ML102250450

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2010 D. C. Cook Nuclear Plant Initial Examination Outline Submittal
ML102250450
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/21/2010
From: Walton R
NRC/RGN-III/DRS/OLB
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Download: ML102250450 (33)
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2010 D. C. COOK NUCLEAR PLANT INITIAL EXAMINATION OUTLINE SUBMITTAL INDIANA MICHIGAN PlOwER" A unit ofAmerican Electric Power Indiana Michigan Power One Cook Place Bridgman, MI 49106 lndianaMichiganPower.com March 29, 2010 U. S. Nuclear Regulatory Commission ATTN: Mr.

Raymond K. Walton Region Ill Examiner 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352 Donald C.

Cook Nuclear Plant Units 1 and 2 2010 NRC EXAMINATION OUTLINE SUBMITTAL Enclosed you will find a copy of the Initial License Examination Outline for the planned August 2010 examination at Donald C. Cook Nuclear Plant (CNP). Also enclosed is the proposed examination schedule, based on 1 Senior Reactor Operator (SRO) (I), 5 SRO (U), and 8 Reactor Operator (RO) candidates. The examination is being prepared in accordance with NUREG 1021, Revision 9, Supplement

1. The following items are enclosed in the sealed envelope: Form ES-201-2 Examination Outline Quality Checklist Form ES-201-3 Examination Security Agreement Draft CNP 2010 ILT Examination Schedule Written Examination Sample Methodology Probabilistic Risk Assessment Input Scenario Outlines Form ES-D-1 COOK201 0-01 Scenario Outlines Form ES-D-1 COOK201 0-02 Scenario Outlines Form ES-D-1 COOK201 0-03 Scenario Outlines Form ES-D-1 COOK201 0-04 ES-301-4, Simulator Checklist ES-301-5, Transient and Event Checklist Crews 1, 2, & 3 ES-301-5, Transient and Event Checklist Crew 4 ES-301-5, Transient and Event Checklist Crew 5 ES-301-6, Competencies Checklist Crews 1, 2, & 3 ES-301-6, Competencies Checklist Crew 4 ES-301-6, Competencies Checklist Crew 5 ES-301-2, SRO (I) JPM Outline ES-301-2, SRO (U) JPM Outline ES-301-2, RO JPM Outline ES-301-1, SRO Admin JPM Outline ES-301-1, RO Admin JPM Outline PWR Exam Outline, Form ES-401-2 (SRO) Generic WA Outline, Form ES-401-3 (SRO)

PWR Exam Outline, Form ES-401-2 (RO)

U. S. Nuclear Regulatory Commission March 29, 2010 Page 2 25) 26) Form ES-401-4, Submittal (RO/SRO) Generic WA Outline, Form ES-401-3 (RO) A hard copy of all the examination materials is provided for your review.

An electronic copy of documents without initials or signatures or other handwritten notations for the Public Document Room (ADAMS) has also been provided.

None of these materials are to go to the Public Document Room (ADAMS) until after the examination has been completed. If you have any questions, please contact Ted Conrad or Steve Pettinger at (269) 465-5901, extension 3738, or myself at (269) 466-3407.

Since re1 y , EE23&- Brian E. Evans Operations Training Manager JTC/jen Enclosures ES-201 Examination Outline Quality Checklist Form ES-201-2 Item 1. W Initials a b* c# Task Description gJW a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. I c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

d. Assess whether the justifications for deselected or rejected WA statements are appropriate.

E $F%W ~~~ ~ 2. S I M U L A T 0 R m,r% ~~~ a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.
c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-3014 and described in Appendix D. wv 3. W I T a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants' audit test(s) (4) the number of new or modified tasks meets or exceeds the, minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria c ecified on Form ES-301-1:

A e. Check the entire exam for balance of coverage.

L am f. Assess whether the exam fits the appropriate job level (RO or SRO). /- a. Author e b. Facility Reviewer r) 3/zr // 0 c. NRC Chief Examiner (#) d. NRC Supervisor Note: Independent NRC reviewer initial items in Column 'c"; chief examiner concurrence required.

Not applicable for NRCprepared examination outlines ES-201, Page 26 of 28 DC Cook 2010 NRC Examination ES-301 Administrative Topics Outline Form ES-301-1 Facility:

DC Cook Examination Level:

RO SRO Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control I Emergency ProcedureslPlan li Type Code* D-R D-R D-R N-S Date of Examination: 6/21/10 Operating Test Number: 2010 NRC Describe activity to be performed NRC201O-Ala Calculate Reactor Vessel Void Vent Time WA 2.1.25 (3.9/4.2) (EPE 009 EA2.38 {3.9/4.3}) NRC2010-A1 b-RO Determination of Reactor Shutdown WA SYS 001 A4.11 334.1 (U2 C-18, Stuck Rod, No Xenon) NRC201O-A2 Perform Unit 2 LTOP Verification.

WA 2.2.37 3.6/4.6 NRC201043 Perform Monthly Rad Liquid And Gaseous Monitor Source Checks WA 2.3.5 2.W2.9 WA 073 A4.03 4.3/4.0 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 (D)irect from bank (I 3 for ROs; I4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (I 1; randomly selected) 3/25/2010 Revision 0 DC Cook 2010 NRC Examination ES-301 Administrative Topics Outline Form ES-301-1 Facility:

DC Cook Examination Level: RO c] SRO Date of Examination: 6/21/10 Operating Test Number: 2010 NRC Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan Type Code* D-R D-R D-R N-S D-R Describe activity to be performed NRC2010-A1 a Calculate Reactor Vessel Void Vent Time WA 2.1.25 (3.9/4.2) (EPE 009 EA2.38 (3.914.3)) NRC2010-A1 b-SRO SRO Review - Determination of Reactor Shutdown Margin. WA SYS 001 A4.11 3.514.1 (U2 C-18, Stuck Rod, No Xenon) NRC2010-A2 Perform Unit 2 LTOP Verification. KIA 2.2.37 3.6/4.6 NRC2010-A3 , ,Perform Monthly Rad Liquid And Gaseous Monitor Source Checks WA 2.3.5 2.9/2.9 WA 073 A4.03 4.3/4.0 NRC201 O-A4-SRO Prepare Prompt NRC Notification Worksheet (SI, safety stuck open) KA: 2.4.30 2.714.1 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 (D)irect from bank (5 3 for ROs; I4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (I 1; randomly selected) 3/25/2010 Revision 0 DC Cook 2010 NRC Examination ES-301 Control Roomh-Plant Systems Outline Form ES-301-2 System / JPM Title a. NRCIO-SIMOI - Perform Emergency Boration due to Shutdown Margin Not Met KA APE 024 AA1.17 3.913.9, SYS 004 A2.14 3.813.9. Facility:

DC Cook Date of Examination:

6/21/2010 Exam Level: RO SRO-I SRO-U Operating Test No.: Cook 2010 Type Code* Safety Function N-S 1 ~ __ ~__ __ Control Room Systems@

(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) b. NRC10-SIM02 - Establish Letdown IAW OHP4023-SUP-15 (Alternate Path to Excess Letdown) KA SYS 004 A2.07 3.413.7 c. NRCl0-SIM03 - Isolate Safety Injection Accumulators per OHP- 4023.ES-1.2 (2 Failed Accumulator Discharge Valves) KA SYS 006 A4.02 4.013.8 2 A-D-L-P-S 2o07 Exam A-D-EN--L-S 3 D-P-S e. NRCl0-SIM05 - Perforrn Steam Generator Stop Valve Dump 2008 Exam A-L-EN-N-S Valve Surveillance Test per l-OHP4030-151-018. SYS 039 K4.05 3.7/3.7 A2.11 3.714.1 F. NRC10-SIM06 - Restoration of 4Kv TI 1A From KA SYS 062 1 L-D-S 1 d. NRC10-SIM04 - Restore Reactor Coolant Pump Cooling per OHP- 4023.ES-1.2 and Supplement 007 KA SYS 003 A4.08 3.212.9 4s 6 4P N-S A-N-S g. NRC10-SIM07 - Restore Scaler Timer Drawer Post Maintenance KA 015 A4.02 3.9/3.9 h. NRC10-SIM08 - Respond to an R5 High Alarm (Auto Actions Failed) KA SYS 033 AI .02 2.813.3, SYS 034 A4.01 3.313.7, APE 036 AA1.02 3.1/3.5 7 8 i. NRC10-INP02 - Locally Control the blender to Charging Pump Suction (QRV400) KA APE 068 AA1.08 3.914.1 KA APE 054 AA1.01 4.5/4.4 I. NRCIO-INPOI - S/G 2/3 Level Control through AFW Unit Crosstie.

k. NRC10-INP03 - Perform Local Diesel Generator Trip and Isolation (DG Fails to Trip with Pushbutton) APE 068 AA1.31 3.9/4.0 (ALTI 6 E-D-R 2 4P E-D-P-R 2007 Exam A-D-E
  • Type Codes Criteria for RO / SRO-I / SRO-U 3/25/2010 Revision 0 ~ ~ :A)ltemate path (C)ontrol room [D)irect from bank :EN)gineered safety feature :E)mergency or abnormal in-plant :L)ow-Power I Shutdown :N)ew or (M)odified from bank including 1 (A) :R)CA :P)revious 2 exams :S)imulator

~~ 4-6 14-6 12-3 I9II8lI4 21 121 I21 21 I2 1 I2 1 22/22121 I 3 I I 3 IS 2 (randomly selected) 21 I21 121 - I - I 21 (control room system)

DC Cook 2010 NRC Examination ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title a. NRC10-SIM01 - Perform Emergency Boration due to Shutdown Margin Not Met KA APE 024 AA1.17 3.913.9, SYS 004 A2.14 3.813.9. Facility:

DC Cook Date of Examination:

6/21/2010 Exam Level: RO 0 SRO-I SRO-U 0 Operating Test No.: Cook 2010 Type Code* Safety Function N-S 1 A-D-L-P-S (Alternate Path to Excess Letdown) KA SYS 004 b. NRCl0-SIM02 - Establish Letdown IAW OHP-4023-SUP-15 A2.07 3.4/3.7 2 c. NRC10-SIM03 - Isolate Safety Injection Accumulators per OHP- 4023.ES-1.2 (2 Failed Accumulator Discharge Valves) KA SYS 006 A4.02 4.013.8 4023.ES-1.2 and Supplement 007 KA SYS 003 A4.08 3.2/2.9 d. NRC10-SIM04 - Restore Reactor Coolant Pump Cooling per OHP- 1 A-D-EN-L-S 3 I 4p L-D-S e. NRCl0-SIM05 - Perform Steam Generator Stop Valve Dump Valve Surveillance Test per l-OHP4030-151-018. SYS 039 K4.05 3.713.7 4s I N-S I 7 11 g. NRC10-SIM07 - Restore Scaler Timer Drawer Post Maintenance KA 015 A4.02 3.9/3.9 1 A-N-S I h. NRC10-SIM08 - Respond to an RyHighxrm (AzActions Failed) KA SYS 033 AI .02 2.8/3.3. SYS 034 ll A4.013.3/3.7, APE 036AA1.02 3.1/3.5 In-Plant Systems@ (3 for RO): (3 for SRO-I); (3 or 2 for SRO-U) I E-D-R I 2 11 i. NRCl0-INP02 - Locally Control the blender to Charging Pump Suction (QRV-400)

KA APE 068 AA1.08 3.9/4.1 4P 1 j. NRClO-INP01 - SIG 213 Level Control through AFW Unit Crosstie.

E-D-P-R I KA APE 054 AA1.01 4.514.4 2007 Exam 1 k. NRC10-INP03 - Perform Local Diesel Generator Trip and Isolation (DG Fails to Trip with Pushbutton)

APE 068 A-D-E 6 AA1.31 3.914.0 (ALT) @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SRO-I I SRO-U ~ ~ (A)ltemate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator

~~~ 4-6 14-6 I 2-3 s91~ais4 2ll2ll2l 2 1 12 1 I2 1 22/22/21 I 3 IS 3 I I 2 (randomly selected) 21 I21 I2 1 - I - I 21 (control room system) 3/25/20 10 Revision 0 DC Cook 2010 NRC Examination ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 System / JPM Title Type Code* Facility:

DC Cook Date of Examination:

6/21/2010 Exam Level: RO 0 SRO-I 0 SRO-U Operating Test No.: Cook 2010 Safety Function a b. c. NRC10-SIM03 - Isolate Safety Injection Accumulators per OHP- 4023.ES-1.2 (2 Failed Accumulator Discharge Valves) KA SYS 006 A4.02 4.0/3.8 d. A-D-EN-L-S 3 e. N-S g. NRC10-SIM07 - Restore Scaler Timer Drawer Post Maintenance KA 015 A4.02 3.913.9 I A-N-S I h. NRC10-SIM08 - Respond to an R5 High Alarm (Auto Actions Failed) KA SYS 033 AI .02 2.8/3.3, SYS 034 I A4.01 3.3/3.7. APE036AA1.02 3.1/3.5 7 8 E-D-R i. NRC10-INP02 - Locally Control the blender to Charging Pump Suction (QRV-4001 KA APE 068 AA1.08 3.914.1 2 j. NRC10-INPOI - S/G 2/3 Level Control through ARN Unit Crosstie.

KA APE 054 AA1.01 4.514.4 k.

  • Type Codes I Criteria for RO I SRO-I I SRO-U ~ 4P E-D-P-R 2007 Exam - (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (WA (S)imulator 3/25/2010 4-6 14-6 I 2-3 59ls81s4 21 I21 I2 1 51 121 121 22122121 5 3 I s 3 Is 2 (randomly selected) 21 I21 I21 - I - I 21 (control room system) Revision 0 ES-301 Transient and Event Checklist Form ES-301-5 I Facility:

j A P P L I C A N T RO 0 0 El SRO-I SRO-U RO 0 IXI RO IXI 0 SRO-U 0 0 0 SRO-I SRO-U SRO-I RO SRO-I SRO-U Instructions:

1. r Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301 Transient and Event Checklist Fo~ ES-301-5 I Facility:

A P P L I C A N T RO 0 IXI SRO-I SRO-U RO *4 0 SRO-I SRO-U RO 0 0 0 SRO-I SRO-U SRO-I SRO-U : Cook Date of Exam: 06/21/2010 Operating Test No.: Crew 5 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.

ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions: Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.

If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a I-for-I basis. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. 3.

ES-301 Transient and Event Checklist Form ES-301-5 Il ! : Cook Date of Exam: 06/21/2010 Operating Test No.: Crews 1.2. 8 3 E Scenarios " TM CREW CREW CREW CREW N T POSITION POSITION POSITION POSITION A Cook 10-01 Cook 10-02 E ~0 I TY 1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.

ROs must serve in both the 'at-the-controls (ATCY and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (VC) malfunctions and one major transient, in the ATC position.

If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two IIC malfunctions required for the ATC position. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (3 Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1 -for-1 basis. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. 2. 3.

ES-401 PWR Examination Outline ~~ Form ES-401-2 Facilitv:

Cook Nuclear Plant Printed: 02/23/2010 Date Of Exam: 06/21/2010 I I RO K/A Category Points I SRO-Only Points Note: I. Ensure that at least two topics from every applicable WA 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

  • I 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. Systemdevolutions 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, sitespecific systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of EM01 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.
3. 4. 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

6. 7.* The generic (G) WAS in Tiers I and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS. 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; 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 #I does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals

(#) on Form ES401-3. 10 CFR 55.43. Limit SRO selections to WAS that are linked to 02/23/2010 7:37:32 am 1 PWR RO Examination Outline Facility:

Cook Nuclear Plant Printed: 02/23/2010 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401 [mp. EIAPE # I Name I Safety Function K1 Point! 000008 Pressurizer Vapor Space Accident I 3 2.7* - 3.9 4.3 - - 2.9 - 3.2 - 3.4 000009 Small Break LOCA I 3 0000 1 1 Large Break LOCA I 3 0000 1510000 17 RCP Malfunctions I 4 000025 Loss of RHR System I4 000027 Pressurizer Pressure Control System Malfunction I 3 000029 ATWS I 1 2.9* - 4.4 1 - 1 000054 Loss of Main Feedwater 14 000055 Station Blackout

/ 6 4.3 1 3.1* - 3.8 3.8 - 000056 Loss of Off-site Power 16 1 1 1 - 000057 Loss of Vital AC Inst. Bus I 6 000058 Loss of DC Power 16 000065 Loss of Instrument Air I 8 3.8 - 3.6 - 3.5 - 4.0 1 1 000077 Generator Voltage and Electric Grid Disturbances 16 WE04 LOCA Outside Containment I 3 WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 02/23/2010 7:36:53 am 1 PWR RO Examination Outline Facility:

Cook Nuclear Plant Printed 02/23/20 10 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 WE12 - Steam Line Rupture - Excessive X Heat Transfer

/ 4 I WA Category Totals:

I 3 associated with Uncontrolled Depressurization of all Steam 02/23/2010 7:36:53 am 2 Printed: 02/23/20 10 PWR RO Examination Outline Facility:

Cook Nuclear Plant Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 I ES - 401 of various types of radiation, exposure levels that are acceptable for nuclear power plant personnel, and the units used for radiation-intensity measurements and for radiation and automatic and operating procedures with Natural Circulation including primary coolant, emergency coolant, the decay heat removal systems, and relations between the 02/23/2010 7:37:02 am 1 Facility:

Cook Nuclear Plant ES - 401 PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Sys/Evol # / Name 1 K1 003 Reactor Coolant Pump I 004 Chemical and Volume Control 006 Emergency Core Cooling X 007 Pressurizer RelieffQuench Tank 008 Component Cooling Water o 1 o Pressurizer Pressure control I 012 Reactor Protection I 012 Reactor Protection I 0 13 Engineered Safety Features Actuation 0 13 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 059 Main Feedwater 06 1 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution I x ~ 063 DC Electrical Distribution 064 Emergency Diesel Generator 064 Emergency Diesel Generator I Printed 02/23/20 10 Form ES-401-2 02/23/2010 7:37: 10 am 1 PWR RO Examination Outline Facility:

Cook Nuclear Plant Printed 02/23/2010 ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 076 Service Water 02/23/2010 7:37: 10 am 2 PWR RO Examination Outline Facility:

Cook Nuclear Plant Printed 02/23/2010 ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Dump/Turbine Bypass understand how operator actions and directives affect 072 Area Radiation Monitoring 02/23/2010 7:37:18 am 1 Generic Knowledge and Abilities Outline (Tier 3) PWR RO Examination Outline Emergency ProceduredPlan Printed: 02/23/20 10 Form ES-401-3 2.4.2 Knowledge of system set points, interlocks and 4.5 1 automatic actions associated with EOP entry conditions.

2.4.6 Knowledge of EOP mitigation strategies.

3.7 1 Category Total:

2 Facilitv:

Cook Nuclear Plant - KA ImD. Points Generic Category Conduct of Operations KA ToDic Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 1 OCFR55, etc. - 1 2.1.4 3.3 66 2.1.5 ~~ ~ ~ ~ ~ Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Knowledge of conservative decision making practices.

Category Total: ~ 2.9* 1 2.1.39 3.6 1 - 3 Equipment Control Category Total: I I Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergencv conditions.

3.2 1 Ability to comply with radiation work permit 3.5 2.3.7 2.3.11 1 1 3 - requirements during normal or abnormal conditions. Ability to control radiation releases. Category Total:

I 74 75- Generic Total:

10 1 02/23/2010 7:37:26 am ES-401 Tier 1. Imergency

& Abnormal Plant Evolutions

2. Plant Systems PWR Examination Outline Group K1 K2 K3 K4 IK5 1 K6 A1 A2 A31 A4 G* Total A2 G* Total 1000 00 00 3 3 6 00 2 2 4 2 000 N/A N/A Tier Totals 0 0 0 00 00 5 5 10 1000000000000 3 2 5 2 000000000000 1 1 1 3 Tier 000000000000 5 3 8 Totals Form ES401-2 1 2 3 4 0 0 0 0 0 3. Generic Knowledge And Abilities Categories Facilitv:

Cook Nuclear Plant Printed: 02/23/2010 Date Of Exam: 06/21/2010 1234 2122 7 ~ ~~ 1 I RO K/A Category Points I SRO-Only Points Note: I. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., 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 *I 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. Systemdevolutions 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, sitespecific systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of EM01 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

3. 4. 5. 6. 7.* The generic (G) WAS in Tiers I and 2 shall be selected from Section 2 of the WA 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 WAS. 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; if fuel handling equipment is sampled in other than Category A2 or G on the SRO-only exam, enter it on the lefl side of Column A2 for Tier 2, Group 2 (Note #I 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 WA numbers, descriptions, IRs, and point totals

(#) on Form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43.

02/23/2010 7:38:26 am 1 PWR SRO Examination Outline Facility:

Cook Nuclear Plant I ES-401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 Printed: 02/23/20 10 EIAPE # I Name I Safety Function 000007 Reactor Trip - Stabilization - Recovery I 1 000022 Loss of Rx Coolant Makeup 12 K1 000026 LOSS of Component Cooling Water

/ 8 DO0038 Steam Gen. Tube Rupture 13 DO0040 Steam Line Rupture - Excessive Heat Transfer 14 DO0062 Loss of Nuclear Svc Water

/ 4 KIA Category Totals: I 0 02/23/2010 7:37:53 am 39 PWR SRO Examination Outline Facility:

Cook Nuclear Plant Printed 02/23/2010 I ES-401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 EIAPE # I Name / Safety Function 000032 Loss of Source Range NI 17 000060 Accidental Gaseous Radwaste Rel. / 9 000069 Loss of CTMT Integrity

/ 5 KIA Category Totals:

0 0 - ,mp. 02/23/2010 7:37:59 am 1 Printed 02/23/20 10 PWR SRO Examination Outline K3 Facility:

Cook Nuclear Plant K4 K5 000 Sys/Evol#

I Name DO5 Residual Heat Removal I DO6 Emergency Core Cooling K1 008 Component Cooling Water 039 Main and Reheat Steam D6 1 AuxiliaryEmergency Feedwater WA Category Totals: I 0 Plant Systems - Tier 2 / Group 1 Form ES-401 Pointr 1 - 1 1 - - 1 1 - 5 02/23/2010 7:38:06 am 1 PWR SRO Examination Outline Facility:

Cook Nuclear Plant Plant Systems - Tier 2 / Group 2 Printed 02/23/20 10 Form ES-401-2 02/23/2010 7:38: 1 3 am 93 '(09 9\ 1 Appendix D Scenario Outline Form ES-D-1 Event No.

1 2 3 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.:COOK 201 0-01 Op-Test No.: Crews 1,2,& 3 Malf. No.

Event Type* N R NTPlll to I-RO Examiners:

RCOIA at 50% Preload RP19D - WRHR Operators: ~ ~~ Major C-RO C-RO Initial Conditions: IC-991 , 78% pwr, 1021 ppm Boron, 8 GWD, 554°F Tave, CBD @I96 steps, 848 MW Turnover: Swap NESW pumps. 1 E MDAFW 00s. Unit was holding at 78% power due to a small oil leak on the West MFW Pump that has recently been repaired, Blender line is full of PW. I TS 650°F I I I I 4 C-BOP CBPN FW58B 6 MPP212 to I ~ I-BOP 100% 7 8 9 Event Description Start South NESW Pump and Stop the North NESW pump. Raise Reactor Power and Turbine Load Loop 1 Hot Leg NTP-111 Temperature Transmitter Fails High North CB pump trip; Middle CB pump fails to start in AUTO Letdown Temperature Controller fails LOW ~~ ~ ~ ~~ ~ S/G 11 Pressure Transmitter MPP-212 Fails High Large Break Loss of Coolant Accident on Loop 1 Slave Relay Failure: 1 E RHR and SI Pumps Fail to Auto Start 1 W RHR Pump Trips 15 minutes after SI * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 Page 1 of 19 Summarv The scenario starts with the plant at 78% power. Power escalation has been on hold for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while repairs were made to the West MFW Pump oil leak. The crew is directed to start the South NESW Pump and shutdown the North NESW pump. An AEO has been briefed and the starting party is ready for the pump start. After NESW Pumps have been swapped, the crew is directed to raise power. The Loop 1 Hot Leg NTP-111 Temperature Transmitter fails high. The rods will insert and power will have to be restored.

The crew will need to enter an Abnormal Operating Procedure, defeat the failed channel, address Technical Specifications, and restore rod control to auto. The next event is a trip of the North Condensate Booster pump.

This will result in reduced feedwater capability.

BOP will be required to manually start the Middle Condensate Booster pump. Crew will be required to implement compensatory actions to stabilize the plant. A short time later a failure of the Letdown Temperature controller will cause the transmitted value to the letdown heat exchanger temperature controller and temperature indicator to fail at the selected severity level.

Selection of a severity level lower than the controller setpoint (normally 120°F.) will cause the letdown temperature control valve (CRV-470) to move to its fully closed position in AUTO. Actual letdown temperature will rise resulting in a rising VCT temperatures. The operator may limit the consequences of this malfunction by taking manual control of CRV-470. Next SG 11 Pressure Channel MPP-212 will fail high, requiring the BOP to take manual control and close the SG PORV valve. The crew should implement an Abnormal Operating Procedure, stabilize the plant, trip bistables, and declare SG PORV Radiation Monitor Inoperable.

Shortly after the SG Pressure Channel failure, a LOCA will develop resulting in a large break LOCA. The plant will trip and Safety Injection will actuate. As the crew performs the actions of E-0 they will note that the 1E RHR and SI pumps failed to auto start on the SI due to a slave relay K610 failure. The crew will transition to E-1 and to ES-1.3 to align for cold leg recirculation. The 1 W RHR will trip 15 minutes into the event. The crew will have to align ECCS to the recirculation sump without the 1 W RHR pump. The scenario will terminate when the crew has aligned ECCS for cold leg injection.

Critical Tasks Establish Low Pressure SI (RHR) Establish Cold Leg Recirculation Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant ES-1.3 Transfer to Cold Leg Recirculation Cook Plant Unit 1 & Unit 2 Page 2 of 19 Appendix D Scenario Outline Form ES-D-1 I Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: Cook 2010-02 Examiners:

Operators:

Op-Test No.: Crews 1,2,& 3 I Initial Conditions:

IC-38 ,loo% pwr; 979 ppm Boron, 8 GWD, 556°F Tave, CBD (@ 219 steps, 1107 MW Turnover: Swap CCP pumps. 1 E MDAFW 00s. 100% power, Blender line is full of PW. A Small Leak on Event ce l6 l8 I the West Mk Malf. No. lump will I Event Type* N R RX21A @ 0 NLP151 @ 0 WCP I-BOP TS I-RO TS C-RO TS RX11 D @I 00% ~~ ED05H ED05D TC02A RP07A RP07B C-BOP TS M C-BOP FW5 1 C-BOP quire a power reduction.

Event Description Start West CCP and Stop East CCP (BOP Performs) Lower Reactor Power and Turbine Load SG Feed Flow Instrument (FFC-210) fails LOW Controlling Pressurizer Level Channel (NLP-151) fails LOW West CCP pump trips (May insert prior to letdown restoration in event 4) SG PORV Controller Failure Loss of Bus TI 1A due to fault on Bus 1A 1A RCP Bus Fault (Loss of RCS Flow in Loop 1) - momentary Main Turbine Fails to Trip/ Steam Line Auto Isolation Failure TDAFW pump T&lV failure due to blown control power fuse West AFW pump power is lost (East AFW is 00s) I Cook Plant Unit 1 & Unit 2 Page 1 of 17 Summary The scenario starts with the plant at 100% power. Power reduction is required due to a small West MFW Pump oil leak.

The crew is directed to start the West Charging Pump and shutdown the East Charging Pump. An AEO has been briefed and the starting party is ready for the pump start. After the Charging pumps have been swapped, the crew is directed to reduce power.

Mer a small power change, a LOW failure of #11 Steam Generator Feed Flow instrument (FFC- 210) will occur.

This will result in a rise in feedwater flow to #11 SG with corresponding SG level rise.

The BOP will be required to take manual control of FRV-2 10. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

The controlling Pressurizer Level channel instrument (NLP-15 1) will fail LOW. This results in charging flow rising, Pressurizer level rising, Pressurizer heaters OFF, and letdown isolation.

RO will be required to restore normal letdown and charging flow conditions. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

The West Charging Pump will trip. This will result in the loss of charging and letdown.

RO will be required to manually start the East Charging Pump to restore charging flow. Crew will be required to take manual control of charging and restore letdown to stabilize the plant. The next event will involve the failure of the SG #14 PORV Controller. The Controller will fail causing PORV 1 -MRV-243 to Fully open, This will also cause Reactor power to slightly rise. The BOP will need to take manual action to close the PORV and the US will need to declare the associated radiation monitor inoperable.

The main event will involve the loss of RCP Bus 1A and Safety Bus T11A requiring a reactor trip. Failure of the Reactor Protection circuit will require a manual turbine trip. As the crew performs the actions of E-0, they should identify the failure to provide adequate feed flow. An SI is expected due to the failure of turbine to trip. The CSFST for Heat Sink will indicate RED due to the loss of all AFW. The crew will immediately transition to FR-H. 1 and re-establish feedwater flow using the TD AFW pump. The scenario will terminate when the crew has established adequate feed flow. Critical Tasks Manually Trip Turbinehsolate Steam Lines Establish AFW flow for Secondary Heat Sink Procedures E-0, Reactor Trip or Safety Injection FR-H. 1, Loss of Secondary Heat Sink Appendix D Scenario Outline Fo~ ES-D-1 Malf. No. Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK 2010-03 Op-Test No.: Crews 4 & 5 Event Event Type* Description N-BOP Start South Hotwell pump and Stop North Hotwell Pump Examiners: Operators:

NTP240 @ 620 MFC140 @ 4E6 over 20 sec RC17C to 50% Initial Conditions: IC-991 , 78% pwr, 1021 ppm Boron, 8 GWD, 554°F Tave, CBD @I 96 steps, 848 MW I-RO TS I-BOP TS C-RO TS RCS Cold Leg Temperature Instrument (NTP-240)

Fails HIGH #24 SG Steam Flow Transmitter (MFC-140) fails HIGH Pressurizer PORV NRV-153 Fails Open. Turnover: Swap Hotwell Pumps, West CCP is 00s for Oil Change this shift. Pump has been 00s for 2 Hours. FWOSA Event No. R-RO Lower Reactor Power and Turbine Load

  • C-BOP East Main Feed Pump Trip .r 1 MSOID @ 20 2 min Ramp 2 M Steam Line Break inside Containment

(#I4 SG) 3 4 5 6 7 8 9 10 FW05B I M I West Main Feed Pump Trip RP03A RP03B I C-RO 1 AUTO/MANUAL Reactor trip actuation failure (ATWS) RP19J 1 C-RO RPS relay K626-X3 failure (2East CTS pump fails to start) I I I Cook Plant Unit 1 & Unit 2 Page 1 of 20 Summarv The Crew is directed to start South Hotwell pump and stop North Hotwell Pump. Following the Hotwell pump shutdown, the crew is preparing to reduce power due to a small oil leak on the East MFP. The RCS Loop 4 Cold Leg Temperature instrument (NTP-240) failing HIGH. This will result in the AUTO insertion of control rods and a lower trip setpoint value for OPAT and OTAT. The RO will be required to take manual control of rods to stop insertion.

Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

After the crew'has addressed the RCS temperature the #14 SG Steam Flow instrument (MFC- 140) failing HIGH. This will result in the opening of #14 SG FWRV (FRV-240) to raise feedwater flow.

BOP will be required to take manual control and regulate FRV-240. Crew will be required to implement AOP actions to stabilize the plant and trip bistables.

The Pressurizer PORV NRVl53 will fail partially Open. This results in Actual RCS pressure lowering.. The RO will be required to take manual actions to isolate the PORV (close block valve) and restore normal pressure conditions.

Next a rapid power reduction is performed (Optional if reactivity change is required - note next event also involves a reactivity change which may be combined with this reactivity change) based on a report of an Oil leak on the East Main feed Pump. A trip of the East Main Feed Pump will result in a rapid power reduction to less than 60% if not already performed. The RO will be required to control reactivity while the BOP monitors the SG levels. The main event will involve a Failure of the RPS function (ATWS) following a trip of the- remaining FW pump. The RPS failure also results in failure of K626-X3 relay which prevents the auto start of the East CTS pump. The reactor must be locally tripped. The crew will implement FR-S.l actions until reactor is subcritical.

A Steam Line Break will cause SG #14 to blow down inside Containment. The BOP will be required to isolate the main steam lines. After the reactor is subcritical, the crew will perform the actions of E-0 to verify the SI actions and then transition to E-2. The scenario will terminate when the crew has completed isolation of the faulted SG in Fr- S. 1 (and completed required steps of E-0) or E-2. Critical Tasks Insert Negative Reactivity Isolate the Faulted Steam Generator Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation FR-S. 1, Response to Anticipated Trip without Scram Cook Plant Unit 1 & Unit 2 Page 2 of 20 Appendix D Scenario Outline Form ES-D-1 ECC, CCO2B - Preload Facility:

Cook Plant Unit 1 & Unit 2 Scenario No.: COOK2010-04 Op-Test No.:Crews 4 & 5 C-BOP TS Examiners:

RP13A, RP13B - Preload Operators:

C-BOP Initial Conditions:

IC-992, 53% pwr, 1 100 ppm Boron, 8 GWD, 551 5°F Tave, CBD @ 189 steps, 550 MW. Turnover:

Start the #I3 CW Pump. 1CD EDG has been out of service for one day for fuel rack repairs. Event No. Event Description Start Circulating Water Pump 1 2 I R-Ro Raise Turbine and Reactor Power to 100%. 3 I C-RO cvo4c 75 gpm Letdown Orifice Isolation Valve QRV-162 Fails Closed 4 1 E CCW pump Trips (1 W CCW [Standby]

Fails to Auto Start) 5 NPP151 to to 103 over 2 min Pressurizer Pressure Channel NPP-151 Fails High S/G 13 Level instrument (BLP-131) failing High 6 7 70% RC1oDto I M-ALL Loop 4 Cold Leg Primary Coolant System 700gpm Leak inside Containment over 5 minutes 8 ~ ~ ~~~ ~ Failure of Automatic Phase A Actuation 9 1 C-RO RP19G, Slave Relay failures:

High Head Charging SI valves fail to align RP20G - Preload (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor (N)orrnal, Cook Plant Unit 1 & Unit 2 Page 1 of21 Summary The Crew is directed to start the 13 C W Pump. The operator will place the 13 C W in service in accordance with the normal operating procedure. Following the CW pump start the crew will perform the power escalation to 80%. After a short ramp the letdown orifice valve will fail closed. The RO will need to restore Letdown through a different valve. While the RO is restoring letdown, a trip of the operating (East) Component Cooling Water (CCW) pump will require the BOP to manually start the standby pump (auto start failure).

After the Crew has addressed the Tech Specs for CCW, the Pressurizer Pressure Channel NPP-15 1 Fails Low. Pressurizer spray valves will go full closed and pressuizer heaters will all be energized at full amps. The crew will need to take manual control of pressurizer pressure and enter an Abnormal Operating Procedure, defeat the failed channel, address Technical Specifications, then restore pressurizer pressure control to auto. Following RCS pressure restoration, the #13 Steam Generator Level instrument (BLP-13

1) fails High. This results in a feedwater flow and Steam Generator level rise.

BOP will be required to take manual control and restore normal level. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications. The major events will occur when the SG level has been stabilized. A 700 gpm Primary System Leak in Containment will occur requiring a Reactor Trip and SI. On the SI, various slave relay failures will cause the High Head Charging SI injection flowpath to fail to align. The RO will need to manually align the High Head Injection Valves. The auto Phase A Isolation will also fail requiring manual actuation to align Phase A equipment.

The crew should progress through E-0 to E-1 to ES-1.2. The scenario will terminate once a transition has been made to ES-1.2. Critical Tasks Restore High Head Injection Trip RCPs Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant Cook Plant Unit 1 & Unit 2 Page 2 of 21

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