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 Task Description II Item I
- b. Verifythat:
(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. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
4 L
a3 g,
Note:
- Not applicable for NRC-developed examinations.
- 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.
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- 3.
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6.*
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- 9.
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.
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.
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.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the category/tier.
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.
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.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
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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BWR Examination Outline Form ES-401-1 ES-401 Emergency and K
K 1
2 E/APE # I Name / Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 (#l) 295003 Partial or Complete Loss of AC I 6 04 volutions -Tier IIGroup 1 (RO)
G WA Topic IR 3.5 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF 3.1 3.1 Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER :
(CFR: 41.8 to 41.10)
Electrical bus divisional separation Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.5 I 45.6) Reactor SCRAM Knowledge of the operatlonal implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP :
(CFR: 41.8 to 41.10)
Pressure effects on reactor power Ability to determine and/or interpret the following as they apply to SCRAM :
(CFR 41.10/43.5/45.13)
Whether a reactor SCRAM has occurred I
295004 Partial or Total Loss of DC Pwr I 6 (W
i 4.0 4.6 295006 SCRAM I 1 06 Knowledge of the interrelations between SCRAM and the following:
(CFR: 41.7 145.8) Reactor power Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT : (CFR: 41.5 145.6)
Disabling control room controls 295016 Control Room Abandonment / 7
(#7)
I I
295018 Partial or Total Loss of CCW / 8 (W
29501 9 Partial or Total Loss of Inst. Air I 8 (a) 295021 Loss of Shutdown Cooling I 4
- 0) 2.4.50 Ability to verify system alarm setpoints and 3.3 1
operate controls identified in the alarm response manual.
2.1.32 Ability to explain and apply system limits and recautions. CFR: 41.10 143.2 145.12 3.0 I-Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.7 I 45.6) Reactor recirculation 1
1 -
1 -
1 295023 Refueling ACC Cooling Mode I 8
(
l l
)
Knowledge of the reasons for the following 3.4 responses as they apply to REFUELING ACCIDENTS : (CFR: 41.5 145.6)
Interlocks associated with fuel handling equipment Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
(CFR: 41.7 I 45.8) A.C. distribution Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:
(CFR: 41.7 145.8) ARIIRPTIATWS:
3.5 3.9 I /I0 295024 High Drywell Pressure I 5 (M2)
I 1 0 4 295025 High Reactor Pressure I 3 (#I 3)
/ I 295026 Suppression Pool High Water Temp. I 5 (M4) 3.7 Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
(CFR: 41.5 145.6) SBLC injection I
I I
295028 High Drywell Temperature I 5
- 5)
NUREG-1021, Draft Revision 9 Ability to operate and/or monitor the following as 3.9 1
they apply to HIGH DRYWELL TEMPERATURE :
(CFR: 41.7 I 45.6) Drywell pressure 18 of 34
Emergency EIAPE #I NameISafety Function 295030 Low Suppression Pool Wtr Lvl I 5 (M 6) 295031 Reactor Low Water Level I 2 (M7) 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 (M8) 295038 High Off-site Release Rate I 9 (M 9) 600000 Plant Fire On Site I 8 (#20)
WA Category Totals:
NUREG-1021, Draft Revision 9 and Abnormal Plant Evolutions -Tier IIGroup 1 (RO)
K K
K A
A G
WA Topic IR 1
2 3
1 2
08 Knowledge of the interrelations between LOW 3.5 1
SUPPRESSION POOL WATER LEVEL and the following: (CFR: 41.7 I 45.8)
SRV discharge submergence REACTOR LOW WATER LEVEL and the following:
(CFR 41.7 145.8) Reactor protection system the main control room during emergency operations including system geography and system implications. (CFR:
43.5 I 45.1 3) 06 Ability to operate and/or monitor the following as 3.5 1
they apply to HIGH OFF-SITE RELEASE RATE :
(CFR: 41.7 145.6) Plant ventilation
& YBp Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE:
l3
>&N eed for emergency plant shutdown 11 Knowledge of the interrelations behnreen 4.4 1
2.4.34 Knowledge of RO tasks performed outside 3.8 1
3.2 1
2 5
4 4
2 3
Group Point Total:
20 18 of 34
NUREG-1021, Draft Revision 9 20 of 34
NUREG-I 021, Draft Revision 9 BWR Examination Outline Form ES-401-1 ibnormal Plan
'02 06 I C utions -Tier ZGroup 1 (RO) 4 G
KIA Topic IR A
T,,
I I
I 1
i Knowledge of electrical power supplies to the following: (CFR: 41.7)
Gland seal compressor (vacuum pump)
Ability to predict andlor monitor changes in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: (CFR: 41.5 I 45.5)
ADS valve tail pipe temperatures f
2.6 -
3.4 2.4.46 Ability to verify that the alarms are 3.5 consistent with the plant conditions.
(CFR: 43.5 145.3 145.12)
Knowledge of the physical connections andlor cause effect relationships between PRIMARY CONTAINMENT ISOLATION 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 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 control room: (CFR: 41.7 I 45.5 to 45.8)
DPlSinglelthree element control selector switch:
Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM : (CFR: 41.7 145.7)
Reactor protection system:
Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; 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 UNINTERRUPTABLE POWER 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 2.7 SYSTEMlNUCLEAR STEAM SUPPLY SHUT-3.4 3.1 3.1 3.6
, alternate power Supplies Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on following: (CFR 41.7 I 45.4)
Systems with D.C. components (i.e. valves, motors, solenoids, etc.)
Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) :
(CFR 41.5 145.3) Load sequencing 3.4 3.4 Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEUJET) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 20 of 34 3.9
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 02 I
ST, 300000 Instrument Air 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 i.ll Emert E/APE # I Name / Safety Function K K 1
2
-..-+
201001 CRD Hydraulic 201002 RMCS 01
(-1 L^--__L_
- __. i 201003 Control Rod and Drive Mechanism 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM I I 124 l
O Nuclear Boiler Inst.
219000 RHWLPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
(#57) 226001 RHWLPCI: CTMT Spray Mode(#58) 241 000 Reacto Regulator (M9)
L J - u 245000 Main Turbine Gen. and Auxiliaries BWR Examination Outline Form ES-401-1 and Abnc 1
nal Plant Evolutions -Tier 2/Group 2 (RO)
A A
A A
G WA Topic IR Not Randomly Selected Knowledge of the physical connections and/or 3.2 1
cause effect relationships between REACTOR MANUAL CONTROL SYSTEM and the following:(CFR: 41.2 to 41.9 I45.7 to 45.8)
Control rod drive hydraulic system Not Randomly Selected Not Randomly Selected Not Randomly Selected Not Randomly Selected I
[ I I I 1
Not Randomly Selected 04 Ability to manually operate and/or monitor in the 3.5 1
control room: (CFR: 41.7 I45.5 to 45.8)
Containmenffdrywell hydrogen concentration Knowledge of RHWLPCI: CONTAINMENT 2.5 1
SPRAY SYSTEM MODE design feature(s) and/or interlocks which provide for the following: (CFR:
41.7) Pump minimum flow protection Not Randomly Selected Not Randomly Selected Not Randomly Selected I
I I l l Not Randomly Selected I
NUREG-1021, Draft Revision 9 21 of 34
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
-- --Date of Exam: 07/07/03 Category WA#
Topic rier 3 Point Total RO SRO-Only 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 1 N/A I N/A 3.1 1
N/A N/A NIA N/A 3.3 1
2.9 1
N/A N/A 27 of 34 NUREG-1021, Draft Revision 9