Text

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)
	v • d • e

OUTLINE SUBMITTAL FOR THE DAVIS-BESSE INITIAL EXAMINATION - MAY 2004

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ES-201 Examination Preparation Checklist FoFES-201-1

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-180 Facility:

Davis-Besse Date of Examination: 05/03 - 091 0/04 Developed by:

(Facility) /

NRC (circle one)

Target Date*

Chief Examiner's Initials Task Description / Reference

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

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-1 20

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

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

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

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

-1 20

[-go1

-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

8. Proposed examinations, supporting documentation, and to facility licensee (C.2.h; C.3.e) reference materials due (C.l.e, f, g & h; C.3.d)

-45

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

-30

-1 4

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

-1 4

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

-1 4

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 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 5501 North State Route 2 Oak Harbor. Ohio 43449 Mark 8. Barilla Hce President - Nuclear 419-321-7676 Fax: 4 19-32 1 - 7582 1 OCFR2.790(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 (41 9) 32 1-8450.

Sincerely yours, AWB/s J

Enclosures cc:

Chief - Operations Branch, NRC Region 111 w/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

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

I

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

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

I.

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I T

T E

N

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$.lk SA $c2l I P I w I *ai I a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

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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.

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

?ti *4b

4.

2.

S I

M

+* sw $45

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section.

3.

W I

T G

E E

R A

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,

b. Assess whether the 10 CFR 55.41143 and 55.45 sampling is appropriate.

c. Ensure that WA importance ratings (except for plant-specific priorities) are at least 2.5.

d. Check for duplication and overlap among exam sections.

f. Asses whether the exam fits the appropriate job level (RO or SRO).

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e. Check the entire exam for balance of coverage.

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; ensure 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 scenarios will not be repeated on subsequent days.

quantitative criteria specified on Form ES-301-4 and described in Appendix D.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and

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.

b. Verify that:

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

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

activitieq Printed Name / Signature Date

a. Author

b. Facility Reviewer (*)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note:

Not applicable for NRC-developed examinations

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 0 ut li ne 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 (see Note)

Conduct of Operations Emergency Plan I

Describe activity to be performed:

Notification to the Federal Aviation Administration for Cooling 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 Page I

I 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-30 1 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 Conduct of Operations Conduct of Operations Equipment Control

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Radiation Control Emergency Plan Describe activity to be performed:

Shutdown Margin Calculation with >I Known Stuck Rod

~~~

~~

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Control of Locked Valves during Post Maintenance Testing Containment Pressure Reduction Release 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)

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

Operating Test No: 1 and 2 Type Code*

Safety Function System/ JPM Title

a. Obtain 0% Lights and In-Limit Lights for All Control 1/

Rods in a Group 1

b. Manual SFAS Level 1 and 2 Actuation I

2

c. Spray the Pressurizer for Boron Equalization I

3

d. 1 Hour Shutdown of Decay Heat Pumps to Support Core Alterations 4P

e. Operate Containment Hydrogen Purge/Dilution 11 Systems 5

6

f. Energize D I Bus from Emergency Diesel Generator 1 7

g. Restore a tripped RPS Channel to Service

h. Shift from 4 to 2 Circulating Water Pump Operation 8

11 In-Plant Systems (3 for RO; 3 for SRO-I: 3 or 2 for SRO-U) 3 I

N 7 R I

i. High Pressure Injection Alternate Minimum Recirc 11 Flowpath

j. Emergency Operation of the Startup Feedwater Pump l D

1 4

s

k. Station Blackout Diesel Generator Emergency 11 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 N, R

i. High Pressure Injection Alternate Minimum Recirc Flowpath Facility: Davis Besse Nuclear Power Station Exam Level (circle one): RO / SRO(1) /@

Date of Examination: 5/3/04 - 511 0104 Operating Test No:

1 3

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

j. Emergency Operation of the Startup Feedwater Pump System/ JPM Title D

4s

a. Obtain 0% Lights and In-Limit Lights for All Control Rods in a Group 11 b. Manual SFAS Level 1 and 2 Actuation

h. Shift from 4 to 2 Circulating Water Pump Operation ll 11 Implant Systems (3 for RO; 3 for SRO-I:

3 or 2 for SRO-U)

Type Code*

Safety Function 1

2 8

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-Plant Systems Outline Form ES-301-2

e. Operate Containment Hydrogen Purge/Dilution Systems Facility: Davis Besse Nuclear Power Station Exam Level (circle one): RO /@/

SRO(U)

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

Date of Examination: 5/3/04 - 5/10/04 Operating Test No: 2 and 3 Dl s 5

System/ JPM Title

h. Shift from 4 to 2 Circulating Water Pump Operation Code*

I Function Safety N, A, s, L 8

a. Obtain 0% Lights and In-Limit Lights for All Control 11 Rods in a Group

i. High Pressure Injection Alternate Minimum Recirc

j. Emergency Operation of the Startup Feedwater Pump Flowpath

k. Station Blackout Diesel Generator Emergency Shutdown I/ b. Manual SFAS Level 1 and 2 Actuation I

2 Nl R 3

D 4s N, A 6

11 c. Spray the Pressurizer for Boron Equalization I

N, s I

3 I

4p

d. I Hour Shutdown of Decay Heat Pumps to Support

//

Core Alterations

f.

11 g. Restore a tripped RPS Channel to Service I

7 23 of 27 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Event Malf.

No.

1 KEP2E 2

R3N5 11 Facility: Davis-Besse NPS Scenario No.:

1 Op-Test No.: I, 2, and 3 Event Event Type*

Description C (BOP)

I (RO)

Inadvertent Service Water Pump 1 trip Power Range Nuclear Instrument 5 fails high (Tech Spec)

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

~~

3 4

5 UKRF C (BOP)

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

P8RFC M (All)

Loss of Offsite Power 11 6

I GF32B I C (RO) I Emergency Diesel Generator 2 fails to automatically start 11 7

I B2M21 I C ( R 0 ) 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 Exam in ers :

Ope rat ors:

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

6 I F41S1595 I I (BOP) 7 I L4, L8 I C(R0)

M (All)

E!4F (N)ormal, (R)eactivity, (I)n!

NUREG-1021, Draft Revision 9 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.)

~

Small RCS leak Power reduction Loss of all Condensate Pumps ATWS Auxiliary Feedwater Target Rock Valve fails open Small Break LOCA

mment, (C)omponent, (M)ajor 40 of 41

Appendix D Scenario Out line Form ES-D-I Malf.

Event No.

Type*

CAEP C (RO)

BMFI C (RO)

Facility: Davis-Besse NPS Scenario No.:

3 Op-Test No.:

3 Examiners :

Operators:

Event Description Inverter YV4 Failure (Tech. Spec)

Makeup Filter differential pressure high 11 Initial Conditions: 50% Reactor Power, Main Feedwater Pump 2 readv to be placed in service DCMI "51 Turnover:

Main Feedwater Pump 2 running at 3900 RPM ready to be placed in service C (BOP)

M (All)

Loss of Condenser Vacuum Steam Generator Tube Rupture Event No.

LlTL20 I

I (BOP)

Steam Generator Level Transmitter fails mid-scale 2

3 4

II 5

T

(

S R

0

)

I Loss of Shield Building Integrity (Tech Spec) 6 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.

2.

3.

4.

5.

6. *

7.

8.

9.

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.

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.

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.

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

The shaded areas are not applicable to the categoryhier.

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.

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.

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

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 Emergency and Abnormal Plant Evolut E/APE # / Name / Safety Functions K

K K

A A

G 1

2 3

1 2

2.2.22 - Knowledge of LCOs and safety limits EA1.04 - Reduction of loads on the battery AA2.43 - Determine occurrence of a turbine trip AK3.01 - EOP actions for loss of a vital bus 2.4.10 -Annunciator reSDonSe Drocedure 300054(CE/E06) ~ossofMain Feedwater14 I

I I

I X I

I I

I 3.4 1

3.5 1

3.9 1

4.1 1

3.0 1

SRO 2.1.32-Ability toexplain'and apply limits and precautions 21 21 41 41 31 31 1

0 0

1 3

2 3.8 1

7 Outline Form ES-401-2 ins -Tier 1lGroup 1 (RO / SRO)

WA Topic(s)

IR EK2.2 - Interrelation between heat removal systems and inadequate heat transfer EKI.02 - Shutdown Mar in AA1.05 - Operate or monitor LPI System SRO AA1.07 - Reseatin of code safe and PORV 4.2 4.2 1

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 3W/E04; WIE05 Inadequate Heat Transfer -

-ass of Secondary Heat Sink I 4 AA2.05 - Limitations on LPI flow 3.1 1

AK3.03 -Actions in EOP for loss of CCW

. ^

X 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

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

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

18/7 Group Point Total:

NUREG-1021, Draft Revision 9 23 of 34

EIAPE # I Name I Safety Functions SRO,442.10 -Tech Spec limits if both IR channels NIE 16 High Containment Radiation I 9 3WIA01 Plant Runback I 1 X

facility AA1.2 - Monitor operating behavior characteristics of 3W/AOZ&A03 LOSS Of 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

~

21 21 21 I /

I t I /

+

3.2 1 2.7 t

</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

ES-401 System # I Name 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/ Quench Tank 008 Component Cooling Water 01 0 Pressurizer Pressure Control 012 Reactor Protection 01 3 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 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 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment WA Category Point Totals:

NUREG-1021, Draft Revision 9 PWR Examination Outline Plant Systems -Tier 2IGroup 1 (RO I SRO)

Form ES-401-2

~~

K A

A A

A G

K/A Topic(s)

IR 6

1 2

3 4

X AI.01 - Monitor RCP vibrations 2.9 1

2.9 I/

X SRO A4.13 -Monitor MUT level and pressure control 2.9 1

X A4.01 - Operate/monitor RHR Pumps 3.6 1

K2.02 - Knowledge of power supplies to MU Pumps I K1.04 - Cause/effect between ECCS and Aux Spray 1 2.7 I 1

I K3.01 - Effect malfunction will have on Ctmt I 3.3 I

\\ K4.01 -Quench Tank cooling I 2.6 I 2

K1.02 - Causeleffect between loads and CCW 3.3 1

I 2.5 I 21 I

I I

I K2.02 - Power s u ~ ~ l v for smav valve I

I I

I A3.01 Monitor PRT during 'PORV test I 3.0 I X I 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 K4.04 - Knowledge of RPS redundancy 3.1 2

2.7 1

K6.01 - Effect of loss of detector on SFAS K3.02 - Effect of loss of CAC on Ctmt instruments 3.0 11 X SRO 2.1.20 -Ability to execute procedure steps 4.2 1

X 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 K1.05 - Causeleffect between EDG and starting air 3.4 1

I I

K3.01 - Effect of malfunction on a release 3.6 1

A I.02 - Monitor TPCW temperatures X

X 2.4.4 - Entry level conditions for abnormal procedure 4.0 2

2.6 K4.02 - IA interlock for crossover to other air systems X 2.1.27 - Knowledge of system purpose 3.2 1

2.8 1

I I

1 3

1 2

2 2

1 1

2814 1 I 0 I 1 I 0 I 1 I 1 I Group Point Total:

25 of 34

ES-401 KIA Category Point Totals:

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

1 1

0 1

1 1

1 l

l t

l l

i l

t t

i l

0 0 0 0 0 0 0 1 0 0 1 Group PointTotal:

Form ES-401-2 1 -

NUREG-1021, Draft Revision 9 26 of 34

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

Form ES-40 1-3

~ Facility: Da\\

ML041830290

Text

Subject:

Dear Mr. Valos:

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