ML041830290

Outline Submittal for Davis-Besse Initial Examination - May 2004

ML041830290
Person / Time
Site:	Davis Besse
Issue date:	05/03/2004
From:	House J FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML041600289	List: ML041830271 ML041830281 ML041830290 ML041830294 ML041830296 ML041830299
References
50-346/04-301
Download: ML041830290 (22)

Text

OUTLINE SUBMITTAL FOR THE DAVIS-BESSE INITIAL EXAMINATION MAY 2004

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ES-201 Examination Preparation Checklist FoFES-201-1 Facility: Davis-Besse Date of Examination: 05/03 - 0910/04 Developed by: (Facility) / NRC (circle one)

Target Chief Date* Task Description / Reference Examiner's Initials

~ -180 1. Examination administration date confirmed (C.l .a; C.2.a & b)

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-120 2. NRC examiners and facility contact assigned (C.l .d; C.2.e)

-120 3. Facility contact briefed on security & other requirements (C.2.c)

-120 4. Corporate notification letter sent (C.2.d)

[-go1 [5. Reference material due (C.l .e; C.3.c)l

-75 6. Integrated examination outline(s) due (C.1 .e & f; C.3.d)

-70 7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)

-45 8. Proposed examinations, supporting documentation, and reference materials due (C.l .e, f, g & h; C.3.d)

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-30 9. Preliminary license applications due (C.l .I; C.2.g; ES-202)

-14 10. Final license applications due and assignment sheet prepared (C.l .I; C.2.g; ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility licensee (C.l .j; C.2.f & h; C.3.g)

-7 13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 14. Final applications reviewed; assignment sheet updated; waiver letters sent (C.2.g, ES-204)

15. Proctoring/written exam administration guidelines reviewed with

-7 facility licensee and authorization granted to give written exams (if applicable) (C.3.k)

-7 16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

• Target dates are keyed to the examination date identified in the corporate notification letter.

They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[ ] Applies only to examinations prepared by the NRC.

23 of 25 NUREG-1021, Draft Revision 9

FENOC FirstEnergy Nuclear Operating Company Mark 8.Barilla 5501 North State Route 2 Oak Harbor. Ohio 43449 419-321-7676 Fax: 4 19-321- 7582 Hce President - Nuclear 10CFR2.790(a)(8)

Docket Number 50-346 License Number NPF-3 Serial Number 1-1344 January 22, 2004 Mr. N. Valos Chief Examiner - Region I11 United States Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-435 1

Subject:

Operator License Examination Outline

Dear Mr. Valos:

Enclosed is the operator license examination outline required to support the operator license examinations being administered at the Davis-Besse Nuclear Power Station (DBNPS) during the week of May 3,2004. This examination outline is considered confidential material and shall be withheld from public disclosure in accordance with 10 CFR 2.790(a)(8) until after the scheduled operator examinations are complete.

Mr. John C. House, Staff Nuclear Instructor, can respond to questions with regard to the submitted materials, at (419) 321-733 1.

If you require additional information, please contact Mr. Gregory A. Dunn, Manager - Regulatory Affairs, at (419) 32 1-8450.

Sincerely yours, AWB/s J Enclosures cc: Chief - Operations Branch, NRC Region 111w/o DB-1 NRC/NRR Senior Project Manager w/o DB-1 Senior Resident Inspector w/o USNRC Document Control Desk w/o Utility Radiological Safety Board w/o

Docket Number 50-345 License Number NPF-3 Serial Number 1- 1344 Operator License Examination Outline

Docket Number 50-346 License Number NPF-3 Serial Number 1- 1344 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station in this document. Any other actions discussed in the submittal represent intended or planned actions by Davis-Besse. They are described only as information and are not regulatory commitments. Please notify the Manager - Regulatory Affairs (419) 321-8450 at Davis-Besse of any questions regarding this document or associated regulatory commitments.

COMMITMENTS DUE DATE None N/A

ES-201 Examination Outline Quality Checklist Form ES-201-2 Initials Item Task Description I I I.

I a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

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R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.l of ES-401 and whether all WA categories are appropriately sampled.

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c. Assess whether the outline over-emphasized any systems, evolutions, or generic topics.

$-+5d $&

N d. Assess whether the justifications for deselected or rejected WA statements are appropriate. kl.$ SA $c2l

a. Using form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, and major transients,

2. 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 S without compromising exam integrity; ensure each applicant can be tested using at least one I new or significantly modified scenario, that no scenarios are duplicated from the applicants; M audit test(s)*, and 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-301-4 and described in Appendix D.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in plant tasks, (2) no more than 30%of the test material is repeated from the last NRC examination, (3)* no tasks are duplicated from the applicants audit test(s), and (4) no more than 80%of any operating test is taken directly from the licensees exam banks.

3. b. Verify that:

(1) the tasks are distributed among the safety function groupings as specified in ES-301 W (2) one task is conducted in a low-power or shutdown condition, I (3) 4 - 6 (2 - 3 for SRO-U) of the tasks require the applicant to implement an alternate path procedure T (4) one in-plant task tests the applicants response to an emergency or abnormal condition, and f

c. Verify that the required administrative topics are covered, with emphasis on performance-based activitieq

d. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days. fy ?ti *4b 4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section. +* sw $45 G b. Assess whether the 10 CFR 55.41143 and 55.45 sampling is appropriate. <$.* jLJ &//

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c. Ensure that W A importance ratings (except for plant-specific priorities) are at least 2.5. {b* (7d&L/

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d. Check for duplication and overlap among exam sections. P %J . 2&

A e. Check the entire exam for balance of coverage. p S W &aL/

f. Asses whether the exam fits the appropriate job level (RO or SRO). fps w aid Printed Name / Signature Date

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note:

• Not applicable for NRC-developed examinations

1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

NUREG-I 021, Draft Revision 9 24 of 25

Es-301- Administrative Topics 0utline Form ES-301-1 Facility: Davis-Besse NPS Date of Examination: 5/3/04 - 5/7/04 Examination Level (circle one): RO /@ Operating Test Number: 1,2 and 3 Administrative Topic Describe activity to be performed:

(see Note)

Notification to the Federal Aviation Administration for Cooling Conduct of Operations Tower Aviation Light Failure Review and Correct a Shutdown Margin Calculation Control of Locked Valves during Post Maintenance Testing Containment Pressure Reduction Release Manually Activate the Emergency Response Organization Group II Emergency Plan I

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

NUREG-1021, Draft Revision 9 22 of 27

ES-301 Administrative Totics Outline Form ES-30 1-1 Facility: Davis-Besse NPS Date of Examination: 5/3/04- 5/7/04 Examination Level (circle one):@ SRO Operating Test Number: 1 and 2 I

Administrative Topic Describe activity to be performed:

Conduct of Operations Shutdown Margin Calculation with >I Known Stuck Rod Conduct of Operations

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Control of Locked Valves during Post Maintenance Testing Equipment Control

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Radiation Control Containment Pressure Reduction Release Emergency Plan Offsite Dose Assessment Using a Nomogram Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

NUREG-1021, Draft Revision 9 22 of 27

Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Davis Besse Nuclear Power Station Date of Examination: 5/3/04 - 5/10/04 Exam Level (circle one):@/ SRO(I) / SRO(U) Operating Test No: 1 and 2 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System/ JPM Title Type Safety Code* Function 1/ a. Obtain 0% Lights and In-Limit Lights for All Control Rods in a Group 1

I b. Manual SFAS Level 1 and 2 Actuation 2 I c. Spray the Pressurizer for Boron Equalization

d. 1 Hour Shutdown of Decay Heat Pumps to Support 3

4P Core Alterations 1 e. Operate Containment Hydrogen Purge/Dilution Systems 5

f. Energize D I Bus from Emergency Diesel Generator 1 6

g. Restore a tripped RPS Channel to Service 7

h. Shift from 4 to 2 Circulating Water Pump Operation 8 1 In-Plant Systems (3 for RO; 3 for SRO-I: 3 or 2 for SRO-U) 1 i. High Pressure Injection Alternate Minimum Recirc Flowpath I N7R I 3

j. Emergency Operation of the Startup Feedwater Pump l D 1 4 s 1 k. Station Blackout Diesel Generator Emergency Shutdown 6

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA 23 of 27 NUREG-1021, Draft Revision 9

Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Davis Besse Nuclear Power Station Date of Examination: 5/3/04 - 5110104 Exam Level (circle one): RO / SRO(1) /@ Operating Test No: 1 I/ Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Type Safety System/ JPM Title Code* Function

a. Obtain 0% Lights and In-Limit Lights for All Control Rods in a Group 1 1 b. Manual SFAS Level 1 and 2 Actuation 2 l h. Shift from 4 to 2 Circulating Water Pump Operation 8 1 Implant Systems ( 3 for RO; 3 for SRO-I:3 or 2 for SRO-U)

i. High Pressure Injection Alternate Minimum Recirc N, R 3 Flowpath

j. Emergency Operation of the Startup Feedwater Pump D 4s

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA 23 of 27 NUREG-1021, Draft Revision 9

Control RoomAn-PlantSystems Outline Form ES-301-2 Facility: Davis Besse Nuclear Power Station Date of Examination: 5/3/04 - 5/10/04 Exam Level (circle one): RO /@/ SRO(U) Operating Test No: 2 and 3 Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System/ JPM Title Code* I Function Safety 1 a. Obtain 0% Lights and In-Limit Lights for All Control Rods in a Group I/ b. Manual SFAS Level 1 and 2 Actuation I 2 1 c. Spray the Pressurizer for Boron Equalization I N,s I 3

/ d. I Hour Shutdown of Decay Heat Pumps to Support Core Alterations I 4p

e. Operate Containment Hydrogen Purge/Dilution Dl s 5 Systems f.

1 g. Restore a tripped RPS Channel to Service I 7

h. Shift from 4 to 2 Circulating Water Pump Operation N, A, s, L 8

i. High Pressure Injection Alternate Minimum Recirc Nl R 3 Flowpath

j. Emergency Operation of the Startup Feedwater Pump D 4s

k. Station Blackout Diesel Generator Emergency N, A 6 Shutdown 23 of 27 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 1 Facility: Davis-Besse NPS Scenario No.: 1 Op-Test No.: I,2, and 3 Examiners: Operators:

Initial Conditions: 28% Reactor Power, Emergency Diesel Generator 1 Out of Service Turnover: Plant Shutdown in progress due to Tech Spec 3.8.1.1 Event Malf. Event Event No. No. Type* Description 1 KEP2E C (BOP) Inadvertent Service Water Pump 1 trip 2 R3N5 I (RO) Power Range Nuclear Instrument 5 fails high (Tech Spec)

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3 UKRF C (BOP) Main Turbine Quill Shaft failure 4 SFEG C (BOP) lsolable Main Steam Line leak (Tech. Spec.)

5 P8RFC M (All) Loss of Offsite Power 1 6 I GF32B I C (RO) I Emergency Diesel Generator 2 fails to automatically start 1 7 I B2M21 I C(R0) I MakeupPump2failstostart

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 40 of 41

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse NPS Scenario No.: 2 Op-Test No.: 1, 2, and 3 Examiners : Ope rators:

Initial Conditions: 100% Reactor Power, Makeup Pump 1 Out of Service Turnover:

Event Description Safety Features Actuation System RCS pressure transmitter fails high (Tech. Spec.)

High Pressure Feedwater Heater tube leak EDG 1 Trouble Alarm (Tech. Spec.)

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Small RCS leak Power reduction 6 I F41S1595 I I (BOP) Loss of all Condensate Pumps 7 I L4, L8 I C(R0) ATWS Auxiliary Feedwater Target Rock Valve fails open M (All) Small Break LOCA E!4F (N)ormal, (R)eactivity, (I)n!

mment, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9 40 of 41

Appendix D Scenario Out line Form ES-D-I Facility: Davis-Besse NPS Scenario No.: 3 Op-Test No.: 3 Examiners : Operators:

1 Initial Conditions: 50% Reactor Power, Main Feedwater Pump 2 readv to be placed in service Turnover: Main Feedwater Pump 2 running at 3900 RPM ready to be placed in service Event Malf. Event Event No. No. Type* Description I CAEP C (RO) Inverter YV4 Failure (Tech. Spec) 2 BMFI C (RO) Makeup Filter differential pressure high 3 T _____-

( S R 0 ) I Loss of Shield Building Integrity (Tech Spec) 4 DCMI C (BOP) Loss of Condenser Vacuum I 5 "51 M (All) Steam Generator Tube Rupture 6 LlTL20 I (BOP) Steam Generator Level Transmitter fails mid-scale I I I I NUREG-1021, Draft Revision 9 40 of 41

h ES-401 PWR Examination Outline Form ES 401-2 Facility: Davis-Besse Date of Exam: May 10,2004 Note: 1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.l .c for additional guidance regarding SRO sampling.

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 k1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only must total 25 points.

3. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system or evolution unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the categoryhier.

6.

• The generic (G) WAS in Tier 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution of system. The SRO WAS must be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance rating (IR) 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; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled "K' and "A." Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

NUREG-1021, Draft Revision 9 22 of 34

ES-401 PWR Examinati 7 Outline Form ES-401-2 Emergency and Abnormal Plant Evolut ins -Tier 1lGroup 1 (RO / SRO)

E/APE # / Name / Safety Functions K K K A A G WA Topic(s) IR #

1 2 3 1 2 EKI .02 - Shutdown Mar in AA1.05 Operate or monitor LPI System SRO AA1.07 - Reseatin of code safe and PORV 4.2 EK2.02 - Interrelations between pumps and LBLOCAs SRO 2.4.31 - Knowledge of annunciators and alarms AK1.03 - Relationship between charging flow and Pzr level 3.0 AA2.05 - Limitations on LPI flow 3.1 1 AK3.03 -Actions in EOP for loss of CCW .^

SRO AA2.04 - Normal values and upper limits of components cooled by CCW AK3.04 -Why level recovers slower on loss of Pzr level 2.8 1 EA1.08 - Operate reactor trip pushbuttons I 4.5 I 1 EA1.28 - Interlock between MSlV and bypass valve I 3.6 I 1 SRO EKI .02 - Leak rate vs. pressure drop 1 3.5 I 1 I I 300054(CE/E06) ~ o s s o f M a i nFeedwater14 I I I I I I X 2.2.22 - Knowledge of LCOs and safety limits 3.4 1 I I I I I I EA1.04 - Reduction of loads on the battery 3.5 1 AA2.43 - Determine occurrence of a turbine trip 3.9 1 AK3.01 - EOP actions for loss of a vital bus 4.1 1 2.4.10 -Annunciator reSDonSe Drocedure 3.0 1 SRO AA2.01 -Verify loss of DC has occurred I 4.1 I 1 2.1.28 - purpose of major components I 3.2 I 1 SRO 2.1.32- Ability toexplain'and apply limits and 3.8 1 precautions AA2.05 - Determine when to shutdown I 3.4 I 1 SRO EA2.1 - Facilitv conditions and selection of 1 appropriate procedures I 4.3 1 1 3W/E04; WIE05 Inadequate Heat Transfer - EK2.2 - Interrelation between heat removal systems

-ass of Secondary Heat Sink I 4 X and inadequate heat transfer 4.2 1 21 21 41 41 31 31 18/7 1 0 0 1 3 2 Group Point Total:

NUREG-1021, Draft Revision 9 23 of 34

EIAPE # I Name I Safety Functions

+

3.2 2.7 1

SRO ,442.10 -Tech Spec limits if both IR channels NIE 16 High Containment Radiation I 9 t AA1.2 - Monitor operating behavior characteristics of 3WIA01 Plant Runback I 1 X facility 3W/AOZ&A03 LOSSO f NNI-XN I 7 3WIA04 Turbine Trip I 4 X 2.4.48 - Interpret Control Room indications AK2.1 - interrelation between EDG and safetv Adherence to procedures and operation 2ElA11; WIE08 RCS Overcooling - PTS I 4

>E/A16 Excess RCS Leakage I 2 2EIE09 Functional Recovery - - - -_

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21 21 21 I/ It I/

</A Category Point Totals: I 0 I 1 I 0 I 1 I 2 I 1 I Group Point Total: I 9/5 NUREG-1021, Draft Revision 9 24 of 34

PWR Examination Outline Form ES-401-2 ES-401 Plant Systems -Tier 2IGroup 1 (RO I SRO)

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System # I Name K A A A A G K/A Topic(s) IR #

6 1 2 3 4 003 Reactor Coolant Pump X AI .01 - Monitor RCP vibrations 2.9 1 K2.02 - Knowledge of power supplies to MU Pumps 2.9 I/

004 Chemical and Volume Control X SRO A4.13 -Monitor MUT level and pressure control 2.9 1 005 Residual Heat Removal X A4.01 - Operate/monitor RHR Pumps 3.6 1 006 Emergency Core Cooling I K1.04 - Cause/effect between ECCS and Aux Spray 1 2.7 I 1 007 Pressurizer Relief/ Quench I K3.01 - Effect malfunction will have on Ctmt I 3.3 I Tank \ K4.01 -Quench Tank cooling I 2.6 I 2 008 Component Cooling Water K1.02 - Causeleffect between loads and CCW 3.3 1 I I I I I I K2.02 - Power s u ~ ~forl vsmav valve I 2.5 I 21 I I I I I I A3.01 Monitor PRT during 'PORV test I 3.0 I 01 0 Pressurizer Pressure Control XI I I X I I I SRO K6.02 - Effect of Pz; malf on pressure control I 3.5 I 1 I K1.01 - Causeleffect between RPS and 120 vac I 3.4 I 012 Reactor Protection K4.04 - Knowledge of RPS redundancy 3.1 2 01 3 Engineered Safety Features Actuation X K6.01 - Effect of loss of detector on SFAS 2.7 1 K3.02 - Effect of loss of CAC on Ctmt instruments 3.0 11 022 Containment Cooling X SRO 2.1.20 -Ability to execute procedure steps 4.2 1 025 Ice Condenser 026 Containment Spray K1.01 - Causeleffect between CSS and ECCS 4.2 1 K5.05 - Basis for RCS cooldown limits 2.7 21 A4.04 ODerate AFP turbines 3.8 039 Main and Reheat Steam 056 Condensate 059 Main Feedwater 061 AuxiliaryIEmergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator K1.05 - Causeleffect between EDG and starting air 3.4 1 I I I I I I I I 073 Process Radiation Monitoring K3.01 - Effect of malfunction on a release 3.6 1 A I .02 - Monitor TPCW temperatures 2.6 076 Service Water X X 2.4.4 - Entry level conditions for abnormal procedure 4.0 2 078 Instrument Air K4.02 - IA interlock for crossover to other air systems 3.2 1 103 Containment X 2.1.27 - Knowledge of system purpose 2.8 1 I I I I I I I I 1 3 1 2 2 2 1 1 1 1 1 1 2814 WA Category Point Totals: I I 1 I 0 I 1 I 1 I Group Point Total:

1 0 NUREG-1021, Draft Revision 9 25 of 34

ES-401 PWR Examination Outline Plant Systems -Tier 2IGroup 2 (RO I SRO) Form ES-401-2

- 1 1 1 1 1 1 1 0 1 1 1 1 l l t l l i l t t i l KIA Category Point Totals: 0 0 0 0 0 0 0 1 0 0 1 Group PointTotal:

NUREG-1021, Draft Revision 9 26 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

~ Facility: Da\ ;-Besse NPS Date of Exam: 5/10/04 Category 2.1.2 II Knowledge of operator responsibilities I I I I 2.1.21 Ability to obtain and verify procedures 3.1 1

1. 2.1.6 Ability to supervise during plant transients 4.3 1 Conduct of 2.1.33 Ability to recognize entry level for Tech Spec 4.0 1 Operations 2.

Equipment Control 3.

Radiation Control 2.4.43 Knowledge of emergency communications 2.8 1

4. 2.4.45 Ability to prioritize annunciator alarms 3.3 I Emergency Procedure 2.4.22 Knowledge of basis for prioritizing safety functions 4.0 1 I Plan 2.4.28 Knowledge of procedures related to sabotage 3.3 1 27 of 34 NURG-1021, Draft Revision 9

ES-401 Record of Rejected WAS Form ES-401-4 Reason for Rejection NUREG-1021, Draft Revision 9 28 of 34

Process for Written Examination Outline Development Each Group was reviewed which subsequently led to the deletion of the following items:

Tier 1 Group 1 Loss of Emergency Coolant Recirc Tier 1 Group 2 Re-diagnosis and SI Termination Steam Generator Overpressure Containment Flooding Functional Recovery Tier 2 Group 2 Ice Condenser Tier 2 Group 2 Containment lodine Removal These items were deleted from the selection process based on not being applicable at Davis-Besse.

For both the SRO and RO examination outlines a Microsoft Excel program was used to randomly select the number of questions to be selected from each WA category based on the required point total for each Group and Tier. Through the use of a computerized random number generator, Group items are chosen for each of the previously selected WA categories. The random number generator is also used to select the specific WA statements with importance ratings of 2.5 or greater. The rejected WA statements are listed on Form ES-401-4.