ML021700258

Final - Outlines (Change Summaries - Optical)

ML021700258
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	04/17/2002
From:	Alan Blamey Exelon Nuclear
To:	Exelon Nuclear, Office of Nuclear Reactor Regulation
References
50-277/02301, 50-278/02301, 50-352/02301, 50-353/02301
Download: ML021700258 (15)

Text

April 17, 2002 MEMORANDUM TO: Exam File Exelon LSRO - Peach Bottom / Limerick Station FROM: Alan Blamey ,* Z3 Senior Operations Engineer

SUBJECT:

CHANGE TO PEACH BOTTOM (PBAPS) / LIMERICK (LGS)

STATION LIMITED SENIOR REACTOR OPERATOR EXAM OUTLINE IN REFERENCE TO ROI 02-04.

The purpose of this memorandum is to document the change to the PBAPS / LGS exam outline in reference to the incorporation of ROI 02-04. The exam outline was reviewed in reference to ROI 02-04 and found to meet the condition specified in the ROI. The outline changes are listed below.

ROI 02-04 changes - Category A JPM A.1-2 Was changed to specifically examine differences between PBAPS and LGS.

JPM A.3 Was changed from a JPM to 2 questions to make the task more PBAPS specific.

Written Exam (Unrelated Changes)

Question 3-12 Fuel handling equipment question changed from a PBAPS to a LGS question.

Question 3-16 Equipment control question changed from a LGS to a common question.

In both cases the K/A remained the same only the effected unit changed. The distribution of the exam is still evenly distributed among PBAPS (28%), LGS (28%) and Common (44%).

Based on these changes the original ES-201-2, "LSRO Examination Outline Quality Checklist,"

was re-reviewed and found to be still valid. A revised ES-201-2 form will not be issued.

ýt&7 Re-rev iewed A Approved

EXELON NUCLEAR 2002 INITIAL LIMITED SENIOR REACTOR OPERATOR LICENSE EXAMINATION SAMPLE PLAN EXAM DATE: 06/03/02 FACILITIES: LIMERICK GENERATING STATION 1 & 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 8 handling or shutdown activities 2 System equipment and instruments that are (30%) important to plant safety and are located near or used during fuel handling activities or 1 during alternate shutdown procedures 3 Normal, abnormal, emergency operating and

"(40%) administrative procedures related to fuel 21 handling activities 4 Health physics and radiation protection for fuel (15%) handling activities and general employee 6 responsibilities 100% Totals 50 Notes:

Question sequence on exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 1 of 14

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 Outline System System Name K/A # K/A Topic(s) Imp. Unit I.D._

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 2.6 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 C1 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 KI.31 Core orificing 3.0 C Hydraulics Notes:

Question sequence on exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 2 of 14

EXELON NULEAR EXEL ON 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.

Outline System System Name KJA # K/A Topic(s) Imp Unit I.D.

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 Racirculation K1.18 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 (WRNM) 2.1.12 Apply Tech Specs for a system 4.0 PB 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 exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 3 of 14

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.

Outline System System Name K/A # K/A Topic(s) Imp Unit i.D.

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 Umerick and Peach Bottom Notes:

Question sequence on exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 4 of 14

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.

Outline System System Name K/A # KWA Topic(s) Imp Unit I.D.

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

_ 1Accidents 3-5 2.2 Equipment 2.2.26 Knowledge of refueling 3.7 LO 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 3.2 C operations 3-11 234000 Fuel handling K5.05 Fuel orientation 3.7 PB I equipment Notes:

Question sequence on exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick I and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 5 of 14

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.

Outline System System Name K/A # K/A Topic(s) Imp Unit I.D. _ __ I" 3-12 234000 Fuel handling K4.03 Protection against lifting rad. 4.2 LG equipment 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 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 C 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 exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 6 of 14

EXELON NULEAR Group 4 - 15%

6 Questions Subject Area: Health physics and radiation protection for fuel handling activities and general employee responsibilities.

Administrative procedures associated with radiation protection.

Outline System System Name K/A*# K/A Topic(s) Imp Unit I.D.

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 exam differs from the outline. The exam key provides a cross reference.

Unit Codes: LG-Limerick 1 and 2, PB-Peach Bottom 2 and 3, C-Common to Limerick and Peach Bottom Page 7 of 14

EXELON NULEAR II. OPERATING EXAM A. CATEGORY A - ADMINISTRATIVE TOPICS OUTLINES ES-301 ADMINISTRATIVE TOPICS OUTLINE Form ES-301-1 Facilities: LGS Units I & 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 (3.4) Ability to locate and use procedures and directives related to shift staffing and activities LGS JPM: Apply working hour limitations for LSRO and platform JPM operator 2.1.3 (3.4) Knowledge of shift turnover practices Shift Turnover LGS/PBAPS JPM: Assess turnover conditions for LGS and PBAPS for different Differences limits

¶ JPM A.2 Core Locations 2.2.3 (3.3) Knowledge of design, procedural, and operational LGS/PBAPS differences between units Differences JPM JPM: Conduct core counting to identify SRM location at LGS and WRNM at PBAPS from above-core pictures A.3 2.3.2 (2.9) Knowledge of facility ALARA program Radiation Control Question: Response to personal contamination PBAPS 2.3.10 (3.3) Ability to perform procedures to reduce excessive Questions radiation levels and guard against personnel exposure Question: Drywell access restrictions during fuel handling A.4 Refueling Accident 2.4.41 (4.1) Knowledge of the emergency action level thresholds Emergency Action and classifications Level (EAL) JPM: Determine EAL for refueling accident conditions PBAPS JPM Page 8 of 14

EXELON NULEAR B. CATEGORY B - SYSTEMS EXAMINATION OUTLINES ES-301 INDIVIDUAL WALK-THROUGH TEST OUTLINE Form ES-301-2 Facility: LGS Units I 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 (K/A 2.2.28 Imp. 3.5)

b. Fuel Handling Equipment I LPRM removal (K/A 2.2.27 Imp. 3.5)

c. Fuel Handling Equipment / Movement of fuel from fuel prep machine to spent fuel pool - alt path due to slack cable warning ANPR FHE (K/A 2.2.28 Imp. 3.5)

d. Aux Systems / Response to loss of air to cavity seals NPR AUX (KJA 233000A2.01 Imp. 3.2)

e. Radiation Monitoring / Defeat Unit I and Unit 2 HVAC rad isolation signals to support irradiated component movement NPR IC (K/A 234000A3.02 Imp. 3.6) f.

g.

B.2 Facility Walk-Through 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 Page 9 of 14

EXELON NULEAR EXEL ES-301ON NULEAR INDIVIDUAL WALK-THROUGH TEST OUTLINE Form ES-301-2 Facility: Peach Bottom 2 and 3 Date of Examination: 6/3/02 -617102 Examination Level: LSRO Operating Test Number:.

System / JPM Title Type Safety Code* Function

a. Fuel Handling Equipment / Log on to refuel platform and set up for DRP FHE semi-automatic motion (K/A 234000A3.02 Imp. 3.7)

b. Fuel Handling Equipment / Automatic dummy bundle transfer in the DRP FHE spent fuel pool (actual movement)

(K/A 234000A3.02 Imp. 3.7)

c. Fuel Handling 'Equipment / Control rod removal using combined grapple NARP FHE

- alternate path due to rod indicating still coupled (K/A 2.2.32 Imp. 3.7)

d. Aux Equipment / Maintenance on the Tri-Nuclear Underwater Vacuum NRP AUX Unit (K/A 2.2.27 Imp. 3.5)

e. Nuclear Instruments / Abnormal WRNM response (inadvertent NARP IC criticality) during core alterations (K/A 295023AA2.04 Imp. 4.1) f.

g.

S fl 0, - 1A 1. II=I B.2 racility WalK- Inrougn a.

b.

C.

• Type Codes: (D) irect from bank, (M) odified from bank, (N) ew, (A) Itemate 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 Page 10 of 14

E)XELON 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. 1 Op-Test Number:

Examiners: _

Operators:

Initial Conditions: Shuffle Part I is in progress on Unit I 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

[damage.

k r,4 )urmal, t K )eactiviy,  % ( I)nstrument, ( C )omponent, ( M )ajor Page 11 of 14

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

Examiners: 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 12 of 14

p 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

( M )ajor N

I(N)ormal, ( K )eacti ty, ( I )nstrument, ( C )omponent, Page 13 of 14

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

• I * ,*'---l-- _+/-_-. "

k,I'm)orlmal, ( R )eactiviy, ( I )nstrument, ( C )omponent, ( M )ajor Page 14 of 14