then return to OP-TM-I CURO EOP-005 CARO (URO: Rule 1, ARO: Steams 'A' OTSG)

(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor I

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

Three Mile Island Scenario No.:

5 Op Test No.:

TMl-2017-1 Examiners:

Operators:

Initial Conditions:

2% power, MOL, ICS is in manual with reactivity control at the diamond Turbine offline for bearing maintenance I

i l&C maintenance is occurring on HSPS, Train B EFW actuation logic circuit FW-P-1A is operating with control on the MSC I

! Turnover:

Raise reactor power to 100%

I i

I Critical Tasks:

Establish and Maintain Reactor Shutdown Requirements (CT-23)

Control HPI (CT 5)

Event No.

Malt. No.

Event Type*

Event Description 1

RM0323 TSCRS Reactor Building Hi Range Radiation Monitor, RM-G-23, Failure 2

N CRS Raise reactor power from 3% to 10%

I I

RURO (URO: Power ascension with ICS in Manual) 3 RC04A ICRS Pressurizer Level Transmitter fails, entry into OP-TM-MAP-G0105, IURO OP-TM-MAP-G0205 I

(URO: Controls MU-V-17 in HAND)

I i

4 IA07 CCRS Loss of Instrument Air, entry into OP-TM-AOP-028 I

IA01C CARO (ARO: Starts IA-P-1A or B) 5 CCRS Cavitating Circ Water Pump I

I CARO (ARO: Secure cavitiating circ water pump) i 6

MU07 ICRS Seal Flow Instrument Fails, RCP Seal flow High I

IURO (URO: MU-V-32, Normalizes Seal Injection) 7 IC388 TSCRS Invalid "B" OTSG Low Level, "B" EFW inadvertent actuation CARO (ARO: Defeats invalid signal, secures EF-P-28) 8 PLA-4-9 MCRS Gire Water Rupture, Loss of Vacuum, Reactor Trip, Entry into EOP-PLB-8-3 MURO 001, Stuck Rods MARO 9

TH06 CCRS RCS leak, PZR Level Cannot be maintained without HPI, Entry into CURO EOP-006 CARO (URO: Initiate HPI, ARO: Initiate EFW)

(N)ormal, (R)eactivity, (I )nstrument, (C)omponent, (M)ajor PWR Examination Outline Form ES-401-2 Facility: Three Mile Island Date of Exam: 06/28/17 RO KIA Cate ~orv 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 2

1 5

2 6

2 18 6

Emergency &

Abnormal 2

1 1

2 N/A 1

3 N/A 1

9 4

Plant Tier Totals Evolutions 3

2 7

3 9

3 27 10 1

3 2

2 3

2 3

2 3

3 2

3 28 5

2.

Plant 2

1 0

1 0

0 0

1 2

2 1

2 10 3

Systems Tier Totals 4

2 3

3 2

3 3

5 5

3 5

38 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

CateQories 2

3 2

3 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A 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 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 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 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) 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 Kl 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 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 K/As that are linked to 10 CFR 55.43.

G*

Generic KIAs

000058 Loss of DC Power I 6 x

AK3.0 I Knowledge of the reasons for the following 3.4/3.7 10 responses as they apply to the Loss of DC Power: Use of de control power bv D/Gs 000062 Loss of Nuclear Svc Water I 4 x

AK3.02 Knowledge of the reasons for the following 3.6/3.9 II responses as they apply to lthe Loss of Nuclear Service Water:The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS 000065 Loss of Instrument Air/ 8 x

AA2..07 Ability to determine and interpret the following 3.6/4.2 66 as they apply to the Loss of Instrument Air: When to trip reactor if instrument air pressure is de-creasing.

W/E04 LOCA Outside Containment 13 W/E11 Loss of Emergency Coolant Recirc. I 4 BW/E04; W/E05 Inadequate Heat x

EKl.2 Knowledge of the operational implications of the 4.0/4.2 47 Transfer - Loss of Secondary Heat Sink I 4 following concepts as they apply to the (Inadequate Heat Transfer): Normal, abnormal and emergency operating procedures associated with (Inadequate Heat Transfer).

000077 Generator Voltage and Electric x

2.4.11 Knowledge of abnonnal condition procedures.

4.0/4.2 49 Grid Disturbances I 6 K/A Cateqory Totals:

2 I

5 2

6 2

Group Point Total:

18 1s II

ES-401 3

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

E/APE #I Name I Safety Function K

K K A A G*

KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal I 1 x

AA2.05 Ability to determine and interpret the 4.4/4.6 12 following as they apply to Continuous Rod Withdrawal :Uncontrolled rod withdrawal, from available indications 000003 Dropped Control Rod I 1 000005 Inoperable/Stuck Control Rod I 1 000024 Emerqencv Boration I 1 x

2.2.12 Knowledge of surveillance procedures.

3.7/4/l 60 000028 Pressurizer Level Malfunction I 2 x

AKI.0 I Knowledge of the operational 2.8/3. l 13 implications of the following concepts as they apply to Pressurizer Level Control Malfunctions:

PZR reference leg leak abnormalities 000032 Loss of Source Range NI I 7 x

AK3.0l Knowledge of the reasons for the 3.2/3.6 14 following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss 000033 Loss of Intermediate Ranqe NI I 7 000036 (BW/A08) Fuel Handlinq Accident I 8 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum I 4 000059 Accidental Liquid Radwaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms I 7 x

AA2.03 Ability to determine and interpret the 3.013.3 15 following as they apply to Area Radiation Monitoring (ARM) System Alarms: Setpoints for alert and high alarms 000067 Plant Fire On-site I 8 000068 (BW/A06) Control Room Evac. I 8 000069 (W/E14) Loss ofCTMT lnteqrity I 5 000074 (W/E06&E07) lnad. Core Cooling I 4 000076 High Reactor Coolant Activity I 9 x

AA 1.04 Ability to operate and I or monitor the 3.2/3.4 16 following as they apply to the High Reactor Coolant Activity: Failed fuel-monitoring equipment W/E01 & E02 Rediaonosis & SI Termination I 3 W/E 13 Steam Generator Over-pressure I 4 W/E15 Containment Floodino I 5 W/E16 Hioh Containment Radiation I 9 BW/A01 Plant Runback I 1 BW/A02&A03 Loss of NNl-X/Y I 7 x

AK2.l Knowledge of the interrelations between 3.8/4.0 17 the (Loss ofNNl-X/Y) and the following:

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

BW/A04 Turbine Trip I 4 BW/A05 Emergency Diesel Actuation I 6 x

AA2. l Ability to determine and interpret the 3.5/4.2 48 following as they apply to (Emergency Diesel Actuation) Facility conditions and selection of appropriate procedures during abnonnal and emergency operations.

BW/A07 Floodinq I 8 BW/E03 Inadequate Subcooling Margin I 4 x

EK3. I Knowledge of the reasons for the 3.2/3.8 51 following responses as they apply to (Inadequate Subcooling Margin) Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

BW/E08; W/E03 LOCA Cooldown - Depress. I 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A 11; W/E08 RCS Overcooling - PTS I 4 CE/A16 Excess RCS Leakaqe / 2 CE/E09 Functional Recovery KIA Cateaorv Point Totals:

I I

2 I

3 I

Group Point Total:

9

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems - Tier 2/Group 1 (RO I 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

2 3

4 003 Reactor Coolant Pump x

KS.03 Knowledge of the operational 3.113.5 58 implications of the following concepts *as they apply to RCPS: Effects of RCP shutdown on T-ave., including the reason for unreliability ofT-ave. in the shutdown loop.

004 Chemical and Volume x

Al.06 Ability to predict and/or monitor 3.0/3.2 18 Control changes in parameters (to prevent exceeding design limits) associated with operating the eves controls including:

VCT level 005 Residual Heat Removal x

x KS.OJ Knowledge of the operational 2.6/2.9 19 implications of the following concepts as they apply the RHRS: Nil ductility transition temperature (brittle fracture)

A4.02: Ability to manually operate 3.413.1 59 and/or monitor in the control room: Heat exchanger bypass flow control.

006 Emergency Core Cooling x

K2.02 Knowledge of bus power supplies 3.6/3.8 68 to the following: ESF AS-operated valves.

007 Pressurizer Relief/Quench x

2.1.23 Ability to perform specific system 4.3/4.4 20 Tank and integrated plant procedures during all modes of plant operation.

008 Component Cooling Water x

A4.09 Ability to manually operate and/or 30/4.9 21 monitor in the control room: CCW temperature control valve 01 O Pressurizer Pressure Control x

x K6.0 I Knowledge of the effect of a loss 2.7/3.1 50 or malfunction of the following will have on the PZR PCS: Pressure detection systems 3.313.6 22 A2.0l Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures 012 Reactor Protection x

K6.02 Knowledge of the effect of a loss 2.9/3. l 52 or malfunction of the following will have on RPS: Redundant channels 01 ~ Engineered Safety Features x

K 1.0 I Knowledge of the physical 4.2/4.4 23 Actuation connections and/or cause effect relationships between the ESF AS and the following systems: Initiation signals for ESF circuit logic

022 Containment Cooling x

x K4.04 Knowledge of CCS design 2.513.0 53 feature(s) and/or interlock(s) which provide for the following: Cooling of containment penetrations.

A2.03 Ability to (a) predict the impacts of 2.613.0 24 the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload/high-speed operation 025 Ice Condenser 026 Containment Spray x

K3.0l Knowledge of the effect that a loss 3.9/4.1 65 or malfunction of the CSS will have on the following: CCS 039 Main and Reheat Steam x

x Kl.08: Knowledge of the physical 2.7/2.9 61 connections and/or cause-effect relationships between the MRSS and the following systems: MFW K5.08 Knowledge of the operational 3.613.6 27 implications of the following concepts as the apply to the MRSS: Effect of steam removal on reactivity 059 Main Feedwater x

Kl.02 Knowledge of the physical 3.413.4 26 connections and/or cause effect relationships between the MFW and the following systems: AFW system 061 Auxiliary/Emergency x

x K3.01 Knowledge of the effect that a loss 4.4/4.6 28 Feedwater or malfunction of the AFW will have on the following: RCS A3.03 Ability to monitor automatic 3.9/3.9 62 operation of the AFW, including: AFW SIG level control on automatic start 062 AC Electrical Distribution x

K4.07 Knowledge of ac distribution 2.7/3.1 54 system design feature(s) and/or interlock(s) which provide for the following: One-line diagram of 4kV to 480V distribution, including sources of normal and alternative power 063 DC Electrical Distribution x

x K4.02 Knowledge of DC electrical system 2.9/3.2 30 design feature(s) and/or interlock(s) which provide for the following: Breaker interlocks, pennissives, bypasses and cross-ties.

A3.01 Ability to monitor automatic 2.7/3.1 29 operation of the DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights 064 Emergency Diesel Generator x

x K2.02 Knowledge of the physical 2.8/3.1 31 connections and/or cause effect relationships between the ED/G system and the following systems: Fuel oil pumps A3.03 Ability to monitor automatic 3.4/3.3 32 operation of the ED/G system, including:

Indicating lights, meters, and recorders 073 Process Radiation Monitoring x

2.1.28 Knowledge of the purpose and 4.1/4.1 55 function of major system components and controls.

076 Service Water x

A2.0 I Ability to predict and/or monitor 3.5/3.7 33 changes in parameters (to prevent exceeding design limits) associated with operating the SWS controls including:

Loss ofSWS 078 Instrument Air x

Kl.04 Knowledge of the physical 2.6/2.9 34 connections and/or cause-effect relationships between the IAS and the following systems: Cooling water to compressor 103 Containment x

2.4.6: Knowledge of EOP mitigation 3.7/4.7 57 strategies.

KIA Category Point Totals:

3 2

2 3

2 3

2 3

3 2

3 Group Point Total:

28 28

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 RO I 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

2 3

4 001 Control Rod Drive x

K3.02:Knowledge of the effect that a loss or 3.4/3.5 35 malfunction of the CRDS will have on the following: res 002 Reactor Coolant x

A3.0 I Ability to monitor automatic 3.7/3.9 36 operation of the RCS, including: Reactor coolant leak detection system 011 Pressurizer Level Control 014 Rod Position Indication x

2.4.4: Ability to recognize abnormal 4.5/4.7 69 indications for system operating parameters that are entry-level conditions for emergency and abnonnal operating procedures.

015 Nuclear Instrumentation x

A2.0 I Ability to (a) predict the impacts of 3.5/3.9 25 the following malfunctions or operations on the N IS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Power supply loss or erratic operation 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and x

A4.0 I Ability to monitor automatic 4.0/4.0 75 Purge Control operation of the HRPS, including: HRPS controls 029 Containment Purae 033 Soent Fuel Pool Coolina 034 Fuel Handlina Equipment 035 Steam Generator x

A2.06 Ability to (a) predict the impacts of 4.5/4.6 37 the following malfunctions or operations on the SGS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Small break LOCA 041 Steam Dump/Turbine Bypass x

Al.02 Ability to predict and/or monitor 3.1/3.2 46 Control changes in parameters (to prevent exceeding design limits) associated with operating the SOS controls including: Steam pressure 045 Main Turbine Generator 055 Condenser Air Removal x

Kl.06Knowledge of the physical 2.6/2.6 38 connections and/or cause effect relationships between the CARS and the following systems: PRM system 056 Condensate 068 Liquid Radwaste x

A3.02 Ability to monitor automatic 3.613.6 39 operation of the Liquid Radwaste System including: Automatic isolation 071 Waste Gas Disposal

072 Area Radiation Monitoring 075 Circulating Water x

2.4.21: Knowledge of the parameters and 3.8/4.5 63 logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

079 Station Air 086 Fire Protection KIA Category Point Totals:

I 0

I 0

0 0

1 2

2 I

2 Group Point Total:

IO IO

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

Form ES-401-3 Facility:

Date of Exam:

Category K/A#

Topic RO SRO-Only IR IR 2.1.25 Ability to interpret reference materials, such as graphs, 3.9/4.2 40 curves, tables, etc.

2.1.42 Knowledqe of new and spent fuel movement procedures.

2.513.4 70

1.

2.1.

Conduct of Operations 2.1.

2.1.

2.1.

Subtotal 2.2.12 KnowledQe of surveillance procedures.

3.7/4.1 72 2.2.38 Knowledge of conditions and limitations in the facility 3.614.5 71 license.

2.

2.2.39 Knowledge of less than or equal to one hour Technical 3.9/4.5 41 Equipment Soecifications action statements for systems.

Control 2.2.

2.2.

2.2.

Subtotal 2.3.4 Knowledge of radiation exposure limits under normal or 3.2/3.7 42 emerqency conditions.

2.3.11 Ability to control radiation releases.

3.8/4.3 43

3.

2.3.

Radiation Control 2.3.

2.3.

2.3.

Subtotal 2.4.9 Knowledge of low power/shutdown implications in 3.8/4.2 74 accident (e.g., loss of coolant !accident or loss of residual heat removal) mitiqation strateqies.

2.4.16 Knowledge of EOP implementation hierarchy and 3.514.4 44 coordination with other! support procedures or guidelines

4.

such as, operating procedures, abnormal! operating procedures, and severe accident management Emergency quidelines.

Procedures I Knowledge of local auxiliary operator tasks during an Plan 2.4.35 emerqency and the resultant operational effects.

3.8/4.0 45 2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA 111 025 AA2.05 Subject not relevant at this facility. Replaced with 025 AA2.01.

1/1 038 EK202 Subject Kl A oversampled. Overlaps with other questions on the written exam. Replaced 038 EA2.0l.

1/1 040 AA2.03 Subject KIA more appropriately tested on operational exam. Replaced with 040 AA2.02.

111 065 AA2.07 Subject not relevant at this facility. Replaced with 065AA2.06.

2/1 006 K2.02 Subject not relevant at this facility. Replaced with 006 K2.04.

2/1 022 K4.04 Subject not relevant at this facility. Replaced with 022 K4.0l.

2/1 039 Kl.06 Subject KIA oversampled. Overlaps with other questions on written exam.

Replaced with 039 Kl.08.

2/1 061 A3.04 Subject not relevant at this facility. Replaced with 061 A3.03.

2/1 103 2.4.2 Subject not relevant at this facility. Replaced with 103 2.4.6.

212 014 2.4.21 KIA for this system is SRO knowledge. Replaced with 014 2.4.4 212 075 2.4.8 Subject generic KIA not relevant to selected system. Replaced with 075 2.4.21 3

2.1.42 Not relevant to the RO position. Replaced with 2.1.1.

3 2.2.23 Not RO LOK. Replaced with 2.2.39

PWR Examination Outline Form ES-401-2 Facilitv: Three Mile Island Date of Exam: 06/26/17 RO K/A Cate ~orv Points SRO-Onlv 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 18 4

2 6

Emergency &

Abnormal 2

N/A N/A 9

1 3

4 Plant Evolutions Tier Totals 27 5

5 10 1

28 2

3 5

2.

Plant 2

10 2

1 3

Systems Tier Totals 38 4

4 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

CateQories 2

2 1

2 Note:

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 outline, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a KIA from another Tier 3 Category).

2.

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

3.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted with justification; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate 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 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 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 K/A numbers, a brief description of each topic, the topics' importance ratings (I Rs) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the 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.

G*

Generic K/As

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emerqency and Abnormal Plant Evolutions - Tier 1/Grouo 1 (RO I SRO)

E/APE #I Name I Safety Function K

K K

A A

G*

KIA Topic(s)

IR 1

2 3

1 2

000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery I 1 000008 Pressurizer Vapor Space x

AA2.20 Ability to determine and interpret the following 3.6 76 Accident/ 3 as they apply to the Pressurizer Vapor Space Accident:

PZR level indicators.

000009 Small Break LOCA I 3 x

2.4.31 Knowledge of annunciator alarms, indications, or 4.1 77 response procedures. I 000011 Larqe Break LOCA I 3 000015/17 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup I 2 000025 Loss of RHR System I 4 000026 Loss of Component Cooling x

AA2.02: Ability to determine and interpret the following 3.6 78 Water I 8 as they apply to the Loss of Component Cooling Water:

The cause of possible CCW loss 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 000038 Steam Gen. Tube Rupture I 3 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer I 4 000054 (CE/E06) Loss of Main x

AA2.0l Ability to detennine and interpret the following 4.4 79 Feedwater I 4 as they apply to the Loss of Main Feedwater (MFW):Occurrence of reactor and/or turbine trip 000055 Station Blackout I 6 000056 Loss of Off-site Power I 6 000057 Loss of Vital AC Inst. Bus I 6 000058 Loss of DC Power I 6 x

AA2.03 Ability to detennine and interpret the following 3.9 80 as they apply to the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant systems 000062 Loss of Nuclear Svc Water I 4 000065 Loss of Instrument Air I 8 W/E04 LOCA Outside Containment I 3 W/E 11 Loss of Emergency Coolant Recirc. I 4 BW/E04; W/E05 Inadequate Heat x

2.4.9: Ability to interpret control room indications to 4.1 81 Transfer - Loss of Secondary Heat Sink I 4 verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

000077 Generator Voltage and Electric Grid Disturbances I 6 KIA Cateqory Totals:

4 2

Group Point Total:

6

ES-401 3

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

E/APE #I Name I Safety Function K

K K

A A

G*

KIA Topic(s)

IR 1

2 3

1 2

000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod I 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emeroencv Boration I 1 000028 Pressurizer Level Malfunction I 2 000032 Loss of Source Ranae NI I 7 000033 Loss of Intermediate Range NI I 7 000036 (BW/A08) Fuel Handlinq Accident I 8 000037 Steam Generator Tube Leak I 3 000051 Loss of Condenser Vacuum/ 4 000059 Accidental Liquid Radwaste Rel. I 9 000060 Accidental Gaseous Radwaste Rel. I 9 000061 ARM System Alarms 17 000067 Plant Fire On-site I 8 000068 (BW/A06) Control Room Evac. I 8 000069 (W/E14) Loss of CTMT lnteoritv / 5 000074 (W/E06&E07) lnad. Core Coolino 14 000076 High Reactor Coolant Activity I 9 x

2.2.38 Knowledge of conditions and limitations 4.5 83 in the facility license.

W/E01 & E02 Rediaonosis & SI Termination I 3 W/E13 Steam Generator Over-pressure I 4 W/E15 Containment Floodinq / 5 W/E16 Hiqh Containment Radiation/ 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNl-X/Y I 7 BW/A04 Turbine Trip I 4 BW/A05 Emerqencv Diesel Actuation I 6 BW/A07 Floodinq I 8 BW/E03 Inadequate Subcooling Margin I 4 x

EA2. l Ability to determine and interpret the 4.0 84 following as they apply to the (Inadequate Subcooling Margin)Facility conditions and selection of appropriate procedures during abnonnal and emergency operations.

BW/E08; W/E03 LOCA Cooldown - Depress. I 4 x

2.4.18: Knowledge of the specific bases for 4.0 82 EOPs.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures x

2.2.44: Ability to recognize system parameters 4.5 84 that are entry-level conditions for technical specifications.

CE/A 11; W/E08 RCS Overcoolinq - PTS I 4 CE/A16 Excess RCS Leakaoe / 2 CE/E09 Functional Recovery KIA Category Point Totals:

1 3

Group Point Total:

4

ES-401 4

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 !RO I 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

2 3

4 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling x

2.4.9: Knowledge oflow power/shutdown 4.2 86 implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

007 Pressurizer Relief/Quench Tank 008 Component Coolinq Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features x

2.4.35 Knowledge of local auxiliary 4.0 87 Actuation operator tasks during an emergency and the!

resultant operational effects.

022 Containment Coolinq 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency x

2.4.18 Knowledge of the specific bases for 4.0 88 Feedwater EOPs.

062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitorinq 076 Service Water 078 Instrument Air x

A2.0l Ability to (a) predict the impacts of 2.9 89 the 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 Ability to (a) predict the impacts of the following malfunctions or operations on the !AS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions 103 Containment x

A2 04 Containment evacuation (including 3.6 90 recognition of the alann)

KIA Cateqorv Point Totals:

2 3

Group Point Total:

5

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 RO I 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

2 3

4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor x

2.4.3 Ability to identify post-accident 3.9 91 instrumentation.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purqe Control 029 Containment Purqe 033 Spent Fuel Pool Coolinq 034 Fuel Handlinq Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate x

A2.04 Ability to (a) predict the impacts of the 2.6 92 following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate oumps 068 Liquid Radwaste x

A2.04 Ability to (a) predict the impacts of the 3.3 93 following malfunctions or operations on the Liquid Radwaste System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection KIA Cateqory Point Totals:

2 1

Group Point Total:

10/3

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

Form ES-401-3 I Facility:

Date of Exam:

I Category K/A#

Topic RO SRO-On Iv IR IR 2.1.32 Ability to explain and apply system limits and precautions.

4.0 94 2.1.42 Knowledge of new and spent fuel movement procedures.

3.4 95

1.

2.1.4 Conduct of 2.1.

Operations 2.1.

2.1.

Subtotal 2.2.7 Knowledge of the process for conducting special or infrequent 3.6 96 tests.

2.2.21 Knowledge of pre-and post-maintenance operability 4.1 97 requirements.

2.

Equipment 2.2.

Control 2.2.

2.2.

2.2.

Subtotal 2.3.6 Ability to approve release permits.

3.8 98 2.3.

3.

2.3.

Radiation 2.3.

Control 2.3.

2.3.

Subtotal 2.4.34 Knowledge of RO tasks performed outside the main control 4.1 99 room during an !emergency and the resultant operational effects 2.4.45 Ability to prioritize and interpret the significance of each 4.3 100

4.

annunciator or alarm.

Emergency 2.4.

Procedures I Plan 2.4.

2.4.

2.4.

Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected Kl A 1/1 SRO 008 AA2.20 This KIA overlaps with the operational exam. Replaced with 008 AA2.12.

1/1 SRO BW/E04 2.2.12 This subject KIA is not relevant to the topic at the subject facility. Replaced with BW/E04 2.4.9 1/2 SRO 059 2.2.25 Unable to make a psychometrically sound question.

Replaced with BW /E09 2.4.18.

1/2 SRO BW/E13 2.2.39 This subject KIA is not relevant to the topic at the subject facility. Replaced with BW/E13 2.2.42.

2/1 SRO 006 2.4.4 Original KIA is RO LOK. Replaced with 006 2.4.9.

212 SRO 068 A2.02.

Unable to make an psychometrically sound SRO question.

Replaced with 068 A2.04.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Three Mile Island Date of Examination: 06/26/17 Examination Level: RO [gl SRO D Operating Test Number: TMl-2017-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Conduct of Operations R, N Shutdown Margin for Low Temperature Conditions 2.1.43 Perform a Transient Leak Rate Calculation Conduct of Operations R, D 2.1.23 Equipment Control S,D Perform the "Shiftly Checks" IAW 1301-1, DATA SHEET 1 2.2.12 Radiation Control ERO Notification Emergency Plan S,P,D 2.4.39 From 12-01 NRC Exam NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

RA1 The examinee will have to calculate shutdown margin(SDM)for a low temperature situation and will determine that SOM is NOT more negative than -1 o/o~k/k.

RA1 The examinee will use OS-24 to calculate a transient leakrate.

RA2 - The examinee will be in the simulator to perform a portion of the shift and daily log set.

The examinee will have to identify all out of specification readings.

RA4 - The examinee will have to make all ERO notifications as shift communicator.