ML102600085

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Final Outlines (Folder 3)
ML102600085
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/06/2010
From:
Public Service Enterprise Group
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML100560172 List:
References
TAC U01788
Download: ML102600085 (32)
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ES-401 Written Examination Outline Form ES-40 1-1 Facility: Hope Creek Station Date of Exam: August 23, 2010 SRO-Only Points Tier . Group Total A2 G* Total 1.

3 20 4 3 7 Emergency 2 1 7 2 3 Plant Evaluations

  • Tier 4 5 27 6 10 Totals 1 2 1 2.

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

  • 3. Generic Knowledge & Abilities 3 4 10 1 7 3 3 2 2 2 Note 1, Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only 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 totals (#) on Form ES-401-3, Limit SRO selections to KlAs that are linked to

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA2.05 - Ability to determine and/or interpret the following 295018 Partial or Total as they apply to PARTIAL 2.9 76 Loss of CCW I 8 OR COMPLETE LOSS OF COMPONENT COOLlI\JG WATER:

AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL 295019 Partial or Total OR COMPLETE LOSS OF 3.6 77 Loss of Inst. Air / 8 INSTRUMENT AIR:

ure AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL 295004 Partial or Total OR COMPLETE LOSS OF 3.9 78 Loss of DC Pwr f 6 D.C. POWER: Extent of partial or complete loss of D.C.

EA2.01 - Ability to determine and/or interpret the following 295030 Low Suppression as they apply to LOW 4.2 79 Pool Water Level / 5 SUPPRESSION POOL WATER LEVEL:

S 295023 Refueling Accidents I 8 295037 SCRAM Conditions 2.2.40 - Equipment Control:

Present and Reactor Power Ability to apply technical 4.7 81 Above APRM Downscale or specifications for a system.

Unknown 11 2.4.30 - Emergency Procedures / Plan; Knowledge of events related to system operation / status that must be reported to 295006 SCRAM / 1 4.1 82 internal organizations or external agencies, such as the state, the NRC, or the transmission system rator.

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KJA Topic(s)

AA2.02 - Ability to determine 600000 Plant Fire On-site I and interpret the following as 8 they apply to PLANT FIRE ON SITE: Dam sition EK1.02 - Knowledge of the operational implications of the following concepts as 295031 Reactor Low Water they apply to REACTOR 3.8 40

!Level/2 LOW WATER LEVEL:

Natural circulation: Plant Snor"tol" AK1.03 - Knowledge of the operational implications of 295006 SCRAM I 1 the following concepts as 3.7 41 they apply to SCRAM:

control AK2.09 - Knowledge of the interrelations between 295019 Partial or Total PARTIAL OR COMPLETE Loss of Inst. Air 18 x LOSS OF INSTRUMENT 3.3 42 AIR and the following:

Containment EK2.07 - Knowledge of the 295024 High Drywell interrelations between HIGH Pressure 15 x DRYWELL PRESSURE and 3.9 43 the followi : PCIS/NSSSS EK2.01 Knowledge of the 295025 High Reactor interrelations between HIGH Pressure 13 x REACTOR PRESSURE and 4.1 44 the follow RPS AK2.03 - Knowledge of the interrelations between LOSS 295021 Loss of Shutdown OF SHUTDOWN COOLING 3.6 45 Cooling 14 and the following:

RHRlShutdown Cooli EK3.02 - Knowledge of the reasons for the following 295030 Low Suppression responses as they apply to Pool Water Level 15 LOW SUPPRESSION POOL WATER LEVEL: HPCI

ES-401 Form ES-40 1-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 AA 1.08 - Ability to operate andlor monitor the following 295016 Control Room as they apply to CONTROL 4.0 47 onment /7 ROOM ABANDONMENT:

Reactor Pressure EA 1.03 - Ability to operate and/or monitor the following 295038 High Off-site as they apply to HIGH OFF 3.7 48 Release Rate I 9 SITE RELEASE RATE:

mon AA 1.02 - Ability to operate andlor monitor the following 295018 Partial or Total as they apply to PARTIAL 3.3 49 Loss of CCW / 8 OR COMPLETE LOSS OF COMPONENT COOLING WATER: m loads AA1.01 - Ability to operate andlor monitor the following 295005 Main Turbine as they apply to MAIN 3.1 50 Generator Trip / 3 TURBINE GENERATOR TRIP: Recirculation system:

cific AA2.02 - Ability to determine and/or interpret the following 295003 Partial or Complete as they apply to PARTIAL 4.2 51 Loss of AC 16 OR COMPLETE LOSS OF A. C. POWER: Reactor ressu and level EA2.04 - Ability to determine and/or interpret the following as they apply to SCRAM 295037 SCRAM Conditions CONDITION PRESENT Present and Reactor Power AND REACTOR POWER 4.0 52 Above APRM Downscale or ABOVE APRM Unknown /1 DOWNSCALE OR UNKNOWN: Suppression tem re EA2.03 - Ability to determine and/or interpret the following as they apply to 295026 Suppression Pool SUPPRESSION POOL 3.9 53 High Water Temp./5 HIGH WATER TEMPERATURE: Reactor

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KJA Topic(s) 2.1.28 - Conduct of 700000 Generator Voltage Operations: Knowledge of and Electric Grid the purpose and function of 4.1 54 Disturbances major system components and controls.

AK3.02 - Knowledge of the reasons for the following 295023 Refueling responses as they apply to Accidents I 8 x REFUELING ACCIDENTS:

3.4 55 Interlocks associated with fuel handli . ment.

2.2.25 - Knowledge of the bases in Technical 295028 High Drywell Specifications for limiting 3.2 56 Temperature / 5 conditions for operations and limits.

AK1.05 - 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 3.3 57 COMPLETE LOSS OF D.C.

POWER: Loss of breaker n

AA2.01 - Ability to determine and/or interpret the following 295001 Partial or Complete as they apply to PARTIAL Loss of Forced Core Flow OR COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION: Power/flow KJA Category Totals 342 Group Point Total:

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 AA2.02 - Ability to determine and/or interpret the following 295009 Low Reactor Water as they apply to LOW Level/2 REACTOR WATER LEVEL:

Steam flow/feed flow mismatch 2.4.45 - Emergency Procedures / Plan: Ability to 295002 Loss of Main prioritize and interpret the 4.3 84 Condenser Vacuum / 3 significance of each annunciator or alarm.

EA2.02 - Ability to determine and/or interpret the following 295032 High Secondary as they apply to HIGH Containment Area SECONDARY 3.5 85 Temperature I 5 CONTAINMENT AREA TEMPERATURE: Equipment AK1.02 - Knowledge of the operational implications of 295022 Loss of CRD X the following concepts as 3.6 59 Pumps /1 they apply to LOSS OF CRD PUMPS: Rea control AK2.01 - Knowledge of the interrelations between HIGH 295012 High Drywell X DRYWELLTEMPERATURE 3.4 .60 Temperature / 5 and the following: Drywell ventilation EK3.02 - Knowledge of the reasons for the following 295036 Secondary responses as they apply to Containment High X SECONDARY 2.8 61 Sump/Area Water Level!5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Reactor SCRAM AA1.03 - Ability to operate and/or monitor the following 295009 Low Reactor Water as they apply to LOW 3.0 62 Level /2 REACTOR WATER LEVEL:

Plant

ES-401 Form ES-401-1 Test Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 e Safety Function KIA Topic(s)

EA2.02 - Ability to determine and / or interpret the following as they apply to HIGH PRIMARY 500000 High CTMT CONTAINMENT 3.0 63 Hydrogen Cone. / 5 HYDROGEN CONCENTRATIONS:

295029 High Suppression 4.4 64 Pool Water Level / 5 295010 High Drywell 3.6 65 Pressure / 5 Drywell floor and equipment drain sum KIA Category Totals Group PointTotal: 7/3

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 L ~te~rll~/N~IK1IK2IK3.K4IK5.K6IA11 A2 IA31A41 G KIA Topic(s)

A2.09 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/..IET) ; and (b) based on those 264000 EDGs 4.1 .86 predictions, use procedures to correct!

control, or mitigate the consequences of those abnormal conditions or operations: Loss of AC.

A2.07 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those 211000 SLC predictions, use 3.2 87 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures 2.4.50 - Emergency Procedures / Plan: Ability to verify system alarm 209001 LPCS

  • 4.0 88 setpoints and operate controls identified in the 262001 AC maintenance activities,
  • Electrical such as degraded power* 4.2 89 Distribution sources, on the status of limiting conditions for 259002 Reactor Water Level Control

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 K1.02 - Knowledge of the physical connections and/or cause- effect .

relationships between 215004 Source Range Monitor x SOURCE RANGE MONITOR (SRM)

SYSTEM and the following: Reactor manual control K1.01 - Knowledge of the physical connections and/or cause- effect 262001 AC

  • x relationships between Electrical 3.8 2 A.C. ELECTRICAL Distribution DISTRIBUTION and the following: Emergency nerators K2.01 - Knowledge of electrical power supplies 2150031RM 2.5 3 to the following: IRM channels/detectors A3.02 - Ability to monitor automatic operations of the REACTOR 1259002 Reactor

!Water Level Control!

WATER LEVEL 3.4 4 CONTROL SYSTEM including: Changes in reactor water level K3.02 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC 218000 ADS DEPRESSURIZATION 4.5 5 SYSTEM will have on following: Ability to rapidly depressurize the reactor K5.06 - Knowledge of the operational implications of the 239002 SRVs following concepts as 2.7 6 x they apply to RELIEF/SAFETY VALVES; Vacuum

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 K4.04 - Knowledge of LOW PRESSURE CORE SPRAY SYSTEM 209001 LPCS X design feature(s) and/or 3.0 7 interlocks which provide for the following: Line Break Detection K4.04 - Knowledge of EMERGENCY GENERATORS (DIESEL/,JET) design 264000 EDGs X 2.6 8 feature(s) and/or interlocks which provide for the following: Field flash K5.06 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE 215005 APRM I POWER RANGE X 2.5 9 LPRM MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

Assignment of LPRM's to specific APRM channels K5.01 - Knowledge of the operational implications of the following concepts as they apply to STANDBY 211000 SLC X 2.7 *10 LIQUID CONTROL SYSTEM: Effects of the moderator temperature coefficient of reactivity on the boron K6.01 - Knowledge of the effect that a loss or malfunction of the 262002 UPS following will have on the 2.7 11 (ACIDC) UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.): A.G.

electrical

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #lName KJA Topic(s)

K6.05 - Knowledge of the effect that a loss or 400000 Com ponent malfunction of the 2.8 12 Cooling Water following will have on the CCWS: Motors A 1.08 Ability to predict and/or monitor changes in parameters associated with operating the HIGH 206000 HPCI PRESSURE COOLANT 4.1 13 INJECTION SYSTEM controls including:

System lineup: BWR 4

A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the 203000 RHRlLPCI:

RHRlLPCI: INJECTION 3.9 14 Injection Mode MODE (PLANT SPECIFIC) controls including: Reactor ressure A2.10 Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING 205000 Shutdown MODE); and (b) based 2.9 15 Cooling on those predictions, use procedures to correct.

control, or mitigate the consequences of those abnormal conditions:

Valve ration

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 A2.01 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those 217000 RCIC 3.8 16 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation al A3.01 - Ability to monitor automatic operations of 263000 DC the D.C. ELECTRICAL Electrical DISTRIBUTION 3.2 17.

Distribution 261000 SGTS 3.2 18

Fan start 223002 Ability to PCIS/Nuclear manually operate and/or 3.6 19 Steam Supply monitor in the control Shutoff room: Valve closures A4.04 - Ability to manually operate and/or monitor in the control .

212000 RPS 3.9 20 room: Bypass SCRAM instrument volume high level SCRAM s nal 2.4.35 - Emergency Procedures / Plan:

Knowledge of local 300000 Instrument Air auxiliary operator tasks 3.8 21 during emergency and the resultant operational effects.

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KJA Topic(s) 2.2.39 - Equipment Control: Knowledge of 205000 Shutdown less than or equal to one 3.9 22 Cooling hour technical specification action statements for K4.02 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or 212000 RPS X interlocks which provide 3.5 23 for the following: The prevention of a reactor SCRAM following a sin e co nt failure K5.03 - Knowledge of the operational implications of the following concepts as 217000 RCIC X they apply to REACTOR 2.6 24 CORE ISOLATION COOLING SYSTEM (RCIC): Differential re indication K6.02 - Knowledge of the effect that a loss or 262001 AC malfunction of the Electrical X following will have on the 3.6 25 Distribution A.C. ELECTRICAL DISTRIBUTION: Offsite r

K4.09 - Knowledge of HIGH PRESSURE COOLANT INJECTION 206000 High SYSTEM Pressure design feature(s) and/or 3.8 26 Injection X

interlocks which provide for the following:

Automatic flow control:

BWR-2 4 KJA Category Totals

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topic(s)

A2.02 - Ability to (a) predict the im pacts of the following on the SECONDARY CONTAINMENT; and (b) based on those 290001 Secondary predictions, use 3.7 91 Containment procedures to correct, control, or mitigate the consequences of those abnormal conditions 272000 Radiation

.4.0 92 Monitoring 241000 ReactorlTurbine 4.6 93 Pressure Regulator 259001 Reactor Feedwater X 3.2 27 and the following:

Condensate K2.03 - Knowledge of 201001 CRD electrical power supplies X 3.5 28

  • Hydraulic to the following: Backup SCRAM valve solenoids K3.05 - Knowledge of the effect that a loss or malfunction of the 202001 RECIRCULATION Recirculation X 3.3 29 SYSTEM will have on following: Recirculation system MG sets: Plant

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2 K4.03 - Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or 233000 Fuel Pool IX interlocks which provide I 2.8 30 Cooling/Cleanup for the following:

Maintenance of adequate pool K5.01 - Knowledge of the operational implications of the following concepts as they apply to 272000 Radiation RADIATION X 3.2 31

  • Monitoring MONITORING SYSTEM:

Hydrogen injection operation's effect on process radiation indications: Plant K6.06 - Knowledge of the effect that a loss or malfunction of the 219000 RHRlLPCI: following will have on the Torus/Pool Cooling X RHRlLPCI: 3.7 32 Mode TORUS/SUPPRESSION POOL COOLING MODE: Suppression Pool A 1.10 - Ability to predict and/or monitor changes in parameters associated with operating the 226001 RHRlLPCI:

RHRlLPCI: 3.0 33 CTMT Spray Mode CONTAINMENT SPRAY SYSTEM MODE controls.

including: Emergency rator load

ES-401 Form ES-401-1 Test Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topic(s)

A2.07 - Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE; and (b) based on those predictions, use 215001 Traversing procedures to correct, 3.4 34 In-core Probe control, or mitigate the consequences of those abnormal conditions or operations: Failure to retract during accident conditions: Mark 1&1 A3.06 - Ability to monitor automatic operations of the MAIN TURBINE 245000 Main GENERATOR AND 2.5 35 Turbine Gen. I Aux.

AUXILIARY SYSTEMS including: Turbine lube oil ure A4.06 Ability to manually operate and/or

  • 230000 RHRlLPCI: monitor in the control Torus/Pool Spray room: Valve logic reset 4.0 36 Mode following automatic initiation of LPCI/RHR in n'QI"TI"n mode 2.1.31 - Conduct of Operations: Ability to locate control room switches, controls, and 215002 RBM 4.6 37 indications, and to determine that they correctly reflect the desired ant line A4.06 - Ability to manually operate and/or 271000 Off-gas monitor in the control room: System indicating hts and alarms KIA Category Totals Group Point Total:

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Hope Creek Generating Station Date: 08/23/2010 I Category KA# Topic RO SRO-Only IR Q# IR Q#

  • Ability to explain and apply all system 2.1.32 3.8 66 limits and precautions. I I
  • Knowledge of procedures, guidelines, I 2.1.37 *or limitations associated with reactivity . 4.3 67 management. I
1. Conduct of Ability to interpret reference materials, 2.1.25 3.9 75 Operations such as graphs, curves, tables, etc.

I 2.1.41 Knowledge of the refueling process. 3.7 I 94 Knowledge of conservative decision 2.1.39 I 4.3 99 making practices.

Subtotal I.,,;..~;<~:f* 3 '<~ .. I 2 lAbility to manipUlate the console 2.2.2 controls as required to operate the

! I I

'facility between shutdown and 4.6 I 68 i designated power levels. I Knowledge of less than or equal to one 2.2.39 hour4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> technical specification action 3.9 73 statements for systems.

2.2.12 Knowledge of surveillance procedures. 3.7 74

2. Equipment Control -I: Ability to perform pre-startup

! procedures for the facility, including 1 operating those controls associated 4.4 95 with plant equipment that could affect

  • reactivity. I Knowledge of pre- and post 2.2.21 4.1 98 maintenance operability requirements.

I Subtotal i~i 3 .. 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of Radiological Safety  !

[ i Principles pertaining to licensed operator duties, such as containment 2.3.12 3.2 70 entry requirements, fuel handling 1 responsibilities, access to locked high-radiation areas, aligning filters, etc. I Knowledge of Radiological Safety  !

Procedures pertaining to licensed 1 operator duties, such as response to 2.3.13 .radiation monitor alarms, containment 3.4 71

3. Radiation entry requirements, fuel handling Control responsibilities, access to locked high radiation areas, aligning filters, etc.

I 2.3.11 Ability to control radiation releases. 4.3 96 Subtotal ... 2 ",>,1 1 Knowledge of EOP entry conditions and 2.4.1 4.6 69 immediate action steps.

Ability to recognize abnormal indications for system operating 2.4.4 parameters which are entry-level 4.5 72 conditions for emergency and abnormal 1 4 . Emergency operating procedures.

Procedures I Plan Knowledge of EOP mitigation 2.4.6 4.7 97 strategies.

2.4.25 Knowledge of fire protection procedures 3.7 100 1 l;:'*

tI

[Subtotal 2 2 Tier 3 Point Total; II 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Selected Tier 1 Group Reason for Rejection KA (RO #1) - Knowledge of the physical connections andlor cause-effect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following: Rod Control and Information 2/1 2150041 K1 .03 System: Plant Specific. This topic does not apply at HC.

Randomly selected K1.02 - Reactor manual control (RO #4) Knowledge of electrical power supplies to the following: Feedwater Coolant Injection (FWCI) initiation logic:

FWCIIHPCI. FWCI does not apply at Hope Creek 2/1 2590021 K2.02 Randomly selected - A3.02 - Ability to monitor automatic operations of the REACTOR WATER LEVEL CONTROL SYSTEM including: Changes in reactor water level

  • (RO #6) - Knowledge of the effect that a loss or malfunction of ithe RELIEF/SAFETY VALVES will have on following: Ability to rapidly depressurize the reactor. Same topic as RO #5 2/1 2390021 K3.03 Randomly selected K5.06 - Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Vacuum breaker operation

,(RO #7) - Knowledge of LOW PRESSURE CORE SPRAY SYSTEM design feature(s) and/or interlocks which provide for 2/1 209001 I K4.02 the following: Prevents Water Hammer. Not discriminating at the

.license level.

IRandoml selected K4.04 Line ~~~~~----------~~ Break Detection (RO #9) - K5.02 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: Effects of voids on LPRM indication. Topic is GFES 2/1 2150051 K5.02 .knowledge and is not referenced in system operating or lesson plan procedures.

Randomly selected K5.06 - Assignment of LPRM's to specific APRM channels (RO #2) - K1.04 - Knowledge of the physical connections and/or cause- effect relationships between AC. ELECTRICAL DISTRIBUTION and the following: Uninterruptible power supply.

Similar to RO #11 topic K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the 2/1 262001 1 K1.04 UNINTERRUPTABLE POWER SUPPLY (AC'/D.C.) : AC.

electrical power.

Randomly selected K1.01 - Emergency generators

' (RO #16) - A2.05 - Ability to (a) predict the impacts of the 2/1 2170001 A2.05 following on the REACTOR CORE ISOLATION COOLING I' --_ _ _ _--'- . . . . . . ____ ~___L:S:....;Y...:S:....:T..::cE::.:.cM_'_(.LIR.c:..;;;..CIC); anQjb} based on those redictions, use

ES-401 Record of Rejected KIA's Form ES-401-4

!prOCedures to correct, control, or mitigate the consequences of I

those abnormal conditions or operations: D.C. power loss. D.C.

ds oversampled. See questions 17, 57, 78.

i Randomly selected A2.01 - System initiation signal (RO #20) - Ability to manually operate and/or monitor in the control room: Individual system relay status: Plant-Specific.

Does not apply at Hope Creek.

I 2/1 2120001 A4.08 Randomly selected A4.04 - Bypass SCRAM instrument volume high level SCRAM signal

! (RO #25) - Knowledge of the effect that a loss or malfunction of i the following will have on the A.C. ELECTRICAL

. DISTRIBUTION: D.C. power. DC Topic is oversampled. See 2/1 262001 1 K6.01 #17,57,78 i Randomly selected K6.02 - Offsite Power (RO #26) -Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Inadequate system flow. System is oversampled. See questions 10 & 87 2/1 211000/ A2.02 Randomly selected 206000 K4.09 Knowledge of HIGH PRESSURE COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic flow control: BWR-2,3,4 i (RO #29) - Knowledge of the effect that a loss or malfunction of I the RECIRCULATION SYSTEM will have on following: Isolation i condenser: Plant-Specific. Does not apply at Hope Creek 2/2 202001/ K3.12 Randomly selected K3.05 - Knowledge of the effect that a loss or i malfunction of the RECIRCULATION SYSTEM will have on

,following: Recirculation system MG Sets: Plant-Specific I(RO #39) - Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting. This does not apply at Hope Creek. A separate Fire Fighting department exists.

1 11 6000001 AK1.02 Randomly selected AA2.05 Ability to determine and Interpret the following as they apply to PLANT FIRE ON SITE: Ventilation alignment necessary to secure affected area (RO #45) - AK3.01 - Knowledge of the reasons for the following I responses as they apply to LOSS OF SHUTDOWN COOLING:

Raising reactor water level. Same concept as RO #40. i 1 11 295021 I AK3.01 Randomly selected AK2.03 - Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following:

RHRlShutdown Cooling

ES*401 Record of Rejected KIA's Form ES-40 1-4 (RO #47) - Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT: Reactor SCRAM. No procedural guidance to support the reason for a scram 1 /1 295016/ AK3.01 Randomly selected AA1.08 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT:

Reactor Pressure (RO #49) - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Affected systems so as to isolate damaged 1 /1 2950181 AA 1.03 portions. Limited procedural guidance for discriminating question.

i Randomly selected AA1.02- System loads.

(RO #54) - 2.4.6 Emergency Procedures/Plan: Knowledge of EOP Mitigation Strategies (grid disturbances). No EOP mitigation strategies associated with grid disturbances.

1/ 1 700000/2.4.6 i Randomly selected 2.1.28 - Conduct of Operations: Knowledge

  • of the purpose and function of major system components and controls.

I (RO #55) - Emergency Procedures 1 Plan: Knowledge of how abnormal operating procedures are used in conjunction with EOP's. Question #69 covers similar topic/system.

1 11 295023/2.4.8 Randomly selected K3.02 - Knowledge of the reasons for the following responses as they apply to REFUELING ACCIDENTS:

Interlocks associated with fuel handling equipment.

(RO #65) - 2.4.41 - Emergency Procedures I Plan: Knowledge of the emergency action level thresholds and classifications. This function is not performed by ROs at Hope Creek.

1/2 295010/2.4.41 Randomly selected AA1.02 - Ability to operate andlor monitor the following as they apply to HIGH DRYWELL PRESSURE: Drywell i fl oorand eqUipmen td rain. sumps (RO #56) - Equipment Control: Knowledge of surveillance procedures. There are no surveillance procedures associated with High Drywell Temperature.

1 /1 295028/2.2.12 i

.Randomly selected 2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (High Drywell Temperature)

(RO #39) Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Ventilation alignment necessary to secure affected area. Oversampled due to overlap with 1 11 600000 I AA2.05 operating exam. i I

i Randomly selected AA2.02- Damper position I 1 11 295030/2.4.35 (SRO # 79) Unable to produce a discriminating question at the SRO :

I

ES-401 Record of Rejected KIA's Form ES-401-4 level.

Randomly selected A2.01 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL Suppression pool level I I

  • (SRO #84) - Emergency Procedures I Plan: Ability to prioritize and i

interpret the significance of each annunciator or alarm. (Secondary Containment Ventilation Hi Rad). This topic was oversampled. See # 18,.

1 /2 295034/2.4.45 71,80.

Randomly selected 295002 - Loss of Main Condenser Vacuum (SRO #93) Conduct of Operations: Ability to interpret and execute procedure steps. (Radwaste). Procedure steps for Radwaste are

  • performed by operators at the local radwaste control room and not 2/2 268000 I 2.1.20 directed by the SRO.
  • Randomly selected 241000 ReactorlTurbine Pressure Regulator (SRO #91) Ability to (a) predict the impacts of the following on the FUEL POOL COOLING & CLEANUP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Closed cooling water failure. Topic/system covered in RO exam - oversampled 2/2 233000 I A2.08 Randomly selected 290001 A2.02 - Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Excessive out leakage
  • (SRO #100) Knowledge of procedures relating to a security event (non-safeguards information). These procedures except for generic information are designated as confidential or safeguards. Could not 3 2.4.28 I write a discriminating SRO question using non-safeguards information.
  • Randomlv selected 2.4.25 - Knowledge of fire protection procedures I

HC ILT 2010 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Date of Examination: 8/23/10 Examination Level: ~ RO D SRO Operating Test Number: NRC 2010 Administrative Topic Type Describe activity to be performed (See Note) Code*

2.1.18 Ability to make accurate, clear, concise logs, records, status boards and reports.

RO: 3.6 Conduct of Operations N,S,A Perform surveillance HC.RE.ST.ZZ-0001 Core Thermal Limits with 2 limits out of spec. (f\IEW) 2.1.29 Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

RO: 4.1 Conduct of Operations D,R,P ZZ030 Generate Off Normal Report.

(Shiftly Routine for Control Room NCO) (2009 NRC RO) 2.2.12 Knowledge of surveillance procedures.

RO 3.7 Equipment Control D,S,A ZZ025 Perform an Accident Monitoring Instrumentation Channel Check.

295038 A 1.01 Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE: Stack gas monitoring system Radiation Control D,S RO: 3.9 ZZ020 Calculate Total Noble Gas Release Rate.

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

(A)lternate Path

HC ILT 2010 NRC EXAM ES-301 Administrative Topics Outline Form ES-301-1 Facility: Hope Creek Date of Examination: 8/23/2010 Examination Level: D RO [Z1 SRO Operating Test Number: NRC 2010 Administrative Topic Type I Describe activity to be performed (See Note) Code*

2.1.18 Ability to make accurate, clear, concise logs, records, status boards and reports Conduct of Operations M,R SRO 3.8 (MODIFIED Bank) ZZ041 Verify DL-26 log requirements for resuming Core Alterations.

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

Conduct of Operations D,R,A SRO 4.0 ZZ031 Initiate And Review System Lineup Sheets. (2 valves out of position) 2.2.23 Ability to track limiting conditions for operation and safety limits.

Equipment Control D,R SRO 4.6 ZZ029 Complete an Action Statement in the TSAS log 2.3.11 Ability to control radiation releases.

SRO: 4.3 0, P, R, ZZ032 Perform Leak Rate Measurement Data Sheet Radiation Control A (Review of completed surveillance determines math error made and actual leakage exceeds Tech Spec.

Determine required actions) (2009 NRC SRO) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as I emergency coordinator if required.

Emergency R

. SRO: 4.4 (MODIFIED Bank) ECG004 Utilize The ECG To Determine The Emergency Classification And/Or Reportability Of An Event And/Or Plant Condition.

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

  • Type Codes & Criteria: (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (:5 3 for ROs; :5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2:1)

(P)revious 2 exams (:51; randomly selected)

(A)lternate Path

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Hope Creek Date of Examination: 8/23/10 Exam Level: RO [8] SRO-I D SRO-U D Operating Test No.: I\JRC2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. AE009 Start a Secondary Condensate Pump (256000 A4.01) S, 0, L 2
b. CH002 Respond To A Low Turbine Hydraulic Pressure (241000 A2.06) . S, 0, E,A 3
c. BJ006 Place HPCI In Full Flow Recire (206000 A4.06) S,D, E,L i 4
d. KL003 Operate The PCIG System During Post LOCAIlsolation S,A, E, EN,I\! I 5 Conditions (223001 A4.11) I
e. EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S,D, E,A 6 (295018 M 1.02)
f. SB004 Respond To A Control Rod System Malfunction (295015 S,D, E,A 7 M1.02) g, ED001 Manually Switch between Chili Water and The Reactor Auxiliary S,D, E 8 Cooling System (RACS) (295018 M 1.01) h, GK002 Isolate Control Room HVAC (290003 A4,01)
  • S,A, E, N 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) I
i. SA001 Defeat ARllnterlocks (295037 EA1.03) D,E 1
j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) 0, E, R,P,L 2 (295030 EA 1.06) k.KJ003 Manually Emergency Start A Diesel Generator From The Local .0, E, L 6 Panel (295003 EA 1.02) i

@ 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 1 SRO-II SRO-U (A)lternate path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank  ::;9/:5.81:5.4 (E)mergency or abnormal in-plant  ;::1/;::1/;::1 (EN)gineered safety feature - I - I ;::1 (control room system)

(L)ow-Power 1 Shutdown  ;::1/~1/~1 (N)ew or (M)odified from bank including 1(A) 2:2/~2/~1

  • (P)revious 2 exams :5. 3/:5. 3/:5. 2 (randomly selected)

(R)CA  ;::1/;::1/;::1 (S)imulator II

ES*301 Control Roomlln*Plant Systems Outline Form ES*301*2 I Facility: Hope Creek Date of Examination: 8/23/10 Exam Level: RO D SRO-I [R] SRO-U D Operating Test No.: NRC2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

, a. AE009 Start a Secondary Condensate Pump (256000 A4.0i) S,D, L 2

b. CH002 Respond To A Low Turbine Hydraulic Pressure (241000 A2.06) Is, D, E,A 3 I
c. BJ006 Place HPCI In Full Flow Recirc (206000 A4.06) S,D, E, L I 4
d. KL003 Operate The PCIG System During Post LOCNlsolation S,A,E, EN,N I 5 Conditions (223001 A4.11) I
e. EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S, D, E,A 6 (295018 AA1.02)

SB004 Respond To A Control Rod System Malfunction (295015 S,D, E,A 7 I II f AA1.02)

I

  • g. NA -
h. GK002 Isolate Control Room HVAC (290003 A4.01) S,A,E,N 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

L SAOOi Defeat ARllnterlocks (295037 EA1.03) 0, E 1

j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) D, E, R, P,L 2 I (295030 EA 1.06)

I k. KJ003 Manually Emergency Start A Diesel Generator From The Local D, E, L 6 Panel (295003 EA 1.02)

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

I

  • Type Codes Criteria for RO J SRO-II SRO-U (A)Iternate path 4-6/4-6/2-3 (C)ontrol room (D)irect from bank  ::;9/$8/::;4

{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  :::; 3 I::; 3 / :::; 2 (randomly selected)

{R)CA  ;::1/;::1/;::1 (S)imulator I

ES*301 Control Roomlln-Plant Systems Outline Form ES-301-2 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, NA b, NA

  • c, BJ006 Place HPCI In Full Flow Recirc (206000 A4,06) S,D, E,L 4
  • d. KL003 Operate The PCIG System During Post LOCAIlsolation S,A, E, EN,N 5

, Conditions (223001 A4.11)

I

e. EG008 Respond To A Safety Auxiliaries Cooling Water Malfunction S,D,E,A 6 (295018 AA1.02)
f. NA

.g. NA

h. NA

! In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

Ir'------------*-----------------------------------------.-------------r--------~I

i. SAOOi Defeat ARI Interlocks (295037 EA 1.03) 0, E
j. BE002 Perform Torus Makeup Via Core Spray System (NRC2009) D,E, R, P,L 2 (295030 EA 1.06)
k. NA

@ 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 1 SRO-II SRO-U

{A)lternate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank  :::;9/:::;8/$4 (E)mergency or abnormal in-plant  ::::1/::::1/::::1 (EN)gineered safety feature - / - 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  ::; 3 / :::; 3 / $ 2 (randomly selected)

(R)CA ?1/;::1/::::1 (S)imulator

D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: ..1.. Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: Rx Power is at 90%.

Turnover:

Swap SJAE's for planned maintenance and raise reactor power to 95% using Group 9B Move Sheet. Hold at 95% for RE data collection.

Event I Malt. Event Type* Event No. No. I Description 1 NA R (RO) I Raise Reactor Power From 90% To 95% With Control N (SRO) . Rods i

2 NA N (PO) I Swap Steam Jet Air Ejectors 3 NM110 I (RO) APRM 0 Fails Upscale (TS SRO)

I (SRO) 4 MS090 I (SRO) Steam line header pressure transmitter 1\10760 fails (TS SRO) 5 5A92 F C (PO) I Steam Jet Air Ejector Malfunction (HV-2016B Fails C (SRO) Closed) 6 MC01 C (ALL) Loss Of Main Condenser Vacuum (Variable Air Leak) i FW26A,B,C Manual Scram Trip of All Reactor Feedwater Pumps 7 EG12 M (ALL) I Loss Of Offsite Power On Main Generator Trip DG07B EDG B Failure 8 OG07A C (RO) i EDG A Fails To Auto Start C (SRO) i 9 RC01 C (PO) RCIC Overs peed C (SRO) 10 HP04 C (PO) HPCI F001 Fails to Open 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.: 2 Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(

Initial Conditions: 100% reactor power.

RCIC is tagged for planned maintenance.

Turnover: Perform Turbine Bypass Valves - Monthly.

Malf. Event Type* Event t

C (SRO) 4 FW29C I (SRO) Feedwater Level Sensor N004C Failure (TS SRO) 5 RR5B C (RO) Recirc Pump B Dual Seal Failure RR6B C (SRO) 6 3A43 B C (RO) Recirc Pump B Discharge Valve Fails To Close C (SRO) 7 CD03 C (ALL) Manual Scram With 5 Rods Out 8 NA M (ALL) High Drywell Pressure 9 TC01 C (ALL) Turbine Bypass Valve Fails Full Open Uncontrolled Cooldown

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

Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Scenario No.: Op-Test No.: NRC2010 Examiners: Operators:

(I Initial Conditions: 84.5% reactor power.

Turnover: Raise reactor power to 89.5% using reactor recirc.

Place "An Containment H2/02 Analyzer in service for surveillance.

Event Malf. Event No. No. Description 1 NA N (PO) Place Containment H2/02 Analyzer In Service.

2 NA R (RO) Raise Reactor Power Using Recire.

N (SRO) 3 AD02LO C (PO) Stuck Open SRV "L" (TS SRO)

C (SRO) 4 CW10A C (SRO) "A" SACS Pump Trip With D Fail To Auto Start (TS SRO)

CW15D 5 CW09 C (ALL) Spurious TACS Isolation 5A53D T ACS Valve Does Not Re-Open Manual Scram 6 5A159 C (ALL) Feedwater Heater Bypass Valve Fails To Open 7 HP07 M (ALL) HPCI Steam Line Leak (Variable) To Drywell With Loss FW30A Of Feedwater And Downcomer Break/Emergency Depressurization FW30B FW30C PC04 8 RH04B C (PO) "B" RHR Pump Trip 9 RC05 I (PO) RCIC Flow Transmitter Failure 10 RH20A C (ALL) Containment Spray Valve Failure

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

Appendix D Scenario Outline Form ES*D*1 Facility: Hope Creek Scenario No.: -+/-- Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(I (BOP)

Initial Conditions: 90% Power Turnover: Reduce power to 84.5% and remove A RFPT from service for planned maintenance.

Event Event No. No. Description 1 NA R(RO) Reduce Reactor Power Using Recirc To 84.5%.

N (SRO) 2 NA N (PO) Remove RFPT "A" From Service.

3 NM12C I (RO) Recirc Flow Unit Failure Downscale. (TS SRO)

I (SRO) 4 FW01B C (ALL) Primary Condensate Pump Trip with Partial Runback RR30B Failure. (TS SRO) 5 TU1508 C (ALL) Main Turbine Vibrations 6 RP07 M (ALL) Manual Main Turbine Trip ATWS Half Core 7 FW11 C (PO) SULCV Fails Closed C (SRO) 8 MS15 C (PO) MSIV Spurious Closure

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (l\i1)ajor APPENDIX 0, Page 38 of 39

Appendix D Scenario Outline Form ES*D*1 Facility: Hope Creek Scenario No.: 2 Op-Test No.: NRC2010 Examiners: Operators: (SRO)

(RO)

(BOP)

Initial Conditions: 95% reactor power. B EHC Pump tagged for planned maintenance.

Turnover: Lower reactor power to 90% using Reactor Recirc Pumps for control rod pattern adjustment.

Swap SSW pump alignment to remove D SSW Pump from service for planned maintenance.

Event I Malf. Event Type* Event No. No. Description 1 NA R(RO) Reduce Reactor Power With Reactor Recirc N(SRO)

I 2 NA N (PO) Swap Service Water Pumps i

3 CW11B C (PO) Service Water Pump Malfunction (TS SRO)

CW05D C (SRO) 4 RR08B C (RO) Single Reactor Recirc Pump Runaway C (SRO)

I 5 RR26B2 C (RO) Reactor Recirc Pump Trip (TS SRO)

C (SRO)

I CR01 C (ALL) Fuel Failure With Manual Scram 7 PC06 I M (ALL) Torus Leak/Emergency Depressurization I

I I I * (N)ormal, (R)eactivity, ~ I)nstrument, (C)omponent, (M)ajor APPENDIX 0, Page 38 of 39

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