ML12011A213

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2011 Davis-Besse Nuclear Power Station Initial License Examination ES-401-2&3 SRO Original Submission
ML12011A213
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/27/2011
From:
Operations Branch III
To:
FirstEnergy Nuclear Operating Co
References
Download: ML12011A213 (6)


Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Davis-Besse SRO Date of Exam Weeks of 12/5 & 12/12 2011 RO K/A Category Points SRO ONLY Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

  • 1 18 3 3 6 1.

Emergency 2

& 9 2 2 4 Abnormal Plant Tier Totals 27 5 5 10 Evolutions 1

2.

28 3 2 5 Plant Systems 2 10 0 2 1 3 Tier Totals 38 5 3 8 1 2 3 4 1 2 3 4

3. Generic Knowledge and 10 7 Abilities Category 2 1 2 2 Note:
1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
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 +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

NUREG-1021, Revision 9 Supplement 1 SRO Page 1 of 6 FENOC Facsimile Rev.0

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 12/2011 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 000022 Loss of Reactor Coolant Makeup AA2.04 Ability to determine and interpret the 3.8 1 X following as they apply to the Loss of Reactor Question 76 Coolant Makeup: How long PZR level can be maintained within limits (CFR 43.5/ 45.13) 000026 Loss of Component Cooling Water 2.2.37 Ability to determine operability and/or 4.6 1 (CCW) X availability of safety related equipment.

Question 77 (CFR: 41.7 / 43.5 / 45.12) 000038 Steam Generator Tube Rupture 2.4.1 Knowledge of EOP entry conditions and 4.8 1 (SGTR) X immediate action steps.

Question 78 (CFR: 41.10 / 43.5 / 45.13) 000077 Generator Voltage and Electric Grid AA2.01 Ability to determine and interpret the 3.6 1 Disturbances X following as they apply to Generator Voltage and Electric Grid Disturbances: Operating point on the Question 79 generator capability curve (CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8)

BW/E05 Steam Line Rupture - Excessive EA2.2 Ability to determine and interpret the 4.0 1 Heat Transfer X following as they apply to the (Excessive Heat Question 80 Transfer): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

(CFR: 43.5 / 45.13)

BW/E10 Post-Trip Stabilization 2.2.44 Ability to interpret control room indications to 4.4 1 X verify the status and operation of a system, and Question 81 understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12)

K/A Category Point Totals: 0 0 0 0 3 3 Group Point Total: 6 NUREG-1021, Revision 9 Supplement 1 SRO Page 2 of 6 FENOC Facsimile Rev.0

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 12/2011 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2(SRO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 000067 Plant Fire On Site 2.4.11 Knowledge of abnormal condition 4.2 1 X procedures.

Question 82 (CFR: 41.10 / 43.5 / 45.13) 000068 Control Room Evacuation AA2.01 Ability to determine and interpret the 4.3 1 X following as they apply to the Control Room Question 83 Evacuation: S/G level (CFR: 43.5 / 45.13) 076 High Reactor Coolant Activity AA2.03 Ability to determine and interpret the 3.0 1 X following as they apply to the High Reactor Coolant Question 84 Activity: RCS radioactivity level meter (CFR: 43.5 / 45.13)

BW/E08 LOCA Cooldown 2.2.25 Knowledge of the bases in Technical 4.2 1 X Specifications for limiting conditions for operations Question 85 and safety limits.

(CFR: 41.5 / 41.7 / 43.2)

K/A Category Point Totals: 0 0 0 0 2 2 Group Point Total: 4 NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 6 FENOC Facsimile Rev.0

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 12/2011 Plant Systems - Tier 2/Group 1(SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR Points 1 2 3 4 5 6 1 2 3 4 004 Chemical and Volume A2.02 Ability to (a) predict the impacts of the 4.2 1 Control System X following malfunctions or operations on the CVCS; and (b) based on those predictions, Question 86 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of PZR level (failure mode)

(CFR: 41.5/ 43/5 / 45/3 / 45/5) 006 Emergency Core Cooling 2.2.25 Knowledge of the bases in Technical 4.2 1 System (ECCS) X Specifications for limiting conditions for Question 87 operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 013 Engineered Safety Features A2.03 Ability to (a) predict the impacts of the 4.7 1 Actuation System (ESFAS) X following malfunctions or operations on the ESFAS; and (b) based Ability on those Question 88 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rapid depressurization (CFR: 41.5 / 43.5 / 45.3 / 45.13) 076 Service Water System 2.4.45 Ability to prioritize and interpret the 4.3 1 (SWS) X significance of each annunciator or alarm.

Question 89 (CFR: 41.10 / 43.5 / 45.3 / 45.12) 103 Containment System A2.02 Ability to (a) predict the impacts of the 3.2* 1 X following malfunctions or operations on the Question 90 containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Necessary plant conditions for work in containment (CFR: 41.5 / 43.5 / 45.3 / 45.13)

K/A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 NUREG-1021, Revision 9 Supplement 1 SRO Page 4 of 6 FENOC Facsimile Rev.0

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 12/2011 Plant Systems - Tier 2/Group 2(SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) 1 2 3 4 5 6 1 2 3 4 IR Points 002 Reactor Coolant System A2.01 Ability to (a) predict the impacts of the 4.4 1 (RCS) X following malfunctions or operations on the RCS; and (b) based on those predictions, Question 91 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of coolant inventory (CFR: 41.5 / 43.5 / 45.3 / 45.5) 014 Rod Position Indication A2.06 Ability to (a) predict the impacts of the 3.0* 1 System (RPIS) X following malfunctions or operations on the RPIS; and (b) based on those on those Question 92 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of LVDT (CFR: 41.5 / 43.5 / 45.3 / 45.13) 079 Station Air System (SAS) 2.1.7 Ability to evaluate plant performance 4.4 1 X and make operational judgments based on Question 93 operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

K/A Category Point Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENOC Facsimile Rev.0

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Davis-Besse SRO Date of Exam Weeks of 12/5 & 12/12 2011 RO SRO Only Category K/A# Topic IR # IR #

1. Knowledge of procedures, guidelines, or limitations associated with 2.1.37 Conduct reactivity management. (CFR: 41.1 / 43.6 / 45.6) 4.6 1 of Operations Question 94 2.1.42 Knowledge of new and spent fuel movement procedures. (CFR: 41.10 /

43.7 / 45.13) 3.4 1 Question 95 Subtotal 2

2. Knowledge of maintenance work order requirements. (CFR: 41.10 /

2.2.19 Equipment 43.5 / 45.13) 3.4 1 Control Question 96 Subtotal 1

3. Knowledge of radiation exposure limits under normal or emergency 2.3.4 Radiation conditions. (CFR: 41.12 / 43.4 / 45.10) 3.7 1 Control Question 97 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring 3.1 1 equipment, etc. (CFR: 41.12 / 43.4 / 45.9)

Question 98 Subtotal 2

4. Knowledge of the bases for prioritizing emergency procedure 2.4.23 Emergency implementation during emergency operations. (CFR: 41.10 / 43.5 / 4.4 1 Procedures/ 45.13)

Plan Question 99 2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11) 4.6 1 Question 100 Subtotal 2 Tier 3 Point Total 7 NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 FENOC Facsimile Rev.0