ML12116A252

Final Outlines (Folder 3)

ML12116A252
Person / Time
Site:	FitzPatrick
Issue date:	02/22/2012
From:	Peter Presby Operations Branch I
To:	Entergy Nuclear Generation Co
Jackson D
Shared Package
ML113070677	List: IR 05000333/2012301 ML113330864 ML120610564 ML12072A344 ML12072A351 ML12072A353 ML12072A356 ML12116A225 ML12116A242 ML12116A252 ML12116A259 ML12116A275 ML12116A290
References
TAC U01843
Download: ML12116A252 (21)

Text

ES*401 BWR Examination Outline Form ES*401*1

~

James A. Fitzpatrick 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 3 10 1 3 I2 I 3 1 2 5 1 2 2 2 3 26 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 2 1 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 (Le.* 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/evolutions that are not included on the outline should be added, Refer to Section O.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 KlAs 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 0.1 ,b of ES-401 for the applicable KlAs.

8. On the following pages. enter the KIA 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 KIA catalog. and enter the KIA numbers. descriptions. IRs.

and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-1 I ES-401 BWR Examination Outline Form ES ",.

• EIAPE # I Na'ne I Safety Function 295001 Parti<!ll or Complete Loss of Forced Core Flow Citculation 11 & 4 ffiillili X

G KIA Topic(s)

AK 2.01 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF FORCED IR 3.61 3.7 1

CORE FLOW CIRCULATION and the following:

(CFR: 41.7/45.8)

Recirculation system 295003 Partial or Complete Loss of AC I 6 X 2.4.50 Emergency Procedures / Plan 4.2/ 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 Parti lor Total Loss of DC Pwr 16 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 I 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 SCR j\M f 1 X AK 3.03 Knowledge of the reasons for the 3.81 5 following responses as they apply to SCRAM: 3.9 (CFR: 41.5 f 45.6)

Reactor pressure response 295016 Cont~ol Room Abandonment 1 7 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 Parti<ill or Total Loss of CCW 18 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

295019 Partie lor Total Loss of Ins!. Air /8 X AA 2.01 Ability to determine and/or interpret the 3.5/ 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 / 4 X AK 3.04 Knowledge of the reasons for the 3.3/ 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 Ace / 8 X AK 1.02 Knowledge of the operational 3.2/ 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 / 5 X EA 1.17 Ability to operate and/or monitor the 3.9/ 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 3,9/ 13 Temp, / 5 following responses as they apply to 4,0 SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.5/45.6)

Suppression pool cooling 295027 High Containment Temperature / 5 295028 High Drywell Temperature /5 X 2.4.35 Emergency Procedures / Plan 3.8/ 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 Lvi / 5 X EK 2,04 Knowledge of the interrelations between 3,7/ 15 LOW SUPPRESSION POOL WATER LEVEL and 3,8 the following: (CFR: 41,7/45,8)

RHR/LPCI

295031 Reactor Low Water Level 12 X 2.4.18 Emergency Procedures 1 Plan 3.31 16 4.0 Knowledge of the specific bases for EOPs.

(CFR: 41.10 143.1/45.13) 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 4.2 Downscale or Unknown 11 apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

(CFR: 41.8 to 41.10)

Cooldown effects on reactor power 295038 High Off-site Release Rate I 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: 41.71 45.6)

Process liquid radiation monitoring system 600000 Plant Fire On Site I 8 X AK 2.01 Knowledge of the interrelations between 2.6/ 19 PLANT FIRE ON SITE and the following: 2.7 Sensors I detectors and valves 700000 Generator Voltage and Electric Grid X AK 2.03 Knowledge of the interrelations between 3.0/ 20 Disturbances I 6 GENERATOR VOLTAGE AND ELECTRIC GRID 3.1 DISTURBANCES and the following:

(CFR: 41.4,41.5,41.7,41.10/45.8)

Sensors, detectors, indicators I

2 4 5 2 4 3 Group Point Total:

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 I SRO)

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

1 2 3 1 2 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 I 45.8)

PCIS 295008 High Reactor Water Levell 2 295009 Low Reactor Water Levell 2 295010 High Drywell Pressure 15 X AA 1.04 Ability to operate andlor monitor the 3.11 24 following as they apply to HIGH DRYWELL 3.0 PRESSURE: (CFR: 41.7/45.6)

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. I 5 295014 Inadvertent Heactivity 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 Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5 & 7 295022 Loss of CRD Pumps 11 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 43.5 I 45.2 I 45.6) 295029 High Suppression Pool Wtr Lvii 5 295032 High Secondary Containment Area T em perature I ei

295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment X 2.1.28 Knowledge of the purpose and function of 4.1/ 21 Ventilation High Radiation / 9 major system components and controls. (CFR: 41.7) 4.1 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High X EK 3.02 Knowledge of the reasons for the following 2.8/ 25 Sump/Area Water Levell 5 responses as they apply to SECONDARY 2.8 CONTAINMENT HIGH SUMP/AREA WATER LEVEL: (CFR: 41.5/45.6)

Reactor SCRAM 500000 High CTMT Hydrogen Conc. I 5 M

01 21 2I 1 o ? nt Total: 7

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

, , 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 RHRlLPCI: 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: 41.5/45.6)

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 2A.6 Knowledge of EOP mitigation 3.71 30 strategies. (CFR: 41.10/43.5/45.13) 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: 41.7/45.5 to 45.8) 3.6 Core spray pump 209002 HPCS 211000 SLC X K 1.05 Knowledge of the physical 31 connections andlor cause effect 3.4/

relationships between STANDBY LIQUID 3.6 CONTROL SYSTEM and the following:

(CFR: 41.2 to 41.9/45.7 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

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 215004 Source Rangle 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 MONITOR/LOCAL 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: 41.7/45.7)

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 38 CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following:

(CFR: 41.7/45.4)

Reactor pressure

239002 SRVs X X K 3.01 Knowledge of the effect that a loss 3.91 41/42 or malfunction of the RELIEF/SAFETY 4.0 VALVES will have on following: (CFR: 41.7 145.4)

Reactor pressure control A 2.03 Ability to (a) predict the impacts of 4.11 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 3.01 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 3.31 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 3,11 46 Distribution or malfunction of the following will have on 34 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.lD.C.) including:

(CFR: 41.7/45,7)

Transfer from preferred to alternate source 263000 DC Electrical X 4.61 48 Distribution 2.1.20 Ability to Interpret and execute 4.6 procedure steps. (CFR: 41.10/43.51 45.12)

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 2.81 50151 supplies to the following: (CFR: 41.7) 2.8 Instrument air compressor K 5.13 Knowledge of the operational implications of the following concepts as 2.9/

they apply to the INSTRUMENT AIR 2.9 SYSTEM: (CFR: 41.5/45.3)

Filters 400000 Component Gaoling X X K 6.05 Knowledge of the effect that a loss 2.8/ 52153 Water or malfunction of the following will have on 2.9 the CCWS: (CFR: 41.7/45.7)

Motors A 1.04 Ability to predict and / or monitor 2.8/

changes in parameters associated with 2.8 operating the CCWS controls including:

(CFR: 41.51 45.5)

Surge Tank Level I

KIA Category Point Totals: 5 1 2~pPointTotal: 26

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

~2{ROISROl System # / Name K K G KIA Topic(s) IR #

1 234 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 41.9 145.7 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 3.3 interlocks which provide for the following: (CFR: 41.7)

"Notch override" rod withdrawal 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS P++H 201006 RWM 202001 Recirculation X A 1.01 Ability to predict andlor 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 H K 4.02 Knowledge of ROD POSITION INFORMATION SYSTEM design feature(s}

2.51 2.5 57 and/or interlocks which provide for the following: (CFR: 41.7)

Thermocouple 215001 Traversing In-cc,re 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 41.9/45.7 to 45.8)

Primary containment isolation system 215002 RBM K 1.05 Knowledge of the physical connections 216000 Nuclear Boiler Inst. X and/or cause effect relationships between 3.71 59 NUCLEAR BOILER INSTRUMENTATION and 39 the following: (CFR: 41.2 to 41.9/45.7 to 45.8)

Residual heat removal: Plant-Specific

I 219000 RHRlLPCI: TorLlslPool Cooling Mode 223001 Primllf}' CTMT clnd Aux, 226001 RHRlLPCI: CTMT Spray Mode = tjl 230000 RHRlLPC1: ToruslPool Spray Mode 233000 Fuel Pool CoolinglCleanup X K 2,02 Knowledge of electrical power supplies 2,81 60 to the following: (CFR: 41,7) 2,9 RHR pumps 234000 Fuel Handling E~uipment X A 3,02 Ability to monitor automatic operations 3,11 61 of the FUEL HANDLING EQUIPMENT 3,7 including: (CFR: 41,7145,7)

Interlock operation 239001 Main and Reheat Steam X A 3,03 Ability to monitor automatic operations 2,81 62 of the MAIN AND REHEAT STEAM SYSTEM 2,8 including: (CFR: 41,7145,7)

Moisture separator reheat steam supply:

Plant-S pecific 239003 MSIV Leakage Control II 241000 ReactorlTurbine Pressure Regulator 245000 Main Turbine Gen, I Aux, 256000 Reactor Condensate X K 6,04 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 I

259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X ttt A 1,01 Ability to predict and/or monitor 3,31 64 3.2 changes in parameters associated with operating the OFFGAS 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: 41.71 45.4)

Plant protection 288000 Plant Ventilation 290001 Second~CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals 3 1~ 0 0 Gro~Point Total:

ES*401 Generic Knowledge and Abilities Outline (Tier 3) Form ES*401*3

.. es A. Fitzpatrick Date of Exam: 3/8/12 Cate90ry 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 3.9 95 Knowledge of the fuel-handling responsibilities of SROs.

(CFR: 41.10 143.7) 2.1.

2.1.

2.1.

2.1.

Subtotal -

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

(CFR: 41.10 143.2/43.5/45.3) 2.

Equipment Control 2.2.

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: 41.12/43.4145.10)

Radiation Control 2.3.4 3.7 9i)

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.

Subtotal! 2

2.4.28 4, I 99 Knowledge of procedures relating to a security event (non-safeguards information).

4.

(CFR: 41.10/43.5/45.13)

Emergency Procedures I Plan 2.4.44 4,4 100 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10/41.12/435/45.11) I 2.4.

2.4.

2.4.

2.4.

Subtotal 2 Tier 3 Point Total 7

ES-40:...:1_ _ _ _ _ _ _ _ _.:..:R:..:.e.::.co::.:r:..:d:...:o:..:f..:,R.:.:e:!;ie:.:c:.:te::.:d:....:.,:KI:.:.A.::s=------_ _ _ _ _-=F0ii i :lr=mi:l:::iEE=S-=4:=0:::i::1-=4 Tier I Randomly Reason for Rejection Group Selected KIA Tier 1 I 295001 JAF is a BWR-4 (K&A specific to BWR-1)

Group 1 AK 2.08 Tier 1 I 295001 LPCI loop select logic not applicable at JAF Group 1 AK 2.05 Tier 1 I 295026 K&A not applicable to JAF operating procedures for high Group 1 torus temperature EK 3.03 Tier 1 I 295027 All K&A's applicable to Mark III containment only Group 1 Tier 1 I 295011 All K&A's applicable to Mark III containment only Group 2 Tier 1 I 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 Qressure regulating s)!stem oQeration.

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

Reactor/turbine Qressure regulating s)!stem oQeration.

• Replaced AK 2.01 with randomly selected KA:

APE 295007, AK2.06, 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 A2.1 0 (NBI failures).

Page 2 of2

ES-301 Administrative Topics Outline - Rev 2 Form ES-301-1 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*

D,R Verify Fuel Movement Sheets Conduct of Operations 2.1.35 SRO 3.9 D,R NPO Task - Qualification Check Conduct of Operations 2.1.8 SRO 4.1 N,R ST-26K Recirc Loop Startup Differential Temperature Equipment Control SRO Review 2.2.12 SRO 4.1 N,R Determine Requirements for Drywell Entry and Tech Radiation Control Spec LCO 2.3.12 SRO 3.7 Determine Protective Action Recommendations and P,D,R Emergency Procedures/Plan Complete Event Notification Form 2.4.38 SRO 4.4 EE 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.

I' Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D}irect from bank (:$ 3 for ROs; s 4 for SROs & RO retakes)

(N}ew or (M)odified from bank (;:: 1)

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

ES-30:...:1~_ _ _ _.....:C:..:o:.:n.::t:..:ro:.:I...::.R.::o:.:o:.:.m:..:.:/..:..:ln..:....-..:....P.::la=n:.:.t-=S:.!.y::...st:.:e:..:..:m:..:..:s:...O=-=.u..:..:tl;::..in:.:e~-_R:...:.:..ev..:.......::.1_ _-=F=o=r=m=E=S=-=3=O=1-=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) r System I JPM Title

a. Switch Relay Room Ventilation Fans Type Code*

N/S Safety Function 9

b. Reset RPS scram with scram valve fail to close A/D/LIS 7

c. Place HPCI in pressure control mode A I EN I LIM I S 4

d. Re-open MSIVs with RPV pressurized DIS 3

e. Transfer 10300 (10400) bus from T-4 to Reserve Transformer A/M/S 6

f. Une-up 'A' RHR keep full for injection to RPV D/E/LIS 2

g. Restore RB Ventilation following isolation DIS 5 h.

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

j. Vent Torus to lower Primary Containment pressure AIEILIM 5

k. Supply cooling water to EDG 'B' I '0' from Fire Protection 0 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)ltemate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature - / - / 2:1 (control room system)

(L)ow-Power I Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)rEwious 2 exams s 31 s 3 1 s 2 (randomly selected)

(R)CA 2:1/2:1/2:1 (S)imulator i

ES.3(:...:)1~_ _ _ _---=C:.:o:.:.n:::tr:...:o:.:.I..:...R::o:..:o~m..::./.:..:.ln:....:.P:....:I:..:a:.:..:n.:...t=S~ys:..:t:..:e.:.:m.::s:.....O==-ut::li:.:..:n=e....:.R.:.:e:.:v_1~_----=F=o=r=m===E=S=-3=O=1==-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 ,I PM Title Type Code* Safety Function

a. Switch Relay Room Ventilation Fans N/S 9 b.

c. Place HPCI in pressure control mode AI EN I LI MIS 4 d.

e.

f. Line-up 'A' RHR keep full for injection to RPV D/E/LIS 2 g.

h.

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

i. Veint the Scram Air Header D/E/R 1

j. Vent Torus to lower Primary Containment pressure A/E/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 1 SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank =>9/=>8/=>4 (E)mI3rgency or abnormal in-plant ~1/~1/~1 (EN)~lineered 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 => 3 1 => 3 1 => 2 (randomly selected)

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fitzpatrick Scenario No.: 1 Op-Test No.: Rev 2 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 be moved from position 00 to position 48. After the exchange is completed, reactor power is to be returned to 100% using Recirc.

EV4:mt Malf. Event Event Nlo. No. Type* Description I 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 Mlbmlhr core R-BOP, flow.

SRO TS-SRO 3 HP05 C-ATC, HPCI inadvertent start TS-SRO 4 DG06A C-AII Loss of 10500 Bus with slow start of EDG "A" and failure of EDG "c" to start.

RPS is lost and restored with MG set or Alternate power supply. The 12 scram is DGOIC TS-SRO reset. (AOP 18 and AOP 59)

ZDILLHO NC05 TRIP 5 MS02 C- BOP, Small leak in drywell. Reactor scram is attempted prior to reaching 2.7 psig.

SRO (AOP-39) 6 RPOIAIB M-AII High power ATWS, injection is terminated and prevented. Level lowered to 110" to prevent power oscillations. (EOP-3)

RP09 RDIO:AII 7 SLOIAIB C-ATC, Failure of first SLC pump, 2nd SLC pump works for seconds and then trips.

SRO SL05AIB 8 RDI3 C-ATC, Removal ofRPS fuses partially works. The remainder of the control rods will be SRO inserted by inserting another manual scram or driving the rods in.

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

Appendix 0 Scenario Outline Form ES-D-1 Facility: Fitzpatrick Scenario No.:2 Op-Test No.: Rev 2 Examiners: Operators:

Initial Conditions: 68% power.

Turnover: The plant is shutting down due to Tech Spec LCO Action Statement. "8" CRO is tagged out of service, AOS '0' is inoperable and RHR Loop 'A' is out of service due to Heat Exchanger issue.

Continue to cold shutdown lAW OP-65.

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

SRO 2 NA N-BOP, Remove Condensate and Condensate booster pump from service SRO 3 AD05 C BOP, SRV fails open and then closes when fuses pulled (AOP-36).

SRO TS-SRO 4 AN932:01 TRM Core Spray Pipe Break Detector Alarm SRO 5 ED43A TRM-SRO Loss of 115kv Line # 3. (AOP-72) 6 FW19B\C M-All Condensate Pump 'B' trip, 'C' fails for start 7 OS C - ATC, RPS fails to scram reactor - Mode Switch works (EOP-2).

RPS3A\B SRO S. TCII C-ATC Main Turbine fails to auto trip

9. ED44 M-All Loss of Offsite Power - Manually close MSIVs due to loss of Circulating Water

10. RRI5 M-AII Coolant leak in drywell requiring initiation of drywell sprays II. HPOI C-BOP, HPCI fails to automatically initiate. After manual initiation, HPCI trips.

SRO HP02

12. RRl5 M - All Leak greater than capacity ofRCIC and CRD. Level lowers, Alternate Level Control entered and Emergency Depressurize at -19". Level to be restored greater than T AF with low pressure systems.

13. EDlSA C-BOP, Loss 10500 bus SRO CS02B Core Spray iniection valve fails to auto open

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