ML15163A244

Hope Creek - Draft - Outlines (Folder 2)

ML15163A244
Person / Time
Site:	Hope Creek
Issue date:	02/17/2015
From:	Fuller B J Operations Branch I
To:	Suzanne Dennis Public Service Enterprise Group
Shared Package
ML14254A267	List: IR 05000354/2015301 ML15048A126 ML15100A040 ML15100A041 ML15100A042 ML15163A241 ML15163A242 ML15163A243 ML15163A244 ML15163A245 ML15163A246 ML16145A244
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TAC U01904
Download: ML15163A244 (23)

Text

ES-401 Facility:

Tier 1. Emergency

& Plant Evolutions

2. Plant Systems Hope Creek 2015 Group K 1 K 2 K 3 Written Examination Outline Date of Exam: 02/23/15 RO KIA Category Points K K K A A A A 4561234 G

• Form ES-401-1 SRO-Only Points Total A2 G* Total 2 Tier Totals 1 2 Tier Totals 3 3 2 3 1 2 4 4 4 4 3 2 2 3 2 2 3 2 2 2 3 2 2 0 1 1 4 3 3 4 3 4 5 2 3 3 4 20 4 3 7 7 2 1 3 27 6 4 10 26 3 2 5 12 0 3 0 3 38 6 2 8 3. Generic Knowledge

& Abilities Categories 1 3 2 3 3 2 4 2 3 4 10 7 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. 3. 4. 5. 6. 7.

• 8. 9. 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.1.b of ES-401, for guidance regarding elimination of inappropriate KIA 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 KIA categories.

The generic (G) Kl 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.1.b of ES-401 for the applicable KIA's 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. 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 1 OCFR55.43 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) EA 2.03 -Ability to determine and/or 295037 SCRAM Conditions interpret the following as they apply to Present and Reactor Power x SCRAM CONDITION PRESENT AND Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown/ 1 DOWNSCALE OR UNKNOWN : SBLC tank level 295003 Partial or Complete x 2.2.12-Equipment Control: Knowledge Loss of AC/ 6 of surveillance procedures EA2.01 -Ability to determine and/or 295031 Reactor Low Water x interpret the following as they apply to Level/2 REACTOR LOW WATER LEVEL: Reactor water level .. 2.4.6 -Emergency Procedures I Plan: 295028 High Drywell x Knowledge of EOP mitigation Temperature I 5 strateqies.

.. AA2.03 -Ability to determine and/or 295004 Partial or Total Loss x interpret the following as they apply to of DC Pwr / 6 PARTIAL OR COMPLETE LOSS OF ... > D.C. POWER: Battery voltaqe AA2.03 -Ability to determine and/or interpret the following as 295018 Partial or Total Loss x they apply to PARTIAL OR COMPLETE ofCCW / 8 . LOSS OF COMPONENT COOLING WATER: Cause for partial or complete loss 2.4.47 -Emergency Procedures I Plan: 295026 Suppression Pool Ability to diagnose and recognize trends High Water Temp. I 5 x in an accurate and timely manner utilizing the appropriate control room reference material.

EK1 .01 -Knowledge of the operational 295028 High Drywell implications of the following concepts as Temperature I 5 x they apply to HIGH DRYWELL 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 Circulation / 1 & 4 LOSS OF FORCED CORE FLOW CIRCULATION:

Thermal limits AK1 .01 -Knowledge of the operational 295004 Partial or Total Loss implications of the following concepts as of DC Pwr/ 6 x they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : tAutomatic load shedding:

Plant-Specific AK2.03 -Knowledge of the 295016 Control Room x interrelations between CONTROL Abandonment I 7 ROOM ABANDONMENT and the following:

Control room HVAC AK2.06 -Knowledge of the 295019 Partial or Total Loss x interrelations between PARTIAL OR of Inst. Air I 8 *. COMPLETE LOSS OF INSTRUMENT . AIR and the following:

Offgas system AK2.07 -Knowledge of the 295006 SCRAM / 1 x c:,(.;. interrelations between SCRAM and the '>>*'*; followinq:

Reactor pressure control EK3.04 -Knowledge of the reasons for 295026 Suppression Pool x the following responses as they apply to High Water Temp. I 5 SUPPRESSION POOL HIGH WATER TEMPERATURE:

SBLC injection 2 IR Q# 4.4 76 4.1 77 4.6 78 4.7 79 2.9 80 3.5 81 4.2 82 3.5 39 3.6 40 2.9 41 2.9 42 2.8 43 4.0 44 3.7 45 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) EK3.01 -Knowledge of the reasons for 295037 SCRAM Conditions the following responses as they apply to Present and Reactor Power SCRAM CONDITION PRESENT AND Above APRM Downscale or x REACTOR POWER ABOVE APRM Unknown/ 1 DOWNSCALE OR UNKNOWN : 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 Disturbances ELECTRIC GRID DISTURBANCES:

,,, , Voltaoe Regulator Controls EA 1.03 -Ability to operate and/or 295038 High Off-site Release monitor the following as they apply to Rate/ 9 x HIGH OFF-SITE RELEASE RATE: Process liquid radiation monitoring system AA 1.04 -Ability to operate and/or 295021 Loss of Shutdown x monitor the following as they apply to Cooling 14 LOSS OF SHUTDOWN COOLING : Alternate heat removal methods AA 1.02 -Ability to operate and/or 295018 Partial or Total Loss monitor the following as they apply to ofCCW 18 x PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System loads EA2.01 -Ability to determine and/or 295030 Low Suppression x interpret the following as they apply to Pool Water Level I 5 LOW SUPPRESSION POOL WATER LEVEL : Suppression pool level AA2.04 -Ability to determine and/or 295023 Refueling Ace x interpret the following as they apply to Cooling Mode I 8 REFUELING ACCIDENTS

Occurrence of fuel handling accident AA2.02 -Ability to determine and/or 295003 Partial or Complete interpret the following as they apply to Loss of AC/ 6 x PARTIAL OR COMPLETE LOSS OF A.G. POWER : Reactor power, ' pressure, and level 295024 High Drywell 2.4.1 -Emergency Procedures I Plan: Pressure/

5 x Knowledge of EOP entry conditions and immediate action steps. 295031 Reactor Low Water 'X 2.4.18 -Emergency Procedures I Plan: Level/2 Knowledoe of specific bases for EOPs. 295025 High Reactor 2.2.38 -Equipment Control: Knowledge Pressure/

3 x of conditions and limitations in the facility license. AA2.13 -Ability to determine and 600000 Plant Fire On-site I 8 x interpret the following as they apply to PLANT FIRE ON SITE: Need for emeroency plant shutdown AA2.08 -Ability to determine and/or 295005 Main Turbine x interpret the following as they apply to Generator Trip I 3 MAIN TURBINE GENERATOR TRIP: Electrical distribution status KIA Category Totals: 3 3 2 4 5/4 3/3 Group Point Total: 3 IR 4.1 46 3.8 47 3.7 48 3.7 49 3.3 50 4.1 51 3.4 52 4.2 53 4.6 54 3.3 55 3.6 56 3.2 57 3.2 58 I 2017 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 A 1 A2 G KIA Topic(s) EA2.01 -Ability to determine and/or 295033 High Secondary

interpret the following as they apply to Containment Area Radiation x HIGH SECONDARY CONTAINMENT Levels/ 9 AREA RADIATION LEVELS: Area radiation levels 295010 High Drywell Pressure 2.4.41 -Emergency Procedures I Plan: x Knowledge of the emergency action 15 c:; ,',' level thresholds and classifications EA2.03 -Ability to determine and I or 500000 High CTMT Hydrogen interpret the following as they apply to x HIGH PRIMARY CONTAINMENT Conc. / 5 13-85 HYDROGEN CONCENTRATIONS:

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

Pressure/

3 Reactor/turbine pressure regulating . :* system ':* AK3.02 -Knowledge of the reasons for 295022 Loss of CRD Pumps I x the following responses as they apply to 1 LOSS OF CRD PUMPS: CROM high temperature EA 1.03 -Ability to operate and monitor 500000 High CTMT Hydrogen the following as they apply to HIGH x CONTAINMENT HYDROGEN Conc. / 5 CONTROL: Containment atmosphere control system AA2.06 -Ability to determine and/or 295020 Inadvertent Cont. x interpret the following as they apply to Isolation I 5 & 7 INADVERTENT CONTAINMENT ISOLATION:

Cause of isolation 295035 Secondary 2.4.11 -Emergency Procedures I Plan: Containment High Differential Knowledge of abnormal condition 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 Temperature I 5 AREA TEMPERATURE:

Reactor SCRAM. KIA Category Totals: 1 1 2 1 1/2 1/1 Group Point Total: 4 IR Q# 3.9 83 4.6 84 3.8 85 3.6 59 3.5 60 2.9 61 3.4 62 3.4 63 4.0 64 3.6 65 I 7/3 ES-401 System #I Name K K K 1 2 3 217000 RCIC 230000 RHR/LPCI Torus/Suppression Pool Spray Mode 212000 RPS 206000 HPCI 215004 Source Range Monitor 262001 AC Electrical Distribution x 203000 RHR/LPCI:

Injection Mode x Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 2.2.37 -Equipment Control: "* x Ability to determine operability and/or availability of safety related equipment.

2.1.32 -Conduct of Operations:

x Ability to explain and apply system limits and precautions.

A2.02 -Ability to (a) predict the ... impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on x those predictions, use procedures to correct, control, or 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) x based on those predictions, use procedures to correct, control, or 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 x *, on those predictions, use procedures to correct, control, or ... mitigate the consequences of .. those abnormal conditions or .. I* operations:

Power supply deqraded K1 .02 -Knowledge of the *. physical connections and/or cause-effect relationships between A.C. ELECTRICAL 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:

Knowledge of the physical connections and/or cause effect relationships between RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) and the following:

Automatic depressurization 5 IR Q# 4.6 86 4.0 87 3.9 88 3.5 89 2.9 90 3.3 1 3.9 2 ES-401 System #I Name K K K 1 2 3 218000 ADS x 215004 Source Range x Monitor 223002 PCIS/Nuclear x Steam Supply Shutoff 205000 Shutdown Cooling x 300000 Instrument Air 261000 SGTS 206000 HPCI 212000 RPS 400000 Component Cooling Water 209001 LPCS 215003 IRM Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 K2.01 -Knowledge of electrical

.. power supplies to the following:

ADS looic K2.01 -Knowledge of electrical power supplies to the following:

SRM channels/detectors K3.09 -Knowledge of the effect *+ that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION 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 SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following:

Reactor water level: Plant-Specific K4.01 -Knowledge of (INSTRUMENT AIR SYSTEM) x design feature(s) and or interlocks which provide for the f; following:

Manual/automatic transfers of control K4.01 -Knowledge of **. STANDBY GAS TREATMENT x SYSTEM design feature(s) and/or interlocks which provide for the following:

Automatic system initiation K5.08 -Knowledge of the operational implications of the x following concepts as they apply to HIGH PRESSURE COOLANT INJECTION SYSTEM : Vacuum breaker operation:

BWR-2,3,4

--*. K5.01-Knowledge of the operational implications of the x following concepts as they apply to REACTOR PROTECTION SYSTEM : Specific logic arranoements K6.01 -Knowledge of the effect x that a loss or malfunction of the ., ,., following will have on the CCWS: Valves * *. K6.04 -Knowledge of the effect 1** that a loss or malfunction of the x following will have on the LOW PRESSURE CORE SPRAY SYSTEM : D.C. power A 1.01 -Ability to predict and/or monitor changes in parameters

.. : '*' associated with operating the x INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including:

Detector position 6 IR Q# 3.1 3 2.6 4 3.4 5 3.2 6 2.8 7 3.7 8 3.0 9 3.3 10 2.7 11 2.8 12 3.4 13 ES-401 System # I Name K K K 1 2 3 259002 Reactor Water Level Control 264000 EDGs 262002 UPS (AC/DC) 263000 DC Electrical Distribution 211000 SLC 239002 SRVs 217000 RCIC 215005 APRM I LPRM 223002 PCIS/Nuclear Steam Supply Shutoff 215005 APRM I LPRM Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A 1.04 -Ability to predict and/or monitor changes in parameters associated with operating the x REACTOR WATER LEVEL 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 1*

x : on those predictions, use 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) X. based on those predictions, use 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. x ELECTRICAL DISTRIBUTION including:

Meters, dials, recorders, alarms, and indicating liqhts A3.07 -Ability to monitor automatic operations of the x STANDBY LIQUID CONTROL SYSTEM including:

Lights and alarms: Plant-Specific A4.01 -Ability to manually x operate and/or monitor in the control room: SRVs A4.07 -Ability to manually x operate and/or monitor in the *. control room: Reactor pressure 2.1.23 -Conduct of Operations:

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

2.4.3 -Emergency Procedures I x Plan: Ability to identify post-accident instrumentation.

K4.02 -Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER x RANGE MONITOR SYSTEM design feature(s) and/or >) interlocks which provide for the following:

Reactor SCRAM ' *.* signals 7 IR Q# 3.6 14 3.7 15 2.6 16 3.2 17 3.7 18 4.4 19 3.9 20 4.3 21 3.7 22 4.1 23 ES-401 System #I Name K K K 1 2 3 215003 IRM 206000 HPCI x 211000 SLC KIA Category Totals: 3 2 2 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K A A2 A A G 4 5 6 1 3 4 A 1.06 -Ability to predict and/or : monitor changes in parameters associated with operating the x INTERMEDIATE RANGE MONITOR (IRM) SYSTEM . controls including:

Lights and alarms : K1 .02 -Knowledge of the physical connections and/or cause-effect relationships between HIGH PRESSURE COOLANT INJECTION SYSTEM and the following:

Reactor water level: BWR-2,3,4

• ; 2.1.25 -Conduct of Operations:

Ability to interpret reference materials, such as graphs, curves, tables, etc. 3 2 2 3 213 2 2 3/2 Group Point Total: 8 IR Q# 3.3 24 4.0 25 3.9 26 I 26/5 ES-401 System # I Name K K K 1 2 3 202001 Recirculation 201001 CRD Hydraulic 288000 Plant Ventilation 201001 CRD Hydraulic x 226001 RHR/LPCI:

CTMT Spray Mode x 290002 Reactor Vessel Internals x 245000 Main Turbine Gen./ Aux. 234000 Fuel Handling Equipment Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 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 .X predictions, use procedures to 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 x procedures to correct, control, or mitigate the 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 x those predictions, use procedures to correct, control, 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 between CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following:

Reactor manual control system K2.02 -Knowledge of electrical power supplies to the following:

Pumps K3.03 -Knowledge of the effect that a loss or malfunction of the REACTOR VESSEL INTERNALS will have on followina:

Reactor power K4.03 -Knowledge of MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS design x feature(s) and/or interlocks which provide for the following:

Sealing to prevent hydrogen leakaae . K5.02 -Knowledge of the ,,'/ operational implications of the ' following concepts as they apply x to FUEL HANDLING EQUIPMENT

tFuel handling equipment interlocks 9 IR Q # 3.4 91 3.6 92 3.7 93 3.4 27 2.9 28 3.3 29 2.7 30 3.1 31 ES-401 System # I Name K K K 1 2 3 259001 Reactor Feedwater 230000 RHR/LPCI:

Torus/Pool Spray Mode 201002 RMCS 202002 Recirculation Flow Control 201006 RWM 201003 Control Rod and Drive Mechanism 233000 Fuel Pool Cooling/Cleanup KIA Category Totals: 1 1 1 Form ES-401-1 Hope Creek 2015 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 K6.07 -Knowledge of the effect that a loss or malfunction of the x following will have on the I>** . REACTOR FEEDWATER SYSTEM : Reactor water level control svstem A 1.1 O -Ability to predict and/or monitor changes in parameters associated with operating the x RHR/LPCI:

• • • • • • • TORUS/SUPPRESSION POOL SPRAY MODE controls includino:

Svstem lineup A 1.02 -Ability to predict and/or monitor changes in parameters x associated with operating the . ) REACTOR MANUAL *,.*), CONTROL SYSTEM controls including:

Control rod position A3.02 -Ability to monitor automatic operations of the x RECIRCULATION FLOW /. CONTROL SYSTEM including:

Liqhts and alarms A4.06 -Ability to monitor automatic operations of the x ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) including:

Selected rod position indication 2.4.31 -Emergency Procedures x I Plan: Knowledge of annunciator alarms, indications, or resoonse procedures.

K6.07 Knowledge of the effect that a loss or malfunction of the x following will have on the FUEL POOL COOLING AND CLEAN-UP : Component cooling water svstems 1 1 2 2 013 1 1 1/0 Group Point Total: 10 IR Q # 3.8 32 3.7 33 2.7 34 3.4 35 3.2 36 4.2 37 2.7 38 I 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility:

Hope Creek 2015 Date: 02/23/15 Category KIA# RO SRO-Only Topic IR Q# IR Q# 2.1.2 Knowledge of operator responsibilities during 4.4 94 all modes of plant operation.

2.1.9 Ability to direct personnel activities inside the 4.5 98 control room. 1. Conduct 2.1.3 Knowledge of shift or short-term relief 3.7 66 of Operations turnover practices.

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

' Subtotal ,, ;;y**"c 3 ;,o\;#\. ;'.'> 2 2.2.7 Knowledge of the process for conducting 3.6 95 special or infrequent tests. 2.2.38 Knowledge of conditions and imitations in the 4.5 99 facility license 2. 2.2.13 Knowledge of tagging and clearance 4.1 68 Equipment procedures.

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

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

2 1 4. 2.4.40 Knowledge of the SRO's responsibilities in 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 2.4.20 Knowledge of the operational implications of 3.8 73 EOP warnings, cautions, and notes. Subtotal ;>*: . 2 . .* :';* 2 Tier 3 Point Total : 10 r 1;:.;S{l!l; 7 12 ES-401 Record of Rejected K/A's Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA 2.1.27 -Knowledge of system purpose and/or function.

Topic not discriminatory at the SRO level. 2/2(#91) 202001 I 2.1.27 A2.08 -Ability to (a) predict the impacts of the following on the 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 2/1 (#34) 268000 I A2.01 The Radwaste system is not operated by the licensed operators 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: SRO D Operating Test Number: Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Code* D,S M,S M,S Describe activity to be performed Complete Daily Surveillance Log. (ZZ016) 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) 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 components, and their required positions, to ISOLATE, VENT, AND DRAIN aleak identified on an ECCS system pipe using controlled station Mechanical Drawin s. 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 Radiation Control D,P,R Flow (ZZ050) [2013 NRC] 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) Operator resets RPS, identifies a control rod out of position and A,D,E 7 reseats the control rod in accordance with HC.OP-SO.SB-0001.

b. RWCU (BG003) Operator responds to a containment isolation and restores E,N 2 RWCU IAW HC.OP-AB.CONT-0002.

c. CRDH SYSTEM (BF012) Operator responds to a loss of CRD regulating function in A,D,E,L 1 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) Operator vents the Drywell, and secures venting the Drywell in EN,N 5 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) Operator responds to an abnormal Main Turbine condition during A,D 3 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 1 N(BOP) Place RFP In Service N(SRO) 2 R(ATC) 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 1 00482 TS( SRO) 5 M(ALL) LOCA 6 C(ATC) RPS Failure-ATWS/ARI Scram Successful C(SRO) 7 C(BOP) 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 1 N(BOP) EHC Pump Swap N(SRO) 2 R(ATC) 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 6 C(BOP) Failure of SBLC to Automatically Initiate C(SRO) 7 C(ATC) 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 5 C(BOP) Auto Start Failure of EDGs C(SRO) 6 C(BOP) RCIC Overspeed Trip C(SRO) 7 C(ATC) 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 1 N(BOP) Containment 02 Weekly Surveillance Test N(SRO) C(BOP) 2 R(ATC) SRV Open/Closes R(SRO) TS( SRO) 3 C(BOP) Earthquake-Service Air Compressor Trip C(SRO) 4 C(ATC) 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 7 C(BOP) LOCA Requiring Steam Cooling-RCIC Isolation C(SRO) 8 C(BOP) RHR Injection Failure C(SRO) * (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39