ML021690527

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Draft - Outlines (Facility Ltr Dtd 3/15/02)
ML021690527
Person / Time
Site: Peach Bottom, Limerick  Constellation icon.png
Issue date: 05/24/2002
From: Wasong A
Exelon Nuclear
To: Conte R
NRC/RGN-I/DRS/OSB
References
Download: ML021690527 (17)
v • d • e


Text

Exek~ni.

Limerick Training Center 341 Longview Road Linfield, PA 19468-1041 Telephone 610.718.4000 Fax 610.718.4028 www.exeloncorp.com Nuclear Exelon Nuclear Limerick Generating Station PO. Box 2300 Sanatoga, PA 19464-0920 March 15, 2002 U.S. NRC Region I Administrator 475 Allendale Road King of Prussia, PA 19406

Subject:

Submittal of Limited Senior Reactor Operator Examination Outline Limerick Generating Station, Units 1 and 2 (Docket # 50-352 and 50-353)

Peach Bottom Atomic Power Station, Units 2 and 3 (Docket # 50-277 and 50-278)

In accordance with NUREG 1021, Revision 8, "Operating Licensing Examination Standards for Power Reactors", Exelon is submitting the Limited Senior Reactor Operator examination outlines for Limerick Generating Station and Peach Bottom Atomic Power Station. This submittal supports the initial license examination scheduled for the week of June 3, 2002.

In accordance with NUREG 1021, Revision 8, Section ES-201, please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Should you have any questions concerning this letter or the examination outlines, please contact Jeff Stevens at (610) 718-4011.

Respectfully, Brandon K. Shultz Facility Representative/Senior Reactor Operator Limerick Generating Station

Enclosure:

(Hand delivered to Allen Blamey, Chief Examiner, NRC Region I)

Examination Outline Quality Checklist ES-201-3, Examination Security Agreements ES-301-1, Administrative Topics Outline ES-301-3, Facility Walk-Through Test Outline ES-701, LSRO Written Examination Outline ES-D-1, Scenario Outlines

EXELON NUCLEAR 2002 INITIAL LIMITED SENIOR REACTOR OPERATOR LICENSE EXAMINATION SAMPLE PLAN EXAM DATE: 06/03/02 FACILITIES:

LIMERICK GENERATING STATION I & 2, and PEACH BOTTOM ATOMIC POWER STATION 2 & 3 I. WRITTEN EXAM A. OUTLINE: (ES-701)

Group Subject area Number of (Sample %)

Questions 1

Reactor and fuel characteristics and physical (15%)

aspects of core construction important to fuel handling or shutdown activities 2

System equipment and instruments that are (30%)

important to plant safety and are located near 15 or used during fuel handling activities or during alternate shutdown procedures 3

Normal, abnormal, emergency operating and (40%)

administrative procedures related to fuel handling activities 21 4

Health physics and radiation protection for fuel (15%)

handling activities and general employee 6

responsibilities 100%

Totals 50 Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 1 of 15

EXELON NUCLEAR B. CONTENT:

Group 1 - 15%

8 Questions Subject Area:

Reactor and fuel characteristics and physical aspects of core construction important to fuel handling or shutdown activities System System Name K/A #

K/A Topic(s)

Imp.

Unit 1-1 291002 Sensors and K1.19 Operation of fission chamber 3.1 C

Detectors 1-2 291006 HX and Cond.

K1.04 Flow effects on heat transfer 2.8 C

1-3 292001 Neutrons K1.03 Define thermal neutrons 2.7 C

1-4 292002 Neutron Life K1.14 Changes to shutdown margin 2.9 C

Cycle 1-5 292003 Rx Kinetics K1.06 Effect of delayed neutrons on 3.7 C

reactor period 1-6 292005 Control Rods K1.01 Rod and notch position 3.3 C

1-7 292008 Rx Operational K1.30 Decay heat and time since S/D 3.5 C

Physics 1-8 293008 Thermal K1.31 Core orificing 3.0 C

Hydraulics Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 2 of 15

EXELON NULEAR Group 2 - 30%

15 Questions Subject Area:

System equipment and instruments that are important to plant safety and are located near or used during fuel handling activities or during alternate shutdown procedures Knowledge and use of radiation monitors, spent fuel pool cooling and residual heat removal (RHR) systems and the Technical Specifications associated with those systems.

Question System System Name K/A #

K/A Topic(s)

Imp Unit 1

2-1 201002 Rx Man A1.01 CRD drive water flow 2.8 PB Control 2-2 201003 CRD Mech K4.06 CRD uncoupling 2.6 C

2-3 202001 Recirculation KI.18 Shutdown cooling mode 3.3 LG 2-4 205000 RHR SDC K2.01 Pump motors 3.1 PB 2-5 290002 RPV Internals 2.2.32 Effects of alterations on core 3.3 C

configuration 2-6 290001 Secondary K3.01 Offsite release rates 4.4 LG Containment 2-7 215003 IRM 2.1.12 Apply Tech Specs for a system 4.0 PB (WRNM) 2-8 215004 SRM A4.06 Alarms and lights 3.1 LG 2-9 234000 Fuel Handling A3.01 Crane/refuel bridge movement 3.6 PB Equipment.

2-10 233000 Fuel Pool K4.06 Maintenance of adequate pool 3.2 LG Cooling level 2-11 234000 Fuel Handling K6.04 Refueling platform air system 3.7 PB Equip 2-12 288000 Plant K4.02 Secondary Containment isolation 3.8 LG Ventilation Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 3 of 15 EXEL ON NULEAR

EXELON NULEAR Group 2 - 30%

15 Questions Subject Area:

System equipment and instruments that are important to plant safety and are located near or used during fuel handling activities or during alternate shutdown procedures Knowledge and use of radiation monitors, spent fuel pool cooling and residual heat removal (RHR) systems and the Technical Specifications associated with those systems.

Question System System Name K/A #

KJA Topic(s)

Imp Unit 2-13 272000 Radiation 2.2.26 Refueling administrative 3.7 LG Monitoring requirements 2-14 234000 Fuel Handling K5.02 Fuel handling equipment 3.7 PB Equipment interlocks 2-15 215004 SRM K3.01 RPS 3.4 LG Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 4 of 15

EXELON NULEAR Group 3 - 40%

21 Questions Subject Area:

Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.

Control room operator's response to events only as it relates to fuel handling activities and the general response expected of employees.

Question System System Name K/A #

K/A Topic(s)

Imp Unit 3-1 295031 Low EK2.05 Low Pressure Coolant Injection 4.3 PB RPV/Cavity (RHR)

Level 3-2 295034 Sec. Cont.

EK2.01 Process rad monitoring system 4.2 LG Vent High Rad 3-3 295023 Refueling AK1.03 Inadvertent criticality 4.0 PB Accidents 3-4 295023 Refueling AK3.01 Refueling floor evacuation 4.3 PB Accidents 3-5 2.2 Equipment 2.2.26 Knowledge of refueling 3.7 LG control administrative requirements 3-6 2.1 Conduct of 2.1.12 Ability to apply technical 4.0 PB operations specifications for a system 3-7 2.2 Equipment 2.2.27 Knowledge of the refueling 3.5 LG control process 3-8 2.2 Equipment 2.2.20 Knowledge of the process for 3.3 C

control managing troubleshooting activities 3-9 2.4 Emergency 2.4.38 Ability to take actions called for in.

4.0 C

Plan the facility emergency plan 3-10 2.1 Conduct of 2.1.20 Ability to execute procedure steps 4.2 C

operations 3-11 234000 Fuel handling K5.05 Fuel orientation 3.7 PB equipment Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 5 of 15

EXELON NULEAR Group 3 - 40%

21 Questions Subject Area:

Normal, abnormal, emergency operating and administrative procedures related to fuel handling activities, core safety, and accident mitigation, including general facility events.

Control room operators response to events only as it relates to fuel handling activities and the general response expected of employees.

Question System System Name K/A #

K/A Topic(s)

Imp Unit 1

3-12 234000 Fuel handling K4.03 Protection against lifting 4.2 equipment radioactive components out of the water 3-13 234000 Fuel handling A2.03 Loss of electrical power 3.1 PB equipment 3-14 234000 Fuel handling A3.02 Interlock operation 3.7 PB I

equipment 3-15 2.2 Equipment 2.2.27 Knowledge of the refueling 3.5, LG control process 3-16 2.2 Equipment 2.2.6 Knowledge of the process for 3.3 control making changes to procedures 3-17 2.2 Equipment 2.2.22 Knowledge of LCOs and safety 4.1 LG control limits 3-18 2.2 Equipment 2.2.22 Knowledge of LCOs and safety 4.1 PB control limits 3-19 2.1 Conduct of 2.1.3 Knowledge of shift turnover 3.4 C

operations practices 3-20 2.1 Conduct of 2.1.18 Ability to make accurate, clear, 3.0 C

operations and concise logs and records 3-21 2.4 Emergency 2.4.10 Knowledge of annunciator 3.1 LG Procedures response procedures Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 6 of 15

EXELON NULEAR Group 4 - 15%

6 Questions Subject Area:

Health physics and radiation protection for fuel handling activities employee responsibilities.

Administrative procedures associated with radiation protection.

and general Question System System Name K/A #

K/A Topic(s)

Imp Unit 4-1 2.3 Radiation 2.3.1 10CFR20 and related facility 3.0 C

Control controls 4-2 2.3 Radiation 2.3.2 Knowledge of facility ALARA 2.9 C

Control program (Dose extension) 4-3 2.3 Radiation 2.3.2 Knowledge of facility ALARA 2.9 C

Control program (Postings and controls) 4-4 2.3 Radiation 2.3.4 Knowledge of exposure limits 3.1 C

Control and controls 4-5 2.3 Radiation 2.3.5 Knowledge of the use and 2.5 C

Control function of personal monitoring equipment 4-6 2.3 Radiation 2.3.7 Knowledge of the process for 3.3 C

Control preparing a radiation work permit Notes:

Question sequence on completed exam may differ from sequence in the outline Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 7 of 15

EXELON NUCLEAR ES-301 ADMINISTRATIVE TOPICS OUTLINE Form ES-301-1 Facilities: LGS Units 1 & 2 Date of Examination: 613102-617102 PBAPS Units 2 & 3 Examination Level:

LSRO Operating Test Number:

Administrative Method of Evaluation:

Topic / Subject

1. ONE Administrative JPM, or Description
2. TWO Administrative Questions A. 1 Working Hour Limits 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities PBAPS JPM JPM: Apply working hour limitations for LSRO and platform operator 2.1.25 Ability to obtain and interpret station reference materials Station Reference such as graphs, monographs, and tables which contain

.=

Material Interpretation performance data LGS JPM JPM:

Evaluate loss of cooling conditions and determine time, to cavity boiling from chart A.2 2.2.3 Knowledge of design, procedural, and operational Core Location differences between units Differences JPM: Conduct core counting to identify IRM location at LGS and LGS/PBAPS JPM WRNM at PBAPS from above-core pictures A.3 2.3.5 Knowledge of the use and function of personnel monitoring Electronic Dosimeter equipment PBAPS JPM JPM: Verify setting of electronic dosimeter for the fuel floor RWP A.4 2.4.41 Knowledge of the emergency action level thresholds and Refueling Accident classifications Emergency Action Level (EAL)

JPM: Determine EAL for refueling accident conditions LGSJPM C'~~

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EXELON NULEAR ES-301 ADMINISTRATIVE TOPICS OUTLINE Form ES-301-1 Facility:

PBAPS Units 2 & 3 Date of Examination:

6/3/02-6002 Examination Level:

LSRO Operating Test Number:

Administrative-Method of Evaluation:

Topic / Subject

1. ONE Administrative JPM, or Description
2. TWO Administrative Questions A. 1 Working Hour Limits 2.1.5 Ability to locate and use procedures nd directives related to shift staffing and activities JPM JPM: Apply working hour limitation

/

or LSRO and platform operator

3. 4 Shift Tumnover 2.1.3 Knowledge of shift tur ver practices JPM JPM: Assess turnover nditions A.2 Secondary 2.2.26 Knowlede of refueling administrative requirements Containment Requirements JPM: Dete mne the requirement for secondary containment while JPM o

m ing loads over spent fuel 37 A.3 2.3.2 nowledge of facility ALARA program Radiatio Controlam Radiation Control estion: Response to personal contamination Z.1 Questions 2.3.10 Ability to perform procedures to reduce excessive radiation levels and guard against personnel exposure

_/

Question: Drywell access restrictions during fuel handling 3.-s A.4 2.4.41 Knowledge of the emergency action level thresholds and Refueling ccident classifications Emerge y Actionclsicaon L/IJPM:

Determine EAL for refueling accident conditions

____4.1 Page 9 of 15

EXELON NULEAR II. OPERATING EXAM A. CATEGORY A - ADMINISTRATIVE TOPICS OUTLINES ES-301 ADMINISTRATIVE TOPICS OUTLINE Form ES-301-1 Facility:

LGS Units I and 2 Date of Examination: 613/02-6/7/02 Examination Level:

LSRO Operating Test Number:

Administrative Method of Evaluation:

Topic / Subject

1. ONE Administrative JPM, or Description
2. TWO Administrative Questions A.l1 2.1.24 Ability to obtain and interpret statio electrical and Print Reading mechanical drawings JPM JPM: Demonstrate the Shutdown CC/ling Alternate Decay Heat Removal flow path on a P&.

Ha 2.1.25 Ability to obtain andi terpret station reference materials Station Reference such as graphs, onographs, and tables which contain S t a t io nt a i R e e e c e f ra nd, t '

Material Interpretation performance d a JPM JPM:

Evaluate I s of cooling conditions and determine time to cavity b *iing from chart

3. 1 A.2 2.2.3 K"ledge of design, procedural, and operational Core Location ifferences between units Differences JP :/Conduct core counting to identify IRM location at LGS and JPM WRNM at PBAPS from above-core pictures 3.3 A.3 2.3.5 Knowledge of the use and function of personnel monitoring Electronic Dosi eter equipment JPM JPM: Verify setting of electronic dosimeter for the fuel floor RWP 2.5 A.4 Eme ency Plan 2.4.42 Knowledge of emergency response facilities uestions Question: Activation levels for response facilities 2.4.29 Knowledge of the emergency plan Question: Evacuation facilities 0,o VO f1<

V 1 Page 8 of 15

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EXELON NULEAR B. CATEGORY B - SYSTEMS EXAMINATION OUTLINES ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE Form ES-301-2 Facility:

LGS Units 1 and 2 Date of Examination:

6/3/02 - 6/7/02 Examination Level:

LSRO Operating Test Number:

System / JPM Title Type Safety Code*

Function

a. Fuel Handling Equipment / Movement of dummy bundle in the spent fuel pool (actual movement) - alt path due to debris obstructing target ANPR FHE location
b. Fuel Handling Equipment / LPRM removal NPR FHE
c. Fuel Handling Equipment / Movement of fuel from fuel prep machine to ANPR FHE spent fuel pool - alt path due to slack cable warning
d. Aux Systems / Response to loss of air to cavity seals NPR AUX
e. Radiation Monitoring / Defeat Unit 1 and Unit 2 HVAC rad isolation NPR ICt signals to support irradiated component movement
f.

g.

Page 10 of 15 B.L F-acility vvalk-I nrougn

a.
b.

C.

  • Type Codes: (D) irect from bank, (M) odified from bank, (N) ew, (A) Iternate path, (C) ontrol room, (S) imulator, (L) ow-Power, (P) lant, (R) CA Safety Function: FHE: Fuel Handling Equipment, AUX: Auxiliary Systems, IC: Instrumentation and Control; DHR: Decay Heat Removal, RM: Radiation Monitoring

EXELON NULEAR ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE Form ES-301-2 Facility:

Peach Bottom 2 and 3 Date of Examination:

6/3/02 -6/7/02 Examination Level:

LSRO Operating Test Number:

System / JPM Title Type Safety Code*

Function

a. Fuel Handling Equipment I Log on to refuel platform and set up for DRP FHE semi-automatic motion
b. Fuel Handling Equipment / Automatic dummy bundle transfer in the DRP FHE spent fuel pool (actual movement)
c. Fuel Handling Equipment / Control rod removal using combined grapple NARP FHE

- alternate path due to rod indicating still coupled

d. Aux Equipment / Storage of the Tri-Nuclear Underwater Vacuum Unit NRP AUX
e. Nuclear Instruments / Abnormal WRNM response (inadvertent NARP IC criticality) during core alterations
f.

g.

Page 11 of 15 D.

r-acliny vvaIK-I nrougn

a.
b.

C.

  • Type Codes: (D) irect from bank, (M) odified from bank, (N) ew, (A) Iternate path, (C) ontrol room, (S) imulator, (L) ow-Power, (P) lant, (R) CA Safety Function: FHE: Fuel Handling Equipment, AUX: Auxiliary Systems, IC: Instrumentation and Control; DHR: Decay Heat Removal, RM: Radiation Monitoring

EXELON NULEAR C. CATEGORY C - INTEGRATED PLANT (REFUELING EQUIPMENT) EXAMINATION OUTLINE Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: LGS 1 and 2 Scenario No.

I Op-Test Number:

Examiners:

Operators:

Initial Conditions: Shuffle Part 1 is in progress on Unit 1 Turnover: A fuel bundle is in transit from the core to the spent fuel pool Event Malf Event Event No.

No.

Type*

Description Minor leakage reported from drywell upper seal plate into the

1.

N/A C

drywell requires temporary suspension of fuel movement to allow /

access to upper drywell area for inspection.

2.

N/A M

A fuel bundle is dropped onto spent fuel pool with significant fuel I_

damage.

  • I I

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( U )omponent,

( M )ajor Page 12 of 15

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EXELON NULEAR Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: LGS 1 and 2 Scenario No.

2 Examiners:

Op-Test Number:

Operators:

Initial Conditions: In-vessel maintenance is in progress on Unit 2 Turnover: The bridge is over the core and moving toward the fuel pool with a double blade guide hanging from the main hoist and a control rod/fuel support piece on the combined grapple hanging from the monorail aux hoist.

Event Malf Event Event No.

No.

Type*

Description

1.

N/A I

Receipt of unexpected rod block over core due to load cell failure

,2.

N/A M

Significant leakage from CRD Mechanism Housing requires installation of the Emergency Guide Tube Seal

( N )ormal,

( R )eactivity,

( I )nstrument, (C )omponent,

( M )ajor Page 13 of 15

EXELON NULEAR Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: PBAPS 2 and 3 Scenario No.

1 Op-Test Number:

Examiners:

Operators:

Initial Conditions: Core alterations are in progress on Unit 3 Turnover: A bundle is being raised from the core.

Event Malf Event Event No.

No.

Type*

Description

1.

N/A C

Hoist jam condition while moving fuel

2.

N/A M

Unexpected fuel floor area radiation monitor alarm

( I )nstrument,

( C )omponent,

( M )ajor Page 14 of 15 k, I*1 rUI lll t I%)eacuvItly,

EXELON NULEAR Appendix D SCENARIO OUTLINE Form ES-D-1 Facility: PBAPS 2 and 3 Scenario No.

2 Op-Test Number:

Examiners:

Operators:

Initial Conditions: Core shuffle part 2 is in progress.

Turnover: A bundle is in transit from the fuel pool to the core.

Event Malf Event Event No.

No.

Type*

Description

1.

N/A I

Wide Range Nuclear Monitoring (WRNM) Instrument failure requires suspension of core alterations

2.

N/A M

Loss of cavity level and emergency makeup k r )eactivity,

( I )nstrument,

(

)omponent,

( M )ajor Page 15 of 15 k,qI' )UIImll,

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