ML15163A244

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Draft - Outlines (Folder 2)
ML15163A244
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/17/2015
From: Brian Fuller
Operations Branch I
To: Suzanne Dennis
Public Service Enterprise Group
Shared Package
ML14254A267 List:
References
TAC U01904
Download: ML15163A244 (23)
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Text

ES-401 Written Examination Outline Form ES-401-1 Facility: Hope Creek 2015 Date of Exam: 02/23/15 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4561234 *

,.-j-~---t-~~-t-~~,.-j-~~~-r-~~--j 1.

3 3 2 3 20 4 3 7 Emergency

& 2 1 2 7 2 1 3 Plant Evolutions Tier Totals 4 4 4 4 27 6 4 10 1 3 2 2 3 2 2 3 2 2 2 3 26 3 2 5 2.

Plant 2 2 2 0 1 1 12 0 3 0 3 Systems Tier Totals 4 3 3 4 3 4 5 2 3 3 4 38 6 2 8 1 2 3 4 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 3 3 2 2 2 2 1 2 Ensure that at least two topics from every applicable KIA category are sampled within each tier of Note: 1. the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the

'Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding 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 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.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. The generic (G) KlAs 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 KIA's
8. On the following pages, enter the KIA 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 KlAs that are linked to 10CFR55.43 1

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) IR Q#

EA 2.03 - Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND Above APRM Downscale or x REACTOR POWER ABOVE APRM 4.4 76 Unknown/ 1 DOWNSCALE OR UNKNOWN : SBLC tank level 295003 Partial or Complete 2.2.12- Equipment Control: Knowledge Loss of AC/ 6 x of surveillance procedures 4.1 77 EA2.01 - Ability to determine and/or 295031 Reactor Low Water interpret the following as they apply to Level/2 x REACTOR LOW WATER LEVEL:

4.6 78 Reactor water level

.. 2.4.6 - Emergency Procedures I Plan:

295028 High Drywell Temperature I 5 x Knowledge of EOP mitigation 4.7 79 strateqies.

.. AA2.03 - Ability to determine and/or 295004 Partial or Total Loss interpret the following as they apply to of DC Pwr / 6 x PARTIAL OR COMPLETE LOSS OF 2.9 80

... > D.C. POWER: Battery voltaqe AA2.03 - Ability to determine and/or interpret the following as 295018 Partial or Total Loss . they apply to PARTIAL OR COMPLETE ofCCW / 8 x LOSS OF COMPONENT 3.5 81 COOLING WATER: Cause for partial or complete loss 2.4.47 - Emergency Procedures I Plan:

Ability to diagnose and recognize trends 295026 Suppression Pool High Water Temp. I 5 x in an accurate and timely manner 4.2 82 utilizing the appropriate control room reference material.

EK1 .01 - Knowledge of the operational implications of the following concepts as 295028 High Drywell Temperature I 5 x they apply to HIGH DRYWELL 3.5 39 TEMPERATURE : Reactor water level measurement AK1 .03 - Knowledge of the operational 295001 Partial or Complete implications of the following concepts as Loss of Forced Core Flow x they apply to PARTIAL OR COMPLETE 3.6 40 Circulation / 1 & 4 LOSS OF FORCED CORE FLOW CIRCULATION: Thermal limits AK1 .01 - Knowledge of the operational implications of the following concepts as 295004 Partial or Total Loss of DC Pwr/ 6 x they apply to PARTIAL OR COMPLETE 2.9 41 LOSS OF D.C. POWER : tAutomatic load shedding: Plant-Specific AK2.03 - Knowledge of the 295016 Control Room interrelations between CONTROL Abandonment I 7 x ROOM ABANDONMENT and the 2.9 42 following: Control room HVAC AK2.06 - Knowledge of the 295019 Partial or Total Loss interrelations between PARTIAL OR of Inst. Air I 8 x *.

COMPLETE LOSS OF INSTRUMENT 2.8 43

. AIR and the following: Offgas system AK2.07 - Knowledge of the 295006 SCRAM / 1 x c:,(.;. interrelations between SCRAM and the 4.0 44

'>>*'*; followinq: Reactor pressure control EK3.04 - Knowledge of the reasons for 295026 Suppression Pool the following responses as they apply to High Water Temp. I 5 x SUPPRESSION POOL HIGH WATER 3.7 45 TEMPERATURE: SBLC injection 2

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) IR EK3.01 - Knowledge of the reasons for the following responses as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above APRM Downscale or x REACTOR POWER ABOVE APRM 4.1 46 DOWNSCALE OR UNKNOWN :

Unknown/ 1 Recirculation pump trip runback: Plant-Specific AA 1.03 - Ability to operate and/or 700000 Generator Voltage monitor the following as they apply to and Electric Grid x '

GENERATOR VOLTAGE AND 3.8 47 Disturbances ,,, ELECTRIC GRID DISTURBANCES:

'~

Voltaoe Regulator Controls EA 1.03 - Ability to operate and/or monitor the following as they apply to 295038 High Off-site Release Rate/ 9 x HIGH OFF-SITE RELEASE RATE: 3.7 48 Process liquid radiation monitoring system AA 1.04 - Ability to operate and/or 295021 Loss of Shutdown monitor the following as they apply to Cooling 14 x LOSS OF SHUTDOWN COOLING :

3.7 49 Alternate heat removal methods AA 1.02 - Ability to operate and/or monitor the following as they apply to 295018 Partial or Total Loss ofCCW 18 x PARTIAL OR COMPLETE LOSS OF 3.3 50 COMPONENT COOLING WATER:

System loads EA2.01 - Ability to determine and/or 295030 Low Suppression interpret the following as they apply to Pool Water Level I 5 x LOW SUPPRESSION POOL WATER 4.1 51 LEVEL : Suppression pool level AA2.04 - Ability to determine and/or 295023 Refueling Ace interpret the following as they apply to Cooling Mode I 8 x REFUELING ACCIDENTS : Occurrence 3.4 52 of fuel handling accident AA2.02 - Ability to determine and/or interpret the following as they apply to 295003 Partial or Complete Loss of AC/ 6 x PARTIAL OR COMPLETE LOSS OF 4.2 53 A.G. POWER : Reactor power,

' pressure, and level 2.4.1 - Emergency Procedures I Plan:

295024 High Drywell Pressure/ 5 x Knowledge of EOP entry conditions and 4.6 54 immediate action steps.

295031 Reactor Low Water 2.4.18 - Emergency Procedures I Plan:

'X 3.3 55 Level/2 Knowledoe of specific bases for EOPs.

2.2.38 - Equipment Control: Knowledge 295025 High Reactor Pressure/ 3 x of conditions and limitations in the 3.6 56 facility license.

AA2.13 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Need for 3.2 57 emeroency plant shutdown AA2.08 - Ability to determine and/or 295005 Main Turbine interpret the following as they apply to Generator Trip I 3 x MAIN TURBINE GENERATOR TRIP:

3.2 58 Electrical distribution status KIA Category Totals: 3 3 2 4 5/4 3/3 Group Point Total:

I 2017 3

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) IR Q#

EA2.01 - Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation x  :

HIGH SECONDARY CONTAINMENT 3.9 83 Levels/ 9 AREA RADIATION LEVELS: Area radiation levels 2.4.41 - Emergency Procedures I Plan:

295010 High Drywell Pressure 15 c:; ,','

x Knowledge of the emergency action 4.6 84 level thresholds and classifications EA2.03 - Ability to determine and I or interpret the following as they apply to 500000 High CTMT Hydrogen Conc. / 5 13-85 x HIGH PRIMARY CONTAINMENT 3.8 85 HYDROGEN CONCENTRATIONS:

Combustible limits for Drywell AK1 .03 - Knowledge of the operational implications of the following concepts as 295002 Loss of Main Condenser Vac I 3 x they apply to LOSS OF MAIN 3.6 59 CONDENSER VACUUM : Loss of heat sink AK2.01 - Knowledge of the interrelations between HIGH REACTOR 295007 High Reactor Pressure/ 3 x PRESSURE and the following: 3.5 60 Reactor/turbine pressure regulating system

':* AK3.02 - Knowledge of the reasons for 295022 Loss of CRD Pumps I the following responses as they apply to 1

x LOSS OF CRD PUMPS: CROM high 2.9 61 temperature EA 1.03 - Ability to operate and monitor the following as they apply to HIGH 500000 High CTMT Hydrogen Conc. / 5 x CONTAINMENT HYDROGEN 3.4 62 CONTROL: Containment atmosphere control system AA2.06 - Ability to determine and/or 295020 Inadvertent Cont. interpret the following as they apply to Isolation I 5 & 7 x INADVERTENT CONTAINMENT 3.4 63 ISOLATION: Cause of isolation 295035 Secondary 2.4.11 - Emergency Procedures I Plan:

Containment High Differential Knowledge of abnormal condition 4.0 64 Pressure/ 5 procedures.

K3.02 - Knowledge of the reasons for 295032 High Secondary the following responses as they apply to Containment Area x HIGH SECONDARY CONTAINMENT 3.6 65 Temperature I 5 AREA TEMPERATURE: Reactor SCRAM.

KIA Category Totals: 1 1 2 1 1/2 1/1 Group Point Total: 7/3 I

4

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G IR Q#

1 2 3 4 5 6 1 3 4 2.2.37 - Equipment Control:

Ability to determine operability 217000 RCIC

"* x and/or availability of safety 4.6 86 related equipment.

230000 RHR/LPCI 2.1.32 - Conduct of Operations:

Torus/Suppression Pool x Ability to explain and apply 4.0 87 Spray Mode system limits and precautions.

A2.02 - Ability to (a) predict the

... impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use 212000 RPS x procedures to correct, control, or 3.9 88 mitigate the consequences of those abnormal conditions or

... operations: RPS bus power supply failure A2.12 - Ability to (a) predict the

. impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use 206000 HPCI x procedures to correct, control, or 3.5 89 mitigate the consequences of those abnormal conditions or operations: Loss of room cooling: BWR-2,3,4 A2.01 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based 215004 Source Range on those predictions, use Monitor x *,

procedures to correct, control, or 2.9 90

..... those abnormal conditions or mitigate the consequences of

.. I*

operations: Power supply deqraded K1 .02 - Knowledge of the physical connections and/or cause- effect relationships 262001 AC Electrical Distribution x between A.C. ELECTRICAL 3.3 1

  • ... *. DISTRIBUTION and the following: D.C. electrical i *. distribution
, K1 .06 - Knowledge of the physical connections and/or cause- effect relationships between RHR/LPCI

INJECTION MODE (PLANT SPECIFIC) and the following:

203000 RHR/LPCI:

Injection Mode x Knowledge of the physical 3.9 2 connections and/or cause effect relationships between RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) and the following: Automatic depressurization 5

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G IR Q#

1 2 3 4 5 6 1 3 4 K2.01 - Knowledge of electrical 218000 ADS x .. power supplies to the following: 3.1 3 ADS looic K2.01 - Knowledge of electrical 215004 Source Range Monitor x power supplies to the following: 2.6 4 SRM channels/detectors K3.09 - Knowledge of the effect

  • + that a loss or malfunction of the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam Supply Shutoff x ISOLATION 3.4 5 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on followinq: Main steam system K3.02 - Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING 205000 Shutdown Cooling x SYSTEM (RHR SHUTDOWN 3.2 6 COOLING MODE) will have on following: Reactor water level:

Plant-Specific K4.01 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and or 300000 Instrument Air x interlocks which provide for the 2.8 7 f;

following: Manual/automatic transfers of control K4.01 - Knowledge of

    • . STANDBY GAS TREATMENT SYSTEM design feature(s) 261000 SGTS x and/or interlocks which provide 3.7 8 for the following: Automatic system initiation K5.08 - Knowledge of the operational implications of the following concepts as they apply 206000 HPCI x to HIGH PRESSURE COOLANT 3.0 9 INJECTION SYSTEM : Vacuum breaker operation: BWR-2,3,4

--*. K5.01- Knowledge of the operational implications of the following concepts as they apply 212000 RPS x to REACTOR PROTECTION 3.3 10 SYSTEM : Specific logic arranoements K6.01 - Knowledge of the effect 400000 Component that a loss or malfunction of the Cooling Water x ., ,.,

following will have on the 2.7 11 CCWS: Valves

    • . K6.04 - Knowledge of the effect 1** that a loss or malfunction of the 209001 LPCS x following will have on the LOW 2.8 12 PRESSURE CORE SPRAY SYSTEM : D.C. power A 1.01 - Ability to predict and/or monitor changes in parameters

.. : '*' associated with operating the 215003 IRM x INTERMEDIATE RANGE 3.4 13 MONITOR (IRM) SYSTEM controls including: Detector position 6

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System # I Name A2 G IR Q#

1 2 3 4 5 6 1 3 4 A 1.04 - Ability to predict and/or monitor changes in parameters associated with operating the 259002 Reactor Water Level Control x REACTOR WATER LEVEL 3.6 14 CONTROL SYSTEM controls including: Reactor water level control controller indications

*/' *'. *. A2.09 - Ability to (a) predict the

impacts of the following on the EMERGENCY GENERATORS

. (DIESEL/JET) ; and (b} based 264000 EDGs 1*: x  : on those predictions, use 3.7 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of A.C. power A2.01 - Ability to (a) predict the impacts of the following on the UNINTERRUPTABLE POWER

,>-,' SUPPLY (A.CJD.C,); and (b) 262002 UPS (AC/DC) X. based on those predictions, use 2.6 16 procedures to correct, control, or mitigate the consequences of

/ y.: those abnormal conditions or operations: Under voltage A3.01 - Ability to monitor automatic operations of the D.C.

263000 DC Electrical ELECTRICAL DISTRIBUTION Distribution x including: Meters, dials, 3.2 17 recorders, alarms, and indicating liqhts A3.07 - Ability to monitor automatic operations of the 211000 SLC x STANDBY LIQUID CONTROL 3.7 18 SYSTEM including: Lights and alarms: Plant-Specific A4.01 - Ability to manually 239002 SRVs x operate and/or monitor in the 4.4 19 control room: SRVs A4.07 - Ability to manually 217000 RCIC x operate and/or monitor in the 3.9 20

  • . control room: Reactor pressure 2.1.23 - Conduct of Operations:

Ability to perform specific system 215005 APRM I LPRM x and integrated plant procedures 4.3 21 during all modes of plant operation.

2.4.3 - Emergency Procedures I 223002 PCIS/Nuclear Steam Supply Shutoff x Plan: Ability to identify post- 3.7 22 accident instrumentation.

K4.02 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 215005 APRM I LPRM x design feature(s) and/or 4.1 23 interlocks which provide for the

>) following: Reactor SCRAM

' *.* signals 7

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A System #I Name A2 G IR Q#

1 2 3 4 5 6 1 3 4 A 1.06 - Ability to predict and/or

monitor changes in parameters associated with operating the 215003 IRM INTERMEDIATE RANGE 3.3 24 x MONITOR (IRM) SYSTEM

. controls including: Lights and alarms

K1 .02 - Knowledge of the physical connections and/or cause- effect relationships 206000 HPCI x between HIGH PRESSURE 4.0 25 COOLANT INJECTION SYSTEM and the following:

Reactor water level: BWR-2,3,4 2.1.25 - Conduct of Operations:

211000 SLC *; Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 26 KIA Category Totals: 3 2 2 3 2 2 3 213 2 2 3/2 Group Point Total: 26/5 I

8

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G IR 1 2 3 4 5 6 1 3 4 #

.*. A2.08 - Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and {b) based on those predictions, use procedures to 202001 Recirculation .X 3.4 91 correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow mismatch: Plant-Soecific A2.10 - the CONTROL ROD DRIVE HYDRAULIC SYSTEM ;

and (b) based on those predictions, use procedures to correct, 201001 CRD Hydraulic x control, or mitigate the 3.6 92 consequences of those

. abnormal conditions or operations: tLow HCU accumulator pressure/hiah level A2.03 - Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS ; and {b) based on those predictions, use 288000 Plant Ventilation x procedures to correct, control, 3.7 93 or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident: Plant-Specific K1 .08 - Knowledge of the physical connections and/or cause- effect relationships 201001 CRD Hydraulic x between CONTROL ROD 3.4 27 DRIVE HYDRAULIC SYSTEM and the following: Reactor manual control system K2.02 - Knowledge of electrical 226001 RHR/LPCI: CTMT Spray Mode x power supplies to the following: 2.9 28 Pumps K3.03 - Knowledge of the effect that a loss or malfunction of the 290002 Reactor Vessel Internals x REACTOR VESSEL 3.3 29 INTERNALS will have on followina: Reactor power K4.03 - Knowledge of MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS design 245000 Main Turbine Gen./ Aux.

x feature(s) and/or interlocks 2.7 30 which provide for the following:

Sealing to prevent hydrogen leakaae

,,'/

K5.02 - Knowledge of the operational implications of the 234000 Fuel Handling ' following concepts as they apply Equipment x to FUEL HANDLING 3.1 31 EQUIPMENT : tFuel handling equipment interlocks 9

ES-401 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System # I Name A2 G IR 1 2 3 4 5 6 1 3 4 #

K6.07 - Knowledge of the effect that a loss or malfunction of the 259001 Reactor following will have on the Feedwater x REACTOR FEEDWATER 3.8 32 I>** .

SYSTEM : Reactor water level control svstem A 1.1 O - Ability to predict and/or monitor changes in parameters associated with operating the 230000 RHR/LPCI:

Torus/Pool Spray Mode x RHR/LPCI: 3.7 33

              • TORUS/SUPPRESSION POOL SPRAY MODE controls includino: Svstem lineup A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 201002 RMCS x . ) REACTOR MANUAL 2.7 34 CONTROL SYSTEM controls
  • ,.*),

including: Control rod position A3.02 - Ability to monitor automatic operations of the 202002 Recirculation Flow Control x RECIRCULATION FLOW 3.4 35

/. CONTROL SYSTEM including:

Liqhts and alarms A4.06 - Ability to monitor automatic operations of the ROD WORTH MINIMIZER 201006 RWM x SYSTEM (RWM) (PLANT 3.2 36 SPECIFIC) including: Selected rod position indication 2.4.31 - Emergency Procedures 201003 Control Rod and I Plan: Knowledge of Drive Mechanism x annunciator alarms, indications, 4.2 37 or resoonse procedures.

K6.07 Knowledge of the effect that a loss or malfunction of the 233000 Fuel Pool following will have on the FUEL Cooling/Cleanup x POOL COOLING AND CLEAN-2.7 38 UP : Component cooling water svstems KIA Category Totals: 1 1 1 1 1 2 2 013 1 1 Group Point Total: 12/3 1/0 I

10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Hope Creek 2015 Date: 02/23/15 RO SRO-Only Category KIA# Topic IR Q# IR Q#

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

Ability to direct personnel activities inside the 2.1.9 4.5 98 control room.

1.

Conduct Knowledge of shift or short-term relief 2.1.3 3.7 66 of Operations turnover practices.

2.1.41 Knowledge of the refueling process. 2.8 67 Ability to locate and operate components, 2.1.30 4.4 75 including local controls.

Subtotal ,, ;;y**"c 3 ;,o\;#\. ;'.'> 2 Knowledge of the process for conducting 2.2.7 3.6 95 special or infrequent tests.

Knowledge of conditions and imitations in the 2.2.38 4.5 99 facility license Knowledge of tagging and clearance

2. 2.2.13 4.1 68 procedures.

Equipment Knowledge of less than or equal to one hour Control 2.2.39 Technical Specification action statements for 3.9 69 systems.

Knowledge of the bases in Technical 2.2.25 Specifications for limiting conditions for 3.2 74 operations and safety limits.

\
,:;::: ..

Subtotal 3 1flt'.~\ 2 2.3.6 Ability to approve release permits. 3.8 96 Knowledge of radiation exposure limits under 2.3.4 3.2 70 normal or emergency conditions.

3.

Knowledge of radiation monitoring systems, Radiation such as fixed radiation monitors and alarms, Control 2.3.15 2.9 71 portable survey instruments, personnel monitoring equipment, etc.

Subtotal , JI~;; 2 .','.~l1 1

4. Knowledge of the SRO's responsibilities in 2.4.40 4.5 97 Emergency emergency plan implementation.

11

ES-401 Generic Knowledge and Abilities Outline {Tier 3) Form ES-401-3 Procedures I Knowledge of events related to system Plan operation/status that must be reported to 2.4.30 internal organizations or external agencies, 4.1 100 such as the State, the NRC, or the transmission system operator.

2.4.25 Knowledge of fire protection procedures. 3.3 72 Knowledge of the operational implications of 2.4.20 3.8 73 EOP warnings, cautions, and notes.

Subtotal . 2 . .* :';* 2 Tier 3 Point Total  : 10 r;:.;S{l!l; 1

7 12

ES-401 Record of Rejected K/A's Form ES-401-4 Randomly Tier I Group Reason for Rejection Selected KIA 2.1.27 - Knowledge of system purpose and/or function.

Topic not discriminatory at the SRO level.

A2.08 - Ability to (a) predict the impacts of the following on the 2/2(#91) 202001 I 2.1.27 RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Recirculation flow mismatch: Plant-Specific Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Operating controls is not an SRO function. Additionally, this KIA is tested in the operating exam frequently.

3 (#100) 2.4.50 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.

Knowledge of the physical connections and/or cause- effect relationships between RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) and the following: Plant air systems: Plant-Specific The only relationship Plant Air has with RHR is via testable check valves. There are no operator functions associated with these 2 I 1 (#2) 203000 I K1 .12 valves and they are only looked at during a flow verification test for the RHR loop. Low discriminatory value for a licensed operator exam.

Randomly selected K1 .06: Automatic depressurization Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM : Fuel thermal time constant.

2 I 1 (#10) 212000 I K5.01 This is a GFES topic - see 293009 K1 .29 & K1 .30.

Selected K5.02 - Specific logic arrangements Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM :

ADS.

2/1(#12) 209001 I K6.11 The ADS system has been oversampled, see questions 2 & 3.

Randomly selected K6.04: D.C. Power 13

ES-401 Record of Rejected K/A's Form ES-401-4 Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following: Effects of detector aging on LPRM/APRM readings.

2 I 1 (#23) 215005 I K4.06 Very low discriminatory value. More of a GFES topic.

Randomly selected K4.02 Reactor SCRAM signals K2.01 - Knowledge of electrical power supplies to the following:

IRM channels/detectors.

Very low discriminatory value. Electrical supply topic oversampled. See #3, #4 2/1 (#24) 215003 I K2.01 Randomly selected A1 .06 - Ability to predict and/or monitor changes in parameters associated with operating the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including: Lights and alarms Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident signal.

2 I 2 (#38) 233000 I A2.16 Could not write discriminating question at the RO level due to very limited procedural guidance. This KIA had very low rating factor (2.5)

Randomly selected K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the FUEL POOL COOLING AND CLEAN-UP: Component cooling water systems A2.01 - Ability to (a) predict the impacts of the following on the RADWASTE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System rupture The Radwaste system is not operated by the licensed operators 2/1 (#34) 268000 I A2.01 and the controls are in a separate Radwaste Control Room.

Randomly selected A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the RADWASTE controls including: Radiation Levels AK3.01 - Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Reactor and turbine trip criteria.

1 /1 (#47) 70000 I AK3.01 Hope Creek abnormal procedures for grid disturbance do not have a bases document for describing specific reasons for turbine trip or reactor scram criteria. The assumption is grid stability and reactor safety. However, the correct answer to the question would not have any documentation for support and 14

ES-401 Record of Rejected K/A's Form ES-401-4 specific plausible distractors are not available.

Randomly selected Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Voltaqe Regulator Controls AK1 .01 - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Classifications by type.

1 / 1 (#57) 600000 I AK2.01 Very low discriminatory value for a licensed operator exam.

Randomly selected AA2. 13 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Need for emerqency plant shutdown 2A 18 - Knowledge of specific bases for EOPs.

This KIA was previously used at Q#55.

3/4 (#74) 2.4.18 Randomly selected 2225. - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

A1 .01 - Ability to predict and/or monitor changes in parameters associated with operating the RADWASTE controls including:

Radiation Levels Similar concept addressed in #48.

2/2(#34) 268000 I A 1.01 Randomly selected 201002 - A1 .02 -Ability to predict and/or monitor changes in parameters associated with operating the REACTOR MANUAL CONTROL SYSTEM controls including:

Control rod position K4.03 - Knowledge of STANDBY GAS TREATMENT SYSTEM design feature(s) and/or interlocks which provide for the following: Moisture removal 2 / 1 (#8) 261000 I A4.03 Moisture removal for FRVS is minutia, is not operationally discriminating at the licensed operator leveL Randomly selected K4.01 - Automatic system initiation 15

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 2/23/15 Examination Level: RO~ SRO D Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

Complete Daily Surveillance Log. (ZZ016)

Conduct of Operations D,S Operator completes required Daily Surveillance Log entries in accordance with HC.OP-DL.ZZ-0026. (Items 61-74)

Perform Power Changes During Operation-Single Loop Operations (ZZ04 7)

Conduct of Operations M,S Operator performs Section 5.1, Jet Pump Operability Verification, of HC.OP-ST.BB-0007 and identifies and reports any Unsatisfactory information Isolate Leak (ZZ048) [2013 NRC]

Operator IDENTIFIES the mechanical and electrical Equipment Control M,S components, and their required positions, to ISOLATE, VENT, AND DRAIN aleak identified on an ECCS system pipe using controlled station Mechanical Drawin s.

Radiation Control Perform Licensed Operator Review of MEES.(ZZ014)

Emergency Procedures/Plan M,S Operator performs the Licensed Operator Review of the Major Equipment and Electrical Status (MEES) Form.

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • 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 (2: 1)

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Generating Station Date of Examination: 2/23/15 Examination Level: ROD SRO ~ Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Complete an Action Statement Log Entry. (ZZ029)

Conduct of Operations D,R Operator completes a manual Action Statement log entry for the failure of a containment isolation valve, AND submits for CONCURRENCE REVIEW in accordance with OP-HC-108-115-1001.

Review Operations Logs In Use During A Shift (ZZ049)

Conduct of Operations N,R Operator performs the CRS review of Attachment 3 of OP-HC-108-116-1001, Spent Fuel Pool Decay Heat Load Determination.

Review Power Distribution Lineup. (ZZ022)

Equipment Control M,R Operator performs the SM/CRS review of the completed HC.OP-ST.ZZ-0001.and identifies applicable Technical Specification requirements.

Determine Liquid Radwaste Rad Monitor CTB Weir Flow (ZZ050) [2013 NRC]

Radiation Control D,P,R Operator performs the Control Room Supervisor review, and correction, of HG.OP DL.ZZ 0026 Surveillance Log Classify an event.

Emergency Procedures/Plan D,S Operator classifies an event and makes notifications within identified Critical Times in accordance with EP-HC-111-101 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :::; 4 for SROs & 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 Generating Station Date of Examination: 2/23/15 Exam Level: RO [2J SRO-I [2J SRO-U D Operating Test No: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. REACTOR PROTECTION SYSTEM (SB013)

A,D,E 7 Operator resets RPS, identifies a control rod out of position and reseats the control rod in accordance with HC.OP-SO.SB-0001.

b. RWCU (BG003)

E,N 2 Operator responds to a containment isolation and restores RWCU IAW HC.OP-AB.CONT-0002.

c. CRDH SYSTEM (BF012)

A,D,E,L 1 Operator responds to a loss of CRD regulating function in accordance with HC.OP-AB.IC-0001.

d. CONTROL ROOM HVAC (GK003)

Operator places Control Area Ventilation Train B in-service EN,N 9 without coolingin accordance with Steps 5.8.1 through 5.8.5 of HC.OP-SO.GK-0001.

e. PRIMARY CONTAINMENT SYSTEM (GS011)

EN,N 5 Operator vents the Drywell, and secures venting the Drywell in accordance with HC.OP-AB.CONT-0001.

f. SACS (EG008)

A,D,E 8 Operator implements Condition A of HC.OP-AB.COOL-0002.

g. MAIN TURBINE (AC007)

A,D 3 Operator responds to an abnormal Main Turbine condition during Main Turbine roll in accordance with HC.OP-SO.AC-0001.

h. RECIRCULATION SYSTEM (BB001) RO ONLY Operator resets the Reactor Recirculation Runbacks in D,E 4 accordance with HC.OP-SO.BB-0002 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. CRDH SYSTEM (BF001)

D,R 1 Operator alternates CRDH System Flow Control Valves in accordance with Section 5.2 of HC.OP-SO.BF-0001.

j. INSTRUMENT GAS (KL006)

E,EN,N 5 Operator overrides a valve containment isolation signal in accordance with HC.OP-AB.COMP-0002

k. 120 VAC Distribution (PN004)

A,N 6 Operator removes a 120 VAC inverter from service IAW HG.OP-SO.PN-0001

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant <::1/<::1/<::1 (EN)gineered safety feature - I - I <::1 (control room system)

(L)ow-Power I Shutdown <::1/<::1/<::1 (N)ew or (M)odified from bank including 1(A) <::2/<::2/<::1 (P)revious 2 exams :5 3 I :5 3 I :5 2 (randomly selected)

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

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 1 Op-Test No.: 2015 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 84% power. Power lowered for RFP maintenance.

Turnover:

Place RFP in service. Raise Reactor power to 100%.

New Event Malf. Event Event No. No. Type* Description N(BOP) 1 Place RFP In Service N(SRO)

R(ATC) 2 Raise Reactor Power with Recirculation System R(SRO)

C(ATC) 3 C(SRO) Recirculation Pump Runaway TS( SRO)

C(BOP) 4 C(SRO) Loss of 100482 TS( SRO) 5 M(ALL) LOCA C(ATC) 6 RPS Failure-ATWS/ARI Scram Successful C(SRO)

C(BOP) 7 HPCI Injection Valve Failures-Loss of Condensate C(SRO)

  • (N)ormal, (R)eactivity, (l)nstrument, (C )om ponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 2 Op-Test No.: 2015 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 95% Power. Power reduction in progress for a rod pattern adjustment.

Turnover:

Swap EHC pumps. Reduce power to 85%. Hold for Reactor Engineer review of plant conditions.

ESG-073 modified.

Event Malf. Event Event No. No. Type* Description N(BOP) 1 EHC Pump Swap N(SRO)

R(ATC) 2 Lower Power With Control Rods and Recirculation Flow R(SRO) l(ATC) 3 l(SRO) Flow Unit Failure TS( SRO) 4 C(ALL) EHC System Leak 5 M(ALL) ATWS-Main Turbine Trip-Bypass Valve Failure C(BOP) 6 Failure of SBLC to Automatically Initiate C(SRO)

C(ATC) 7 CRD Pump trip- EOP Implementation Failure C(SRO)

  • (N)ormal, (R)eactivity, (l)nstrument, (C )om ponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 3 Op-Test No.: 2015 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 100% Power.

Turnover:

Maintain 100% power.

ESG-002 Modified Event Malf. Event Event No. No. Type* Description R(ATC) 1 R(SRO) FWH Leak C(BOP)

C(ATC) 2 C(SRO) Inadvertent SBLC System Actuation TS(SRO) 3 TS(SRO) Loss of 100410 4 M(ALL) Loss of Offsite Power C(BOP) 5 Auto Start Failure of EDGs C(SRO)

C(BOP) 6 RCIC Overspeed Trip C(SRO)

C(ATC) 7 SACS Pump Trip C(SRO)

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: 4 Op-Test No.: 2015 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 100% Power.

Turnover:

Maintain 100% power.

ESG-082 Modified Event Malf. Event Event No. No. Type* Description N(BOP) 1 Containment 02 Weekly Surveillance Test N(SRO)

C(BOP)

R(ATC) 2 SRV Open/Closes R(SRO)

TS( SRO)

C(BOP) 3 Earthquake- Service Air Compressor Trip C(SRO)

C(ATC) 4 RWCU Pump Leak-Failure to Automatically Isolate C(SRO) 5 C(ALL) Air Leak w/Multiple Rod Drift -Scram 6 M(ALL) LOP-Station Blackout C(BOP) 7 LOCA Requiring Steam Cooling-RCIC Isolation C(SRO)

C(BOP) 8 RHR Injection Failure C(SRO)

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39
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