ML19282A573

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Final Written Examination and Operating Test Outlines (Folder 3)
ML19282A573
Person / Time
Site: Hope Creek 
Issue date: 10/01/2019
From:
Public Service Enterprise Group
To:
NRC Region 1
Shared Package
ML19007A361 List:
References
EPID: L-2019-OLL-0016
Download: ML19282A573 (18)
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Text

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

Hoee Creek Generating Station Date of Examination:

8/12/2019 Examination Level: RO !XI SRO D Operating Test Number: -*

Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations S,D Complete The Daily Surveillance Logs Conduct of Operations S,M Perform A Shift Turnover As On-Coming/Off-Going NCO Equipment Control S,D Perform Actions to Achieve Criticality and Raise Power to the Point of Adding Heat Radiation Control R,D Purge The Containment Emergency Plan 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 Administrative Topics Outline Form ES-301-1 Facility:

_Hope Creek Generating Station Date of Examination:

8/12/2019 Examination Level: RO D SRO lg]

Operating Test Number: ---*

Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations R,D,P Ensure The Operating Shift Is Adequately Manned Conduct of Operations R,D Review All Operations Logs In Use During A Shift Including Computer Logs Equipment Control R,M Complete an Action Statement Log Sheet Radiation Control R,D Verify Compliance with Gaseous Release Permit Emergency Plan R,M Utilize The ECG To Determine The Emergency Classification 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:

Hope Creek Generating Station Date of Examination:

8/12/2019 Exam Level: RO

[ZI SRO-I D SRO-U D Operating Test Number:

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.

AC. Electrical Dist. / Respond To A Turbine Generator Malfunction A,D,L,S 6

b.

Reactor Core Isolation Cooling/ Reduce Torus Level Using RCIC D,S 4

System C.

Component Cooling Water / Transfer T ACS To The Standby SA Cs D,S 8

Loop

d.

Low Pressure Core Spray /Manually Start the Core Spray System A,D,EN,S 2

e.

Control Rod and Drive Mechanism/ Respond To A Control Rod High A,M,S 1

Temperature

f.

Primary Containment System and Auxiliaries/ Operate The PCIG A,D,EN,S 5

System During Post LOCA/lsolation Conditions

g.

Average Power Range Monitor/Local Power Range Monitor I D,S 7

Respond To A Recirculation Pump Malfunction

h.

Reactor/Turbine Pressure Regulating / Perform a Cooldown Using D,L,P,S 3

Bypass Valves In-Plant Systems:.

3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water/ Respond To A SACS Malfunction D,EN,R 8

j.

Uninterruptable Power Supply (A.G. /D.C.) / Remove 120 VAC A,D 6

Electrical Distribution System From Service

k.

Primary Containment System and Auxiliaries/ Purge the Vent line E,EN,L,N 5

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 Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank
.9/:.8/:.4 (E)mergency or abnormal in-plant i!: 1/i!: 1/i!: 1 (EN)gineered safety feature i!: 1/i!: 1/i!: 1 (control room system)

(L)ow-Power/Shutdown i!:1/i!:1/i!:1 (N)ew or (M)odified from bank including 1 (A) i!: 2k. 2/i!: 1 (P)revious 2 exams s 3/s 3/s 2 (randomly selected)

(R)CA i!:1/i!:1/i!:1 (S)imulator

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

Hoee Creek Generating Station Date of Examination:

8/12/2019 Exam Level: RO D SRO-I

[8J SRO-U D Operating Test Number:

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.

A.G. Electrical Dist./ Respond To A Turbine Generator Malfunction A,D,L,S 6

b.

Reactor Core Isolation Cooling/ Reduce Torus Level Using RCIC D,S 4

System C.

Component Cooling Water/ Transfer TAGS To The Standby SACs D,S 8

Loop

d.

Low Pressure Core Spray /Manually Start the Core Spray System A,D,EN,S 2

e.

Control Rod and Drive Mechanism/ Respond To A Control Rod High A,M,S 1

Temperature

f.

Primary Containment System and Auxiliaries/ Operate The PCIG A,D,EN,S 5

System During Post LOCA/lsolation Conditions

g.

Average Power Range Monitor/Local Power Range Monitor/

D,S 7

Respond To A Recirculation Pump Malfunction

h.

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water I Respond To A SACS Malfunction D,EN,R 8

j.

Uninterruptable Power Supply (A.C. /D.C.} I Remove 120 VAC A,D 6

Electrical Distribution System From Service

k.

Primary Containment System and Auxiliaries / Purge the Vent line E,EN,L,N 5

Alf 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 Criteria for R /SR0-1/SRO-U (A)ltemate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank S9/S 8/S4 (E)mergency or abnormal in-plant
,
1/;?: 11;?: 1 (EN)gineered safety feature 2: 1/2: 1/2: 1 (control room system)

(L)ow-Power/Shutdown 2: 1/2: 1/2: 1 (N)ew or {M)odified from bank including 1 (A) 2: 2k 2/2: 1 (P)revious 2 exams s 3/S 3/-s. 2 (randomly selected)

(R)CA 2: 1/2: 1/2: 1 (S)imulator

ES-301 Control Roomnn-Plant Systems Outline Form ES-301-2 Facility:

Hope Creek Generating Station Date of Examination:

8/12/2019 Exam Level: RO D SRO-I D SRO-U IZl Operating Test Number:

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.

A.C. Electrical Dist. / Respond To A Turbine Generator Malfunction A,D,L,S 6

b.

C.

d.

BE005; Manually Start the Core Spray System A,D,EN,S 2

e.

Control Rod and Drive Mechanism / Respond To A Control Rod High A,M,S 1

Temperature

f.
g.
h.

In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

Component Cooling Water/ Respond To A SACS Malfunction D,EN,R 8

j.

i

k.

Primary Containment System and Auxiliaries / Purge the Vent line E,EN,L,N 5

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 Criteria for R /SR0-1/SRO-U (A)ltemate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank S9/:.s.8/S 4 (E)mergency or abnormal in-plant

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

~ 1k 1k 1 (control room system)

(L)ow-Power/Shutdown

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

~2k2k1 (P)revious 2 exams

.s. 3/s 3/:.s. 2 (randomly selected)

(R)CA

.:: 1k 1/.:: 1 (S)imulator

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

Ho~Creek Scenario No.:

1 Op-Test No.:

Examiners:

Operators:

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

~-------

-*-**-**-**-- ---*--**------- ----------- ------ -------~--~

Initial Conditions:

Plant is oeeratin.9. at a.epJOXimately_ 75% eower. _____

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

Turnover:

__ Lower gower to a£f'roximately 70%. Remove __ a. RFP from service.

Critical Tasks:.. tManu~l!y_initiate ARI to shut down the reactC?i:.c ~-Pl~~~-ljPCI in service to restore and maintain Reactor water level.

    • ------*--**-**-*--*-~

Event Malf.

Event Event No.

No.

Type*

Description 1

R Lower Reactor Power with Recirculation System 2

N Remove RFP In Service 3

RM9635 I

Radiation Monitor Failure 4

CU07 C

RWCU Leak Into RAGS 5

ED09D2 C

Loss of 1 D0482 6

RR31 M

LOCA 7

RP04 C

RPS Failure-ATWS/ARI Scram Successful 8

FW30/

C Loss of Condensate-HPCI Injection Valves' Failure HP14/5

  • 1

=1 I

I I

I i

~

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

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

Hoee Creek Scenario No.:

2 Op-Test No.:

Examiners:

Operators:

~--*-----

Initial Conditions: ~p_Qroximately 95% Reactor eower with a startue in erogress. SSW Pum_e_f_ __

tagged out for maintenance.

Turnover:

Secure Drywellmakeup.. Raise Reactor Power to 100% Power.

~ ***- ----**

Critical Tasks:.. 1. Start the A EOG. 2. Isolate HPCI steam leak. 3. Initiate actions to Emergency De2.r.essurize the reactor/Restore RPV Level.

Event Malf.

Event Event No.

No.

Type*

Description 1

N Secure containment makeup 2

R Raise power with Recirculation Pumps 3

SL03 I

Inadvertent SBLC Initiation 4

ED11B C

Loss of 1 OD420 125 VDC Bus 5

5A127 C

Secondary Condensate Pump Malfunction 6

EG12 M

Loss of Offsite Power 7

DG07A C

Auto Start Failure of EDG/LOP Sequencer Failure 8

HP09 C

Steam Leak in HPCI Room with Auto Isolation Failure (N)ormal, (R)eactivity,

{l)nstrument,

{C)omponent.

{M)ajor

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

Hope Creek Scenario No.:

3 Op-Test No.:

- --****** ---*~-----** -*** --

Examiners:

Operators:

  • -~,---

Initial Conditions:

100%_power. __ -

Turnover:

  • =**-~-. *-*

Critical Tasks:. LI!!E and isolates RR pumQ before DRWL pressure reaches 1.68 p_ajg_~

__ £ Open five SRVs after determining SC pressure cannot be maintained below PSP curve.

Event Malf.

Event Event No.

No.

Type"'

Description 1

N Swap In-feeds to Non-1E bus 2

RR19 I

Recirculation flow transmitter failure 3

RC08 C

RCIC Suppression Pool Suction Valve Failure 4

RR26 C

Reactor Recirculation Pump Seal Failures 5

CR02 R

Core Instabilities 6

MS15 I

Spurious Group 1 MSIV Isolation 7

RR31 M

LOCA 8

QQ21 C

RHR Pump Failure 9

RH20 C

Drywall Spray Valve Failure/Downcomer Failure I

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

ES-401 1

Form ES-401-1 i=acility: Hope Creek Date of Exam: 2019 Tier Group RO KIA Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

1 3

3 3

3 4

4 20 3

4 7

Emergency and 2

1 1

1 N/A 1

2 N/A 1

7 2

1 3

Abnormal Plant Evolutions Tier Totals 4

4 4

4 6

5 27 5

5 10

2.

1 3

2 3

3 1

2 3

2 2

2 3

26 3

2 5

Plant 2

2 0

1 1

1 2

1 1

1 1 1

12 0 I 1 2

3 Systems Tier Totals 5

2 4

4 2

4 4

3 3

3 4

38 4

4 8

3. Generic Knowledge and Abilities 1

2 3

4 10 I

1 I

2 I

3 I

4 I

7 I

Categories 3

2 2

3 2

2 1

2 Note: 1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA from another Tier 3 category.)

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
5.

Absent a plant-specific priority, only those KIAs having an importance rating (IR) of 2.5 or higher. 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 Kl As.
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' I Rs for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply.) Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, I Rs, and point totals (#) on Form ES-401-3. Limit SRO selections to Kl As that are linked to 10 CFR 55.43.

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

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

ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emeraencv and Abnormal Plant Evolutions Tier 1/Grouo 1 <RO/SRO)

E/APE # / Name/ Safetv Function K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR G 2.4.35 Knowledge of local auxiliary 4.0 76 295016 (APE 16) Control Room Abandonment X

operator tasks during an emergency and the 17 resultant ooerational effects.

X AA2.01 Ability to determine and/or interpret 3.6 77 295019 (APE 19) Partial or Complete Loss of the following as they apply to PARTIAL OR Instrument Air/ 8 COMPLETE LOSS OF INSTRUMENT AIR:

Instrument air svstem oressure X

G 2.4.47 Ability to diagnose and recognize 4.2 78 295021 (APE 21) Loss of Shutdown Cooling/

trends in an accurate and timely manner 4

utilizing the appropriate control room reference material.

AA2.04 Ability to determine and/or interpret 4.1 79 295023 (APE 23) Refueling Accidents / 8 X

the following as they apply to REFUELING ACCIDENTS:

I tOccurrence of fuel handlinQ accident X

G 2.2.40 Ability to apply Technical 4.7 80 295024 High Drywell Pressure / 5 Snecifications for a svstem.

EA2.01 Ability to determine and/or interpret 4.3 81 295025 (EPE 2) High Reactor Pressure / 3 X

the following as they apply to HIGH REACTOR PRESSURE: Reactor oressure X

G 2.1.20 Ability to interpret and execute 3.9 82 295031 (EPE 8) Reactor Low Water Level / 2 I orocedure steos.

X AA2.06 Ability to determine and/or interpret 3.2 1

295001 (APE 1) Partial or Complete Loss of the following as they apply to PARTIAL OR Forced Core Flow Circulation / 1 & 4 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Nuclear boiler instrumentation G 2.2.39 Knowledge of less than or equal to 3.9 2

295003 (APE 3) Partial or Complete Loss of X

one hour Technical Specification action AC Power/6 statements for svstems.

AK1.05 Knowledge of the operational 3.3 3

295004 (APE 4) Partial or Total Loss of DC X

implications of the following concepts as Power/6 they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Loss of breaker lorotection AK2.05 Knowledge of the interrelations 2.6 4

295005 (APE 5) Main Turbine Generator Trip/

X between MAIN TURBINE GENERATOR 3

TRIP and the following: Extraction steam svstem AK3.04 Knowledge of the reasons for the 3.1 5

295006 (APE 6) Scram / 1 X

following responses as they apply to SCRAM: Reactor water level setpoint setdown: Plant-Soecific AA 1.05 Ability to operate and/or monitor the 2.8 6

295016 (APE 16) Control Room Abandonment X

following as they apply to CONTROL

/7 ROOM ABANDONMENT: D.C. electrical distribution AA2.03 Ability to determine and/or interpret 3.2 7

295018 (APE18) Partial or Complete Loss of X

the following as they apply to PARTIAL OR CCW/8 COMPLETE LOSS OF COMPONENT COOLING WATER: Cause for partial or comolete loss G 2.4.50 Ability to verify system alarm 4.2 8

295019 (APE 19) Partial or Complete Loss of X

setpoints and operate controls identified in Instrument Air/ 8 the alarm resoonse manual..

AK 1. 02 Knowledge of the operational 3.3 9

295021 (APE 21) Loss of Shutdown Cooling/

X implications of the following concepts as 4

they apply to LOSS OF SHUTDOWN COOLING: Thermal stratification AK2.03 Knowledge of the interrelations 3.4 10 295023 (APE 23) Refueling Accidents/ 8 X

between REFUELING ACCIDENTS and the followina: Radiation monitorinQ eauioment

ES-401 3

Form ES-401-1 EK3.02 Knowledge of the reasons for the 3.5 11 295024 High Drywall Pressure I 5 X

following responses as they apply to HIGH DRYWELL PRESSURE: Suppression pool snrav oneration: Plant-Snecific EA 1.04 Ability to operate and/or monitor the 3.8 12 295025 (EPE 2) High Reactor Pressure I 3 X

following as they apply to HIGH REACTOR PRESSURE: HPCI: Plant-Soecific EA1.01 Ability to operate and/or monitor the 4.1 13 295026 (EPE 3) Suppression Pool High Water X

following as they apply to SUPPRESSION Temperature/ 5 POOL HIGH WATER TEMPERATURE:

Sunnression nool coolina X

G 2.1.23 Ability to perform specific system 4.3 14 295028 (EPE 5) High Drywall Temperature and integrated plant procedures during all (Mark I and Mark II only) / 5 modes of olant ooeration.

EK1.03 Knowledge of the operational 3.8 15 295030 (EPE 7) Low Suppression Pool Water X

implications of the following concepts as Level/ 5 they apply to LOW SUPPRESSION POOL WATER LEVEL: Heat caoacitv EK2.05 Knowledge of the interrelations 4.2 16 295031 (EPE 8) Reactor Low Water Level / 2 X

between REACTOR LOW WATER LEVEL and the following: Low pressure coolant iniection (RHR)

EK3.01 Knowledge of the reasons for the 4.1 17 295037 (EPE 14) Scram Condition Present X

following responses as they apply to and Reactor Power Above APRM Downscale SCRAM CONDITION PRESENT AND or Unknown / 1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Recirculation pump trip/runback: Plant-Snecific EA 1.04 Ability to operate and/or monitor the 2.8 18 295038 (EPE 15) High Offsite Radioactivity X

following as they apply to HIGH OFF-SITE Release Rate I 9 RELEASE RATE: SPDS/ERIS/CRIDS/GDS:

Plant-Soecific AA2.17 Ability to determine and interpret the 3.1 19 600000 (APE 24) Plant Fire On Site/ 8 X

following as they apply to PLANT FIRE ON SITE: Systems that may be affected by the fire.

G 2.4.47 Ability to diagnose and recognize 4.2 20 700000 (APE 25) Generator Voltage and X

trends in an accurate and timely manner Electric Grid Disturbances / 6 utilizing the appropriate control room reference material.

KIA Cateaorv Totals:

3 3

3 3

4/3 4/4 Grouo Point Total:

20/7

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emeraencv and Abnormal Plant Evolutions-Tier 1/Grouo 2 {RO/SRO)

E/APE # / Name I Safety Function K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR X

EA2.02 Ability to determine and/or interpret 4.2 83 295031 (EPE 8) Reactor Low Water Level/ 2 the following as they apply to REACTOR LOW WATER LEVEL: Reactor Power X

G2.1.20 Ability to interpret and execute 4.6 84 295009 (APE 9) Low Reactor Water Level / 2 I orocedure steos.

X EA2.01 Ability to determine and/or interpret 4.2 85 295034 (EPE 11) Secondary Containment the following as they apply to Ventilation High Radiation / 9 SECONDARY CONTAINMENT VENTILATION HIGH RADIATION:

Ventilation radiation levels X

AA2.02 Ability to determine and/or interpret 3.2 21 295002 (APE 2) Loss of Main Condenser the following as they apply to LOSS OF Vacuum/ 3 MAIN CONDENSER VACUUM: Reactor

  • oower: Plant-Specific G 2.4.31 Knowledge of annunciator 4.2 22 295010 (APE 10) High Drywell Pressure / 5 X

alarms, indications, or response I orocedures.

AK 1.03 Knowledge of the operational 3.7 23 295014 (APE 14) Inadvertent Reactivity X

implications of the following concepts as Addition/ 1 they apply to INADVERTENT REACTIVITY ADDITION: Shutdown marain AK2.11 Knowledge of the interrelations 3.5 24 295015 (APE 15) Incomplete Scram/ 1 X

between INCOMPLETE SCRAM and the followina: Instrument air AK3.02 Knowledge of the reasons for the 3.3 25 295017 (APE 17) Abnormal Offsite Release X

following responses as they apply to HIGH Rate I 9 OFF-SITE RELEASE RATE: Plant ventilation EA 1.03 Ability to operate and/or monitor 2.9 26 295029 (EPE 6) High Suppression Pool Water X

the following as they apply to HIGH Level/ 5 SUPPRESSION POOL WATER LEVEL:

RHR/LPCI X

EA2. Ability to determine and/or interpret 3.1 27 295036 (EPE 13) Secondary Containment the following as they apply to High Sump/Area Water Level / 5 SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Water level in the affected area KIA Cateaorv Point Totals:

1 1

1 1

2/2 1/1 Grouo Point Total:

7/3

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Svstems-Tier 2/Group 1 RO/SRO)

System # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

KIA Topic(s)

IR 203000 (SF2, SF4 RHR/LPCI)

X A2.04 Ability to (a) predict the impacts of the 3.6 86 RHR/LPCI: Injection Mode following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C.

failures 215004 (SF7 SRMS) Source-Range X G2.2.40 Ability to apply Technical 4.7 87 Monitor Specifications for a system.

215005 (SF7 PRMS) Average Power X

A2.08 Ability to (a) predict the impacts of the 3.4 88 Range Monitor/Local Power Range following on the AVERAGE POWER RANGE Monitor MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.08 Faulty or erratic operation of detectors/svstems 262002 (SF6 UPS) Uninterruptable X G 2.1.20 Ability to interpret and execute 4.6 89 Power Supply (AC/DC) procedure steps.

206000 (SF2, SF4 HPCIS)

X A2.01 Ability to (a) predict the impacts of the 4.0 90 High-Pressure Coolant Injection following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or ooerations: Turbine trios: BWR-2,3,4 203000 (SF2, SF4 RHR/LPCI)

X G 2.1.25 Ability to interpret reference 3.9 28 RHR/LPCI: Injection Mode materials, such as graphs, curves, tables, etc.

205000 (SF4 SCS) Shutdown Cooling X G 2.4.47 Ability to diagnose and recognize 4.2 29 trends in an accurate and timely manner utilizing the appropriate control room reference material.

205000 (SF4 SCS) Shutdown Cooling X K1.08 Knowledge of the physical connections 3.9 30 and/or cause/effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the followinq: LPCI 206000 (SF2, SF4 HPCIS)

  • x K2.01 Knowledge of electrical power supplies 3.2 31 High-Pressure Coolant Injection to the following: System valves: BWR-2,3,4 209001 (SF2, SF4 LPCS)

X K3.01 Knowledge of the effect that a loss or 3.8 32 Low-Pressure Core Spray malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:

Reactor water level 209001 (SF2, SF4 LPCS)

X K4.07 Knowledge of LOW PRESSURE 2.8 33 Low-Pressure Core Spray CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for the followinq: Pump ooerabilitv testina 211000 (SF1 SLCS) Standby Liquid X

K4.03 Knowledge of STANDBY LIQUID 3.8 34 Control CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Keeoinq sodium oentaborate in solution 212000 (SF7 RPS) Reactor Protection X K1.10 Knowledge of the physical connections 3.2 35 and/or cause/effect relationships between REACTOR PROTECTION SYSTEM and the followino: Main turbine 212000 (SF7 RPS) Reactor Protection X

K5.02 Knowledge of the operational 3.3 36 implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:

Soecific loaic arranoements

ES-401 6

Form ES-401-1 215003 (SF? IRM)

X K6.03 Knowledge of the effect that a loss or 2.8 37 Intermediate-Range Monitor malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM)

SYSTEM: Detector drive motor 215004 (SF? SRMS) Source-Range X

A 1.06 Ability to predict and/or monitor 3.1 38 Monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: Lights and alarms 215005 (SF? PRMS) Average Power X

A2.01 Ability to (a) predict the impacts of the 2.7 39 Range Monitor/Local Power Range following on the AVERAGE POWER RANGE Monitor MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Power suoolv dearaded 217000 (SF2, SF4 RCIC} Reactor X

A3.02 Ability to monitor automatic operations 3.6 40 Core Isolation Cooling of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including:

Turbine startuo 218000 (SF3 ADS) Automatic X

A4.07 Ability to manually operate and/or 3.5 41 Depressurization monitor in the control room: ADS valve acoustical monitor noise: Plant-Specific 223002 (SF5 PCIS) Primary X G 2.4.50 Ability to verify system alarm 4.2 42 Containment Isolation/Nuclear Steam setpoints and operate controls identified in Supply Shutoff the alarm response manual.

239002 (SF3 SRV) Safety Relief X

K1.04 Knowledge of the physical connections 3.6 43 Valves and/or cause/effect relationships between RELIEF/SAFETY VALVES and the following:

Main steam 259002 (SF2 RWLCS) Reactor Water X

K2.02 Knowledge of electrical power supplies 3.5 44 Level Control to the following: Feedwater coolant injection I <FWCI) initiation loaic: FWCI/HPCI 261000 (SF9 SGTS) Standby Gas X

A4.07 Ability to manually operate and/or 3.1 45 Treatment monitor in the control room: System flow 261000 (SF9 SGTS) Standby Gas X

K3.04 Knowledge of the effect that a loss or 3.1 46 Treatment malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: High pressure coolant injection system: Plant-Saecific 262001 (SF6 AC) AC Electrical X

K4.06 Knowledge of A.C. ELECTRICAL 3.6 47 Distribution DISTRIBUTION design feature(s) and/or interlocks which provide for the following:

Redundant power sources to vital buses 262002 (SF6 UPS) Uninterruptable X

A 1.02 Ability to predict and/or monitor 2.5 48 Power Supply (AC/DC) changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor I oenerator cutouts 263000 (SF6 DC) DC Electrical X

K6.01 Knowledge of the effect that a loss or 3.2 49 Distribution malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION: A.C.

electrical distribution 264000 (SF6 EGE) Emergency X

A 1.03 Ability to predict and/or monitor 2.8 50 Generators (Diesel/Jet) EDG changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET) controls including: Operating voltaoes, currents, and temperatures 300000 (SF8 IA} Instrument Air X

K3.02 Knowledge of the effect that a loss or 3.3 51 malfunction of the INSTRUMENT AIR SYSTEM will have on the following: Systems havino oneumatic valves and controls

ES-401 7

Form ES-401-1 300000 (SF8 IA} Instrument Air X

A2.01 Ability to (a) predict the impacts of the 2.9 52 following on the INSTRUMENT AIR SYSTEM and (b} based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Air drver and filter malfunctions 400000 (SF8 CCS) Component X

A3.01 Ability to monitor automatic operations 3.0 53 Cooling Water of the CCWS including: Setpoints on instrument signal levels for normal operations, warnings, and trips that are aoolicable to the CCWS

_ ry Point Totals:

3 2

3 3

1 2

3 2/ 2 2

3/ Group Point Total:

26/5 3

2

ES-401 8

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Svstems-Tier 2/Grouo 2 (RO/SRO\\

Svstem # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

KIA Tooic(s)

IR 201001 (SF1 CRDH) CRD Hydraulic X

G 2.4.45 Ability to prioritize and 4.3 91 interpret the significance of each annunciator or alarm.

214000 (SF? RPIS) Rod Position Information X

A2.02 Ability to (a} predict the 3.7 92 impacts of the following on the ROD POSITION INFORMATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Reactor SCRAM 272000 (SF?, SF9 RMS) Radiation Monitoring X

G 2. 1.31 Ability to locate control room 4.3 93 switches, controls, and indications, and to determine that they correctly reflect the desired olant lineuo.

201002 (SF1 RMCS) Reactor Manual Control X

K1.03 Knowledge of the physical 3.4 54 connections and/or cause/effect relationships between REACTOR MANUAL CONTROL SYSTEM and the following: Control rod block interlocks/power operation &

refuelina 201003 (SF1 CRDM) Control Rod and Drive X

K3.01 Knowledge of the effect that a 3.2 55 Mechanism loss or malfunction of the CONTROL ROD AND DRIVE MECHANISM will have on followina: Reactor Power 202001 (SF1, SF4 RS) Recirculation X

K4.01 Knowledge of 3.9 56 RECIRCULATION System design feature(s) and/or interlocks which provide for the following: 2/3 core coveraae: Plant-Soecific 204000 (SF2 RWCU) Reactor Water Cleanup X

K5.05 Knowledge of the operational 2.6 57 implications of the following concepts as they apply to REACTOR WATER CLEANUP SYSTEM: Flow controllers 216000 (SF? NBI) Nuclear Boiler Instrumentation X

K6.01 Knowledge of the effect that a 3.1 58 loss or malfunction of the following will have on the NUCLEAR BOILER INSTRUMENTATION: A.C. electrical distribution 223001 (SF5 PCS) Primary Containment and X

Al.09 Ability to predict and/or monitor 3.5 59 Auxiliaries changes in parameters associated with operating the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES controls including:

Suooression oool temoerature 256000 (SF2 CDS) Condensate X

A2.01 Ability to (a) predict the 3.3 60 impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or ooerations: Pump trios 259001 (SF2 FWS) Feedwater X

A3.09 Ability to monitor automatic operations of the REACTOR 3.0 61 FEEDWATER SYSTEM including:

Liahts and alarms 268000 (SF9 RW) Radwaste X

A4.01 Ability to manually operate and/or monitor in the control room:

3.4 62 A4.01 Sumo intearators

ES-401 9

Form ES-401-1 271000 (SF9 OG) Offgas X

G 2.4.4 Ability to recognize abnormal 4.5 63 indications for system operating

!parameters that are entry-level conditions for emergency and abnormal ooeratina orocedures.

288000 (SF9 PVS) Plant Ventilation X

K1.04 Knowledge of the physical 2.6 64 connections and/or cause/effect relationships between PLANT VENTILATION SYSTEMS and the following: Applicable component coolina water svstem: Plant Specific 290001 (SF5 SC) Secondary Containment 1

K6.01 Knowledge of the effect that a 3.5 65 loss or malfunction of the following will have on the SECONDARY CONTAINMENT:

Reactor building ventilation: Plant-Soecific KIA Cateaorv Point Totals:

2 0

1 1

1 2

1 1/1 1 1

1/2 Grouo Point Total:

12/3

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

Form ES-401-3 Facility: Hope Creek Date of Exam: 2019 Category KIA#

Topic RO SRO-onlv IR IR 2.1.4 Knowledge of individual licensed operator responsibilities 3.3 66 related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 1 OCFR55, etc.

2.1.31 Ability to locate control room switches, controls, and 4.6 67 indications, and to determine that they correctly reflect the

1. Conduct of desired plant lineup.

Operations 2.1.1 Knowledge of conduct of operations requirements.

3.8 68 2.1.2 Knowledge of operator responsibilities during all modes of plant 4.4 94 operation.

2.1.29 Knowledge of how to conduct system lineups, such as valves, 4.0 95 breakers, switches, etc.

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

3.0 69 2.2.13 Knowledge of tagging and clearance procedures.

4.1 70

2. Equipment 2.2.5 Knowledge of the process for making design or operating 3.2 96 chanqes to the facilitv.

Control Knowledge of the process for managing maintenance activities 2.2.18 during shutdown operations, such as risk assessments, work 3.9 97 Prioritization, etc.

Subtotal 2.3.5 Ability to use radiation monitoring systems, such as fixed 2.9 71 radiation monitors and alarms, portable survey instruments, personnel monitorinq equipment, etc.

3. Radiation 2.3.7 Ability to comply with radiation work permit requirements during 3.5 72 Control normal or abnormal conditions.

2.3.11 Ability to control radiation releases.

4.3 98 Subtotal 2.4.2 Knowledge of system set points, interlocks and automatic 4.5 73 actions associated with EOP entrv conditions.

2.4.39 Knowledge of RO responsibilities in emergency plan 3.9 74 implementation.

2.4.29 Knowledge of the emergency plan.

3.1 75

4. Emergency Procedures/Plan 2.4.38 Ability to take actions called for in the facility emergency plan, 4.4 99 including supporting or acting as emergency coordinator if reauired.

2.4.25 Knowledge of fire protection procedures.

3.7 100 Subtotal Tier 3 Point Total 10 7

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