ML060880008

Final Outlines for the D.C. Cook Initial Examination - February 2006

ML060880008
Person / Time
Site:	Cook
Issue date:	02/06/2006
From:	Bailey R Indiana Michigan Power Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML060670557	List: ML060880006 ML060880007 ML060880008 ML060880009 ML060880010 ML060880011 ML060880012 ML060880013
References
Download: ML060880008 (18)

Text

FINAL OUTLINES FOR THE DC COOK INITIAL EXAMINATION - FEBRUARY 2006

ES-301 Administrative Topics Outline Form ES-301-1 Facility: DC Cook Examination Level: RO 0S R a Date of Examination: 02/06/06 Operating Test Number-I Administrative Topic (See Note) 1 TY Pe*

Code 1 Describe activity to be performed 1

Conduct of Operations NO6-SRO-a Review Completed SDM Calculation KA: 2.1.25 2.813.1 (01-OHP-4021-001-012 Attachment 2)

I Conduct of Operations D, R NO6-SRO-b Review AFD Log KA: 2.1.12 2.914.0

& SYSO15 A1.05 3.7/3.9 (01-OHP-4024-110 Drop 44 Attachment A)

I I I 1 Equipment Control DP,R NO6-SRO-C Verify Clearance Permit For East ESW Pump (NRC 2002 Exam)

KA 2.2.13 3.613.8 (12-OHP-21IO-CPS-001) 1 Radiation Control I I NO6-SRO-d Respond to a High SJAE Radiation Alarm (Graph Leakrate & Determine Actions)

KA: 2.3.10 2.9/3.3

& APE037 AK3.05 3.714.0

( 12-OHP-4024-139 Drop 25)

Emergency Plan D, R NO6-SROe Prepare Prompt NRC Notification Worksheet (SFIFW flow trip, safety stuck open)

K A 2.4.30 2.213.6 (PMP-7030-001 Data Sheet I)

I I I

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom I

I (D)irect from bank ( 5 3 for ROs; 5 4 for SROs 8 RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (S 1 randomly selected)

~

I Revision 1 11-3-2005 NUREG-I021 Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: DC COOK 2006 ILT Date of Examination: 02/06/06 Exam Level: R O U S R O ( l h d SRO(U) Operating Jest No.:

Control Room S y s t e m s @ ( 8 for RO: 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title Type Code" Safety Function

a. NRC2006-SIM01 -Perform Emergency Boration Step of A.MS 1 02-OHP-4023-FR-S. 1 ATWS (Boric Acid Pumps fail -

Alian RWST) KA APE 024 A1.17 3.9/3.9. SYS 004 A2.14 per 02-OHP-4023-SUP-002. KA SYS Attachment 13 and OHP-4024.201 Drop 5 9 [Charcoal 07(CCW isolated - Restore) KA SYS 0 0 3 A4.08 PORVs per 4025-ant) systems must be different and serve different safety ve different safety functions; in-plant systems and Criteria for ROISRO-IISRO-U 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant 21/21/21 (L)ow-Power / Shutdown 21/21/21 (N)ew or (MJodified from bank including 1(A) 22/22/21 5 3 / s 3 / S 2 (randomly selected) 21/21/21 Revision 1, 1 1 2 0 0 5

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code* Safety Function

a. NRC2006-SIM01 -Perform Emergency Boration Step of A,MS 1 02-OHP-4023-FR-S.l ATWS (Boric Acid Pumps fail -

Ali n RWST) KA APE 024 A1.17 3.913.9, SYS 004 A2.14 3.8739

b. NRC2006-SIM02 - Raise SI Accumulator Level KA SYS D.S 2 0 0 6 A1.13 3.513.7

g. NRC2006-SIM07 - Start a RCP per 02-OHP-4023-SUP- 4P 010 & 007(CCW isolated - Restore) KA SYS 0 0 3 A4.08

j. NRC2006-INP02 Local Operation of SG PORVs per 4025-LS-4-3 KA APE 0 6 8 A A I .01 4.314.5 D.E,R 4s

k. ~ ~ ~ 2 0 0 6 - Restore 1 ~ ~ 0"N" 3 Train Battery Charger per OHP 4021.082.015 and OHP 4024.115 Drop 57 (In-Service A,D,E,P,R 6 Charger fails, align Standby) KA APE 058 AA1.01 3.413.5 2002

• Type Codes Criteria for ROISRO-IISRO-U (A)lternate path 4.6/4-6/2-3 (C)ontrol room (D)irect from bank ~9/5;81~4 (E)mergency or abnormal in-plant 2 1/ 2 1/2 1 (L)ow-Power / Shutdown 2 I/> 1/21 (N)ew or (M)odified from bank including I ( A ) 22122121 (P)revious 2 exams 5; 3 / 5 3 I S 2 (randomly selected)

(WCA 2 11 2 1 I 2 1 (S)imulator Revk 1 1, 1 1-3-2005

~ _ _ _ ~ ~ ~

ES 401 PWR Examination Outline Form ES-401-2 FaCilitV: DCCook Printed: 01/31/2006 Date Of Exam: 0212012006 I 1 RO KIA Category Points I SRO-Only Points Vote:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only wlines (i-e.. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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

'inal point total for each group and tier may deviate by f l from that specified in the table based on NRC

'evisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions 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 that are not included on the the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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 WAS 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 WA categories 7.' The generic ( G ) WAS 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.

8. On the following pages, enter the WA 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. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3. select topices from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

I

PWR RO Examination Outline Prinled: 0113112006 Facility: DC Cook ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 I WAPE # / Name / Safety Function I K1 IK2 I K3 4 1 A2 G KATopic Imp. Points 000007 Reactor Trip - Stabilization -

1 1 Jreactor trip I I AK2.03 - Controllers and positioners 2.5 I 1 000009 Small Break LOCA I 3 I 1x1 EK2.03 - SlGs 3.0 I

~000015/000017RCP Malfunctions I 4 I I1 IX 1 X AA2.09 - When to secure RCPs on high stator temperatures IAA2.02 - Charging pump problems 1 3.4 3.2 I I

I 000022 I m s s of Rx Coolant Makeup 1 2 X 2.2.23 -Ability to track limiting 2.6 1 conditions for operations.

AK3.01 - T h e conditions that will 3.2* I lx I I1 initiate the automatic opening and closing of the SWS isolation valves to the CCWlnuclear service water coolers 000027 Pressurizer Pressure Control System X AK1.03 -Latent heat of 2.6 I Malfunction I 3 vaporizationicondensation I 000029 ATWS I I I I I X EA1.05 - BIT outlet valve switches 3.7* I 000038 Steam Gen. Tube Rupture 1 3 X EKI .02 - Leak rate vs. pressure drop 3.2 1 000054 Loss of Main Feedwater 1 4 I I AAI .04 - HPI, under total feedwater loss conditions 000055 Station Blackout I 6 I I X 12.4.29

~ - Knowledge of the emergency I 2.6 I I I I ]plan.

000056 Loss (if Off-site Power 1 6 X IAKI.01 - Principle of cooling by natural1 3.7 I I convection 000058 Loss of DC Power I 6 2.5 I administrative requirements.

000062 Loss (if Nuclear Svc Water I 4 I I AK3.03 - Guidance actions contained in EOP for Loss of nuclear service watei-4.0 I WIF.04 LOCA Outside Containment 1 3 X EA2.2 - Adherence to appropriate 3.6 I procedures and operation within the limitations i n the facility's liccnhe and amendnrents I WIE EK2.2 - Facility's heat removal systems, 3.9 I including primary coolant. emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems t u the operation (if the facility EAI.3 - Desired operatin& results 3.4 I during abnormal and emergency situations I

PWR RO Examination Outline Printed: 01/31/2006 Facility: DC Cook ES - 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 1 Form ES-401-2 EIAPE # I Name I Safety Function K1 K2 K3 A1 A2 G KATopic Imp. Points 2

PWR RO Examination Outline Printed: 01/31/2006 Facility: DC Cook ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 000069 Loss o ersonne ac AA2.02 - Corrective actions require procedures and operati I

~

PWR RO Examination Outline Printed: 010 112006 Facility: DC Cook rs .ant Plant stems Tier 2 I Group 1

~ Form ES-401-2 Sys/Fvol # I Name T

~~~

I C 4 Tonic I Imn.

103 Reactor Coolant Pump A2.05 - Effects of VCT 2.5 pressure on RCP seal leakoff ilows 103 Reactor Coolant Pump A4.02 - RCP niotor 2.9 parameters 104 Chemical and Volume Control K3.07 - PZR level and 3.8 pressure 305 Residual Heat Removal A2.01 -Failure modes for 2.7 pressure, tlow, pump nintor amps, nlotor temperature.

and tank level instrumentation 306 Emergency Core Cooling K1.10 - Safety injection tank 2.6*

heating systelll 307 Pressurizer Relief/Quench X 2.1.1 - Knowledge of - 3.7 Tank conduct of operations requirements.

007 Pressurizer Relief/Quench K5.02 - Method of forming 3.1 a steam bubble in the PZR 008 Component Cooling Water A I .04 - Surge tank level 3. I 010 Pressurizer Pressure Control A4.02 - PZR heaters 3.6 010 Pressurizer Pressure Control KI .07 - Containment 2.9 012 Reactor Protection K2.01 - RPS channels. 3.3 Icomponents, and I 013 Engineered Safety Features Actuation detectors 022 Containment Cooling X 12.1.32 -Ability to exdain I 3.4 and apply all systeni limits and precautions.

022 Containment Cooling K3.02 - Containiiient 3.0 instrumentation readings 025 Ice Condenser K6.01 -Upper and lower 3.4*

doors of the ice condenser 026 Containment Spray K4.04 - Reduction of 3.7 temperature and pressure in containment after a LOCA by condensing steam, ti1 reduce radiological hazard.

and protect equipment froni I corrosion damage (hpray) I 03Y Main and Reheat Steam I K I .09 - RMS I 2.7 OS9 Main Feedwatei including norillill contriil speed for ICs 061 Auxiliary/Emergency K5.01 - Relationship Feedwater between AFW tlow and I

PWR RO Examination Outline Facility: DC Cook l2c nn, -

Plant Systems Tier 2 I Group 1 2

PWR RO Examination Outline Printed: 0113 I /?006 Facility: DC Cook

-

Plant Systems Tier 2 I Group 2 Form ES-401.2 range power range outside annunciators a amls an indications and iise of the ontrols between manual nd automatic control, by X IA3.02 - Automatic isolation I 1.6 I I WACategoryTotals: 1 1 1 1 0 1 1 1 1 1 1 Group Point Total: 10 I

Generic Knowledge and Abilities O u t l i n e ( T i e r 3)

PWR RO Examination Outline Printcd: 01/31/2006 Facilitv: DC Cook Form ES-401-3 KA Took

~~

r Conduct of Operations 2.1.12 Ability to apply technical specifications for a 2.9 I system.

2.1.19 Ability to use plant computer to obtain and 3.0 I evaluate parametric information on system or component Status I-2. I .29 Knowledge of how to conduct and verify villve 3.4 I lineups.

~ ~

Equipment Control 2.2.1 I Knowledge o f the process for controlling 2.5 I temporary changes.

2.2.27 Knowledge ofthe refueling process. 2.6 I Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.3.9 Knowledge of the process for performing a 2.5 containment purge.

2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel

- exposure.

Cateeorv Total: 3 Emergency ProcedureslPlan 2.4.29 Knowledge of the emergency plan. 2.6 I I 2.4.50 Ability to verify system alarm setpoints and 3.3 I operate controls identified in the alarm response manual.

Category Total: L Generic ToldI: 10 I

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCCook Printed: 01/31/2006 Date Of Exam: 0212012006 Tier RO K/A Category Points I SRO-Only Points 1.

mergenc)

&

ibnormal Plant ivolutions 2.

Plant Systems

1. Ensure that at least two topics from every KIA 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 WA 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 t 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. Systemsievolutions 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 that are not included on the the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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 WAS 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 KIA categories.

7.' The generic (G)KiAs 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.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)foreach system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages lor RO and SRO-only exams.

9. For Tier 3, select topices from Section 2 of the WA catalog, and enter the KIA 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.

I

PWR SRO Examination Outline Printzd: 01/31/2006 Facility: DC Cook ES - 401 -

Emergency a n d Abnormal Plant Evolutions Tier 1I G r o u p 1 Form ES-401-2

~ _ _ _ _

WAPE # / Name I Safety Function I IG I A1 A2 KA Topic I Imp. I Points 000009 Small Break LOCA / 3 2.2.25 - Knowledge o f bases in 3.7 I technical specifications f i x limiting conditions for operations and safety limits.

00001 I Large Break LOCA / 3 X 2.3.10 -Ability to perform procedures 3.3 I to reduce excessive levels of radiation and guard against personnel exposure.

000040 Steam Line Rupture - Excessive AA2.01 - Occurrence and Iixafion of a Heat Transfer I 4 steam line rupture from pressure and flow indications

~~

000057 Loss of Vital AC Inst. Bus / 6 IxI AA2.08 - Reactor power digital display and remote flux meter 000065 Loss of lnstrunient Air I 8 lxI AA2.06 - When to trip reactor if instrument air pressure is decreasing W E 1 I Loss of Emergency Coolant Recirc., EA2.2 - Adherence to appropriate 4 procedures and operation within the limitations in the ficility's license and amendments WA Category Totals: Group Point Total: 6 I

PWR SRO Examination Outline Printcd: 0113112006 Facility: DC Cook ES - 401 Emergency and Abnormal Plant Evolutions tier 1 I Group 2 Form ES-401-2 i

E/APE # I Name I Safety Functinn KI K2 000033 Loss of Intermediate Renee NI 1 7 X 2.4.46 -Ability to verify that the alarnis 3.6 are consistent with the plant conditions.

WIE07 Inad. Core Cooling 14 X EA2. I - Facility conditions and 4.0 selection of appropriate procedures during abnormal and emergency operations WlEl3 Steam Generator Over-pressure I 4 X 2.1.7 - Ability to evaluate plant 4.4 performance and make operational judgments hased on operating characteristics, reactor behavior, and instrument interpretation.

W E I S Containment Flooding I S X EA2.2 - Adherence to appropriate 3.3 procedures and opcr;ition within the limitations i n the facility's license and amendments WACategory Totals: 0 0 0 0 2 2 Croup Point Total:

PWR SRO Examination Outline Printed: 0 113I /2006 Facility: DC Cook

. In. -

Plant Systems Tier 2 / Group 1 Form ES-401-2 KA Topic Imp. Points 2.2.24 - Ability to analyze 3.8 I the affect of maintenance activities on LCO status.

A2.04 - PRMS alarm 3.5* I 3.5 I 3.1 I A2.03 - Loss of dc power 3.4 I I I Group Point Total: 5 I

PWR SRO Examination Outline Printed: 01/31/2006 Facility: DC Cook ES - 401 Plant Svstems -Tier 2 I G r o w 2 Form ES-401.:

I I I I I

I Sys/F.vol# / Name IK1 1K2 IK3 01 6 Non-nuclear Instrumentation maintenance activities 034 Fuel Handling Equipment 075 Circulating Water WACategoryTotals: 0 0 0 I

Generic Knowledge and Abilities O u t l i n e ( T i e r 3)

PWR SRO Examination Outline Prinrcd: 01/3 1/2006 Facility: DCCook Form ES-401-3 Generic Cateeory -

KA KA ToDic m m Conduct of Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 I 2.1 . I 3 Knowledge of facility requirements for 2.9 I controlling vital I controlled access.

Equipment Control 1 2.2.6 I Knowledge of the process for making changes i n procedures as described in the safety analysis I 1 3.3 I 2.2.24 Ability to analyze the affect of maintenance 3.8 I activities on LCO status.

Radiation Control 2.3.6 Knowledge of the requirements for reviewing and 3.1 1 approving release permits.

2.3.8 Knowledge of the process for performing a 3.2 I Emergency ProceduredPlan 2.4.28 Knowledge of procedures relating to emergency 3.3 I response to sabotage.

Generic Total: 7