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

I Facility:

DC Cook Examination Level: RO 0 S R a Conduct of Operations Date of Examination: 02/06/06 Operating Test Number-I 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)

Administrative Topic TY Pe*

1 Code 1 (See Note)

DP,R Describe activity to be performed 1

NO6-SRO-C Verify Clearance Permit For East ESW Pump (NRC 2002 Exam)

Conduct of Operations I

I I

1 Equipment Control KA 2.2.13 3.613.8 (12-OHP-21 IO-CPS-001)

I I

1 Radiation Control 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.

I I

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (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 SRO(lhd SRO(U)

Control Room Systems@ (8 for RO: 7 for SRO-I; 2 or 3 for SRO-U)

Operating Jest No.:

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 3 and OHP-4024.201 Drop 59 [Charcoal 07(CCW isolated - Restore) KA SYS 003 A4.08 PORVs per 4025-ant) systems must be different and serve different safety ve different safety functions; in-plant systems and (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (MJodified from bank including 1(A)

Criteria for ROISRO-IISRO-U 4-6 / 4-6 / 2-3 S 9 / S 8 / S 4 2 1 / 2 1 / 2 1 2 1 / 2 1 / 2 1 2 2 / 2 2 / 2 1 5 3 / s 3 / S 2 (randomly selected) 2 1 / 2 1 / 2 1 Revision 1, 1 1-3-2005

Revk System / JPM Title Type Code*

ES-301 Control Roodln-Plant Systems Outline Form ES-301-2 Safety Function

a. NRC2006-SIM01 -Perform Emergency Boration Step of 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 006 A1.13 3.513.7 A, M S 1

D.S 2

g. NRC2006-SIM07 - Start a RCP per 02-OHP-4023-SUP-4P 010 & 007(CCW isolated - Restore) KA SYS 003 A4.08

j. NRC2006-INP02 Local Operation of SG PORVs per 4025-

k. ~ ~ ~ 2 0 0 6 - 1 ~ ~ 0 3 Restore "N" Train Battery Charger per Charger fails, align Standby) KA APE 058 AA1.01 3.413.5 LS-4-3 KA APE 068 A A I.01 4.314.5 OHP 4021.082.015 and OHP 4024.115 Drop 57 (In-Service D.E,R 4s A,D,E,P,R 6

2002

• Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (M)odified from bank including I(A)

(P)revious 2 exams (WCA (S)imulator 1 1, 1 1-3-2005 Criteria for ROISRO-IISRO-U 4.6/4-6/2-3

~ 9 / 5 ; 8 1 ~ 4 2 1 / 2 1 / 2 1 2 I/>

1 / 2 1 2 2 1 2 2 1 2 1 5; 3 / 5 3 I S 2 (randomly selected) 2 1 1 2 1 I 2 1

~

~

~

~

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.

wlines (i-e.. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in shall not be less than two).

2.

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

'evisions. The final RO exam must total 75 points and the SRO-only exam Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only each KIA category The point total for each group and tier in the proposed outline must match that specified in the table. The table based on NRC 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.

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.

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'

4.

5.

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.

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.

9.

I

Prinled: 0113112006 PWR RO Examination Outline Facility:

DC Cook ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 41 I WAPE # / Name / Safety Function I K1 IK2 I K3 A2 G

KATopic Imp.

Points 000007 Reactor Trip - Stabilization -

X I

1x1 1 000009 Small Break LOCA I 3 AK2.03 - Controllers and positioners 2.5 I

EK2.03 - SlGs 3.0 I

AA2.09 - When to secure RCPs on high 3.4 I

stator temperatures I I 1

~000015/000017 RCP Malfunctions I 4 X

000022 Imss of Rx Coolant Makeup 1 2 X 2.2.23 -Ability to track limiting 2.6 1

conditions for operations.

AK3.01 -The conditions that will 3.2*

I initiate the automatic opening and closing of the SWS isolation valves to the CCWlnuclear service water coolers AK1.03 -Latent heat of 2.6 I

vaporizationicondensation EA1.05 - BIT outlet valve switches 3.7*

I EKI.02 - Leak rate vs. pressure drop 3.2 1

lx 000027 Pressurizer Pressure Control System Malfunction I 3 I I 1 X

000038 Steam Gen. Tube Rupture 1 3 000054 Loss of Main Feedwater 14 000055 Station Blackout I 6 000056 Loss (if Off-site Power 1 6 I 000029 ATWS I I I

I I

X X

2.5 4.0 3.6 3.9 3.4 000058 Loss of DC Power I 6 000062 Loss (if Nuclear Svc Water I 4 I

I I

I I

WIF.04 LOCA Outside Containment 1 3 X

I WIE EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's liccnhe and amendnrents 1

1 Jreactor trip I

I I X 1 IAA2.02 - Charging pump problems 1 3.2 I I

AAI.04 - HPI, under total feedwater I I loss conditions I

~

I X 12.4.29 - Knowledge of the emergency I

2.6 I I

I I

]plan.

IAKI.01 - Principle of cooling by natural1 3.7 I I

convection administrative requirements.

AK3.03 - Guidance actions contained in I I EOP for Loss of nuclear service watei-EK2.2 - Facility's heat removal systems, including primary coolant. emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems tu the operation (if the facility EAI.3 - Desired operatin& results during abnormal and emergency situations I

Facility:

DC Cook ES - 401 EIAPE #I Name I Safety Function K1 Printed: 01/31/2006 PWR RO Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 Imp.

Points K2 K3 A1 A2 G

KATopic 2

Printed: 01/31/2006 PWR RO Examination Outline Facility:

DC Cook ES - 401 Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 000069 Loss o ersonne ac AA2.02 - Corrective actions require procedures and operati I

Facility:

DC Cook rs.ant Sys/Fvol # I Name 103 Reactor Coolant Pump 103 Reactor Coolant Pump 104 Chemical and Volume Control 305 Residual Heat Removal 306 Emergency Core Cooling 307 Pressurizer Relief/Quench Tank 007 Pressurizer Relief/Quench 008 Component Cooling Water 010 Pressurizer Pressure Control 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 03Y Main and Reheat Steam OS9 Main Feedwatei 061 Auxiliary/Emergency Feedwater

~

PWR RO Examination Outline Plant stems ~ Tier 2 I Group 1 Printed:

010 112006 Form ES-401-2 TIC4 Tonic I Imn.

~~~

A2.05 - Effects of VCT pressure on RCP seal leakoff ilows A4.02 - RCP niotor 2.9 parameters K3.07 - PZR level and 3.8 pressure A2.01 -Failure modes for 2.7 pressure, tlow, pump nintor amps, nlotor temperature.

and tank level instrumentation K1.10 - Safety injection tank heating systelll 2.5 2.6*

X 2.1.1 - Knowledge of 3.7 conduct of operations requirements.

K5.02 - Method of forming a steam bubble in the PZR A I.04 - Surge tank level

3. I A4.02 - PZR heaters 3.6 KI.07 - Containment 2.9 K2.01 - RPS channels.

3.3 3.1 I components, and I

detectors X 12.1.32 -Ability to exdain I 3.4 and apply all systeni limits and precautions.

K3.02 - Containiiient 3.0 instrumentation readings K6.01 -Upper and lower 3.4*

doors of the ice condenser 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 I KI.09 - RMS I 2.7 including norillill contriil speed for ICs K5.01 - Relationship between AFW tlow and I

Facility:

DC Cook l2c nn, PWR RO Examination Outline Plant Systems - Tier 2 I Group 1 2

PWR RO Examination Outline Facility:

DC Cook WACategoryTotals:

Printed:

0113 I /?006 1

1 1

1 0

1 1

1 1

1 1

Group Point Total:

10 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

I A3.02 - Automatic isolation I 1.6 I I

I

Facilitv: DC Cook

~~

Ability to apply technical specifications for a Ability to use plant computer to obtain and system.

evaluate parametric information on system or component Status Knowledge of how to conduct and verify villve lineups.

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 2.9 I

3.0 I

3.4 I

Printcd: 01/31/2006 Form ES-401-3 Conduct of Operations 2.1.12 2.1.19 r Knowledge of the process for controlling Knowledge ofthe refueling process.

temporary changes.

2. I.29 I-2.5 I

2.6 I

KA Took 3.3 I

~

~

Equipment Control Radiation Control Emergency ProcedureslPlan 2.2.1 I 2.2.27 Category Total:

2 2.3.4 2.3.9 2.3.10 -

Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Knowledge of the process for performing a containment purge.

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

Cateeorv Total:

2.5 3

2.4.29 2.4.50 Knowledge of the emergency plan.

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Category Total:

2.6 I I

L Generic ToldI:

10 I

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCCook Printed: 01/31/2006 Tier

1.

mergenc) ibnormal Plant ivolutions

2.

Plant Systems Date Of Exam:

0212012006 RO K/A Category Points I

SRO-Only Points

1.

outlines (i.e.. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals in shall not be less than two).

2.

final point total for each group and tier may deviate by t 1 from that specified in the revisions. The final RO exam must total 75 points and the SRO-only exam Ensure that at least two topics from every KIA category are sampled within each tier of the RO and SRO-only each WA category The point total for each group and tier in the proposed outline must match that specified in the table. The table based on NRC 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.

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.

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'

4.

5.

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 lor RO and SRO-only exams.

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.

9.

I

PWR SRO Examination Outline Facility:

DC Cook Printzd: 01/31/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2

~ _ _ _ _

WAPE # / Name I Safety Function 000009 Small Break LOCA / 3 00001 I Large Break LOCA / 3 000040 Steam Line Rupture - Excessive Heat Transfer I 4

~~

000057 Loss of Vital AC Inst. Bus / 6 000065 Loss of lnstrunient Air I 8 WE1 I Loss of Emergency Coolant Recirc.,

4 WA Category Totals:

A1 I A2 I G I KA Topic I Imp. I Points 2.2.25 - Knowledge of bases in 3.7 I

technical specifications fix limiting conditions for operations and safety limits.

X 2.3.10 -Ability to perform procedures 3.3 I

to reduce excessive levels of radiation and guard against personnel exposure.

AA2.01 - Occurrence and Iixafion of a steam line rupture from pressure and flow indications I x I AA2.08 - Reactor power digital display and remote flux meter l x I AA2.06 - When to trip reactor if instrument air pressure is decreasing EA2.2 - Adherence to appropriate procedures and operation within the limitations in the ficility's license and amendments 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 E/APE #I Name I Safety Functinn 000033 Loss of Intermediate Renee NI 17 KI K 2 WIE07 Inad. Core Cooling 14 WACategory Totals:

0 WlEl3 Steam Generator Over-pressure I 4 0

0 0

2 2

Croup Point Total:

i X

2.4.46 -Ability to verify that the alarnis 3.6 are consistent with the plant conditions.

X EA2. I - Facility conditions and 4.0 selection of appropriate procedures during abnormal and emergency operations 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 in the facility's license and amendments

PWR SRO Examination Outline KA Topic the affect of maintenance 2.2.24 - Ability to analyze Printed:

0 113 I /2006 Imp.

Points 3.8 I

Facility:

DC Cook 3.5*

3.5 3.1 Plant Systems - Tier 2 / Group 1 Form ES-401-2 I

I I

. I n.

A2.03 - Loss of dc power activities on LCO status.

A2.04 - PRMS alarm 3.4 I

I I

Group Point Total:

5 I

PWR SRO Examination Outline Printed:

01/31/2006 WACategoryTotals:

0 0

Facility:

DC Cook 0

Plant Svstems -Tier 2 I Grow 2 ES - 401 I

I I

I I Sys/F.vol# / Name IK1 1K2 IK3 01 6 Non-nuclear Instrumentation 034 Fuel Handling Equipment 075 Circulating Water Form ES-401.:

I maintenance activities I

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Facility: DCCook 2.1.4 2.1. I 3 Prinrcd: 01/3 1/2006 Form ES-401-3 Knowledge of shift staffing requirements.

3.4 I

Knowledge of facility requirements for 2.9 I

controlling vital I controlled access.

Generic Cateeory KA KA ToDic m

m 2.2.24 Conduct of Operations 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 approving release permits.

2.3.8 Knowledge of the process for performing a Equipment Control 3.1 1

3.2 I

1 2.2.6 I Knowledge of the process for making changes in I 3.3 1 I

procedures as described in the safety analysis 2.4.28 Knowledge of procedures relating to emergency 3.3 I

response to sabotage.

Emergency ProceduredPlan Generic Total:

7