ML102420204

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and Peach Bottom Lsro - Final Outlines (Folder 3)
ML102420204
Person / Time
Site: Peach Bottom, Limerick  Constellation icon.png
Issue date: 07/09/2010
From: Dickenson R, Wasong A
Exelon Generation Co
To: D'Antonio J
Operations Branch I
Hansell S
Shared Package
ML092470056 List:
References
TAC U01795, TAC U01796
Download: ML102420204 (10)
v • d • e


Text

ES-701 LSRO BWR Written Examination Outline Form ES-701-1

LGS Date of Exam: 192010 KIA Points Tier K1 K2 K3 K4 K5 K6 A1 A2 A3 G Total
1. 2 2 1 1 Emergency & 10 Abnormal Plant Evolutions
2. 2 1 2 2 2 1 2 2 2 Plant 20
3. Generic Knowledge and 1 3 4 GFE Abilities Categories 10 2 2 2 2 Note: 1. Ensure that at least one topic from every KIA category is sampled within each tier.
2. The point total for each tier in the proposed outline must match that specified in the table. The final pOint total for each tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 40 points.
3. Select topics from many systems and evolutions; avoid selecting more than two KIA topics from a given system (except fuel handling equipment) or evolution (except refueling accident).
4. The shaded areas are not applicable to the category/tier.

5.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

6. If the applicants have not previously taken the GFE, Tier 3 shall include basic reactor theory, component, and thermodynamic topiCS that apply to fuel handling operations.
7. Systems/evolutions within each tier are identified on the associated outline.

Enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the SRO license level, and the point totals (#) for each system and category. Enter the tier totals for each category in the table above.

8. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, importance ratings, and point totals (#) on Form ES-701-3.
9. Refer to ES-401, Section D.1, for guidance regarding the elimination of inappropriate KIA statements. The facility licensee's JTA for fuel handlers should be used as the basis for eliminating or adding testable topiCS.

ES*701 LSRO BWR Written Examination Outline Form ES*701*1 Emergency and Abnormal Plant Evolutions* Tier 1

~G K 3

A 1

A 2

G KIA Topic(s) IR #

295003 Partial or Complete Loss of AC X I I AK 1.04, Electrical bus divisional separation 3.2 1 295004 Partial or Total Loss of DC 295014 Inadvertent Reactivity Addition AK2.07, Reactor Power 3.9 1 295018 Partial or Total Loss of CCW

  • 295021 Loss of Shutdown Cooling 11 X AA 1.01, Backup systems X G2.2.42, Ability to recognize system parameters that 3.4 4.6 I 1 1

are entry-level conditions for Technical Specifications.

295023 Refueling Accidents 295033 High Secondary Containment X EK1.02, Personnel protection 4.2 1 Area Radiation Levels 295034 Secondary Containment X EA2.01, Area radiation levels 4.2 1 Ventilation High Radiation 295006 SCRAM X AA2.02, Control rod position 4.4 1 295008 High Reactor Water Level 295009/295031 Reactor Low Water X EK2.03, Low pressure core spray 4.3 1 Level 295017/295038 High Offsite Release Rate 295019 Partial or Total Loss of Inst. Air X AA 1.02, Instrument air system valves 3.1 1 295020 Inadvertent Cont. Isolation 295030 Low Suppression Pool Wtr Lvi 295035 Secondary Containment High Differential Pressure I I +=

600000 Plant Fire On Site X AK3.04, Actions contained in the abnormal procedure 3.4 1 for plant fire on site I

KIA Category Totals:  ?  ? 1 ~.

. ~otal:

IlWI

ES-701 LSRO BWR Examination Outline Form ES-701-1 Plant Systems - Tier 2 205000 Shutdown Cooling K

1 X

KGG 2 KMA 4 5 2 A

3 4 G KJA Topic(s)

K1.15, RHR service water 3.6 IR 1

215004 Source Range Monitor X K2.01, SRM channels/detectors 2.8 1 233000 Fuel Pool X 2.1.45, Ability to identify and interpret diverse 4.3 1 Cooling/Cleanup indications to validate the response of another indication.

234000 Fuel Handling X A2.01, Interlock failure 3.7 1 Equipment 262001 AC Electrical Dist.

263000 DC Electrical Dist.

=G A3.02, Automatic bus transfer 3.3 1 290002 Reactor Vessel X K4.05, Natural circulation 3.5 1 Intemals 201002 RMCS X A4.01, Rod movement control switch 3.4 1 201003 Control Rod and X K4.01, Limiting control rod speed in the event 3.0 1 Drive Mechanism I ofa rod drop 203000 RHA/LPCI: X K3.01, Reactor water level 4.4 1 Iniection Mode 204000 RWCU 211000 SLC X X A4.01, System pumps A1.08, RWCU system lineup 3.0 3.8 j 212000 RPS X K5.02, Specific logic arrangements 3.4 1 214000 RPIS 01 Traversing In-Core e

2150031RM X AS.OS, RPS status 3.6 1 215005 APRM I LPRM 223001 Primary CTMT and Aux.

223002 PCISlNuclear Steam X K6.0S, VariOUS process instrumentation 2.9 1 Supply Shutoff 261000 SGTS X A1.01, System flow S.1 1 264000 EDGs X K3.01, Emergency core cooling systems 4.4 1 272000 Radiation Monitoring X 2.4.11, Knowledge of abnormal condition 4.2 1 procedures 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 300000 Instrument Air X H X K5.01, Airbome contamination control K1.04, SBGT 3.2 3.9 1

1 400000 Component Cooling X K6.06, Heat exchangers and condensers 2.9 1 Water I KJA Category Totals: 2m2 2 2 oint Total: 20

ES-701 LSRO Generic Kr .1......

and Abilities Outline (Tier 3) Form ES-701-3 Facility: LGS Date of Exam: July 192010 Cah~yv,y KIA # Topic IR #

2.1.3 Knowledge of shift or short-term relief turnover 3.9 1 pradir.p~

1.

Conduct of 2.1.29 Knowledge of how to conduct system lineups, 4.0 1 Operations such asyah/~~ breakers, ':>YYILvl n::.:>, etc.

2.1 2.1 Subtotal 2 2.2.39 Knowledge of less than or equal to one hour 4.5 1

2. Technical Specification action statements for tiytil~lllti.

Equipment Control 2.2.3 (multi-unit license) Knowledge of the design, 3.9 1 procedural, and operational differences between units.

2.2.

2.2.

Subtotal 2.3.15 Knowledge of radiation monitoring systems, such 3.1 1

3. as fixed radiation monitors and alarms, portable Radiation Control survey instruments, personnel monitoring equipment, etc.

2.3.12 Knowledge of radiological safety principles 3.7 1 pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning fillers, etc.

2.3, 2.3.

Subtotal 2 2.4.40 Knowledge of SRO responsibilities in emergency 4.7 1 plan'Iml-'ICIIICI

.1. IlCUIVII.

4.

Emergency 2.4.28 Knowledge of procedures relating to a security 4.1 1 Procedures I event (non-safeguards information).

Plan 2.4.

2.4.

$ubtotal ~"< *. i8l.' 2 291003 Function and operation of flow controller in 3.7 1

5. K1.01 manual and automatic modes I Generic 292002 Evaluate change in shutdown margin due to 2.9 1 Fundamentals K1.14 chd.'-!Y~ti in FlantFarClr.I~L~1 ti i i

Bl,~o Subtotal Tier 3 Point Total

ES-701 LSRO BWR Written Examination Outline Form ES-701-1 Facil PBAPS Date of Exam: Ju 192010 KIA Points Tier K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Total

1. 1 1 0 0 2 1 Emergency & 5 Abnormal Plant Evolutions
2. 1 0 1 0 0 1 0 1 0 0 1 Plant 5
3. Generic Knowledge and 1 2 3 4 GFE Abilities Categories o o o o o o

Note: 1. Ensure that at least one topic from every KIA category is sampled within each tier.

2. The point total for each tier in the proposed outline must match that specified in the table. The final pOint total for each tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final exam must total 40 pOints.
3. Select topics from many systems and evolutions; avoid selecting more than two KIA topics from a given system (except fuel handling equipment) or evolution (except refueling aCCident).
4. The shaded areas are not applicable to the category/tier.

5.* The generic (G} KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

6. If the applicants have not previously taken the G FE, Tier 3 shall include basic reactor theory, component, and thermodynamic topics that apply to fuel handling operations.
7. Systems/evolutions within each tier are identified on the associated outline.

Enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the SRO license level, and the point totals (#) for each system and category. Enter the tier totals for each category in the table above.

8. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, importance ratings, and point totals (#) on Form ES-701-3.
9. Refer to ES-401 , Section 0.1, for guidance regarding the elimination of inappropriate KIA statements. The facility licensee's JTA for fuel handlers should be used as the basis for eliminating or adding testable topics.

ES-701 LSRO BWR Written Examination Outline Form ES-701-1 Emergency and Abnormal Plant Evolutions - Tier 1 K K K A A G KJA Topic(s) IR #

1 2 3 1 2 295003 Partial or Complete Loss of AC X AK1.04, Electrical bus divisional s~aration 3.2 1 295004 Partial or Total Loss of DC 295014 Inadvertent Reactivity Addition 295018 Partial or Total Loss of CCW 295021 Loss of Shutdown Cooling X G2.2.42, Ability to recognize system parameters that 4.6 1 are entry-level conditions for Technical Specifications.

295023 Refueling Accidents 295033 High Secondary Containment Area Radiation Levels 295034 Secondary Containment X EA2.01, Area radiation levels 4.2 1 Ventilation High Radiation 295006 SCRAM X AA2.02, Control rod~sition 4.4 1 295008 High Reactor Water Level 295009/295031 Reactor Low Water X EK2.03, Low pressure core spray 4.3 1 Level 295017/295038 High Offsite Release Rate 295019 Partial or Total Loss of Inst. Air 295020 Inadvertent Cont. Isolation 295030 Low Suppression Pool Wtr Lvi 295035 Secondary Containment High Differential Pressure 600000 Plant Fire On Site KJA Category Totals: 1 1 0 0 2 1 Tier Point Total: 5

ES*701 LSRO BWR Examination Outline Form ES*701*1 Plant Systems* Tier 2 K K K K K K A A A A G KJA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 205000 Shutdown Cooling X K1.15, RHR service water 3.6 1 215004 Source Range Monitor 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling X A2.01, Interlock failure 3.7 1 Equipment 262001 AC Electrical Dist.

263000 DC Electrical Dist.

290002 Reactor Vessel Internals 201002 RMCS 201003 Control Rod and Drive Mechanism 203000 RHRlLPCI:

Injection Mode 204000 RWCU 211000SLC 212000 RPS 214000 RPIS 215001 Traversing In-Core Probe 2150031RM 215005 APRM / LPRM 223001 Primary CTMT and Aux.

223002 PCIS/Nuclear Steam X K6.06, Various process instrumentation 2.9 1 Supply Shutoff I 261000 SGTS 264000 EDGs X K3.01, Emergency core coolil}g systems 4.4 1 I I

272000 Radiation Monitoring X 2.4.11, Knowledge of abnormal condition 4.2 1 procedures 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 300000 Instrument Air 400000 Component Cooling Water KJA Category Totals: 1 0 1 0 0 1 0 1 0 0 1 Tier Point Total: 5

ES-701 LSRO Generic Krluwlbdyc and Abilities Outline (Tier 3) Form ES-701-3 Facility: PBAPS Date of Exam: July 19 2010

(':.

Y KIA # Topic IR #

2.1.

1.

2.1.

Conduct of Operations 2.1.

2.1.

Subtotal 0 2.2.

2.

2.2.

Equipment Control 2.2.

2.2.

Subtotal 0 2.3.

3.

2.3.

Radiation Control 2.3.

2.3.

Subtotal 0 2.4.

4.

2.4.

Emergency Procedures I 2.4.

Plan 2.4.

Subtotal 0 5.

Generic Fundamentals Tier 3 Point Total Subtotal fflo

ES-701 LSRO Operating Test Outline Form ES-701-4 Applicant Docket Number: 55-352 I 353 Page 1 of 1 Facility: LGS Date of Examination: July 19 2010 Title / Description of Tasks (JPMs) Type Evaluation Comment Page Codes* (S or U) Number Administrative

1. FHD turn over checklist NT
2. GP-13, CRD, CRB and Maintenance N Coordination I Alternate Path - Two cell separation not ensured
3. Calculate Stay Time (2701) DL Systems
1. Fuel Movement in the Spent Fuel Pool I DAI Alternate Path - HOIST JAM Light Illuminates (2035)
2. Fuel movement in the Spent Fuel Pool I NAI Alternate Path - Hoist Tube Hang Up
3. Refuel Floor ARM Return to Service NIT
4. Install rod position test box (2029) DIL Emergency/Abnormal Plant Evolutions
1. New Fuel Movement in the Spent Fuel Pool MAIR from fuel prep machine I Alternate Path New Fuel Drops
2. Spent Fuel Pool Makeup using Fire System NIR standpipes per TSG-4.1
3. Emergency Classification, Inability to NR Maintain Cold shutdown Type Codes & Criteria: (A)lternative path (2 systems; 1 ElAPE))

(C)ontrol room (D)irect from bank (S 7)

{I)n-plant (N)ew or (M)odified from bank including 1(A) (;::0; 1 I section)

(L)ast NRC exam (S 1 I section)

(R)efueling accident (1)

(T)echnical specification (;::0; 2)

ES-701 LSRO Operating Test Outline Form ES-701-4 Applicant Docket Number: 50-277/278 Page 1 of 1 Facility: PBAPS Date of Examination: July 19 2010 Title / Description of Tasks (JPMs) Type Evaluation Comment Page Codes* (S or U) Number i Administrative 1.

2.

3.

Systems

1. Drywell to Reactor Well Bellows Failure NI
2. Fuel Support Piece Removal using FSP NAI Grapple 1 Alternate Path - Fault Lockout
3. Transfer of Recently Irradiated Fuel 1 NTAI Alternate Path - Loss of SBGT
4. Bridge End Structure Panel Lineup NI Emergency/Abnormal Plant Evolutions
1. Dummy Fuel Movement in Spent Fuel Pool MI 1 Fire (3064) 2.

3.

Type Codes & Criteria: (A)lternative path (2 systems; 1 EIAPE))

(C)ontrol room (D)irect from bank (S 7)

(I)n-plant (N)ew or (M)odified from bank including 1(A) (~ 1 1 section)

(L)ast NRC exam (S 1 1 section)

(R)efueling accident (1)

(T)echnical specification (~ 2)

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