ML022460409

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Draft - Outlines (Facility Ltr Dated 04/18/2002)
ML022460409
Person / Time
Site: Pilgrim
Issue date: 04/18/2002
From: Mitchell D
Entergy Nuclear Generation Co
To: Bissett P
NRC Region 1
Conte R
References
50-293/02301 50-293/02301
Download: ML022460409 (33)
v • d • e


Text

E* sEntergy Nuclear Generating Company Chiltonville Training Center EuseIda 46 Sandwich Road Plymouth, MA 02360-2505 April 18, 2002 Mr. Paul Bissett U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415

Dear Mr. Bissett:

Enclosed for your review are the examination outline materials to support the NRC Examination currently scheduled for the week of July 29, 2002 for Pilgrim Nuclear Power Station. The materials are organized per the index before Tab 1.

The Knowledge and Abilities for the written outlines were randomly selected using the "WD Associates BWR K/A Catalog Program, Version 1.07" designed for that purpose.

SRO/RO Written Examination Outlines Forms ES-401-1 are the original randomly selected Knowledge and Abilities. They will be modified to reflect rejected K/As and Plant Specific Priorities after NRC approval of the outline. Replacement/Rejected K/As were systematically selected to provide balanced coverage including Plant Specific High Risk Human Error Probabilities. The proposed replacement/rejected K/As have been verified to adhere to the Examiner Standards. (i.e., after proposed revisions all tier and group totals are per the examiner standards and no tier totals fall below two.)

As per our discussion the list of Suppressed Knowledge and Abilities are included with the Outline for your review.

The audit exam is being developed independently of the NRC exam but has not been developed as of this date. After its development the audit exam will be reviewed. Any overlap noted between the NRC exam and the audit exam will be discussed with the NRC.

Per ES-201 Attachment 1, regarding exam security, I would request that the enclosed materials be withheld from public disclosure until after the examinations have been completed.

If I can provide any additional assistance, please feel free to call Scott Willoughby at (508) 830-7638 or Keith Vines at (508) 830-7620.

Sincerely yours, David Mitchell Training Development Supervisor

ES-401 BWR SRO Examination Outline Printed: 04/18/2002 Facility: Pilgrim Nuclear Power Station Form ES-401-1 Exam Date: 07/29/2002 Exam Level: SRO K/A Category Points Tier Group Point Total KI K2 K3 K4 K5 K6 Al A2 A3 A4 G

1. 1 5 4 4 5 4 4 26 Emergency

& 2 3 3 3 2 3 3 17 Abnormal Plant Tier Evolutions Totals 8 7 7 7 7 7 43 1 2 2 2 3 2 2 2 2 2 1 3 23 2.

2 1 1 1 1 2 1 1 1 1 1 2 13 Plant Systems 3 0 0 1 0 1 0 0 1 0 0 1 4 Tier Totals 3 3 4 4 5 3 3 4 3 2 6 40 Cat I Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 5 4 4 4 17 Note:
1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category tier.

1

BWR SR<( amination Outline Printed: 04/1( 2 Facility: Piii,. imNuclear Power Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-1 E/APE # E/APE Name / Safety Function K1 lK2 lK3 Al A2 G KA Topic Imp. Points 295007 High Reactor Pressure / 3 X I AA2.01 - Reactor pressure 4.1* 1 295007 High Reactor Pressure /3 X AK2.05 - Shutdown cooling: Plant-Specific 3.1 1 295009 Low Reactor Water Level /2 X AK.2.04 - Reactor water cleanup 2.6 1 295009 Low Reactor Water Level /2 X AK3.02 - Reactor feedpump runout flow control: 2.8 1 Plant-Specific 295010 High Drywell Pressure / 5 X AA2.06 - Drywell temperature 3.6 I 295013 High Suppression Pool Temperature / 5 X 2.3.6 - Knowledge of the requirements for reviewing 3.1 1 and approving release permits.

295013 High Suppression Pool Temperature /5 X AK2.01 - Suppression pool cooling 3.7 1 295014 Inadvertent Reactivity Addition / I X AK3.02 - Control rod blocks 3.7 1 295016 Control Room Abandonment / 7 X AA2.02 - Reactor water level 4.3* 1 295017 High Off-Site Release Rate /9 X X_ AA1.07 - Process radiation monitoring system 3.6 1 295017 High Off-Site Release Rate /9 X 2.2.2 - Ability to manipulate the console controls as 3.5 1 required to operate the facility between shutdown and designated power levels.

295023 Refueling Accidents / 8 X 2.2.11 - Knowledge of the process for controlling 3.4* 1

_ temporary changes.

295023 Refueling Accidents / 8 X AKI.01 - Radiation exposure hazards 4.1 1 295024 High Drywell Pressure / 5 X 2.1.22 - Ability to determine Mode of Operation. 3.3 I

BWR SR( lamination Outline Printed: 04/1( 2 Facility: Pi,,.

1 im Nuclear Power Station ES- 401 Emergency and Abnormal Plant Evolutions - Tier 1 / GrouD 1 Form ES-401-1 E/APE # E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 295025 High Reactor Pressure / 3 X EK1.03 - Safety/relief valve tailpipe 3.8 1 temperature/pressure relationships 295025 High Reactor Pressure / 3 X EK3.03 - HPCI operation: Plant-Specific 3.8 1 295026 Suppression Pool High Water Temperature / 5 X EK1.01 -Pump NPSH 3.4 1 295030 Low Suppression Pool Water Level / 5 X _ EK3.07 - NPSH considerations for ECCS pumps 3.8 1 295030 Low Suppression Pool Water Level /5 X EAI.02 - RCIC: Plant-Specific 3.5 1 295031 Reactor Low Water Level / 2 X EK2.16 - Reactor water level control 4.1 1 295037 SCRAM Condition Present and Reactor Power Above X EKI.07 - Shutdown margin 3.8 1 APRM Downscale or Unknown / 1 295037 SCRAM Condition Present and Reactor Power Above X EAI.04 - SBLC 4.5* 1 APRM Downscale or Unknown / 1 295038 High Off-Site Release Rate /9 X _ EA2.04 - Source of off-site release 4.5* 1 295038 High Off-Site Release Rate /9 X EKI.01 - Biological effects of radioisotope ingestion 3.1 1 500000 High Containment Hydrogen Concentration / 5 X _ EA1.03 - Containment Atmosphere Control System 3.2 1 500000 High Containment Hydrogen Concentration /5 X EAI1.02 - Primary containment oxygen instrumentation 3.2 1 K/A Category Totals: 5 4 4 5 4 4 Group Point Total: 26 2

BWR SR( amination Outline Printed: 04/1( 2 Facility: im Nuclear Power Station ES- 401 Emerrencv and Abnormnil Plant Fvnoitins - Tier 1 / Grann 2 Fo~rm F.S-^4a1_

E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic I Points 295002 Loss of Main Condenser Vacuum / 3 X AK1.03 - Loss of heat sink 3.8 1 295004 Partial or Complete Loss of D.C. Power /6 X AK1.02 - Redundant D.C. power supplies: 3.4 1 Plant-Specific 295005 Main Turbine Generator Trip /3 X AA 1.0 - Recirculation system: Plant-Specific 3.3 1 295012 High Drywell Temperature / 5 X 2.2.7 - Knowledge of the process for conducting tests or 3.2 1

_ __ experiments not described in the safety analysis report.

295012 High Drywell Temperature / 5 X AK3.01 - Increased drywell cooling 3.6 1 295019 Partial or Complete Loss of Instrument Air / 8 X AK3.02 - Standby air compressor operation 3.4 295020 Inadvertent Containment Isolation / 5 X 2.4.1 - Knowledge of EOP entry conditions and 4.6 1

_immediate action steps.

295021 Loss of Shutdown Cooling / 4 X AA2.04 - Reactor water temperature 3.5 1 295021 Loss of Shutdown Cooling / 4 X AA1.02 - RHR/shutdown cooling 3.5 1 295022 Loss of CRD Pumps / 1 X AK2.04 - Reactor water level 2.7 1 295022 Loss of CRD Pumps / I X AK3.02 - CRDM high temperature 3.1 1 295032 High Secondary Containment Area Temperature / 5 X _ EA2.02 - Equipment operability 3.5 1 295032 High Secondary Containment Area Temperature / 5 X EK2.03 - Fire protection system 3.4 1 295033 High Secondary Containment Area Radiation Levels / X EK2.02 - Process radiation monitoring system 4.1 1

_ _ 9 9__

1

BWR SR( lamination Outline Printed: 04/1( 2 Facility: im Nuclear Power Station we Af11 Emerpenev and Abnormal Plant Evolutions - Tier 1 / Group 2

- c _AA Form ES-401-1 W153 Vm E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Points Secondary Containment High Differential Pressure / 5 X 2.4.33 - Knowledge of the process used track inoperable 2.8 1 295035 alarms.

295035 Secondary Containment High Differential Pressure / 5 X EK1.02 - tRadiation release 4.2 1 295036 Secondary Containment High Sump/Area Water X EA2.01 - Operability of components within the affected 3.2 1 Level /5 area K/A Category Totals: 3 3 3 2 3 3 Group Point Total: 17 2

BWR SRO ( nination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-1 Sys/Ev # System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Im. Points 202002 Recirculation Flow Control System / 1 X K3.03 - Reactor water level 3.4 1 202002 Recirculation Flow Control System / I X A2.04 - Recirculation pump speed mismatch 3.2 1 between loops: Plant-Specific 203000 RHR/LPCI: Injection Mode (Plant X K6.10 - Component cooling water systems 3.1 1 Specific) /22 203000 RHR/LPCI: Injection Mode (Plant X A4. 10 - Pump/system discharge pressure: 3.6 1 Specific) /2 Plant-Specific 206000 High Pressure Coolant Injection X K4. 0 - Surveillance for all operable 3.8 System / 2 components: BWR-2, 3, 4 206000 High Pressure Coolant Injection X K5.05 - Turbine speed control: BWR-2, 3, 4 3.3 1 System /2 _

211000 Standby Liquid Control System / I X 2.2.18 - Knowledge of the process for managing 3.6 l maintenance activities during shutdown operations. ___

211000 Standby Liquid Control System! 1 X K2.01 - SBLC pumps 3.1* 1 212000 Reactor Protection System / 7 X K2.02 - Analog trip system logic cabinets 2.9 1 212000 Reactor Protection System / 7 X A3.02 - Individual system relay status: 3.5 I

_ Plant-Specific 215004 Source Range Monitor (SRM) System X K1.01 - Reactor protection system 3.7 1

/7 I

Printed: 044 )102 BWR SRO ( nination Outline Facility: Pilgrim Nuclear Power Station PDI.an vQtame - Tier 2 / Grnun 1 Form ES-401-1 ES401

- 41 I-A At 7. - -ar

- A K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points Sys/Ev # System / Evolution Name 2.6 1 215004 Source Range Monitor (SRM) System X K5.01 - Detector operation

/7 X KI.16 - Flow converter/comparator network: 3.4 1 215005 Average Power Range Monitor/Local Power Range Monitor System / 7 Plant-Specific X A3.07 - Lights and alarms 3.6 1 218000 Automatic Depressurization System /

X K6. 11 - A.C. electrical distribution 3.2 1 223001 Primary Containment System and Auxiliaries /5 _ r r r X K4.03 - Manual initiation capability: 3.6 1 223002 Primary Containment Isolation System/Nuclear Steam Supply Plant-Specific Shut-Off/ 5 X 2.2.27 - Knowledge of the refueling process. 3.5 1 226001 RHR/LPCI: Containment Spray System Mode / 5 X A 1.05 - Reactor steam flow 3.6 1 241000 Reactor/Turbine Pressure Regulating System / 3 X 2.4.35 - Knowledge of local auxiliary operator 3.5 1 262001 A.C. Electrical Distribution / 6 tasks during emergency operations including

_ _ _Wsystem

+ geography and system implications.

X A2.08 - Opening a disconnect under load 3.6 1 262001 A.C. Electrical Distribution / 6 X K3.03 - Major loads powered from electrical 4.2* 1 264000 Emergency Generators (Diesel/Jet) / 6 buses fed by the emergency generator(s)

X K4.03 - Fluid leakage collection 2.9 1 290001 Secondary Containment / 5 2

Printed: 04; )02 BWR SRO mination Outline Facility: Pilgrim Nuclear Power Station Group Point Total: 23 2 2 2 3 2 2 2 2 2 1 3 K/A Category Totals:

3

BWR SRO ( nination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station ES - 401 Plant Systems - Tier 2/ Group 2 Form ES-401-1 SysfEv # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201002 Reactor Manual Control System / I X K1.06 - Rod sequence control system: 3.3 1

__ Plant-Specific 201002 Reactor Manual Control System / I X K4.08 - Continuous In rod insertion 3.2 1 205000 Shutdown Cooling System (RHR X K2.01 - Pump motors 3.1* 1 Shutdown Cooling Mode) /4 205000 Shutdown Cooling System (RHR X K5.03 - Heat removal mechanisms 3.1 1 Shutdown Cooling Mode) /4 I 215002 Rod Block Monitor System / 7 X 2.1.6 - Ability to supervise and assume a 4.3 _

management role during plant transients and

__ upset conditions.

215003 Intermediate Range Monitor (IRM) X 2.2.33 - Knowledge of control rod 2.9 1 System / 7 _ programming.

215003 Intermediate Range Monitor (IRM) X A4.05 - Trip bypasses 3.4 1 System / 7 219000 RHR/LPCI: Torus/Suppression Pool X K6.04 - Keep fill system 3.0 1 Cooling Mode / 5 245000 Main Turbine Generator and Auxiliary X A2.04 - Reactor scram 3.8 1 Systems /4 263000 D.C. Electrical Distribution / 6 X A3.01 - Meters, dials, recorders, alarms, and 3.3 1 indicating lights 272000 Radiation Monitoring System / 7 X K5.01 - Hydrogen injection operation's effect 3.5 1 on process radiation indications: Plant-Specific 1

BWR SRO ( nination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-1

  1. Sstem ys/Ev / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA To ic Imp. Points 286000 Fire Protection System / 8 X A1.05 - System lineups 3.2 1 290003 Control Room HVAC / 9 X K3.02 - Computer/instrumentation: 3.6 1

_ Plant-Specific K/A Category Totals: 1 1 1 1 2 1 1 1 1 1 2 Group Point Total: 13 2

BWR SRO t nination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station PDI..nt :-+ - Tier 2/ I .ron 3 Form ES-401-1 ES -401 Imp.IaPint Sys-Ev # System / Evolution Name - l K2 K3 K4 IK5 K6 Al A2 A3 A4 G KA Topic . Point X K3.01 - Reactor power 3.4 1 201003 Control Rod and Drive Mechanism / I X 2.4.16 - Knowledge of EOP implementation 4.0 1 233000 Fuel Pool Cooling and Clean-up /9 hierarchy and coordination with other support procedures.

X Te A IO - Mainpturbine trip 3.1 1 256000 actor Condensate System /92 X _L I IK5.03 - Temperature control 2.6 1 288000 Plant Ventilation Systems / 9 0 1 0 1 0 0 1 0 0 1 Group Point Total: 4 K/A Category Totals: 0 1

Generic Knowledge -1Abilities Outline (Tier 3)

( Printed: 04/18/204' BWR SRO Examination Outline Form ES-401-5 Facility: Pilgrim Nuclear Power Station Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 1 2.1.13 Knowledge of facility requirements for controlling vital / controlled access. 2.9 1 2.1.11 Knowledge of less than one hour technical specification action statements for systems. 3.8 1 2.1.20 Ability to execute procedure steps. 4.2 1 2.1.28 Knowledge of the purpose and function of major system components and controls. 3.3 1 Category Total: 5 Equipment Control 2.2.5 Knowledge of the process for making changes in the facility as described in the safety 2.7 1 analysis report.

2.2.32 Knowledge of the effects of alterations on core configuration. 3.3 1 2.2.33 Knowledge of control rod programming. 2.9 1 2.2.24 Ability to analyze the affect of maintenance activities on LCO status. 3.8 1 Category Total: 4 Radiation Control 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1 personnel exposure.

2.3.8 Knowledge of the process for performing a planned gaseous radioactive release. 3.2 1 2.3.2 Knowledge of facility ALARA program. 2.9 I 2.3.11 Ability to control radiation releases. 3.2 1 Category Total: 4 I

Generic Knowledge 1-Abilities Outline (Tier 3)

( Printed: 04/18/20k BWR SRO Examination Outline Form ES-401-5 Facility: Pilgrim Nuclear Power Station Generic Category KA KA Topic Imp. Points Emergency Plan 2.4.7 Knowledge of event based EOP mitigation strategies. 3.8 1 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) 3.9 1 mitigation strategies.

2.4.3 Ability to identify post-accident instrumentation. 3.8 1 2.4.25 Knowledge of fire protection procedures. 3.4 1 Category Total: 4 Generic Total: 17 2

ES-401 BWR RO Examination Outline Printed: 04/18/2002 Facility: Pilgrim Nuclear Power Station Form ES-401-2 Exam Date: 07/29/2002 Exam Level: RO

-I -

K/A Category Points Tier Group Kl K2 K3 K4 K5 K6 Al A2 A A4 G Point Total 4 1 0 13 1.

Emergency 2 4 3 4 3 3 2 19 Abnormal 2 1 0 1 0 0 4 Plant 3 Evolutions _

Totals 8 7 7 8 4 2 36 Tier 1 3 2 2 3 2 3 3 2 3 3 28 2.

2 2 2 2 2 2 1 2 3 2 1 0 19 Plant Systems 3 0 0 1 0 1 0 0 1 1 0 0 4 Tier Totals 5 4 5 5 5 4 5 6 6 4 2 51 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 4_3_13 4 3 3 3 13 Note:
1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category tier.

1

BWR R( imination Outline Printed: 04/1( 2 Facility: Pkif m Nuclear Power Station ES - 401 Emeroenev aend Abnor-mal Plant F~unvilti.- ie / irw rA__A r52 and ^

n hnrn irfI'flufn~-T~ AMRec AI "IV upj A form ES-40U1-2 E/APE EIAPE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295005 Main Turbine Generator Trip / 3 x AAI .01 - Recirculation system: Plant-Specific 3.1 1 295007 High Reactor Pressure / 3 X AK2.05 - Shutdown cooling: Plant-Specific 2.9 295009 Low Reactor Water Level /2 _ X _ AK2.04 - Reactor water cleanup 2.6 1 295009 Low Reactor Water Level /2 X AK3.02 - Reactor feedpump runout flow control: 2.7 1

_ Plant-Specific 295010 High Drywell Pressure / 5 X AA2.06 - Drywell temperature 3.6 I 295014 Inadvertent Reactivity Addition / 1 X AK3.02 - Control rod blocks 3.7 1 295025 High Reactor Pressure / 3 X EK1.03 - Safety/relief valve tailpipe 3.6 1

_ temperature/pressure relationships 295025 High Reactor Pressure / 3 X EK3.03 - HPCI operation: Plant-Specific 3.8 1 295031 Reactor Low Water Level / 2 X EK2.16 - Reactor water level control 4.1

  • 1 295037 SCRAM Condition Present and Reactor Power Above X EK1.07 - Shutdown margin 3.4 1 APRM Downscale or Unknown / I 295037 SCRAM Condition Present and Reactor Power Above X EA1.04 - SBLC 4.5* 1 APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Concentration /5 X _ _ EA 1.03 - Containment Atmosphere Control System 3.4 1 500000 High Containment Hydrogen Concentration / 5 X EAl1.02 - Primary containment oxygen instrumentation 3.3 1 K/A Category Totals: 2 3 3 4 1 0 Group Point Total: 13 1

BWR Rq imination Outline Printed: 04/1l 2 Facility: Ptkb. im Nuclear Power Station C- -!#O AnII- Rmervencv

- - --- J and Abnormal Plant Evolutions - Tier 1 / Group 2 A - - - _, -

Form ES-401-2 E/APE U E/APE Name / Safety Function Ki K2 K3 Al A2 G KA Topic Imp Points 295002 Loss of Main Condenser Vacuum / 3 X AK1.03 - Loss of heat sink 3.6 1 295004 Partial or Complete Loss of D.C. Power / 6 X AKI.02 - Redundant D.C. power supplies: 3.2 1 Plant-Specific 295004 Partial or Complete Loss of D.C. Power / 6 X AA1.02 - Systems necessary to assure safe plant 3.8 1 shutdown 295012 High Drywell Temperature / 5 X AK3.01 - Increased drywell cooling 3.5 1 295012 High Drywell Temperature / 5 X AA2.02 - Drywell pressure 3.9 1 295013 High Suppression Pool Temperature / 5 X AK2.01 - Suppression pool cooling 3.6 1 295017 High Off-Site Release Rate /9 X __ AA1.07 - Process radiation monitoring system 3.4 1 295017 High Off-Site Release Rate /9 X 2.2.2 - Ability to manipulate the console controls as 4.0 1 required to operate the facility between shutdown and designated power levels.

295018 Partial or Complete Loss of Component Cooling X AA2.01 - Component temperatures 3.3 1 Water / 8 295019 Partial or Complete Loss of Instrument Air! 8 X AK3.02 - Standby air compressor operation 3.5 1 295022 Loss of CRD Pumps! 1 - X AK2.04 - Reactor water level 2.5 1 295022 Loss of CRD Pumps / 1 X AK3.02 - CRDM high temperature 2.9 1 295026 Suppression Pool High Water Temperature /5 X EK1.01 - Pump NPSH 3.0 1 295028 High Drywell Temperature / 5 _ _ X 2.2.27 - Knowledge of the refueling process. 2.6 1 1

BWR R(4i( imination Outline Printed: 04/1( 2 Facility: Piiasm Nuclear Power Station ES - 401 Emergencv and Abnormal Plant Evolutions - Tier 1/ Groun 2 Form ES-401-2 E/APE # E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp points 295030 Low Suppression Pool Water Level /5 X EK3.07 - NPSH considerations for ECCS pumps 3.5 1 295030 Low Suppression Pool Water Level / 5 X EA1.02 - RCIC: Plant-Specific 3.4 1 295033 High Secondary Containment Area Radiation Levels / X EK2.02 - Process radiation monitoring system 3.8 1 295033 High Secondary Containment Area Radiation Levels / X EA2.03 - tCause of high area radiation 3.7 1 9

295038 High Off-Site Release Rate / 9 X EKI.01 - Biological effects of radioisotope ingestion 2.5 1 K/A Category Totals: 4 3 4 3 3 2 Group Point Total: 19 2

BWR RI( amination Outline Printed: 04/1( 2 Facility: Pl 81 fm Nuclear Power Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 3 Form ES-401-2 E/APE # E/APE Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points 295021 Loss of Shutdown Cooling / 4 X AAl.02 - RHR/shutdown cooling 3.5 1 295023 Refueling Accidents / 8 X AKi .01 - Radiation exposure hazards 3.6 1 295032 High Secondary Containment Area Temperature / 5 X EK2.03 - Fire protection system 3.3 1 295035 Secondary Containment High Differential Pressure / 5 X EK1.02 - tRadiation release 3.7 1 K/A Category Totals: 2 1 0 1 0 0 Group Point Total: 4 1

BWR RO ( aination Outline Printed: 04( 302 Facility: Pilgrim Nuclear Power Station Vf -nA Plant Systems - Tier 2/ Group 1 Form ES-401-2 S sEv # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201002 Reactor Manual Control System / 1 X K1.06 - Rod sequence control system: 3.2 1

__ Plant-Specific 201002 Reactor Manual Control System / I X K4.08 - Continuous In rod insertion 3.2 1 202002 Recirculation Flow Control System / I X K3.03 - Reactor water level 3.3 202002 Recirculation Flow Control System / 1 X A2.04 - Recirculation pump speed mismatch 3.0 1 between loops: Plant-Specific 203000 RHR/LPCI: Injection Mode (Plant X K6. 10 - Component cooling water systems 3.0 1 Specific) /2 _ _

203000 RHR/LPCI: Injection Mode (Plant X A4. 10- Pump/system discharge pressure: 3.7 1 Specific) / 2 Plant-Specific 206000 High Pressure Coolant Injection X K4.10 - Surveillance for all operable 3.7 1 System /2 _ _ components: BWR-2, 3, 4 206000 High Pressure Coolant Injection X K5.05 - Turbine speed control: BWR-2, 3, 4 3.3 1 System /2 _ _ _ _

211000 Standby Liquid Control System / I X _K2.01 - SBLC pumps 2.9* 1 211000 Standby Liquid Control System / 1 X A1.09 - SBLC system lineup 4.0* 1 212000 Reactor Protection System / 7 X _K2.02 - Analog trip system logic cabinets 2.7 1 212000 Reactor Protection System / 7 X A3.02 - Individual system relay status: 3.2 1 Plant-Specific _

I

Printed: 04( 902 BWR RO ( aination Outline

(

Facility: Pilgrim Nuclear Power Station

-  ! AA1 Plant Svstems - Tier 2 / GrouD 1 Form ES-401-2 KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Points Sys/E#System / Evolution Name X A4.05 - Trip bypasses 3.4 1 215003 Intermediate Range Monitor (IRM)

System /7 X A2.03 - Stuck detector 2.9 1 215003 Intermediate Range Monitor (IRM)

System / 7 X Kl.01 - Reactor protection system 3.6 1 215004 Source Range Monitor (SRM) System

/77 X K5.01 - Detector operation 2.6 1 215004 Source Range Monitor (SRM) System

/7 X KI.16 - Flow converter/comparator network: 3.3 1 215005 Average Power Range Monitor/Local Power Range Monitor System / 7 Plant-Specific X A3.07 - Lights and alarms 3.7 1 218000 Automatic Depressurization System /

3 X K6.11 - A.C. electrical distribution 3.0 I 223001 Primary Containment System and Auxiliaries / 5 _

X A3.01 - Suppression pool level 3.4 1 223001 Primary Containment System and Auxiliaries / 5 X K4.03 - Manual initiation capability: 3.5 1 223002 Primary Containment Isolation System/Nuclear Steam Supply Plant-Specific Shut-Off / 5 _ _

X A4.02 - Manually initiate the system 3.9 I 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off/ 5 _

2

BWR RO ( Aination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station be _ AnI Plant Svqtems - Tier 2 / Group 1 Form ES-401-2 F - '

  • 1. oan-Sys/Ev # System / Evolution Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 239002 Relief/Safety Valves / 3 X 2.2.25 - Knowledge of bases in technical 2.5 1 specifications for limiting conditions for operations and safety limits.

241000 Reactor/Turbine Pressure Regulating X A 1.05 - Reactor steam flow 3.5 System / 3 _ _

241000 Reactor/Turbine Pressure Regulating X 2.3.11 - Ability to control radiation releases. 2.7 1 System / 3 _

259001 Reactor Feedwater System /2 X A1.02 - Feedwater inlet temperature 3.2 1 264000 Emergency Generators (Diesel/Jet) / 6 X K3.03 - Major loads powered from electrical 4.1* 1 buses fed by the emergency generator(s) 264000 Emergency Generators (Diesel/Jet) /6 X K6.09 - D.C. power 3.3 1 K/A Category Totals: 3 2 2 3 2 3 3 2 3 3 2 Group Point Total: 28 3

( BWR RO ( tination Outline Printed: 04( )02 Facility: Pilgrim Nuclear Power Station ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Ev # System / Evolution Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201003 Control Rod and Drive Mechanism / 1 X K3.01 - Reactor power 3.2 1 205000 Shutdown Cooling System (RHR X K2.01 - Pump motors 3.1* 1 Shutdown Cooling Mode) / 4 205000 Shutdown Cooling System (RHR X K5.03 - Heat removal mechanisms 2.8 1 Shutdown Cooling Mode) /4 219000 RHR/LPCI: Torus/Suppression Pool X K6.04 - Keep fill system 2.9* 1 Cooling Mode /5 _

219000 RHRALPCI: Torus/Suppression Pool X KI.04 - LPCI/RHR pumps 3.9 1 Cooling Mode /5 _

226001 RHR/LPCI: Containment Spray X K4.03 - Reduction in vessel injection flow 2.9 System Mode / 5 during accident conditions 239001 Main and Reheat Steam System / 3 X A3.03 - Moisture separator reheat steam supply: 2.8 1

_ Plant-Specific 245000 Main Turbine Generator and Auxiliary X A2.04 - Reactor scram 3.7 1 Systems /4 245000 Main Turbine Generator and Auxiliary X KI.09 - D.C. electrical distribution 2.7 1 Systems / 4 256000 Reactor Condensate System / 2 X A2.I0 - Main turbine trip 3.1 1 262001 A.C. Electrical Distribution /6 X A2.08 - Opening a disconnect under load 3.3 1 263000 D.C. Electrical Distribution / 6 X A3.01 - Meters, dials, recorders, alarms, and 3.2 1 indicating lights 1

( BWR RO ( fination Outline Printed: 048 )02 Facility: Pilgrim Nuclear Power Station ES - 401 Plant Systems - Tier 2 / Groun 2 Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 263000 D.C. Electrical Distribution / 6 X K2.01 - Major D.C. loads 3.1I 272000 Radiation Monitoring System / 7 X K5.01 - Hydrogen injection operation's effect 3.2 1 on process radiation indications: Plant-Specific 286000 Fire Protection System / 8 X Al.05 - System lineups 3.2 1 286000 Fire Protection System /8 X A4.05 - Fire pump 3.3 1 290001 Secondary Containment / 5 X K4.03 - Fluid leakage collection 2.8 1 290001 Secondary Containment / 5 X Al.01 - System lineups 3.1 1 290003 Control Room HVAC / 9 X K3.02 - Computer/instrumentation: 3.3 1

-1 1_ Plant-Specific K/A Category Totals: 2 2 2 2 2 1 2 3 2 1 0 Group Point Total: 19 2

BWR RO ( nination Outline Printed: Ol 902 Facility: Pilgrim Nuclear Power Station UQ-

!1 7 AM J Plant SvstPms

/ Gmrnun 3

- Tipr. 2-IA.__ Form ES-401-2 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. I Points 215001 Traversing In-Core Probe / 7 X A2.02 - High primary containment pressure: 2.9 1 Mark-I&II(Not-BWR1) 233000 Fuel Pool Cooling and Clean-up / 9 X K3.03 - Fuel pool water clarity 2.6 1 288000 Plant Ventilation Systems /9 X IK5.03 - Temperature control 2.5 1 288000 Plant Ventilation Systems / 9 X A3.01 - Isolationlinitiation signals 3.8 1 K/A Category Totals: 0 0 1 0 1 0 0 1 1 0 0 Group Point Total: 4 1

Generic Knowledge 4 Abilities Outline (Tier 3)

Printed: 04/18/20(

(

BWR RO Examination Outline Form ES-401-5 Facility: Pilgrim Nuclear Power Station Imp. Points Generic Category KAA KA Topic 2.1.11 Knowledge of less than one hour technical specification action statements for systems. 3.0 Conduct of Operations 1 2.1.20 Ability to execute procedure steps. 4.3 1

2.1.28 Knowledge of the purpose and function of major system components and controls. 3.2 1

2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 3.7 rhrr ~irraco --- ehvo andiinetniment intemrplnttionn Category Total: 4 2.2.33 Knowledge of control rod programming. 2.5 I Equipment Control 2.2.24 Ability to analyze the affect of maintenance activities on LCO status. 2.6 1 2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and 2.5 1 safety limits.

Category Total: 3 2.3.2 Knowledge of facility ALARA program. 2.5 1 Radiation Control 2.3.11 Ability to control radiation releases. 2.7 1 2.3.9 Knowledge of the process for performing a containment purge. 2.5 1 Category Total: 3 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) 3.3 1 Emergency Plan mitigation strategies.

2.4.3 Ability to identify post-accident instrumentation. 3.5 1 2.4.25 Knowledge of fire protection procedures. 2.9 1 Ca1hsaaU1 ,Tatups Generic Total: 13 1

o -,jUIA ES-301 Administrative Topics Outline Form ES-30l-1 PNPS Date of Examination: 07/29/02 Facility:

Operating Test Number: I Examination Level (circle one): SRO Administrative Describe method of evaluation:

Topic/Subject Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions Plant Parameter JPM - Perform a Short Form Heat Balance A. 1 Verification Security Question #1 - Requirements for degraded vital area barriers.

Question #2 - Escort responsibilities.

l Surveillance JPM - Determine SSW Pump Operability using Flowrate A.2 esting Surveillance Test Data A3 Ability to Question #1 - Supervisor responsibilities for work Perform performed under RWP.

Procedures to Reduce Excessive Question #2 - Actions for refuel floor hi radiation levels.

Levels of Radiation and Guard Against Personnel Exposure A Emergency JPM - Off-site Notification for Contaminated, Injured AA Communications Person.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: PNPS Date of Examination: 07/29/02 Operating Test Number: 1 Examination Level (circle one): RO Administrative Describe method of evaluation:

Topic/Subject Description 1. ONE Administrative JPM, OR

2. TWO Administrative Questions Plant Parameter JPM - Perform a Short Form Heat Balance A. 1 Verification Security Question #1 - Requirements for degraded vital area barriers.

Question #2 - Escort responsibilities.

Tagging and Question #1 A.2 Clearances What is the recommended sequence for tagging out a centrifugal pump?

Question # 2 Describe the tagout verification requirements for removal/

installation of fuses.

Ability to Perform Question #1 - Requirements for entry into very high radiation A.3 Procedures to areas.

Reduce Excessive Levels of Radiation and Question #2 - Actions for refuel floor hi radiation levels.

Guard Against Personnel Exposure Lines of Authority Question #1 - Emergency dose limits.

A.4 During an Emergency Question #2 - Actions in the event of a bomb threat.

ES-301 Control Room Systems and Facility Form ES-301-2 Walk-Through Test Outline Facility: PNPS Date of Examination: 07/29/02 Examination Level (circle one): RO / SRO Operating Test Number: 1 B.1 Control Room Systems l System / JPM Title Type Safety Code* Function D

a. Start turbine generator and sync to grid L 4 S

N

b. Transfer MPR to EPR 3 S

D

c. Manually start SBGT and vent torus. A 9 S

D

d. APRM/LPRM/"Perform an APRM setdown Functional L 7 Test" S M
e. Restart RWCU following auto isolation A 2 SD D
f. Normal control rod withdrawal uncoupled rod. A 1 SD D
g. Manual transfer of emergency buses to SUT. 6 B.2 Facility Walk-Through l D
a. Swapping spent fuel pool pumps. 9 DRl D
b. RCIC start from ASP A 4 DRl D
c. EDG operation from outside CR 6
  • 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

1-orm L.S-U-1 ppenaix UID Appendix Scenario uutiine icenario Outline Form E-S-D-1 Facility: Pilgrim Scenario No.: 1 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 100% RCIC OOS, 'A' APRM Bypassed Turnover: Reduce reactor power to 50% in prep for backwash Event No.

Malf.

No.

Event Type*

1 Event Description 1 N/A R-RO Reduce reactor power for thermal backwash 2 1 I-RO FWLC transmitter fails high 3 2 N-BOP Shift TBCCW pumps for maint. vibes 4 3 C-RO 'B' recirc scoop tube lockup 5 4 C-BOP TBCCW pump trip 6 5 M-ALL Steamline break inside containment 7 6 C-BOP HPCI fails to start 1- t I

I t I t I +

I +

I 4-

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

ippenoix scenario Outline ForrWES-D-1 Appendix UD Scenario Outi~ne Form ES-D-1 Facility: Pilgrim Scenario No.: 2 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 60% power, 'A' IRM bypassed Turnover: Shutting down for maintenance outage Event Malf. Event Event No. No. Type* Description 1 N/A R-RO Continue shutdown 2 1 I-RO 'C' IRM fails downscale 3 2 N-BOP Remove 'C' RFP from service 4 3 C-BOP HPCI spurious ECCS actuation 5 4 C-RO Rod drift 6 5 C-BOP 'B' RFP trips 7 6 M-ALL Large break LOCA ramped in 8 7 M-ALL Loss of off-site power 9 8 C-BOP RHR pump fails to auto start I (N)ormal, (K)eactivity, (I)nstrument, (C)omponent, (M)ajor

I-arm Li-U-1 ppenaix D Appendix u scenario uutiine cenario Outlne Form ES-D-1 Facility: Pilgrim Scenario No.: 3 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 20% turbine synced to grid, 'A' RBCCW pump out of service Turnover: Startinq up following scram Event No.

MaIf.

No.

1 Event JType*

Event Description 1 N/A R-RO Continue reactor startup 2 1 N-BOP MSIV twice weekly surveillance, PNPS 8.7.4.5 3 2 I-RO FRV lockup 4 3 C-BOP 'B' RBCCW pump trip 5 4 C-RO CRD FCV fails closed 6 5 C-BOP Turbine high vibration 7 6 M-ALL ATWS 8 7 C-RO SLC pump failure 4 4 4.

4 4 4.

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

Appendix D Scenario Outline Form ES-D-11 Aooendix D Scenario Outline Form ES-D-1 Facility: Pilgrim Scenario No.: (Spare) Op-Test No.:

Examiners: Operators:

Initial Conditions: 75%, 'A' core spray OOS, 'B' recirc MG aux oil pump OOS Turnover: Raise reactor power following backwash Event Malf. Event Event No. No. Type* Description 1 N/A R-RO Raise reactor power 2 1 N-BOP Swap SSW pump for vibes 3 2 C-RO RPS MG set trip 4 3 C-BOP SRV fails open 5 4 C-RO CRD pump trips 6 5 M-ALL Small break LOCA inside containment 7 6 C-BOP Bypass valves fail closed after scram I

+i I i I I i i I i i I I1 i I I i II..

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1
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