ML032880205

Draft Outlines

ML032880205
Person / Time
Site:	Pilgrim
Issue date:	09/29/2003
From:	Santiago M Entergy Nuclear Operations
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-293/03-301
Download: ML032880205 (31)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facility:

PNPS Date of Exam:

10/03/2003 Pilgrim / VY Combined Sample Plan (Pilgrim Specific)

Note:

1.

2.

3.

4.

5.

6.*

7.

8.

9.

Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the Tier Totals in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.

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 +I 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.

Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

Systems/evolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryhier.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

On the following pages, enter the WA 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

K K

1 2

X X

X X

ES-401 BWR Examination Outline Form ES-401-I Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO)

IR 3.1 -

EIAPE # I Name I Safety Function WA Topic@)

295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

(CFR: 41.10143.5145.13)

AA2.05 Jet pump operability: Not-BWR-1&2 4.3 Emergency Procedures /Plan G2.4.1 Knowledge of EOP entry conditions and immediate action steps.

(CFR: 41.10143.5145.13)

Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

(CFR: 41.7 145.6)

AA1.03 A.C. electrical distribution 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 3.4 3.8 3.7 3.2 295005 Main Turbine Generator Trip I 3 Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following:

(CFR: 41.7 145.8)

AK2.01 RPS 295006 SCRAM I 1

Knowledge of the operational implications of the following concepts as they apply to SCRAM :

(CFR: 41.8 to 41.10)

AKI.01 Decay heat generation and removal Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT:

(CFR: 41. I O 143.5 145.13)

AA2.07 Suppression chamber pressure 295016 Control Room Abandonment 17

_ _ _ ~

~

Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:

(CFR: 41.7 145.8)

AK2.01 System loads 3.3 29501 8 Partial or Total Loss of CCW I 8

295019 Partial or Total Loss of Inst. Air 18 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :

(CFR: 41.7 145.6)

AA1.04 Service air isolations valves: Plant-Specific 3.3 3.6 295021 Loss of Shutdown Cooling I 4 Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.8 to 41.10)

AKI.04 Natural circulation Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO)

EIAPE #I Name I Safety Function 295023 Refueling Acc Cooling Mode I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 295028 High Drywell Temperature 15 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1

K/A Topic@)

Knowledge of the interrelations between REFUELING ACCIDENTS and the following:

(CFR: 41.7 145.8)

AK2.03 Radiation monitoring equipment Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:

(CFR: 41.7 145.8)

EK2.12 Suppression pool cooling Conduct of Operations G2.1.32 Ability to explain and apply system limits and precautions.

ICFR: 41.10143.2145.12~

Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:

(CFR: 41.7 145.8)

EK2.04 SPDSIERISICRIDSIGDS: Plant-Specific Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE :

(CFR: 41.10143.5145.13)

EA2.05 Toruslsuppression chamber pressure:

Plant-Specific Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

(CFR: 41.7 145.6)

EA1.02 RCIC: Plant-Specific Ability to determine andlor interpret the following as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.10 143.5145.13)

EA2.02 Reactor power Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL :

(CFR: 41.10145.3145.13)

EA1.I 1 Condensate Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR: 41.5 I 45.6)

EK3.04 Hot shutdown boron weight: Plant-Specific IR -

3.4 3.5 3.4 2.5 3.6 3.4 4.0 4.1 3.2 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier IlGroup 1 (RO)

K A

3 1

X 295038 High Off-site Release Rate I 9 IR 2.5 2.8 600000 Plant Fire On Site 18 WA Category Totals:

2 WA Topic@)

Equipment Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

ICFR: 43.2)

Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE:

AK3.04 Actions contained in the abnormal procedure for plant fire on site Group Point Total: 20 I 20/8 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 2 (RO)

WAPE # I Name / Safety Function WA Topic(s) 295002 Loss of Main Condenser Vac I 3

Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM :

(CFR: 41.8 to 41.10)

AKI.04 Increased offgas flow 295007 High Reactor Pressure 13 295008 High Reactor Water Level 12 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I 5 Knowledge of the reasons for the following responses as they apply to HIGH DRWELL PRESSURE :

(CFR: 41.5 I 45.6)

AK3.02 Increased drywell cooling 3.4 295012 High Drywell Temperature 1 5 295013 High Suppression Pool Temp. I 5 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE :

(CFR: 41.5 145.6)

AK3.01 Suppression pool cooling operation 3.6 295014 Inadvertent Reactivity Addition I 1

295015 Incomplete SCRAM I 1

3.4 Equipment Control 62.2.22 Knowledge of limiting conditions for operations and safety limits.

(CFR: 43.2 145.2) 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation 15 & 7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Wtr Lvl I 5 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL :

(CFR: 41.8 to 41.10)

EKI.01 Containment Integrity 3.4 295032 High Secondary Containment Area Temperature 15 3.8 295033 High Secondary Containment Area Radiation Levels I 9 Ability to determine andlor interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :

(CFR: 41.10143.5145.13)

EA2.01 Area radiation levels Ability to operate andlor monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :

(CFR: 41.7 I 45.6)

EA1.02 Process radiation monitoring system 3.9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

WA Category Point Totals Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details) 2 -

2 1

1 1

GroupPointTotal:7 714

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

Form ES-401-1 I:

System # I Name 203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 209001 LPCS WA Topic@)

Ability to monitor automatic operations of the RHWLPCI:

INJECTION MODE (PLANT SPECIFIC) including:

(CFR: 41.7 I 45.7)

A3.05 Reactor water level Conduct of Operations G2.1.28 Knowledge of the purpose and function of major system components and controls.

(CFR: 41.7)

Ability to predict andlor monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:

(CFR: 41.5 I 45.5)

AI.08 System lineup: BWR-2,3,4 Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.03 Initiation logic: BWR-2,3,4 Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:

(CFR: 41.7 I 45.4)

K3.02 ADS logic Knowledge of the physical connections and/or causeeffect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:

(CFR: 41.2 to 41.9 145.7 to 45.8)

K1.02 Core plate differential pressure indication Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:

(CFR: 41.7 I 45.4)

K3.01 tAbility to shutdown the reactor in certain conditions

2.8 Legend

X - KIA selected 0 - KIA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier 2/Group 1 System # I Name WA Topic(s)

Ability to predict andlor monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including:

(CFR: 41.5 I 45.5)

AI.09 Individual relay status: Plant-Specific 2.7 3.6 3.0 212000 RPS 215003 IRM Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following:

(CFR: 41.7 I 45.4)

K3.04 Reactor power indication Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

(CFR: 41.7 I 45.7)

K6.04 Detectors Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.01 SRM channelsldetectors 2.6 215004 Source Range Monitor Ability to predict andlor monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONlTORlLOCAL POWER RANGE MONITOR SYSTEM controls including:

(CFR: 41.5 I45.5)

AI.02 RPS status 3.9 21 5005 APRM I LPRM 2.7' Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) :

(CFR: 41.5 145.3)

K5.06 Turbine operation Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following:

(CFR 41.7 I 45.4)

K3.02 Ability to rapidly depressurize the reactor 217000 RCIC 4.5' 218000 ADS Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

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

F O I ~

ES-401-1 WA Topic(s)

System #I Name 223002 PCISINuclear Steam Supply Shutoff 2.9 Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 145.6)

A2.02 D.C. electrical distribution failures Knowledge of the physical connections and/or causeeffect relationships between RELIEF/SAFETY VALVES and the following:

(CFR: 41.2 to 41.9 I 45.7 to 45.8)

K1.09 Drywell pressure (for safety valves which discharge to the drywell airspace): Plant-Specific Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM :

(CFR: 41.5 145.3)

K5.01 GEMACIFoxborolBailey controller operation: Plant-Specific.

Knowledge of the physical connections and/or causeeffect relationships between STANDBY GAS TREATMENT SYSTEM and the following:

(CFR: 41.2 to 41.9 145.7 to 45.8)

K1.03 Suppression pool 4.0 239002 SRVs 3.1 2.9 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature(s) andlor interlocks which provide for the following:

(CFR: 41.7)

K4.05 Paralleling of A.C. sources (synchroscope)

Ability to manually operate andlor monitor in the control room:

(CFR: 41.7 145.5 to 45.8)

A4.01 All breakers and disconnects (including available switch yard): Plant-SDecitic 3.4 3.4 3.1 262002 UPS (ACIDC)

Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design feature(s) andlor interlocks which provide for the following:

(CFR: 41.7)

K4.01 Transfer from preferred power to alternate power supplies Legend:

X - K/A selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 WA Category Point Totals I:

System # I Name 4

263000 DC Electrical I x Distribution 264000 EDGs 300000 Instrument Air Plant BWR Examination Outline

[stems - Tier ZGroup 1 (RO)

WA Topic(s)

Form ES-401-1 Knowledge of the physical connections andlor causeeffect relationships between D.C.

ELECTRICAL DISTRIBUTION and the following:

(CFR: 41.2 to 41.9 I 45.7 to 45.8)

K1.O1 A.C. electrical distribution Ability to (a) predict the impacts of the following 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: 41.5 145.6)

A2.01 Grounds Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :

(CFR: 41.7 I 45.7)

K6.09 D.C. power Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:

(CFR: 41.7 I 45.7)

A3.02 Air temperature Ability to monitor automatic operations of the CCWS including:

(CFR: 41.7 I 45.7)

A3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws Group Point Total: 26 3.3 2.8 3.3 2.9 3.0 2614 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

U L

ES-401 I:

System # I Name 201001 CRD Hydraulic I

201002 RMCS I

201 003 Control Rod and Drive Mechanism I

201 006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

21 9000 RHWLPCI: Torus/Pool Cooling Mode BWR Examination Outline Plant Systems - Tier ZGroup 2 (RO)

Legend:

X - WA selected FOINI ES-401-1 WA Topic(s)

Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 145.6)

A2.01 Rod movement sequence timer malfunctions Conduct of Operations G2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

ICFR: 43.2 143.3 145.31 Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM ; 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)

A2.01 Withdrawal of control rod in high power region of core: BWR-3,4,5 Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 145.6)

A2.11 Heatup or cooldown of the reactor vessel Knowledge of electrical power supplies to the following:

(CFR: 41.7)

K2.01 tValves 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems -Tier ZGrou WA Topic(s)

System # I Name 223001 Primary CTMT and Aux.

Knowledge of the operational implications of the following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :

(CFR: 41.5 I 45.3)

K5.13 Oxygen concentration measurement: Plant-Specific 226001 RHWLPCI: CTMT Spray Mode 230000 RHWLPCI: ToruslPool Spray Mode 233000 Fuel Pool CoolinglCleanup Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT ; 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)

A2.03 $Loss of electrical power 234000 Fuel Handling Equipment 239001 Main and Reheat Steam Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.

(CFR: 43.2 145.2) 241000 ReactorlTurbine Pressure Regulator Ability to monitor automatic operations of the REACTOIUTURBINE PRESSURE REGULATING SYSTEM including:

(CFR: 41.7 145.7)

A3.12 Turbine trip testing 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate Ability to manually operate andlor monitor in the control room:

(CFR: 41.7 145.5 to 45.8)

A4.07 Lights and alarms 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation Conduct of Operations G2.1.30 Ability to locate and operate components I including local controls.

(CFR: 41.7 145.7) 290001 Secondary CTMT 290003 Control Room HVAC Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 System # / Name 290002 Reactor Vessel lnternals X

K 1

WA Category Point Totals K

K K

K A

A A

A

(

2 3

4 5

6 1

2 3

4 1

4 1

1 WA Topic@)

Knowledge of the physical connections andlor causeeffect relationships between REACTOR VESSEL INTERNALS and the following:

(CFR: 41.2 to 41.9 145.7 to 45.8)

K1.19 TIP F O ~ I ES-401-1 IR 2.5 Group Point Total: 12 I l a 2 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: PNPS Category

1.

Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures Plan Date of Exam: 10/03/2003 Topic 2.1.18 Ability to make accurate / clear and concise logs /

records/ status boards / and reports.

2.9 2.1.20 Ability to execute procedure steps.

4.3 2.1.

2.1.

2.1.

2.1.

I I

I 2.2.23 Ability to track limiting conditions for operations.

I I 2*5 I I

I 2.2.11 I Knowledge of the process for controlling temporary changes.

2.2.1 Ability to perform pre-startup procedures for the 3.7 facility / including operating those controls associated with plant equipment that could affect reactivity.

2.2.

2.3.1 1 2.3.1 0 2.3.

Ability to control radiation releases.

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

2.3. I I

I 2.3.

I I

I I

I I

I I

2.3.

2.4.18 Knowledge of the specific bases for EOPs 2.7 2-4-23 Knowledge of the bases for prioritizing emergency 2.8 procedure implementation during emergency operations.

1 I

I I

I 2.4.19 1 Knowledge of the EOP layout / symbols / and icons I 2.7 I I

I 2.4.

2.4.

ES-401 Record of Rejected WAS Form ES-401-4 Reason for Rejection Randomly Selected KIA Tier I Group 3

2.2.31 WA 2.5 for RO (2.2)

WA 2.5 for RO (1.6) 3 2.2.5 3

2.4.41 WA 2.5 for RO (2.3) 1 I1 295031 A1.05 Already have 2 WAS for RClC system 1 I2 295029 A I.04 Already have 2 WAS for RClC system 211 21 1000 K3.03 Very similar to 21 1000 K1.02 211 223002 K2 No KIA > 2.5 211 259002 K5.09 FWCl not at WNIPilgrim 259002 K5.08 FWCl not at WNIPilgrim 211 211 211 211

~

400000 AI No KIA 262001 Kl.01 Deselected to allow selection of 2"d K4 in Tier 2 300000 A I No A I WAS in this system; picked from remaining 10 chips 202002 K2.01 K/A 2.5 212 Equipment not installed at WNIPilgrim 212 202002 K2.02 290002 K l.I2 Very similar to 21 1000 K1.02 212

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (SRO)

WA Topic@)

WAPE # I Name I Safety Function Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :

(CFR: 41.10143.5145.13)

AA2.02 Neutron monitoring 3.2 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC 16

~

295004 Partial or Total Loss of DC Pwr I 6 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

(CFR: 41.7 145.6)

AA1.01 D.C. electrical distribution systems 3.4 295005 Main Turbine Generator Trip I 3

295006 SCRAM I 1

295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :

(CFR: 41.10 143.5 145.13)

AA2.04 System flow 2.9 295019 Partial or Total Loss of Inst. Air I 8

~

295021 Loss of Shutdown Cooling I 4 Ability to operate andlor monitor the following as they apply to LOSS OF SHUTDOWN COOLING :

(CFR: 41.7 I 45.6)

AA1.02 RHRlshutdown cooling 3.5 295023 Refueling Acc Cooling Mode I 8 4.0 4.2 295024 High Drywell Pressure I 5 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE:

(CFR: 41.10 143.5145.13)

EA2.02 Drywell temperature Ability to determine andlor interpret the following as they apply to HIGH REACTOR PRESSURE:

(CFR: 41.10 143.5 145.13)

EA2.02 Reactor power 295025 High Reactor Pressure 13 3.8 295026 Suppression Pool High Water Temp. / 5 Emergency Procedures /Plan G2.4.3 Ability to identify post-accident instrumentation.

ICFR: 41.6 I 45.41 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1lGroup I (SRO)

II Form ES-401-1 EIAPE #I Name I Safety Function K

K K

A A

G I 1 1 2 I 3 I 1 12 I 295037 SCRAM Condition Present and Power Above APRM Downscale or 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site 18 1 t

WA Categoty Totals:

1 0 1 0 1 0 13 1 4 1 1 I I R I # I WA Topic@) I I

~~

~~

Ability to operate and I or monitor the following as they apply to PLANT FIRE ON SITE:

AA1.05 Plant and control room ventilation systems 3.1 Group Point Total:

8 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

Equipment Control G2.2.22 Knowledge of limiting conditions for 4.1 Equipment Control G2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

(CFR: 45.2) 3.5 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE :

(CFR: 41.10 143.5 145.13)

AA2.02 Drywell pressure 3.9 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (SRO)

WAPE #I Name I Safety Function WA Topic(s)

I IR 295002 Loss of Main Condenser Vac I 3

295007 High Reactor Pressure I3 operations and safety limits-(CFR: 43.2 I 45.2) 295008 High Reactor Water Level I2 295009 Low Reactor Water Level I2 295010 High Drywell Pressure I 5 295012 High Drywell Temperature I5 295013 High Suppression Pool Temp. I 5 295014 Inadvertent Reactivity Addition I 1 29501 5 Incomplete SCRAM I 1

295017 High Off-site Release Rate I 9

295020 Inadvertent Cont. Isolation I5 & 7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Wtr Lvl I 5 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I9 295034 Secondary Containment Ventilation High Radiation I9 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :

(CFR: 41.5 I 45.6)

EK3.02 Starting SBGTIFRVS: Plant-Specific 4.1 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High SumpIArea Water Level I 5

500000 High CTMT Hydrogen Conc. I5 K/A Category Point Totals 0

0 1

0 1

Group Point Total:

4 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

Form ES-401-1 ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 1 (SRO)

WA Topic&)

System # / Name 203000 RHWLPCI: Injection Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; 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)

A2.12 Inadequate system flow 3.0 205000 Shutdown Cooling I

206000 HPCl Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ;

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)

A2.09 Low suppression pool level 3.3 215003 IRM I

215004 Source Range Monitor I 215005 APRM / LPRM I

217000 RClC I

218000 ADS I

223002 PClSlNuclear Steam Supply Shutoff 239002 SRVs I

259002 Reactor Water Level Control I

261000 SGTS Conduct of Operations G2.1.27 Knowledge of system purpose and or function.

(CFR: 41.7) 262001 AC Electrical Distribution 262002 UPS (AC/DC)

I 263000 DC Electrical Distribution Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

ES-401 WA Category Point Totals I:

System # / Name 0

264000 EDGs 300000 Instrument Air I

I 400000 Component Cooling Water Plant:

BWR Examination Outline I 010 stems -Tier ZGroup 1 (SRO)

Y Form ES-401-1 WA Topic@)

Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :

(CFR: 41.7 / 45.7)

K6.01 Starting air Group Point Total:

IR 3.9 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

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

K/A Topic@)

IR K

K 5

6 System #I Name 201001 CRD Hydraulic 201002 RMCS 201 003 Control Rod and Drive Mechanism 201 006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHWLPCI: TorusIPool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHWLPCI: CTMT Spray Mode 230000 RHWLPCI: TorusIPool Spray Mode Equipment Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

ICFR: 43.2) 3.7 3.2 233000 Fuel Pool CoolingICleanup Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 145.6)

A2.07 High fuel pool temperature 234000 Fuel Handling Equipment 239001 Main and Reheat Steam 241 000 Reactornurbine Pressure Regulator 245000 Main Turbine Gen. I Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel lnternals Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

System # I Name K

K K

K K K 1

2 3

4 5

6 1

2 3

4 WA Categoly Point Totals 0

0 0

0 0 0 Legend:

X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)

A A

A A

G WA Topic(s)

IR 0

1 0

0 1 Group PointTotal:

2

\\-

(1 ;onduct of ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 2.1.22 Ability to determine Mode of Operation 3.3 2.1 -25 Ability to obtain and interpret station reference 3.1 materials such as graphs / monographs / and tables which contain performance data.

2.1.

- 1 Facility: PNPS Date of Exam: 10/03/2003 II Operations I W A # I LJ.

I I

2.1.

Topic

2.

Equipment I

RO I SRO-Onlv 2.2.

2.2.

11 Control I

I I

I I

n n I

I I

I I

I 2.1.

2.3.10 I

I requirements.

I I

I I

containment purge.

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

3.3 I 2.2.. I

7.

Emergency Procedures I Plan ll I

I 2.4.

2.4.

2.4.

2.4.

L.L.

2.2.

u.

Radiation Control 2.3.

2.3.

2.3.

2.3.

ES-401 Record of Rejected WAS Form ES-401-4 Tier /

Group I

Randomly Selected WA 1/1 1 600000 AA1.02 1/1 I 600000 AA1.03 1/1 I 600000 AA1.07 Reason for Rejection WA 2.5 WA 2.5 WA 2.5

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Pilgrim Station Date of Examination: 09/29/03 Examination Level: RO Administrative Topic (see Note)

~~~

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Operating Test Number:

1 Describe activity to be performed Daily Log Task #20 - Check Drywell to Torus D/P during power operations per 2.1.15, Daily Surveillance Log, Attachment 1 Procedure Change - Make a change to a procedure for Emergent Work per NOP98A1, Procedure Process, pgs 26 & 27.

Rod Worth Minimizer Operability - Perform 2.1.31 I Rod Worth Minimizer Operability Determine Low Dose Area per 1.3.1 14, Conduct of Radiological Operations 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.

L NUREG-I 021 I Draft Revision 9 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Examination Level: SRO-I Administrative Topic (see Note)

Operating Test Number:

I Describe activity to be performed Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Daily Log Task #20 - Check Drywell to Torus D/P during power operations per 2.1.15, Daily Surveillance Log, Attachment 1 Procedure Change - Make a change to a procedure for Emergent Work per NOP98A1, Procedure Process, pgs 26 & 27.

Rod Worth Minimizer Operability - Perform 2.1.31, Rod Worth Minimizer Operability Determine Low Dose Area per 1.3.1 14, Conduct of Radiological Operations Classify an Event - Classify an Event per EP-IP-100, Emergency Classification and Notification 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.

NUREG-I 021, Draft Revision 9 22 of 27

ES-301 Control Room/ln-Plant Systems Form ES-301-2 u

Outline

i. Main Steam / Closing MSlV from Outside Control Room

j. Radwaste / Open Bkrs for RB Floor & Equip Sump Pumps (Abnormal)

(Emergency)

k. N C Electrical / Manual Transfer of B6 (Abnormal)

Facility: Pilgrim Station Date of Examination: 09/29/03 Exam Level: RO Operating Test No.:

I D

3 DR 9

DR 6

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code*

a. CRD / CRD Weekly Exercises - Uncoupled Control Rod (Used on last NRC exam) 1 DAS I

DASE

b. PClS / Restart RWCU Following Group Isolation (Used on last NRC exam)

I DS

c. MHC / Transfer from MPR to EPR (Used on last NRC exam)

I DSLE

d. RHR-LPCI / Manual Initiation of LPCl While in Shutdown Coolina DAS

e. EDG / Manual Start and Load of EDG for Monthly

f. LPRM / Bypass Failed LPRM Sum. per 8.9.1. Fault is Phase '6' Current = Zero NS DASE

g. SBGT / Man. Start of SBGT & Vent Torus; C-I 9 Alarm During Venting (Used on last NRC exam)

h. Reactor Feed / Start of a Third Reactor Feed Pump I

Safety Function 1

5 3

4 6

7 9

2

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E)ngineered Safety Feature L

NUREG-1021, Draft Revision 9 23 of 27

ES-301 Control Room/l n-Pla nt Systems Form ES-301-2 i/

Outline

b. PClS / Restart RWCU Following Isolation of MO-1201-2 Valve (Used on last NRC exam)

Facility: Pilgrim Station Date of Examination: 09/29/03 Exam Level: SRO-I Operating Test No.:

1 DASE 5

Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

d. RHR-LPCI / Manual Initiation of LPCl While in Shutdown Cooling Surveillance per 8.9.1. Fault is Phase B Current =

e. EDG / Manual Start and Load of EDG for Monthly

f. LPRM / Bypass Failed LPRM System / JPM Title DSLE 4

DAS 6

NS 7

1 Type Code*

g. SBGT / Man. Start of SBGT & Vent Torus; C-I 9 Alarm During Venting (Used on last NRC exam)

Safety Function DASE 9

a. CRD / CRD Weekly Exercises - Uncoupled Control Rod I

DAS (Used on last NRC exam)

i. Main Steam / Closing MSlV from Outside Control Room

j. Radwaste / Open Bkrs for RB Floor & Equip Sump Pumps (Abnormal)

(E merge ncy)

k. A/C Electrical / Manual Transfer of B6 (Abnormal)

I D

3 DR 9

DR 6

I DS

c. MHC / Transfer from MPR to EPR (Used on last NRC exam) 3 I

I I

I

h.

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E)ngineered Safety Feature L

NUREG-1021, Draft Revision 9 23 of 27

Appendix D Scenario Outline Form ES-D-1 N/A NM20 RD02 CW03 I/O PCOl PC23 I/O Facility: PNPS Scenario No.:

1 Op-Test No.:

1 Examiners:

0 pe rat0 rs :

WRO)

N(SR0, BOP)

I(R0, SRO)

I(R0, SRO)

C(ALL)

C(BOP, SRO)

M(ALL)

M(ALL)

C(BOP, SRO)

I/ Initial Conditions: 15% Power, reactor startup is in progress Turnover: Reactor is in the process of being started, currently at step 120 in 2.1.I.

The goal for this shift is to continue the reactor startup. A TBCCW pump is 00s.

Event No.

I 2

3 7

8 Event Description Power change - pull rods to continue power ascension CRD Flow Control Valve failure APRM Fails upscale B TBCCW pump trips causing loss of TBCCW RClC cooling valve fails to open Recirc leak within makeup capacity Torus leak leading to Emergency Depressurization SRV fails to open due to solenoid failure NUREG-I 021, Draft Revision 9 40 of 41

Appendix D Scenario Outline Form ES-D-I RP09 NIA Facility: PNPS Scenario No.:

2 Op-Test No.:

1 C(SR0)

N(R0, BOP)

Trip of RPS MG Set Place RPS bus on backup Examiners :

Operators:

0 RM02 HPOI I/ Initial Conditions: 100% Power, A EDG tagged out for bearing replacement.

I(BOP, RO)

C(BOP, SRO)

Main Steam Line Rad Monitor fails downscale Inadvertent initiation of HPCl Turnover: Continue operating the plant at loo%, Currently in day 5 of a 14 day extended (due to verifying SBODG operable) LCO for A EDG 00s.

I(R0, SRO)

C(ALL)

M(ALL)

C(R0, SRO)

Event No.

1 A Recirc Pump runs back, requires locking scoop tube

.Turbine bearing high vibration Failure to scram upon tripping of turbine SBLC Squib valve fails to fire 2

3 4

5 6

7 8

9 Malf. I EventType*

No.

Event Description RR2 1 MT03 RD26 I RP16 LP02 I

I R/F I I(BOP, SRO) I RWCU fails to isolate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021. Draft Revision 9 40 of 41

Atmendix D Scenario Outline Form ES-D-I Event Type*

C(BOP, SRO)

Facility: PNPS Scenario No.: 3 (Spare)

Event Description B RBCCW pump trip, stby pump does not pick up Op-Test No.:

1 4

5 Examiners:

Operators:

MCOI C(ALL)

Condenser air in-leakage causes scram ED08 C(ALL)

A I Lockout upon scram, loss of all high pressure feed Initial Conditions: 100% Power, A RBCCW pump 00s Turnover: Continue operating at 100% power, A RBCCW is tagged out for breaker maintenance which is scheduled to be completed by the end of the shift.

Event Malf.

No.

1 1 CW05l I

I(R0, SRO) I B FWLC Instrument fails downscale 1

C(ALL)

I B RFP trip I

I 6

I RC06 ]

M(ALL)

I Unisolable steam leak from RClC I

I I

7 I

WF I C(BOP, SRO) I Failure of Group 5 Isolation

. s,%

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-I 021, Draft Revision 9 40 of 41