ML18099A093
| ML18099A093 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  (NPF-057) |
| Issue date: | 02/02/2018 |
| From: | Todd Fish Operations Branch I |
| To: | Public Service Enterprise Group |
| Shared Package | |
| ML17138A098 | List: |
| References | |
| CAC U01958 | |
| Download: ML18099A093 (24) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility:
Hope Creek Scenario No.:
1 Op-Test No.:
Examiners:
Operators:
Initial Conditions:
100% power.
Turnover:
Maintain 100% QOWer. Swap SACS Pumps for UQCOming maintenance.
Critical Tasks:
- 1. Reduce power to below License Limit. 2. Erner. DeQressurize {Containment}.
Event Malf.
Event Event No.
No.
Type*
Description
- 1.
N(BOP)
- 2.
l(SRO)
R(ATC)
- 3.
R(SRO)
- 4.
TS(SRO)
Loss Of Essential 480V Bus 1 OB420
- 5.
C(ALL)
Earthquake/Condensate Pipe Break
- 6.
(P)
M(ALL)
- 7.
C(ATC)
Penetration Failure to Isolate C(SRO)
- 8.
C(BOP)
Drywell Spray Valve Failure C(SRO)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (P)=Previous 2 NRC Examinations
Appendix D Scenario Outline Form ES-D-1 Facility:
Hope Creek Scenario No.:
2 Op-Test No.:
Examiners:
Operators:
Initial Conditions:
95% power with power ascension to 100% power in progress.
Turnover:
Raise power to 100%.
Critical Tasks:
- 1. Reduce 12ower. 2. Manual scram/isolation. 3. Isolate leak.
Event Malf.
Event Event No.
No.
Type*
Description
- 1.
(P)
R(ATC)
Raise Reactor Power with Recirculation System N(SRO)
!(ATC)
- 2.
(P)
R(SRO)
Recirculation Pump Runaway TS(SRO)
- 3.
TS(SRO)
Failure of RRCS Level Transmitter
- 4.
C(BOP)
Trip of a Fuel Pool Cooling Pump C(SRO)
- 5.
M(ALL)
Fuel Cladding/MSIV Isolation.
- 6.
C(ATC)
C(SRO)
- 7.
C(BOP)
RCIC Failure To Auto Initiate C(SRO)
- 8.
C(BOP)
(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (P)=Previous 2 NRC Examinations
Appendix D Scenario Outline Form ES-D-1 Facility:
Hope Creek Scenario No.:
3 Op-Test No.:
Examiners:
Operators:
Initial Conditions:
100% power.
Turnover:
Maintain 100% power.
Critical Tasks:
- 1. Start EOG. 2. Erner. Depressurize {RPV Level). 3. RPV flooding.
Event Malf.
Event Event No.
No.
Type*
Description
- 1.
C(ATC)
C(BOP)
- 2.
(P)
R(ATC)
TS(SRO)
- 3.
(P)
TS(SRO)
Loss of 1OD410 125VDC 1 E Bus
- 4.
C(ALL)
Main Turbine High Vibration
- 5.
(P)
C(ALL)
- 6.
(P)
C(BOP)
EDG Failure to Auto-start C(SRO)
- 7.
(P)
M(ALL)
- 8.
l(ALL)
Loss of RPV Level Indication (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor (P)=Previous 2 NRC Examinations
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Hope Creek Date of Examination:
2/12/2018 Examination Level: RO D SRO
~
Operating Test Number:
Administrative Topic (see Note)
Type Describe activity to be performed Code*
Conduct of Operations D,P,R Complete the Daily Surveillance Logs. (ZZ017)
Conduct of Operations D,R Complete OP-HC-108-114-1001 Attachment 3.
(ZZ052)
Review Operations Department Tests for Equipment Control D,R Completeness and Compliance with Acceptance Criteria. (ZZ027)
Verify and Close Out today's Containment Radiation Control M,R Prepurge Cleanup, lnerting, Or Pressure Control Valve Permit. (ZZ059)
Utilize The ECG To Determine The Emergency Emergency Plan N,R Classification And/Or Reportability Of An Event And/Or Plant Condition (ESG016)
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(~ 3 for ROs; ~ 4 for SROs and RO retakes)
(N)ew or (M)odified from bank (e:: 1)
(P)revious 2 exams (~ 1, randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility:
Hope Creek Date of Examination:
2/12/2018 Examination Level: RO
~ SRO D Operating Test Number:
Administrative Topic (see Note)
Type Describe activity to be performed Code*
Conduct of Operations N,S Complete A Control Console Log For Conditions 4 And 5. (ZZ058)
Conduct of Operations M,S Conduct Reactor Recirculation Single Loop Operation. (ZZ013)
Equipment Control D,P,R Perform A Manual Tagout When ESOMS is Unavailable. (ZZ055)
Radiation Control Perform the Licensed Operator Review of the Emergency Plan M,S Major Equipment and Electrical Status (MEES)
Form. (ZZ060)
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 (:5 3 for ROs; :5 4 for SROs and RO retakes)
(N)ew or (M)odified from bank(~ 1)
(P)revious 2 exams (:5 1, randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Hope Creek Date of Examination:
2/12/2018 Exam Level: RO D SRO-I D SRO-U
~
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.
Reactor Protection /Control Rod Out Of Position (SB013)
A,D,L,P,S 7
- b.
C.
High Pressure Coolant Injection/Place HPCI into the Full Flow Test A,D,EN,P,S 4
Mode (BJ014)
- d.
- e.
- f.
- g.
- h.
Reactor Condensate/Start a Primary Condensate Pump (AD001)
A,N,S 2
In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
- j.
D.C. Electrical Distribution/Respond To A LOP (NJ002)
E,EN,L,N,R 6
- k.
Reactor Manual Control System/Bypass Rod (SF012)
E,M 1
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.
I
- Type Codes I
Criteria for R /SR0-1/SRO-U I
(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 e:1/.::1/.::1 (EN)gineered safety feature e: 1/.:: 1/.:: 1 (control room system)
(L)ow-Power/Shutdown 2: 1/.:: 1/.:: 1 (N)ew or (M)odified from bank including 1 (A) e: 2/2: 2/.:: 1 (P)revious 2 exams
$. 3/$. 3/$. 2 (randomly selected)
(R)CA 2: 1/.:: 1/.:: 1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Hope Creek Date of Examination:
2/12/2018 Exam Level: RO D SRO-I
~ 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.
Reactor Protection /Control Rod Out Of Position (SB013)
A,D,L,P,S 7
- b.
C.
High Pressure Coolant Injection/Place HPCI into the Full Flow Test A,D,EN,P,S 4
Mode (BJ014)
- d.
Main Turbine Generator and Auxiliary/Roll the Main Turbine (AC004)
A,D,S 3
- e.
A.C. Electrical Distribution/Shift The Breaker Alignment (KJ008)
D,EN,S 6
- f.
Component Cooling Water/Place RAGS Pump BP209 In Service A,D,S 8
(ED002)
- g.
Plant Ventilation Systems/Place Control Area Ventilation In-Service D,EN,S 9
Without Cooling (GK003)
- h.
Reactor Condensate/Start a Primary Condensate Pump (AD001)
A,N,S 2
In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
Residual Heat Removal/Line up for Alternate Injection Using Fire D,E,EN,L 2
Water (BC007)
- j.
D.C. Electrical Distribution/Respond To A LOP (NJ002)
E,EN,L,N,R 6
- k.
Reactor Manual Control System/Bypass Rod (SF012)
E,M 1
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.
I
- Type Codes I
Criteria for R /SR0-1/SRO-U I
(A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank S 9/S 8/S 4 (E)mergency or abnormal in-plant
- 11::::11::::1 (EN)gineered safety feature
- 1/:::: 1 /:::: 1 (control room system)
(L)ow-Power/Shutdown
- 1/::::1/::::1 (N)ew or (M)odified from bank including 1(A)
- 2/:::: 2/:2: 1 (P)revious 2 exams s 3/s 3/s 2 (randomly selected)
(R)CA
- 11::::11::::1 (S)imulator
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:
Hope Creek Date of Examination:
2/12/2018 Exam Level: RO
[2J 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.
Reactor Protection /Control Rod Out Of Position (SB013)
A,D,L,P,S 7
- b.
Recirculation Flow Control/Reset Scoop Tube Lockup (88002)
D,S 1
C.
High Pressure Coolant Injection/Place HPCI into the Full Flow Test A,D,EN,P,S 4
Mode (BJ014)
- d.
Main Turbine Generator and Auxiliary/Roi\\ the Main Turbine (AC004)
A,D,S 3
- e.
A.C. Electrical Distribution/Shift The Breaker Alignment (KJ008)
D,EN,S 6
- f.
Component Cooling Water/Place RAGS Pump BP209 In Service A,D,S 8
(ED002)
- g.
Plant Ventilation Systems/Place Control Area Ventilation In-Service D,EN,S 9
Without Cooling (GK003)
- h.
Reactor Condensate/Start a Primary Condensate Pump (AD001)
A,N,S 2
In-Plant Systems: 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U
- i.
Residual Heat Removal/Line up for Alternate Injection Using Fire D,E,EN,L 2
Water (BC007)
- j.
D.C. Electrical Distribution/Respond To A LOP (NJ002)
E,EN,L,N,R 6
- k.
Reactor Manual Control System/Bypass Rod (SF012)
E,M 1
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
- 5 9/::5 8/::5 4 (E)mergency or abnormal in-plant
?: 1 /?: 1 /?: 1 (EN)gineered safety feature
?: 1/?: 1/?: 1 (control room system)
( L )ow-Power/Shutdown
?: 1/?: 1/?: 1 (N)ew or (M)odified from bank including 1 (A)
?: 2/?: 2/?: 1 (P)revious 2 exams
- 5 3/::5 3/::5 2 (randomly selected)
(R)CA
?: 1/?: 1/?: 1 (S)imulator
ES-401 Written Examination Outline Form ES-401-1 Facility:
Hope Creek 2018 NRC Exam Date of Exam:
02/12/18 SRO-Only Points Tier Group K
K K
G 1
2 3
Total A2 G*
Total
- 1.
1 4
3 4
3 20 2
5 7
Emergency 2
1 1
2 1
7 1
2 3
Plant Tier Evolutions Totals 5
4 6
4 27 3
7 10 1
3 3
2 3
3 1
3 2
3 1
2 26 3
2 5
- 2.
Plant 2
1 0
2 1
1 2
1 1
1 12 0
2 1
3 Systems Tier Totals 4
3 4
4 4
2 5
3 4
2 3
38 5
3 8
- 3. Generic Knowledge & Abilities 1
2 3
4 2
3 4
10 7
Note:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
Categories 2
2 3
3 2
2 1
2 Ensure that at least two topics from every applicable Kl 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 KIA is allowed if the KIA is replaced by a Kl A from another Tier 3 Category).
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.
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 D. l.b ofES-401, for guidance regarding elimination of inappropriate Kl A statements.
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.
Absent a plant specific priority, only those KAs 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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and Kl A categories.
The generic (G) K/As 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. l.b ofES-401 for the applicable K/A's.
- 8.
On the following pages, enter the Kl A numbers, a brief description of each topic, the topics' importance ratings (IR) 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 K/As that are linked to IOCFR55.43 G*
Generic Kl As
ES-401 2 OF 16 Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A 1 A2 G
KIA Topic(s) 2.4.30 - Knowledge of events related to system operation/status that must be 295006 SCRAM/ I X
reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
EA2.02 - Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power Above X
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM APRM Downscale or Unknown / I DOWNSCALE OR UNKNOWN: Reactor water level AA2.04 - Ability to determine and/or 295018 Partial or Complete Loss of interpret the following as they apply to X
PARTIAL OR COMPLETE LOSS OF CCW/8 COMPONENET COOLING WATER:
System flow 295016 Control Room 2.1.32 - Conduct of Operations: Ability to Abandonment / 7 X
explain and apply all system limits and precautions.
295038 High Off:site Release Rate 2.4.45 - Emergency Procedures/ Plan:
X Ability to prioritize and interpret the
/9 significance of each annunciator or alarm.
295024 High Drywell Pressure/ 5 X
2.4.6 - Knowledge ofEOP mitigation strategies.
2.4.30 - Knowledge of events related to 295004 Partial or Total Loss of DC system operation/status that must be Pwr/6 X
reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
AKl.04 - Knowledge of the operational 295004 Partial or Total Loss of implications of the following concepts as DCPwr/6 X
they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Effect ofbattery discharge rate on capacity EKl.02 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as Water Temp. / 5 X
they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : Steam condensation 295006 SCRAM/ I AKl.02 - Knowledge of the operational X
implications of the following concepts as they apply to SCRAM : Shutdown margin EK2.0l - Knowledge of the interrelations 295031 Reactor Low Water Level X
between REACTOR LOW WATER
/2 LEVEL and the following: Reactor water level indication EK2.02 - Knowledge of the interrelations 295037 SCRAM Conditions between SCRAM CONDITION Present and Reactor Power Above X
PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR APRM Downscale or Unknown/ I UNKNOWN and the following: RRCS:
Plant-Specific C
AK2.01 - Knowledge of the interrelations 29500 I Partial or Complete Loss between PARTIAL OR COMPLETE of Forced Core Flow Circulation / I X
LOSS OF FORCED CORE FLOW
&4 CIRCULATION and the following:
Recirculation system 295016 Control Room AK3.03 - Knowledge of the reasons for Abandonment / 7 X
the following responses as they apply to CONTROL ROOM ABANDONMENT :
Imp.
Q#
4.1 76 4.2 77 2.9 78 4.0 79 4.3 80 4.7 81 4.1 82
- 2.
8 39
- 3.
5 40
- 3.
4 41
- 4.
42 4
- 4.
43 0
- 3.
6 44
- 3.
5 45
ES-401 2 OF 16 Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #/Name Safety Function K1 K2 K3 A1 A2 G
KIA Topic(s)
Disabling control room controls
.,co:.,
EK3.06 - Knowledge of the reasons for 295025 High Reactor Pressure/ 3 X
the following responses as they apply to HIGH REACTOR PRESSURE :
Alternate rod insertion: Plant-Specific EK3.02 - Knowledge of the reasons for 295038 High Off-site Release Rate X
the following responses as they apply to
/9 HIGH OFF-SITE RELEASE RATE:
Svstem isolations AA 1.03 - Ability to operate and/or 295005 Main Turbine Generator monitor the following as they apply to Trip/3 X
MAIN TURBINE GENERATOR TRIP:
Reactor manual control/Rod control and information system AA 1.01 - Ability to operate and/or 295018 Partial or Total Loss of monitor the following as they apply to CCW/8 X
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:
Backup systems EA 1.16 - Ability to operate and/or monitor the following as they apply to 295024 High Dl)'Well Pressure/ 5 X
HIGH DRYWELL PRESSURE:
Containment/drywell vacuum breakersContainment/drywell vacuum breakers.
EA2.01 - Ability to determine and/or 295030 Low Suppression Pool X
interpret the following as they apply to Water Level/ 5 LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level AA2.17 - Ability to determine and 600000 Plant Fire On-site/ 8 X,
interpret the following as they apply to PLANT FIRE ON SITE: Systems that may be affected by the fire AA2.03 - Ability to determine and/or 295021 Loss of Shutdown Cooling X
interpret the following as they apply to
/4 LOSS OF SHUTDOWN COOLING:
Reactor water level 295019 Partial or Total Loss of 2.4.18 - Emergency Procedures/ Plan:
Inst. Air/ 8
,x Knowledge of the specific bases for EOPs.
2.4.50 - Emergency Procedures/ Plan:
700000 Generator Voltage and X.
Ability to verify system alarm setpoints Electric Grid Disturbances and operate controls identified in the alarm response manual.
2.4.9 - Emergency Procedures/ Plan:
295023 Refueling Accidents Knowledge of low power/ shutdown Cooling Mode/ 8 X
implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitii:iation stratei:iies.
AK3.05 - Knowledge of the reasons for 295003 Partial or Complete Loss X
the following responses as they apply to of AC I 6 PARTIAL OR COMPLETE LOSS OF A.C. POWER : Reactor SCRAM EK1.02 - Knowledge of the operational 295028 High Dl)'Well Temperature implications of the following concepts as X
they apply to HIGH DRYWELL
/5 TEMPERATURE: Equipment environmental qualification Kl A Category Totals:
4 3
4 3
3/2 3/5 Group Point Total:
Imp.
Q#
- 4.
46 2
- 3.
47 9
- 2.
7 48
- 3.
3 49
- 3.
50 4
- 4.
51 I
3.1 52
- 3.
53 5
- 3.
3 54
- 4.
55 2
- 3.
8 56
- 3.
57 7
2.9 58 I
20/7
ES-401 3
Hope Creek 2018 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function K1 K2 K3 A1 A2 G
KIA Topic(s)
Imp.
Q#
EA2.03 - Ability to determine and/or 295029 High Suppression Pool X
interpret the following as they apply to 3.5 83 Water Level/ 5 HIGH SUPPRESSION POOL WATER LEVEL : Drywell/containment water level 295034 Secondary Containment 2.4.41 - Emergency Procedures / Plan:
X Knowledge of the emergency action level 4.6 84 Ventilation High Radiation/ 9
}"v thresholds and classifications.
2.1.7 - Conduct of Operations: Ability to 295014 Inadvertent Reactivity evaluate plant performance and make X
operational judgements based on operating 4.7 85 Addition/ I t>>>S,,,
characteristics, reactor behavior, and instrument interpretation.
EKl.03 - Knowledge of the operational 295032 High Secondary implications of the following concepts as they apply to HIGH SECONDARY
- 3.
Containment Area Temperature I 5 X
CONTAINMENT AREA 5
59 TEMPERATURE: Secondary containment leakage detection: Plant Specific AK2.08 - Knowledge of the interrelations 295008 High Reactor Water Level X
between HIGH REACTOR WATER 3.4 60
/2 LEVEL and the following: Main turbine:
Plant-Specific EK3.0! - Knowledge of the reasons for the 295036 Secondary Containment following responses as they apply to
- 2.
High Sump/Area Water Level/ 5 X
SECONDARY CONTAINMENT HIGH 6
61 SUMP/AREA WATER LEVEL:
Emergency depressurization AAl.01 - Ability to operate and/or monitor
- 3.
295015 Incomplete SCRAM/ I X
the following as they apply to 8
62 INCOMPLETE SCRAM : CRD hydraulics AA2.03 - Ability to determine and/or 295022 Loss ofCRD Pumps/ I X
interpret the following as they apply to
- 3.
63 LOSS OF CRD PUMPS : CRD mechanism I
temperatures 295035 Secondary Containment 2.4.11 ~ Knowledge of abnormal condition
- 4.
High Differential Pressure / 5 X
procedures.
0 64 AK3.04 - Knowledge of the reasons for the 295010 High Drywell Pressure/ 5 X
following responses as they apply to HIGH
- 3.
65 DRYWELL PRESSURE : Leak 5
investigation Kl A Category Totals:
1 1
2 1
1/1 1/2 Group Point Total:
I 7/3
ES-401 System # / Name K
K K
1 2
3 264000 EDGs 211000 SLC 215005 APRM / LPRM 206000 HPCI 400000 Component Cooling Water 218000 ADS X
239002 SRVs X
206000 HPCI X
203000 RHR/LPCI: Injection Mode X
4 Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A2.06 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEUJET); and (b) based on X
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Opening normal and/or alternate power to emernencv bus A2.08 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to SCRAM 2.2.44 - Equipment Control: Ability to interpret control room indications X
to verify the status and operation of a system, and understand how operator actions and directives effect olant and system conditions.
2.2.37 - Equipment Control: Ability X
to detennine operability and / or availability of safety related equipment.
A2.02 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: High/low surge tank level Kl.OJ - Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: RHR/LPCI:
Plant-Specific K1.04 - Knowledge of the physical connections and/or cause-effect relationships between RELIEF/SAFETY VALVES and the following: Main steam K2.04 - Knowledge of electrical power supplies to the following:
Turbine control circuits: BWR-2,3,4 K2.03 - Knowledge of electrical power supplies to the following:
Initiation looic Imp Q#
3.4 86 4.2 87 4.4 88 4.6 89 3.0 90 4.0 l
3.6 2
2.5 3
2.7 4
ES-401 System # I Name K
K K
1 2
3 261000 SGTS 259002 Reactor Water Level X
Control 212000 RPS 262002 UPS (AC/DC) 215004 Source Range Monitor 26200 I AC Electrical Distribution 400000 Component Cooling Water 300000 Instrument Air 209001 LPCS 264000 EDGs 4
Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
K4.01 - Knowledge of STANDBY GAS TREATMENT X
SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic system initiation K3.02 - Knowledge of the effect that a loss or malfunction of the REACTOR WATER LEVEL CONTROL SYSTEM will have on following: Reactor feedwater system K4.08 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s)
X and/or interlocks which provide for the following: Complete control rod insertion following SCRAM siqnal qeneration K4.01 - Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design X
feature(s) and/or interlocks which provide for the following:
Transfer from preferred power to
' alternate power supplies K5.03 - Knowledge of the operational implications of the X
following concepts as they apply to SOURCE RANGE MONITOR
' (SRM) SYSTEM : Changing detector position K5.02 - Knowledge of the operational implications of the X
following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: Breaker control K6.05 - Knowledge of the effect X
that a loss or malfunction of the following will have on the CCWS: Motors K5.01 - Knowledge of the X
operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air compressors A 1.08 - Ability to predict and/or monitor changes in parameters X
associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls includinq: System lineup A 1.03 - Ability to predict and/or monitor changes in parameters associated with operating the X
EMERGENCY GENERATORS (DIESEL/JET} controls including:
Operating voltages, currents, and temperatures Imp Q#
3.7 5
3.7 6
4.2 7
3.1 8
2.8 9
2.6 10 2.8 11 2.5 12 3.3 13 2.8 14
ES-401 System # I Name K
K K
1 2
3 215003 !RM 211000 SLC (new KIA to align with system not EOP) 215005 APRM I LPRM 205000 Shutdown Cooling 217000 RCIC 263000 DC Electrical Distribution 223002 PCIS/Nuclear Steam Supply Shutoff 215005 APRM / LPRM 209001 LPCS X
4 Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A2.01 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM ; and (b) based on those predictions, X
use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded A2.01 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on X
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Pump trip A3.01 - Ability to monitor automatic operations of the AVERAGE POWER RANGE X
MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Four rod display:
Plant-Specific A3.02 - Ability to monitor automatic operations of the X
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:
Pump trips A4.06 - Ability to manually X
operate and/or monitor in the control room: Suppression pool level A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the X
D.C. ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate 2.1.31 - Ability to locate control room switches, controls, and X
indications, and to determine that they correctly reflect the desired plant lineup.
2.4.34 - Emergency Procedures
/ Plan: Knowledge of RO tasks X
performed outside the main control room during an emergency and the resultant operational effects.
C K2.01 - Knowledge of electrical power supplies to the following:
Pump power Imp Q#
2.8 15 3.5 16 3.5 17 3.2 18 3.6 19 2.5 20 4.6 21 4.2 22 2.5 23
ES-401 System # I Name K
K K
1 2
3 218000 ADS 259002 Reactor Water Level Control X
262001 AC Electrical Distribution X
Kl A Category Totals:
3 3
2 4
Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A3.04 - Ability to monitor automatic operations of the X
~
AUTOMATIC DEPRESSURIZATION SYSTEM including: Primary containment pressure K1.03 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor water level K3.01 - Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: Major system loads 3
3 1
3 2/3 3
1 2/2 Group Point Total:
Imp Q#
3.7 24 3.8 25 3.5 26 I
26/5
ES-401 System # I Name K
K K
1 2
3 214000 RPIS 202002 Recirculation Flow Control 288000 Plant Ventilation 288000 Plant Ventilation X
233000 Fuel Pool X
Cooling/Cleanup 245000 Main Turbine Gen. I Aux.
X 215002 RBM 234000 Fuel Handling Equipment 223001 Primary CTMT and Aux.
5 Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K A A2 A A G
4 5
6 1
3 4
A2.03 - Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Overtravel/in-out 2.2.42 - Ability to recognize system X
parameters that are entry-level conditions for Technical Specifications.
A2.01 - Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnonnal conditions or operations: High drywell pressure: Plant-Specific Kl.04 - Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEMS and the following: Applicable component cooling water system:
Plant-Specific K3.0l - Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on the following: Fuel pool temperature K3.03 - Knowledge of the effect that a loss or malfunction of the MAIN TURBINE GENERA TOR AND AUXILIARY SYSTEMS will have on following: Reactor power K4.01 - Knowledge of ROD BLOCK MONITOR SYSTEM X
design feature(s) and/or interlocks which provide for the following: Prevent control rod withdrawal: BWR-3,4,5 K5.01 - Knowledge of the operational implications of the
.. following concepts as they apply X
to FUEL HANDLING EQUIPMENT : Crane/hoist operation K6.11 - Knowledge of the effect that a loss or malfunction of the X
following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES:
A.C. electrical distribution Imp.
Q 3.9 91 4.6 92 3.4 93 2.6 27 3.2 28 3.9 29 3.4 30 2.9 31 3.0 32
ES-401 System # I Name K
K K
1 2
3 256000 Reactor Condensate 202002 Recirculation Flow Control 201001 CRD Hydraulic 230000 RHR/LPCI:
Torus/Pool Spray Mode 268000 Radwaste 226001 RHR/LPCI: CTMT Spray Mode Kl A Category Totals:
1 0
2 5
Form ES-401-1 Hope Creek 2018 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
A A2 A
A G
4 5
6 1
3 4
A 1.08 - Ability to predict and/or monitor changes in parameters X
associated with operating the REACTOR CONDENSATE SYSTEM controls including:
Svstem water quality A2.06 - Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b)
X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor water level: Plant-Specific A3.08 - Ability to monitor automatic operations of the X
CONTROL ROD DRIVE HYDRAULIC SYSTEM including: Drive water flow A4.02 - Ability to manually X
operate and/or monitor in the control room: Sprav valves X
2.3.11 - Ability to control radiation releases.
A 1.10 - Ability to predict and/or monitor changes in parameters associated with operating the X
RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE controls including: Emergency generator loading 1
1 1
2 1/2 1
1 1/1 Group Point Total:
Imp.
Q 2.7 33 3.3 34 3.0 35 3.8 36 3.8 37 3.0 38 I
12/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Hope Creek 2018 NRC Exam Date:
02/12/18 Category KIA#
RO SRO-Only Topic IR Q#
IR Q#
Knowledge of the station's 2.1.38 requirements for verbal 3.8 94 communications when implementinq procedures.
2.1.41 Knowledge of the refueling process.
3.7 100
- 1.
Conduct 2.1.8 Ability to coordinate personnel 3.4 66 of Operations activities outside the control room.
Ability to perform specific system 2.1.23 and integrated plant procedures 4.3 67 during all modes of plant operation.
Subtotal
.. ':i=:
2 :i:::rir 2
Knowledge of the process for 2.2.5 making design or operating 3.2 95 chanqes to the facility.
Ability to determine the expected plant configuration using design 2.2.15 and configuration control 4.3 98 documentation, such as drawings, line-ups, taq-outs, etc.
- 2.
Equipment Ability to perform pre-startup Control procedures for the facility, 2.2.1 including operating those controls 4.5 68 associated with plant equipment that could affect reactivity.
Knowledge of less than or equal to 2.2.39 one hour Technical Specification 3.9 69 action statements for systems.
Subtotal
- 'Jh 2
2 Knowledge of Radialogical Safety Procedures pertaining to licensed
- 3.
operator duties, such as response Radiation 2.3.13 to radiation monitor alarms, 3.8 96 Control containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aliqning filters, etc.
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Ability to comply with radiation 2.3.7 work permit requirements during 3.5 70 normal or abnormal conditions.
Knowledge of radiation exposure 2.3.4 limits under normal or emergency 3.2 71 conditions.
Knowledge of radiation or 2.3.14 containment hazards that may 3.4 74 arise during normal, abnormal, or emerqencv conditions or activities.
Subtotal
- ii&ffo\\
3
- .. :if.
1 2.4.29 Knowledge of the emergency plan.
4.4 97 2.4.6 Knowledge of EOP mitigation 4.7 99 strateqies.
- 4.
Emergency 2.4.25 Knowledge of fire protection 3.3 72 Procedures /
procedures.
Plan 2.4.18 Knowledge of the specific bases 3.3 73 for EOPs.
2.4.42 Knowledge of emergency 2.6 75 response facilities.
Subtotal
- )i.)frihit" 3
- tt'"
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/A's Form ES-401-4 Tier/ Group Randomly Selected Reason for Rejection KIA Emergency Procedures/ Plan: Knowledge of the specific bases for EOPs.
No Bases document for Loss of DC Pwr.
1/1 (#82) 295004 I 2.4.18 Randomly selected 2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.
Equipment Control: Knowledge of limiting conditions for operations and safety limits.
No safety limit associated with HI D/W Pressure. The associated 1/1(#81) 295024 I 2.2.22 T.S. is a 1 Hour LCO which is an RO level question topic. The KIA is not discriminating at SRO Level.
Randomly selected 2.4.6 - Knowledge of EOP mitigation strategies.
Emergency Procedures / Plan: Knowledge of EOP entry conditions and immediate action steps No EOP entries on Reactor Recirc Flow Control malfunctions.
2/2 (#92) 202002 I 2.4.1 Randomly selected 2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
600000 I AA2.12 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Location of vital equipment within fire zone.
Topic not discriminatory at the SRO level.
1 /1 (#78) 600000 I AA2.12 Randomly selected 295018 I AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENET COOLING WATER: System flow.
Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENT AIR SYSTEM: Temperature indicators.
No relationship of a loss or malfunction of a temperature 2/1 (#12) 300000 I K6.03 indicator and operation of the Instrument Air Compressor.
Randomly selected K5.01 - Knowledge of the operational implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: Air compressors.
ES-401 Record of Rejected K/A's Form ES-401-4 Emergency Procedures / Plan: Knowledge of operational implications of EOP warnings, cautions, and notes.
There are no EOP warnings, cautions, or notes that specifically 2/1 (#21) address NS4 or PCIS.
223002 /2.4.20 Randomly selected 2.1.31 -Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: Suppression pool level.
There is no direct relationship of Suppression Pool Level to the 2/1 (#24) 218000 /A3.05 automatic operation of ADS.
Randomly selected A3.04 - Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: Primary containment pressure.
Knowledge of electrical power supplies to the following: RHR pumps.
Could not write a discriminating question at the RO level.
2/2 (#28) 233000 /K2.02 Randomly selected K3.01 - Knowledge of the effect that a loss or malfunction of the FUEL POOL COOLING AND CLEAN-UP will have on the following: Fuel pool temperature.
Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Personnel protection.
There is no licensed level discriminating question. More of a generic employee training topic.
1/2(#59) 295032 /EK1.01 Randomly selected EK1.03 - Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
Secondary containment leakage detection: Plant Specific.
Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: HPCI: Plant-Specific.
No physical connection or direct relationship between HPCI and 2/1 (#25)
Digital Reactor Feedwater Control System.
259002 /K1.16 Randomly selected K1.03 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor water level.
ES-401 Record of Rejected K/A's Form ES-401-4 Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: Hydrogen recombiner: Plant-Specific Very low discriminatory value for a licensed operator exam.
The Hydrogen Recombiner does not function IAW normal, 2/2 (#32) 223001 /K6.05 abnormal, or EOPs. (SAMG)
Randomly selected K6.11 - Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES: A.G. electrical distribution.
Ability to manually operate and/or monitor in the control room:
System venting.
There are no dedicated indicators or controls from the control room for system venting of RHR in Torus Spray mode. There is 2/2 (#36) 230000 /A4.11 no procedural guidance of system venting of RHR in Torus Spray mode.
Randomly selected A4.02 - Ability to manually operate and/or monitor in the control room: Spray valves.
Conduct of Operations: Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation.
2/2 (#37) 268000 /2.1.7 No direct relationship between reactor behavior and Radwaste systems.
Randomly selected 2.3.11 - Ability to control radiation releases.
Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, coordination with the transmission system operator.
3 (#68) 2.2.17 Risk assessment is at the SRO level.
Randomly selected 2.2.1 - Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.
Ability to track Technical Specification limiting conditions for operations.
Tracking LCOs is at the SRO level.
3 (#69) 2.2.23 Randomly selected 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.
ES-401 Record of Rejected K/A's Form ES-401-4 Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following:
Primary containment oxygen content: Mark-1&11 2/1 (#5) 261000 /K3.06 No direct relationship between SGTS (RBVS/FRVS) and Primary containment oxygen concentration.
Randomly selected K4.01 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) and/or interlocks which provide for the followinq: Automatic system initiation.
Ability to manually operate and/or monitor in the control room:
Battery discharge rate: Plant-Specific No indications or controls specific to battery discharge rate in the 2/1 (#20) 263000 /A4.03 main control room.
Randomly selected A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the D.C.
ELECTRICAL DISTRIBUTION controls including: Battery charqinq/discharqinq rate. (This is outside MCR)
Ability to manually operate and/or monitor in the control room:
Voltage, current, power, and frequency on A.G. buses Similar to KIA for question #14. (Ability to predict and/or monitor changes in parameters associated with operating the 2/1 (#26) 262001 /A4.05 EMERGENCY GENERATORS (DIESEL/JET) controls including:
Operating voltages, currents, and temperatures)
Randomly selected K3.01 - Knowledge of the effect that a loss or malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: Major system loads.
Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Drywell/containment pressure:
Plant-Specific.
Similar to the KIA for question #24. (Ability to monitor automatic 2/1 (#1) 218000 /K1.04 operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including: Primary containment pressure)
Randomly selected K1.01 - Knowledge of the physical connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following:
RHR/LPCI: Plant-Specific.