ML12072A351

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Draft - Outlines (Folder 2)
ML12072A351
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/09/2011
From: Laing D
Entergy Nuclear Northeast, Entergy Nuclear Operations
To: Peter Presby
Operations Branch I
Jackson D
Shared Package
ML113070677 List:
References
TAC U01843, JTRG-11-007
Download: ML12072A351 (32)
v • d • e


Text

  • Entergy

-===-

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP P.O. Box 110 Lycoming, NY 13093 Tel 315 342 3840 December 9,2011 JTRG-11-007 Mr. Peter Presby, NRC Chief Examiner United States Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415

SUBJECT:

LICENSED OPERATOR INITIAL EXAMINATION OUTLINES

Dear Mr. Presby,

In accordance with NUREG-1021 Revision 9, please find the attached Initial License Examination Outlines and Exam Outline Quality Checklist Random sampling for written test items was completed per ES-401 Attachment 1. The attached materials shall be withheld from public disclosure until the examinations are complete.

If you have any questions, please do not hesitate to contact me at (315) 349 6023.

DANIEL LAING TRAINING MANAGER Attachment CC: Ops Initial Training Superintendent JTRG File

-75 Day NRC Outline Submittals

ES-401 BWR Examination Outline Form ES-401-1 Date of Exam: 3/8/12 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total
1. 1 2 4 5 2 4 3 20 5 2 7 Emergency &

Abnormal Plant 2 0 2 2 N/A 1 0 N/A 2 7 2 1 3 Evolutions Tier Totals 2 6 7 3 4 5 27 7 3 10 1 3 2 3 1 2 5 1 2 2 2 3 26 3 2 5 II

2. II

')

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 1 2 Note: 1. Ensure that at least two topics from every applicable KJA 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 KJA 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those KJAs 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 K/A categories.

7.* The generiC (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs.

8. On the following pages, enter the KJA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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 KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

~S-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emeraencv and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

EIAPE # I Name I Safety Function K KIA Topic(s) IR #

1 295001 Partial or Complete Loss of Forced AK 2,01 Knowledge of the interrelations between 3,61 1 Core Flow Circulation 11 & 4 PARTIAL OR COMPLETE LOSS OF FORCED 3.7 CORE FLOW CIRCULATION and the following:

(CFR: 41.7 I 45.8)

Recirculation system 295003 Partial or Complete Loss of AC 16 X 2,4.50 Emergency Procedures I Plan 4.21 2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. (CFR: 41.10 I 43.5 / 45.3) 295004 Partial or Total Loss of DC Pwr / 6 X AA 2.03 Ability to determine and/or interpret the 2.8/ 3 following as they apply to PARTIAL OR 2.9 COMPLETE LOSS OF D.C. POWER:

(CFR: 41.10/43.5/45.13)

Battery voltage

  • 295005 Main Turbine Generator Trip / 3 X AK 3.07 Knowledge of the reasons for the 3.81 4 following responses as they apply to MAIN 3.8 TURBINE GENERATOR TRIP: (CFR: 41.5/45.6)

Bypass valve operation 295006 SCRAM 1 1 X AK 3.03 Knowledge of the reasons for the 3.81 5 following responses as they apply to SCRAM: 3.9 (CFR: 415/45.6)

Reactor pressure response 295016 Control Room Abandonment 17 X AA 2.03 Ability to determine and/or interpret the 4.31 6 following as they apply to CONTROL ROOM 4.4 ABANDONMENT: (CFR: 41.10/43.5/45.13)

Reactor pressure 295018 Partial or Total Loss of CCW /8 X AA 2,03 Ability to determine and/or interpret the 3.21 7 following as they apply to PARTIAL OR 3.5 COMPLETE LOSS OF COMPONENT COOLING WATER: (CFR: 41.10/43.5/45.13)

Cause for partial or complete loss

If 295019 Partial or Total Loss of Inst. Air 18 X AA 2.01 Ability to determine andlor interpret the 3.51 8 following as they apply to PARTIAL OR 3.6 COMPLETE LOSS OF INSTRUMENT AIR:

(CFR: 41.10/43.5/45.13)

Instrument air system pressure 295021 Loss of Shutdown Cooling 14 X AK 3.04 Knowledge of the reasons for the 3.31 9 following responses as they apply to LOSS OF 3.4 SHUTDOWN COOLING: (CFR: 41.5 /45.6)

Maximizing reactor water cleanup flow 295023 Refueling Acc I 8 X AK 1.02 Knowledge of the operational 3.21 10 implications of the following concepts as they 3.6 apply to REFUELING ACCIDENTS:

(CFR: 41.8 to 41.10)

Shutdown margin 295024 High Drywell Pressure 1 5 X EA 1.17 Ability to operate andlor monitor the 3.91 11 following as they apply to HIGH DRYWELL 3.9 PRESSURE: (CFR: 41.7/45.6)

Containment spray: Plant*Specific 295025 High Reactor Pressure / 3 X EK 3.08 Knowledge of the reasons for the 3.5/ 12 following responses as they apply to HIGH 3.5 REACTOR PRESSURE: (CFR: 41.5/45.6)

Reactor/turbine pressure regulating system operation 295026 Suppression Pool High Water X EK 3.02 Knowledge of the reasons for the 3.91 13 Temp. 1 5 following responses as they apply to 4.0 SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.5 1 45.6)

Suppression pool cooling 295027 High Containment Temperature 1 5 295028 High Drywell Temperature I 5 X 2.4.35 Emergency Procedures I Plan 3.81 14 4.0 Knowledge of local auxiliary operator tasks during an emergency and the resultant operational  !

effects. (CFR: 41.10/43.5/45.13) 295030 Low Suppression Pool Wtr Lvii 5 X EK 2.04 Knowledge of the interrelations between 3.71 15 LOW SUPPRESSION POOL WATER LEVEL and 3.8 the following: (CFR: 41.7 I 45.8)

RHRlLPCI

295031 Reactor Low Water Levell 2 X 2.4.18 Emergency Procedures I Plan 3.31 16 4.0 Knowledge of the specific bases for EOPs.

(CFR: 41.10/43.1 145.13) 295037 SCRAM Condition Present X EK 1.06 Knowledge of the operational 4.01 17 and Reactor Power Above APRM implications of the following concepts as they 42 Downscale or Unknown 1 1 apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

(CFR: 41.8 to 41.10)

Cool down effects on reactor power 295038 High Off-sile Release Rate 1 9 X EA 1.03 Ability to operate and/or monitor the 3.71 18 following as they apply to HIGH OFF-SITE 3.9 RELEASE RATE: (CFR: 41,7 1 45.6)

Process liquid radiation monitoring system 600000 Plant Fire On Site 1 8 X AK 2.01 Knowledge of the interrelations between 2.61 19 PLANT FIRE ON SITE and the following: 2,7 Sensors 1 detectors and valves 700000 Generator Voltage and Electric Grid X AK 2.03 Knowledge of the interrelations between 3,01 20 Disturbances 1 6 GENERATOR VOLTAGE AND ELECTRIC GRID 3,1 DISTURBANCES and the following:

(CFR:41A,41~,41~,41.10/45.8)

Sensors, detectors, indicators KIA Category Totals: 2 4 5 2 4 3 Group Point Total: 20

ES-401 3 Form ES401-1 I ES-401 BWR Examination Outline Form ES-401-1

~

- )

I~

! EIAPE # I Name I Safety Function K K K A G KIA Topic(s) IR #

1 2 3 1 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I 3 X AK 2.06 Knowledge of the interrelations between 3.51 23 HIGH REACTOR PRESSURE and the following: 3.7 (CFR: 41.7 145.8)

PCIS 295008 High Reactor Water Level "

295009 Low Reactor Water Levell 2 I 295010 High Drywell Pressure I 5 X AA 1.04 Ability to operate andlor monitor the 3,11 24 following as they apply to HIGH DRYWELL 3,0 PRESSURE: (CFR: 41,7/456)

Drywell sampling system 295011 High Containment Temp 15 295012 High Drywell Temperature 15 X AK 3,01 Knowledge of the reasons for the following 3,51 27 responses as they apply to HIGH DRYWELL 3,6 TEMPERATURE: (CFR: 41,5/45,6)

Increased drywell COOling 295013 High Suppression Pool Temp, 15 295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM 11 X AK 2.03 Knowledge of the interrelations between 3.21 22 INCOMPLETE SCRAM and the following: (CFR: 41,7 3,6 145,8)

Rod control and information system 295017 High Oft-site Release Rate I 9 295020 Inadvertent Cont. Isolation 1 5 & 7 295022 Loss of CRD Pumps I 1 X 2.1.23 Ability to perform specific system and 4.31 26 integrated plant procedures during all modes of plant 4.4 operation.

(CFR: 41.10 I 43.51 45,2/45,6) 295029 High Suppression Pool Wtr Lvl/5 295032 High Secondary Containment Area Temperature 1 5

295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment X 2.1.28 Knowledge of the purpose and function of 4.11 21 Ventilation High Radiation I 9 major system components and controls. (CFR: 41.7) 4.1 295035 Secondary Containment High I I Differential Pressure / 5 295036 Secondary Containment High X EK 3.02 Knowledge of the reasons for the following 2.81 25 Sump/Area Water Levell 5 responses as they apply to SECONDARY 28 CONTAINMENT HIGH SUMP/AREA WATER LEVEL: (CFR: 41.5/45.6)

Reactor SCRAM 500000 Hi2h CTMT Hydrogen Conc. I 5 fBI 0 2 2 1 0 2 Group Point Total: 7

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection X A 2.10 Ability to (a) predict the impacts of 3.31 28 Mode the following on the RHR/LPCI: 3.5 INJECTION MODE (PLANT SPECIFIC) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6)

Nuclear boiler instrument failures 205000 Shutdown Cooling X K 3.03 Knowledge of the effect that a loss 3.81 29 or malfunction of the SHUTDOWN 3.9 COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following:

(CFR:41.7/45.4)

K3.03 Reactor temperatures (moderator, vessel, flange) 206000 HPCI X 2.4.6 Knowledge of EOP mitigation 3.71 30 strategies. (CFR: 41.10 I 43.5 I 45.13) 4.7 207000 Isolation (Emergency)

Condenser A4.01 Ability to manually operate and/or 209001 LPCS X monitor in the control room: 3.81 32 (CFR: 41.7 I 45.5 to 45.8) 3.6 Core spray pump 209002 HPCS 211000 SLC X K 1.05 Knowledge of the physical 31 connections and/or cause effect relationships between STANDBY LIQUID 3.41 CONTROL SYSTEM and the following: 3.6 (CFR: 41.2 to 41.9 I 45.7 to 45.8)

RWCU 212000 RPS X K 6.02 Knowledge of the effect that a loss 3.71 33 or malfunction of the following will have on 3.9 the REACTOR PROTECTION SYSTEM:

(CFR:41.7/45.7)

Nuclear instrumentation II

2150031RM X K 3.04 Knowledge of the effect that a loss 3.6/ 34 or malfunction of the INTERMEDIATE 3.6 RANGE MONITOR (IRM) SYSTEM will have on following: (CFR: 41.7/45.4)

Reactor power indication i

215004 Source Range Monitor X K 2.01 Knowledge of electrical power 2.6/ 35 supplies to the following: (CFR: 41.7) 2.8 SRM channels/detectors 215005 APRM / LPRM X K 1.02 Knowledge of the physical 3.7/ 36 connections and/or cause effect 3.7 relationships between AVERAGE POWER RANGE MONITORILOCAL POWER RANGE MONITOR SYSTEM and the following: (CFR: 41.2 to 41.9/45.7 to 45.8)

IRM 217000 RCIC X K 5.01 Knowledge of the operational 2.6/ 37 implications of the following concepts as 2.6 they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) :

(CFR: 41.5/45.3)

Indications of pump cavitation 218000 ADS X X K 6.01 Knowledge of the effect that a loss 3.9/ 38/39 or malfunction of the following will have on 4.1 the AUTOMATIC DEPRESSURIZATION SYSTEM: (CFR: 41.7 145.7)

RHRlLPCI system pressure: Plant-Specific 2.1.27 Knowledge of system purpose 3.9/

and/or function. (CFR: 41.7) 4.0 223002 PCIS/Nuclear Steam X K 3.07 Knowledge of the effect that a loss 3.7/ 40 Supply Shutoff or malfunction of the PRIMARY 3.8 CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

(CFR: 41.7/45.4)

Reactor pressure

'I 239002 SRVs X X K 3.01 Knowledge of the effect that a loss 3.9/ 41/42 or malfunction of the RELIEF/SAFETY 4.0 VALVES will have on following: (CFR: 41.7

/45.4)

Reactor pressure control A 2.03 Ability to (a) predict the impacts of 4.1/

the following on the RELIEF/SAFETY 4.2 VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5/45.6)

Stuck open SRV 259002 Reactor Water Level X K 1.14 Knowledge of the physical 2.9/ 43 Control connections and/or cause effect 3.0 relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8)

Main turbine 261000 SGTS X X K 6.03 Knowledge of the effect that a loss 3.0/ 44/45 or malfunction of the following will have on 3.1 the STANDBY GAS TREATMENT SYSTEM: (CFR: 41.7/45.7)

Emergency diesel generator system A 4.06 Ability to manually operate and/or 3.3/

monitor in the control room: 3.6 Reactor building differential pressure 262001 AC Electrical X K 6.01 Knowledge of the effect that a loss 3.1/ 46 Distribution or malfunction of the following will have on 3.4 the A.C. ELECTRICAL DISTRIBUTION:

(CFR: 41.7/45.7)

D.C. power 262002 UPS (AC/DC) X A 3.01 Ability to monitor automatic 2.8/ 47 operations of the UNINTERRUPTABLE 3.1 POWER SUPPLY (A.C'/D.C.) including:

(CFR: 41.7/45.7)

Transfer from preferred to alternate source 263000 DC Electrical X 4.6/ 48 Distribution 2.1.20 Ability to interpret and execute 4.6 procedure steps. (CFR: 41.10/43.5/

45.12)

,I

264000 EDGs X A 3.05 Ability to monitor automatic 3.41 49 operations of the EMERGENCY 3.5 GENERATORS (DIESEUJET) including:

(CFR: 41.7/45.7) load shedding and sequencing 300000 Instrument Air X X K 2.01 Knowledge of electrical power 2.8/ SO/51 supplies to the following: (CFR: 41.7) 2.8 Instrument air compressor K 5.13 Knowledge of the operational 2.9/

implications of the following concepts as they apply to the INSTRUMENT AIR

2.9 SYSTEM

(CFR: 41.5/ 45.3)

Filters 400000 Component Cooling X X K 6.05 Knowledge of the effect that a loss 2.8/ 52/53 Water or malfunction of the following will have on 2.9 the CCWS: (CFR: 41.7 / 45.7)

Motors 2.8/

A 1.04 Ability to predict and lor monitor changes in parameters associated with 2.8 operating the CCWS controls including:

(CFR: 41.5/45.5)

Surge Tank level KJA Category Point Totals: 3 21 31 1 2 5 1 Total:

ES-401 5 Form ES-401-1 I ES-401 BWR Examination Outline Form ES-401-1 System # I Name K K K KIA Topic(s) IR #

1 2 3 201001 CRD Hydraulic X K 1.03 Knowledge of the physical connections 3.11 54 andlor cause effect relationships between 3.1 CONTROL ROD DRIVE HYDRAULIC SYSTEM and the following: (CFR: 41.2 to 41.9

/45.7 to 45.8)

Recirculation pumps (seal purge): Plant-Specific 201002 RMCS X K 4.05 Knowledge of REACTOR MANUAL 3.31 55 CONTROL SYSTEM design feature(s) and/or 33 interlocks which provide for the following: (CFR: 41.7)

"Notch override" rod withdrawal 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation X A 1.01 Ability to predict and/or monitor 3.61 56 changes in parameters associated With 3.5 operating the RECIRCULATION SYSTEM controls including: (CFR: 41.5/45.5)

Recirculation pump flow: Plant-Specific 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS X K 4.02 Knowledge of ROD POSITION 2.5/ 57 INFORMATION SYSTEM design feature(s) 2.5 and/or interlocks which provide for the following: (CFR: 41.7)

Thermocouple 215001 Traversing In-core Probe X K 1.05 Knowledge of the physical connections 3.31 58 and/or cause effect relationships between 3.4 TRAVERSING IN-CORE PROBE and the following: (CFR: 41.2 to 41.9 I 45.7 to 45.8)

Primary containment isolation system 215002 RBM K 1.05 Knowledge of the physical connections 216000 Nuclear BOiler Insl. X and/or cause effect relationships between 3.7/ 59 NUCLEAR BOILER INSTRUMENTATION and 3.9 the following: (CFR: 412 to 41.91 45.7 to 45.8)

Residual heat removal: Plant-Specific

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and AUK 226001 RHR/LPCI: CTMT Spray Mode 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup X K 2.02 Knowledge of electrical power supplies 2.8/ 60 to the following: (CFR: 41.7) 2.9 RHR pumps 234000 Fuel Handling Equipment X A 3.02 Ability to monitor automatic operations 3.1/ 61 of the FUEL HANDLING EQUIPMENT 3.7 including: (CFR: 41.7/45.7)

Interlock operation 239001 Main and Reheat Steam X A 3.03 Ability to monitor automatic operations 2.8/ 62 of the MAIN AND REHEAT STEAM SYSTEM 2.8 including: (CFR: 41.7 f 45.7)

Moisture separator reheat steam supply:

Plant-S pecific 239003 MSIV Leak§lf!e Control 241000 ReactoriTurbine Pressure Regulator 245000 Main Turbine Gen. I Aux. I I 256000 Reactor Condensate X K 604 Knowledge of the effect that a loss or 2.81 63 malfunction of the following will have on the 28 REACTOR CONDENSATE SYSTEM: (CFR:

41.7/45.7)

A.C. power 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X A 1.01 Ability to predict and/or monitor changes in parameters associated with 3.31 3.2 64 =

operating the OFF GAS SYSTEM controls including: (CFR: 41.5/45.5)

Condenser vacuum 272000 Radiation Monitoring 286000 Fire Protection X K 3.03 Knowledge of the effect that a loss or 3.61 65 malfunction of the FIRE PROTECTION 3.8 SYSTEM will have on following: (CFR: 41.7 {

45.4)

Plant protection 288000 Plant Ventilation II 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals

~

Gtt: 2 0 1 Rffi 21 I Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facil' ~"

Date of Exam: 3/8/12 Category KIA # Topic RO/SRO SRO-Only IR # IR #

2.1.2 4.1/4.4 66 Knowledge of operator responsibilities during all modes of plant operation. (CFR: 41.10/45.13) 1.

Conduct of Operations 2.1.1 3.8/4.2 67 Knowledge of conduct of operations requirements.

(CFR: 41.10/45.13) 2.1.45 4.3/4.3 68 Ability to identify and interpret diverse indications to validate the response of another indication.

(CFR: 41.7/43.5/45.4) I 2.1.

2.1.

2.1.

Subtotal 3 2.2.6 3.0/3.6 69 Knowledge of the process for making changes to procedures.

(CFR: 41.10 143.3/45.13) 2.

Equipment Control 2.2.35 3.6/4.5 70 Ability to determine Technical Specification Mode of Operation.

(CFR:41.7/41.10/43.2/45.13) 2.2.

2.2.  !

2.2.

2.2.

Subtotal 2 2.3.11 3.8/4.3 71 Ability to control radiation releases.

(CFR:41.11 143.4/45.10)

3. I Radiation I 2.3.13 3.4/3.8 72 Control Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12/43.4/45.9/45.10)

2.3.

2.3.

2.3.

2.3.

Subtotall 2 2.4.27 3.4/3.9 73 Knowledge of "fire in the plant" procedures.

(CFR: 41.10/43.5/45.13) I 4.

Emergency Procedures 1 2.4.5 3.7/4.3 74 Plan Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

(CFR: 41.10/43.5/45.13) 2.4.49 4.6/4.4 75 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

(CFR: 41.10 1 43.2 145.6) 2.4.

2.4.

2.4.

Subtotal 3 Tier 3 Point Total 10

ES-401 2 Form ES-401-1

<::. CC An BWR Examination Outline Emergency and Abnormal Plant Evolutions* Tier lIGroup 1 (RO I SRO)

EIAPE # I Name / Safety Function K K K A A G KIA Topic(s} IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced Core Flow Circulation 11 & 4 295003 Partial or Complete Loss of AC 16 X AA2.04 Ability to determine and/or interpret the 3.7 81 following as they apply to PARTIAL OR COMPLETE LOSS OF AC. POWER: (CFR: 41.10/43.5/45.13)

System lineups 295004 Partial or Total Loss of DC Pwr 16 295005 Main Turbine Generator Trip 1 3 295006 SCRAM / 1 295016 Control Room Abandonment /7 295018 Partial or Total Loss of CCW /8 29501 9 Partial or Total Loss of Insl. Air 18 295021 Loss of Shutdown Cooling 14 X AA2.07 Ability to determine and/or interpret the 3.1 77 following as they apply to LOSS OF SHUTDOWN COOLING: (CFR: 41.10 J 43.5 /45.13)

Reactor recirculation now 295023 Refueling Acc /8 m 295024 High Drywell Pressure 1 5 X EA2.02 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL

~

PRESSURE: (CFR: 4110! 43.5/45.13)

Drywell temperature 295025 High Reactor Pressure I 3 X 2.1.7 Conduct of Operations 4.7 78 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5/43.5/45.12/45.13) 295026 Suppression Pool High Water Temp. /5 295027 High Containment Temperature / 5 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr LviI 5 X EA2.03 Ability to determine and/or interpret the 3.9 79 following as they apply to LOW SUPPRESSION POOL WATER LEVEL: (CFR 41.10/435 I 45.13)

Reactor pressure

'I Level/2 X EA204 Ability to determine and/or interpret the 4.8 76 following as they apply to REACTOR LOW WATER LEVEL: (CFR: 41.10143.5145.13)

Adequate core cooling 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 X 2.4.4 Emergency Procedures / Plan 4.7 80 Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures (CFR: 41.10 I 43.2 I 45.6) 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances I 6 II KIA Category Totals: 5 2 Group Point Total: 7

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition /1 295015 Incomplete SCRAM / 1 X AA2.02 Ability to determine and/or interpret the 4.2 83 following as they apply to INCOMPLETE SCRAM:

(CFR 41.10/43.5/45.13)

Control rod position 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvi / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment X 2.1.32 Ability to explain and apply system limits and 4.0 85 Area Radiation Levels / 9 precautions. (CFR 41.10 I 43.2 / 45.12) 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 X EA2.03 Ability to determine and I or interpret the 3.8 84 following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS (CFR 41.10 I 43.5 145.13)

Combustible limits for drywell KIA Category Point Totals: 2 1 Group Point Total: 3

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO I SRO)

System # I Name K K K K K K A A A A G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection X A2.17 Ability to (a) predict the impacts of the 3.5 90 Mode following on the RHRILPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6)

Keep fill system failure 205000 Shutdown Cooling X 2.4.31 Knowledge of annunciator alarms, 4.1 86 indications, or response procedures.

(CFR:41.10/45.3) 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 209002 HPCS 211000SLC 212000 RPS 2150031RM 215004 Source Range Monitor 215005 APRM I LPRM 217000 RCIC X A2.17 Ability to (a) predict the impacts of the 3.4 87 following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: (CFR: 41.5 I 45.6)

High suppression pool level 218000 ADS 223002 PCISINuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control II 261000 SGTS

II 262001 AC Electrical Distribution 262002 UPS (ACIDe) 263000 DC Electrical X A2.01 Ability to (a) predict the impacts of the 3.2 88 Distribution followmg on the D.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct control, or mitigate the consequences of those abnormal conditions or operations:

(CFR 41.5/456)

Grounds 264000 EDGs 300000 Instrument Air I

400000 Component Cooling X 2.2.44 Ability to interpret control room 4.4 89 Water indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5/43.5/45.12)

KJ 1:+/-:t+/-+/-:Q 5 II

ES-401 5 Form ES-401-1 BWR Examination Outline Form ES-401-1

~"'m' -n" 21G,,", 2 IRO I SROI System # / Name K A A A A G KIA Topic(s) IR #

1 6 1 2 3 4 201001 CRD Hvdraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe EE 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Prima~ CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handlina Eauipment 239001 Main and Reheat Steam 239003 MSIV Leakalle Control 241000 ReactorlTurbine Pressure Reoulator 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate X 2.4.11 Knowledge of abnormal condition 42 91 procedures.

(CFR: 41.10 i 43.5/4513)

~

sle Offaas 272000 Radiation Monitorina 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT if X 2.4.1 Knowledge of EO? entry conditions and immediate action steps.

4.8 92 (CFR 41.1 0 i 43.51 45.13)

II 290003 Control Room HVAC X A202 Ability to (e) predict the impacts of the 3.4 93 following on the CONTROL ROOM HVAC :

and (b) based on those predictions. use procedures to correct, control. or mitigate the consequences of Ihose abnormal conditions or operations (CFR: 41.S/45.6)

Extreme environmental conditions 290002 Reactor Vessel Internals KIA Category Point Totals: 1 2 Group Point Total: 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: James A. Fitzpatrick Date of Exam: 3/8/12 Category KIA # Topic RO SRO-Only IR # IR #

2.1.34 3.5 94 Knowledge of primary and secondary plant chemistry limits.

1.

(CFR: 41.10/43.5/45.12)

Conduct of Operations 2.1.35 3.'1 95 Knowledge of the fuel-handling responsibilities of SROs.

(CFR: 41.10/43.7) 2.1.

2.1.

2.1.

2.1.

Subtotal 2.2.40 4.7 96 Ability to apply Technical Specifications for a system.

(CFR: 41.10/43.2/43.5/45.3) 2.

Equipment 2.2.

Control 2.2.

2.2.

2.2.

2.2.

Subtotal I 2.3.14 3.8 97 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.

(CFR: 41.12/43.4 1 45.10)

Radiation Control 2.3.4 3.7 98 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12/43.4 /45.10) 2.3.

2.3.

2.3.

2.3.

Subtotall 2

2.4.28 I 4.1 99 Knowledge of procedures relating to a security event

4. (non-safeguards information).

Emergency (CFR: 41.10 143.5/45.13)

Procedures I Plan 2.4.44 4.4 100 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10/41.12/43.5/45.11) I 2.4.

2.4.

2.4.

2.4.

Subtotal 2 Tier 3 Point Total E

ES*401 Record of Rejected KlAs Form ES*401*4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 1 / 295001 JAF is a BWR-4 (K&A specific to BWR-1)

Group 1 AK 2.08 Tier 1 / 295001 LPCI loop select logic not applicable at JAF Group 1 AK 2.05 Tier 1 / 295026 K&A not applicable to JAF operating procedures for high Group 1 torus temperature EK 3.03 Tier 1 / 295027 All K&A's applicable to Mark III containment only Group 1 Tier 1 / 295011 All K&A's applicable to Mark III containment only Group 2 Tier 1 / 295007 Rejected K&A AK 2.01 on basis of previously sampled K&A Group 2 similarities. Similarities are:

AK 2.01

  • 012: EPE 295025 High Reactor Pressure, EK 3.08:

Reactor/turbine I2ressure regulating system ol2eration.

  • 023: APE 295007: High Reactor Pressure, AK 2.01:

Reactor/turbine I2ressure regulating system ol2eration.

  • Replaced AK 2.01 with randomly selected KA:

APE 295007, AK 2.06, PCIS/NSSSS The guidance for this rejection is stated in ES-401 Section D 1.d: ensure that no EPE/APE, system, or KIA category is over-sampled ...

Page 1 of2

Tier 2/ 207000 K&A's not applicable to JAF (Iso/Emergency Condensers)

Group 1 Tier 2/ 209002 K&A's not applicable to JAF (HPCS)

Group 1 Tier 3 2.3.5 Could not write a discriminating, operationally oriented question.

Randomly selected 2.3.11.

Tier 2/ 203000 A2.01 Rejected K&A A2.01 on basis of previously sampled K&A Group 1 similarities. Similarities are:

  • Q 15 was already written testing the concept of inadequate NPSH in LPCI mode.
  • 203000 A2.01 addressed inadequate NPSH in LPCI mode also.
  • Replaced with 203000 A2.01 with randomly selected 203000 A2.10 (NBI failures).

Page 2 of2

ES-301 Administrative Topics Outline Form ES-301-1 I Facility: James A. Fitzpatrick Date of Examination: 2/27/12 Examination Level: RO SRO X Operating Test Number:

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

M,S Control Panel Walkdown Conduct of Operations M,R Determine Shift Staffing Conduct of Operations N,R ST-26K Recirc Loop Startup Differential Temperature Equipment Control Check D,R Evaluate an RWP and Survey Map Radiation Control P,D EAP-17 Pager and CAl\! Activation During Security Emergency Procedures/Plan Event 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 (S 3 for ROs; S 4 for SROs & RO retakes)

(N)ew or (l\t1)odified from bank (~ 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: James A. Fitzpatrick Date of Examination: 2/27/12 Exam Level: RO SRO-I X SRO-U Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System !,JPM Title I Type Code* I Safety Function I

a. Secure 'B' SBGT train following auto initiation D! LI S 9 II
b. Reset RPS scram with scram valve fail to close A/D/LIS 7
c. Place HPCI in pressure control mode AI EN! LI M! S 4
d. Re-open MSIVs with RPV pressurized D/S 3 I
e. Transfer 10300 (10400) bus from T-4 to Reserve Transformer A/MIS 6
g. Line-up 'A' RHR keep full for injection to RPV DIE/LIS 2
f. Restore RB Ventilation following isolation DIS 5 g.

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

i. Vent the Scram Air Header D/E/R 1 I j. Vent Torus to lower Primary Containment pressure AlE/LIM 5  !

i k. Supply cooling water to EDG 'A' ! 'C' from 46P-2B D 8

@ 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-II SRO-U (A)lternate path 4-6 /4-6 I 2-3 (C)ontrol room

{D)irect from bank ~9/s8/S4 (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 ~ 3I s 3I s2 (randomly selected)

.* (R)CA ~1f~1/~1 II (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: James A. Fitzpatrick Date of Examination: 2/27/12 Exam Level: RO SRO-I SRO-U X Operating Test No.:

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 i a. Secure 'B' SBGT train following auto initiation 01 LI S 9

b. Place HPCI in pressure control mode AI EN I LIM 1 S 4
c. Line-up 'A' RHR keep full for injection to RPV D/E/LIS 2 d.

e.

f.

i g.

h.

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

I I i. Vent the Scram Air Header D/E/R 1 I j. Vent Torus to lower Primary Containment pressure AlE/LIM 5

@ 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 S9/S8/S4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ;:::1 (control room system)

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

(R)CA ~1/~1/~1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Fitzpatrick Scenario No.: _ 2 _ Op-Test No.:

Examiners: Operators:

Initial Conditions: Reactor at 75% power Turnover: Reactor is at 75% power. No equipment is OOS. A rod sequence exchange is in progress.

There are 3 rods that are to moved from position 00 to position 48. After the exchange is completed, reactor power is to be returned to 100% using Recirc.

Event Malf. Event Event No. No. Type* Description 1 NA N - ATC, 2 Rods are moved to position 48 and coupling check performed.

SRO 2 RD07 C - ATC, 3rd Rod moved to position 48 but drifts in and then driven full in. (AOP-27)

SRO Reactor power reduced with recirc to < 25% pre-transient or 42.4 mlbm/hr core R BOP, flow.

SRO TS - SRO 3 RMOI:29 ODCM- Reactor Building Rad Monitor Fails downscale SRO 4 DG06A C All Loss of 10500 Bus with slow start of EDG "An and failure of EDG "C" to start. I RPS is lost and restored with MG set or Alternate power supply. The Y2 scram is :

DGOIC TS" SRO reset. (AOP 18 and AOP 59) I ZDILLHO NC05 TRIP 5 MS02 C BOP, Small leak in drywell. Torus is vented. Reactor scram is attempted prior to SRO reaching 2.7 psig. (AOP-39) 6 RPO I AlB M-All High power A TWS, injection is terminated and prevented. Level lowered to 110" to prevent power oscillations. (EOP-3)

RP09 RDIO:AlI 7 SLOIA/B C ATC, Failure of first SLC pump, 2 nd SLC pump works for seconds and then trips.

SL05A/B SRO I 8 RDB C ATC, Removal ofRPS fuses partially works. The remainder of the eontrol rods will be SRO inserted by inserting another manual scram or driving the rods in.

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

Appendix 0 Scenario Outline Form ES-D-1 Facility: _ _ Fitzpatrick Scenario No.: - - Op-Test No.:

Examiners: Operators:

Initial Conditions: 68% power.

Turnover: The plant is shutting down for a refueling outage. "9" CRD is tagged out for maintenance.

Continue to cold shutdown lAW OP-65.

I Event Malf. Event Event No. No. Type* Description 1 NA R-ATC, Lower power with recire to 65% with control rods.

SRO i

2 NA N BOP, Remove Condensate and Condensate booster pump from service SRO 3 AN932:01 TRM- Core Spray Pipe Break Detector Alarm SRO 4 AD05 C- BOP, SR Y fails open, then closes when fuses pulled (AOP-36).

SRO TS - SRO 5 ED43A TR.\1-SRO Loss of 115kv Line # 3. (AOP-72) 6 EGO! M-All Generator Trip i i I 7 RPOIA/8 C - ATC, RPS fails to scram reactor ARI works (EOP-2).

SRO 11 8 ED44 C - ATC, Loss of Offsite Power - Manually close MSIYs due to loss of Circulating Water SRO 9 RRI5 C-80P, Coolant leak in drywell requiring initiation of drywell sprays SRO I 10 HPOI C-BOP, HPCI fails to automatically initiate. After manual initiation, HPCI trips.

SRO HP02 II RRI5 M - All Leak greater than capacity of RCIC and CRD. Level lowers, Alternate Level Control entered and Emergency Depressurize at -19". Level to be restored i

.g;reater than T AF with low pressure systems.

I i

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