ML102220055

From kanterella
Revision as of 18:37, 21 August 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
DC Cook, 2010 Initial License Exam, SRO Written 401-2 Form
ML102220055
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/21/2010
From:
Division of Nuclear Materials Safety III
To:
References
Download: ML102220055 (5)


Text

04/12/2010 Printed: ES-401 Facility: Cook Nuclear Plant PWR Examination Outline Form ES-401-2 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*1.Emergency&Abnormal Plant Evolutions 1 1 2 2 Tier Totals Tier Totals 2.Plant Systems 1 2 3 4 3. Generic Knowledge And Abilities Categories 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.

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.

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.

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.

Note: Date Of Exam:

06/21/2010 0 0 0 0 0 0 0 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).

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.

SRO-Only Points A2 G* 3 3 2 2 5 5 3 2 1 1 3 2 1 2 2 1 2 3 4 10 4 6 5 3 8 7 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.

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

N/A N/A Total 1 5 1 04/12/2010 9:28:07 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:

ES - 401 Facility: Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 EA2.04 - If reactor should have tripped but has not done so, manually trip the reactor and carry out actions in ATWS EOP 4.4 1 X 000007 Reactor Trip - Stabilization -

Recovery / 1 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.0 1 X 000022 Loss of Rx Coolant Makeup / 2 AA2.02 - The cause of possible CCW loss 3.6 1 X 000026 Loss of Component Cooling Water /

8 EA2.09 - Existence of natural circulation, using plant parameters 4.2 1 X 000038 Steam Gen. Tube Rupture / 3 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.7 1 X 000040 Steam Line Rupture - Excessive Heat Transfer / 4 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.

4.3 1 X 000062 Loss of Nuclear Svc Water / 4 6 0 0 0 0 3 3 K/A Category Totals:

Group Point Total:

1 04/12/2010 9:27:39 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:

ES - 401 Facility: Cook Nuclear Plant E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 AA2.03 - Required actions if more than one rod is stuck or inoperable 4.4 1 X 000005 Inoperable/Stuck Control Rod / 1 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

4.7 1 X 000032 Loss of Source Range NI / 7 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

4.3 1 X 000060 Accidental Gaseous Radwaste Rel. /

9 AA2.01 - Loss of containment integrity 4.3 1 X 000069 Loss of CTMT Integrity / 5 4 0 0 0 0 2 2 K/A Category Totals:

Group Point Total:

1 04/12/2010 9:27:44 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Cook Nuclear Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.4.6 1 X 005 Residual Heat Removal A2.11 - Rupture of ECCS header 4.4 1 X 006 Emergency Core Cooling A2.07 - Consequences of high or low CCW flow rate and temperature; the flow rate at which the CCW standby pump will start 2.8*1 X 008 Component Cooling Water 2.2.37 - Ability to determine operability and/or availability of safety related equipment.

4.6 1 X 039 Main and Reheat Steam A2.04 - pump failure or improper operation 3.8 1 X 061 Auxiliary/Emergency Feedwater 5 0 0 0 0 3 2 K/A Category Totals:

0 0 0 0 0 Group Point Total:

1 04/12/2010 9:27:50 am 04/12/2010 K1 KA Topic Imp.K2 K3 A1 A2 G Points Printed:

K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Cook Nuclear Plant PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A2.11 - Failure of PZR level instrument - low 3.6 1 X 011 Pressurizer Level Control K1.01 - RCS 3.2 1 X 034 Fuel Handling Equipment 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 1 X 045 Main Turbine Generator 3 1 0 0 0 1 1 K/A Category Totals:

0 0 0 0 0 Group Point Total:

1 04/12/2010 9:27:56 am