ML032480903
| ML032480903 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/07/2003 |
| From: | Lanksbury R Division of Reactor Safety III |
| To: | Detroit Edison |
| References | |
| 50-341/03-302 | |
| Download: ML032480903 (12) | |
Text
OUTLINE SUBMITTAL FOR THE FERMI RETAKE EXAMINATION -JULY 7,2003
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ES-20 1 Examination Outline Quality Checklist Form ES-201-2 Facility: Fermi 2 Date of Examination: 07/07/03 I Item I Task Description NIA
- b. Verifythat: ' N/A NIA (1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 4 - 6 (2 - 3 for SRO-U)of the tasks require the applicant to implement an alternate path (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA. --
- a. Author b.
c.
d.
Facility Reviewer (*)
NRC Chief Examiner (#)
NRC Supervisor g, 9 4 L a3 Note:
- Not applicable for NRC-developedexaminations.
- Independent NRC reviewer initial items in Column "c:" chief examiner concurrence required.
NUREG-1021, Draft Revision 9 24 of 25
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Note: 1. 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.1.c for additional guidance regarding SRO sampling.
- 2. 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 exam must total 75 points and the SRO-only exam must total 25 points.
- 3. 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.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* 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 10CFR 55.43 or an SRO-level Learning objective.
- 7. 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.
- 8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
- 9. Refer to ES-401, Attachment 2 for guidance
- regarding
- - the elimination of inappropriate WA statements.
17 of 34 NUREG-1021, Draft Revision 9
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ES-401 BWR Examination Outline Form ES-401-1 Emergency and volutions -Tier IIGroup 1 (RO)
E/APE # I Name / Safety Function K K G WA Topic IR #
1 2 295001 Partial or Complete Loss of Forced Ability to operate and/or monitor the following as 3.5 Core Flow Circulation I 1 & 4 (#l) they apply to PARTIAL OR COMPLETE LOSS OF 295003 Partial or Complete Loss of AC I 6 04 Knowledge of the operational implications of the 3.1 following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :
(CFR: 41.8 to 41.10)
Electrical bus divisional separation -
295004 Partial or Total Loss of DC Pwr I 6 Knowledge of the reasons for the following 3.1 (W responses as they apply to PARTIAL OR I COMPLETE LOSS OF D.C. POWER :
(CFR: 41.5 I 45.6) Reactor SCRAM i
Knowledge of the operatlonal implications of the 4.0 following concepts as they apply to MAIN TURBINE GENERATOR TRIP :
(CFR: 41.8 to 41.10)
Pressure effects on reactor power -
295006 SCRAM I 1 Ability to determine and/or interpret the following 4.6 as they apply to SCRAM :
(CFR 41.10/43.5/45.13)
Whether a reactor SCRAM has occurred 06 Knowledge of the interrelations between SCRAM and the following:
(CFR: 41.7 145.8) Reactor power 295016 Control Room Abandonment / 7 Knowledge of the reasons for the following
(#7) responses as they apply to CONTROL ROOM ABANDONMENT : (CFR: 41.5 145.6)
I I Disabling control room controls 295018 Partial or Total Loss of CCW / 8 2.4.50 Ability to verify system alarm setpoints and 3.3 1 (W operate controls identified in the alarm response manual.
295019 Partial or Total Loss of Inst. Air I 8 2.1.32 Ability to explain and apply system limits (a) and recautions. CFR: 41.10 143.2 145.12 295021 Loss of Shutdown Cooling I 4 Ability to operate and/or monitor the following as 3.0 I-
- 0) they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.7 I 45.6) Reactor recirculation -
295023 Refueling ACCCooling Mode I 8 Knowledge of the reasons for the following 3.4 1
) l l # ( responses as they apply to REFUELING ACCIDENTS : (CFR: 41.5 145.6)
Interlocks associated with fuel handling equipment -
295024 High Drywell Pressure I 5 (M2)
I /I0 Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
(CFR: 41.7 I 45.8) A.C. distribution 3.5 1 295025 High Reactor Pressure I 3 (#I3)
I 104 Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:
(CFR: 41.7 145.8) ARIIRPTIATWS:
3.9 1 295026 Suppression Pool High Water Temp. I 5 (M4)
/I I
II .
Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
(CFR: 41.5 145.6) SBLC injection 3.7 1 295028 High Drywell Temperature I 5 Ability to operate and/or monitor the following as 3.9 1
- 5) they apply to HIGH DRYWELL TEMPERATURE :
(CFR: 41.7 I 45.6) Drywell pressure NUREG-1021, Draft Revision 9 18 of 34
Emergency and Abnormal Plant Evolutions -Tier IIGroup 1 (RO)
EIAPE # I NameISafety Function K K K A A G WA Topic IR #
1 2 3 1 2 295030 Low Suppression Pool Wtr Lvl I 5 08 Knowledge of the interrelations between LOW 3.5 1 (M6) SUPPRESSION POOL WATER LEVEL and the following: (CFR: 41.7 I 45.8)
SRV discharge submergence 295031 Reactor Low Water Level I 2 (M7) 11 Knowledge of the interrelations behnreen 4.4 1 REACTOR LOW WATER LEVEL and the following:
(CFR 41.7 145.8) Reactor protection system 295037 SCRAM Condition Present and
- 2.4.34 Knowledge of RO tasks performed outside 3.8 1 Power Above APRM Downscale or the main control room during emergency Unknown I 1 (M8) operations including system geography and system implications. (CFR:43.5 I 45.13) 295038 High Off-site Release Rate I 9 06 Ability to operate and/or monitor the following as 3.5 1 (M9) they apply to HIGH OFF-SITE RELEASE RATE :
(CFR: 41.7 145.6) Plant ventilation 600000 Plant Fire On Site I 8 (#20) & YBp Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
3.2 1 l3 >&N eed for emergency plant shutdown WA Category Totals: 2 5 4 4 2 3 Group Point Total: 20 NUREG-1021, Draft Revision 9 18 of 34
NUREG-1021, Draft Revision 9 20 of 34 BWR Examination Outline Form ES-401-1 ibnormal Plan utions -Tier ZGroup 1 (RO) 4 G KIA Topic IR A
T ,
I I
I 1
i Knowledge of electrical power supplies to the 2.6 following: (CFR: 41.7)
Gland seal compressor (vacuum pump) -
Ability to predict andlor monitor changes in 3.4 parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: (CFR: 41.5 I 45.5)
ADS valve tail pipe temperatures 2.4.46 Ability to verify that the alarms are 3.5 consistent with the plant conditions.
(CFR: 43.5 145.3 145.12) f Knowledge of the physical connections andlor 2.7 cause effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEARSTEAM SUPPLY SHUT-OFF and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
Component cooling water systems Knowledge of the operational implications of the 3.4 following concepts as they apply to RELIEFBAFETY VALVES : (CFR: 41.5 145.3)
Relief function of SRV operation Ability to manually operate and/or monitor in the 3.1 control room: (CFR: 41.7 I 45.5 to 45.8)
DPlSinglelthreeelement control selector switch:
Knowledge of the effect that a loss or malfunction 3.1 of the following will have on the STANDBY GAS TREATMENT SYSTEM : (CFR: 41.7 145.7)
Reactor protection system:
'02 Ability to (a) predict the impacts of the following 3.6 on the A.C. ELECTRICALDISTRIBUTION ; 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) Loss of coolant accident Knowledge of UNINTERRUPTABLEPOWER 3.1 SUPPLY (A.C.1D.C.) design feature(s) and/or interlocks which provide for the following:
(CFR: 41.7) Transfer from preferred power to
,, alternate power Supplies Knowledge of the effect that a loss or malfunction 3.4 of the D.C. ELECTRICAL DISTRIBUTIONwill have on following: (CFR 41.7 I 45.4) --_.
Systems with D.C. components (i.e. valves, motors, solenoids, etc.)
06 Knowledge of the operational implications of the 3.4 following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) :
(CFR 41.5 145.3) Load sequencing IC Ability to (a) predict the impacts of the following 3.9 on the EMERGENCY GENERATORS (DIESEUJET) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequencesof those abnormal NUREG-I021, Draft Revision 9 20 of 34
ES-401 BWR Exan Emergency and Abnormal Plar E/APE#INameISafetyFunction K K K K K K A A 1 2 3 4 5 6 1 2 300000 Instrument Air : ST, I
02 400000 Component Cooling Water 03
(*3)
WA Category Totals: 2 2 3 3 3 2 3 3 NUREG-1021, Draft Revision 9 20 of 34
ES-401 BWR Examination Outline Form ES-401-1 Emert and Abnc nal Plant Evolutions -Tier 2/Group 2 (RO) i i.ll
-..-+
E/APE # I Name / Safety Function K K A A A A G WA Topic IR #
1 2 201001 CRD Hydraulic Not Randomly Selected 201002 RMCS 01 Knowledge of the physical connections and/or 3.2 1
(-1 - __ .
cause effect relationships between REACTOR L^--__L_
MANUAL CONTROL SYSTEM and the following:(CFR: 41.2 to 41.9 I45.7 to 45.8)
Control rod drive hydraulic system 201003 Control Rod and Drive Not RandomlySelected Mechanism 201006 RWM Not Randomly Selected 202001 Recirculation Not RandomlySelected 202002 Recirculation Flow Control Not Randomly Selected 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM O: $ l Nuclear Boiler Inst.
II 124 219000 RHWLPCI: Torus/Pool Cooling Mode I [ I I I Not RandomlySelected 1 223001 Primary CTMT and Aux. 04 Ability to manually operate and/or monitor in the 3.5 1
(#57) control room: (CFR: 41.7 I45.5 to 45.8)
Containmenffdrywellhydrogen concentration 226001 RHWLPCI: CTMT Spray Knowledge of RHWLPCI: CONTAINMENT 2.5 1 Mode(#58) , SPRAY SYSTEM MODE design feature(s) and/or interlockswhich provide for the following: (CFR:
41.7) Pump minimum flow protection Not RandomlySelected Not Randomly Selected LJ-u 241000 Reacto Regulator (M9) 245000 Main Turbine Gen. and Auxiliaries NUREG-1021, Draft Revision 9 1 Not Randomly Selected I l l Not RandomlySelected 21 of 34 I
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1 Secondary CTMT NUREG-I 021, Draft Revision 9 21 of34
ES-401 Generic Knowledge and Abilities Outline ( Tier 3) Form ES-401-3 Facility: Fermi 2 -- --Dateof Exam: 07/07/03 RO SRO-Only Category WA# Topic IR # IR #
3.0 1 N/A N/A 2.8 1 N/A N/A 3.4 1 N/A N/A 2.6 1 1 I 1 N/A N/A 3.1 1 N/A N/A 3.3 1 NIA N/A 2.9 1 N/A N/A rier 3 Point Total 27 of 34 NUREG-1021, Draft Revision 9