ML13259A192

2013 Davis-Besse Nuclear Power Station Initial License Examination Outline Submittal

ML13259A192
Person / Time
Site:	Davis Besse
Issue date:	06/03/2013
From:	Bielby M NRC/RGN-III/DRS/OLB
To:	FirstEnergy Nuclear Operating Co
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ML11354A430	List: ML13259A192
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Download: ML13259A192 (36)

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2013 DAVIS-BESSE NUCLEAR POWER STATION INITIAL LICENSE EXAMINATION OUTLINE SUBMITTAL

5501 North State Route 2 RrstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 RaymondA.Ueb -OPERATOR LICENSE EXAMINATION MATERIAL- 419-321-7676 Vice President, Nucle~WHEN SEPARATED FROM ENCLOSURE, HANDLE THIS DOCUMENT Fax. 419-321 - 7582 AS UNRESTRICTED-March 14, 2013 10 CFR 55 L-13-115 Mr. Michael Bielby Chief Examinator, Region Ill U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352

Subject:

Davis-Besse Nuclear Power Station, Unit 1 Docket Number 50-346, License Number NPF-3 Operator License Examination Outline 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 weeks of June 3 and June 10, 2013. These outlines are submitted in accordance with NUREG 1021, Operator Licensing Examination Standards for Power Reactors (Revision 9, Supplement 1).

The unsigned Form ES-301-4, Simulator Scenario Quality Checklist, is being sent to support Form ES-201-2, Examination Outline Quality Checklist. A signed version of this form will be sent with the exam materials.

The Westinghouse developed PWROG Random Generator software was used to generate both the RO and SRO written examination outlines. This software follows the selection process described in ES-401, Attachment 1, Example Systematic Sampling Methodology and the KIA Elimination Guidance provided in ES-401. Replacement K/As were manually selected utilizing this same guidance. Rejected K/As were documented on Form ES-401-4, Record of Rejected K/As.

The expected additions to the Exam Security Agreement are additional Operations Validation Team members.

We request these materials be withheld from public disclosure until after the completion of the exam.

Richard Brooks, Fleet Exam Development- Lead, can respond to questions with regard to submitted operator license examination outline at (724) 682-5723.

MAR 1 8 2013

-OPERATOR LICENSE EXAMINATION MATERIAL-

- WHEN SEPARATED FROM ENCLOSURE, HANDLE THIS DOCUMENT AS UNRESTRICTED -

Davis-Besse Nuclear Power Station, Unit 1 L-13-115 Page 2 of 2 There are no regulatory commitments in this letter. If there are any questions or if additional information is required, please contact Mr. Anthony Stallard, Superintendent-Nuclear Operations, at (419) 321-7161 or Mr. Mark Klein- Fleet Exam Developer, at (419) 321-7773.

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Enclosure:

NUREG 1021 Forms and Operator License Examination Outline cc: Regional Administrator, NRC Region Ill (w/o Enclosure)

Chief, Operations Branch, NRC Region Ill (w/o Enclosure)

DB-1, NRC/NRR Senior Project Manager (w/o Enclosure)

DB-1 Senior Resident Inspector (w/o Enclosure)

USNRC Document Control Desk (w/o Enclosure)

Utility Radiological Safety Board (w/o Enclosure)

- OPERATOR LICENSE EXAMINATION MATERIAL -

-WHEN SEPARATED FROM ENCLOSURE, HANDLE THIS DOCUMENT AS UNRESTRICTED -

Davis-Besse Nuclear Power Station, Unit 1 L-13-115 Enclosure List of Enclosed NUREG Forms Form ES-201-2, Examination Outline Quality Checklist Form ES-201-3, Examination Security Agreement Form ES-301-1, Administrative Topics Outline RO- Rev. 0 Form ES-301-1, Administrative Topics Outline SRO- Rev. 0 Form ES-301-2, Control Room/In-Plant Systems Outline RO - Rev. 0 Form ES-301-2, Control Room/In-Plant Systems Outline SR0 Rev. 0 Form ES-301-2, Control Room/In-Plant Systems Outline SRO-U - Rev. 0 Form ES-301-4, Simulator Scenario Quality Checklist- Rev. 0 Form ES-301-5, Transient and Event Checklist - Rev. 0 Form ES-301-6, Competencies Checklist - Rev. 0 RO Written Outline:

Form ES-401-2, PWR Examination Outline - RO - Rev. 0 Form ES-401-3, Generic Knowledge and Abilities Outline Tier 3- RO- Rev. 0 SRO Written Outline:

Form ES-401-2, PWR Examination Outline- SRO- Rev. 0 Form ES-401-3, Generic Knowledge and Abilities Outline Tier 3 - SRO - Rev. 0 Form ES-401-4, Record of Rejected K/As- Rev. 0 Form ES-D-1, Scenario Outline - Rev. 0

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 Initials Item Task Description a b* c#

1.

w

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

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b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of R

I ES-401 and whether all KIA categories are appropriately sampled. f;'!J- ~ SL T

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c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. ~~~ ~ c1l.

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

P;7:J- ;v1' Jl-v

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal 2.

evolutions, instrument and component failures, technical specifications and major transients. /)lj_!J A ~

v s b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of I applicants in accordance with the expected crew composition and rotation schedule without compromising M exam integrity; and ensure that each applicant can be tested using at least one new or significantly modified vz, scenario, that no scenarios are duplicated from the applicant's audit test(s), and scenarios will not be repeated on subsequent days. ff'!J f""i

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. 'dtJ- ~ rJ1-IV

a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

3.

(1) the outline(s) contain(s} the required number of control room and in-plant tasks distributed among the w safety functions as specified on the form.

I T (2) task repetition from the last two NRC examinations is within the limits specified on the form. uz_,.-

(3) no tasks are duplicated from the applicant's audit test(s). 1/)~

vi (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 on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form.

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(2) at least one task is new or significantly modified. jV'i rfl.---

(3) no more than one task is repeated from the last two NRC licensing examinations.

c. 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. {Jj;J

v-1 ..5'-

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section. I}J'!J ~- sz, G

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

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

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d. Check for duplication and overlap among exam sections.

@!J ,.rt oJZ-L e. Check the entire exam for balance of coverage.

~ r{ vz-

f. Assess whether the exam fits the appropriate job level (RO or SRO). (If'~  ::1* ~-1 Jl-Printed Name I Signature Date

a. Author Ric}1.qJ S t3f'*!CJ~) J P:J-~---******* B)-1(!3

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{/ _..r( 3l1'\\t7

b. Facility Reviewer(*) A-t.JiY'"' "' '-.),}* ~ \i\l\wVU\ ---61 f 3 )fl.\)! s

\)Cloi ~ \)). ee~ /Uo A)(?l/.LLI ~~,}. ;fa\"~ t 3 Ize\1.5 s4:& ~../ /

c. NRC Chief Examiner (#)

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3/~o;?D/3 I

d. NRC SupeNisor !t/Yl'll/flb-l ~1 - -~~~~

/ _V Note: # Independent NRC reviewer initial items in C'olumn "c"; chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 mination Level RO 1&1 Operating Test Number _

Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of Operations D,R 2.1.43 (4.1)

(RO A1.1) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

JPM 58 Calculate SDM with Tave > 500°F Conduct of Operations N,R 2.1.7 (4.4)

(RO A1.2) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

JPM New Plot and evaluate 1/M data Equipment Control D,R 2.2.12 (3.7)

A2) Knowledge of surveillance procedures.

JPM 227 Calculate RCS flow with F744 inoperable Radiation Control D,S 2.3.5 (2.9)

(RO A3) Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

JPM 260 Adjust RE1878A Warning and High setpoints Emergency NOT EVALUATED Procedures/Plan 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 (::. 3 for ROs; ~ 4 for SROs & RO retakes)

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

(P)revious 2 exams (::. 1; randomly selected)

NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 mination Level SRO 00 Operating Test Number _ _ __

Administrative Type Describe activity to be performed Topic Code*

(See Note}

Conduct of D,S 2.1.18 (3.8)

Operations Ability to make accurate, clear, and concise logs, records, status (SRO A1.1) boards, and reports.

JPM 246 Notification to FAA Conduct of N,R 2.1.5 (3.9)

Operations Ability to use procedures related to shift staffing, such as minimum (SRO A1.2) crew complement, overtime limitations, etc.

JPM New Determine Availability For Call-ln.

Equipment Control N,R 2.2.18 (3.9)

(SRO A2) Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

JPM New Shutdown Defense In Depth Assessment Radiation Control N,R 2.3.6 (3.8)

(SRO A3) Ability to approve release permits.

JPM New Perform Administrative Checks For Radioactive Liquid Batch Release Emergency D,S 2.4.44 (4.4)

Procedures/Plan Knowledge of emergency plan protective action recommendations.

(SRO A4)

JPM 150 Make Protective Action Recommendations 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 ~ 3 for ROs; ~ 4 for SROs & RO retakes)

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

(P)revious 2 exams ~ 1; randomly selected)

NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Control Room/In-Plant S:,.:Jt~:m*~ Outline Form ES-301-2 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 Exam Level: RO IRl SRO(I) 0 SRO(U) 0 Control Room S;,-...... ,.;(!!l (8 for RO); (7 for SR0-1); (2 or 3 for ~~n.

Operating Test No.:

including 1 ESF)

System I JPM Title Type Code* Safety Function S1 Initiate Deboration Using Deborating Demineralizers (JPM New) N,A,S 1 004 A4.07 3.9/3.7 S2 De-energize SFAS CH 4 RCS Pressure Transmitter (JPM New) N,S,EN 2 013 K2.01 3.6/3.8 S3 Perform HPI Flow Balance (JPM New) N,A, S, L, 3 EN 006 A4.02 4.0/3.8 S4 Rapid Cooldown of the RCS (JPM New) N,A,S,L 4S 041 A3.01 3.2/3.2 S5 Shift CTMT Air Cooler From Slow to Fast Speed (JPM 151 D,S,L 5 022 A4.01 3.6/3.8 S6 13.8 KV Bus Transfer to Aux 11 Transformer (JPM New) N,A,S 6 062 A4.01 3.3/3.1 S7 Bypass SFRCS Logic Channel Trips (JPM 108) D,S 7 012 A4.03 3.6/3.6 S8 CCW Essential Header Leak Isolation (JPM 125) D,A,S 8 008 A2.02 3.2/3.5 In-Plant Systems (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P1 Clear the Asymmetry Fault (JPM 60) D,E,R 1 003 AK3.04 3.8/4.1 P2 Emergency Idle Start EDG 1 (JPM 242) D,A,E 6 064 A3.06 3.3/3.4 P3 Service Water Primary Header Pressure Control (JPM New) N 4S 076 K1.01 3.4/3.3 All RO and SRO control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U stems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO I SR0-1 I SRO-U (A)Iternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I - I~ 1 (Control room system)

(L)ow-power I Shutdown ~11~11~1 (N)ew or {M)odified from bank including 1{A) ~21~21~1 (P)revious 2 exams S31S31S2 (randomly selected)

{R)CA ~11~11~1 (S)imulator NUREG-1 021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Control Room/In-PlantS~... ., Outline Form ES-301-2 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 Exam Level: RO D SRO(I) IRl SRO(U) D Operating Test No.:

"'om:ro1 Room Sy.. *c:ml:l (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function S1 Initiate Deboration Using Deborating Demineralizers (JPM New) N,A, S 1 004 A4.07 3.9/3.7 S2 De-energize SFAS CH 4 RCS Pressure Transmitter (JPM New) N,S,EN 2 013 K2.01 3.6/3.8 S3 Perform HPJ Flow Balance (JPM New) N,A, S, L, 3 006 A4.02 4.0/3.8 ENS4 Rapid Cooldown of the RCS (JPM New) N,A,S,L 4S 041 A3.01 3.2/3.2 S6 13.8 KV Bus Transfer to Aux 11 Transformer (JPM New) N,A,S 6 062 A4.01 3.3/3.1 S7 Bypass SFRCS Logic Channel Trips (JPM 108) D,S 7 012 A4.03 3.6/3.6 S8 CCW Essential Header Leak Isolation (JPM 125) D,A,S 8 008 A2.02 3.2/3.5 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P1 Clear the Asymmetry Fault (JPM 60) D,E,R 1 003 AK3.04 3.8/4.1 P2 Emergency Idle Start EDG 1 (JPM 242) D,A,E 6 064 A3.06 3.3/3.4 P3 Service Water Primary Header Pressure Control (JPM New) N 4S 076 K1.01 3.4/3.3

@ All RO and SRO 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 SR0-11 SRO-U (A)Iternate Path 4-6 14-612-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant <=11<=11<:1 (EN)gineered safety feature - I - I~ 1 (Control room system)

(L)ow-power I Shutdown <=11<=11<=1 (N)ew or (M)odified from bank including 1(A) <:2/<:2/<:1 (P)revious 2 exams S31S31S2 (randomly selected)

(R)CA <:1/<:1/<:1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Control Room/In-Plant S~m~ Outline Form ES-301-2 Facility: Davis Besse Date of Examination: 6/3 thru 6/14 2013 Exam Level: RO 0 SRO(I) 0 SRO(U) 00 Operating Test No.:

Control Room s, ....,..... (8 for RO); (7 for SR0-1) (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function 83 Perform HPI Flow Balance (JPM New) N,A, S, L, 3 EN 006 A4.02 4.0/3.8 84 Rapid Cooldown of the RCS (JPM New) N,A,S,L 48 041 A3.01 3.2/3.2 87 Bypass SFRCS Logic Channel Trips (JPM 108) D,S 7 012 A4.03 3.6/3.6 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

P1 Clear the Asymmetry Fault (JPM 60) D,E,R 1 003 AK3.04 3.8/4.1 P2 Emergency Idle Start EDG 1 (JPM 242) D,A,E 6 064 A3.06 3.3/3.4

@ All RO and SRO 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 SR0-1 I SRO-U (A)Iternate Path 4-6 14-6 12-3 (C)ontrol room (D)irect from bank S91S81S4 (E)mergency or abnormal in-plant <:11;::11<:1 (EN)gineered safety feature - I - I .::. 1 (Control room system)

(L)ow-power I Shutdown  ;::11<:11;::1 (N)ew or (M)odified from bank including 1 (A) <:21;::21<:1 (P)revious 2 exams S31S31S2 (randomly selected)

(R)CA  ;::11;::11<:1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Transient and Event Checklist Form ES-301-5 Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

A E Scenarios p v 1 2 3 4 Backup M p E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 N T

I T I c T A M A y s A B s A B s A B s A B L u N p R T 0 R T 0 R T 0 R T 0 M(.)

T E 0 c p 0 c p 0 c p 0 c p R I u RX 1 1 3 3 4 4 1 1 1 1 0 M

NOR 3 3 1 1 1 1 1 A

s 1/C 4,6,7, 4,10 6,7 1,2,4 1,5,7 2,4 2,3,5 2,3 2,5,7 2,4,5 2,4, 5,7,8 4 4 2 T 10 5,7,8 8 7 7,8 E MAJ 8,9 8,9 8,9 6 6 6 6 6 6 6 6 6 2 2 1 R

TS 2,5 1,5 2,4 3,4 0 2 2 RX 1 3 2 1 1 0 SROI-1 NOR 0 1 1 1 IX]

1/C 4,10 1,2,4 8 4 4 2 5,7,8 MAJ 8,9 6 3 2 2 1 TS 1,5 2 0 2 2 RX 1 3 2 1 1 0 SROI-2 NOR 0 1 1 1 IX]

1/C 4,10 1,2,4 8 4 4 2 5,7 ,8 MAJ 8,9 6 3 2 2 1 TS 1,5 2 0 2 2 RX 3 4 2 1 1 0 SROI-3 NOR 0 1 1 1 IX]

1/C 1,2,4 2,3 8 4 4 2 5,7,8 MAJ 6 6 2 2 2 1 TS 1,5 2 0 2 2 Instructions:

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 (1/C) malfunctions and one major transient , in the ATC position . If an Instant SRO additionally serves in the BOP position , one 1/C malfunction can be credited toward the two 1/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 1-for-1 basis .

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.

NUREG-1 021, Revision 9 Supplement 1 Page 1 of 3 FENOC Facsimile Rev. 0

ES-301 Transient and Event Checklist Form ES-301-5 cility Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

A E Scenarios p v 1 2 3 4 Backup M p E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 N T

I T I c T A M A y s A B s A B s A B s A B L u N p R T 0 R T 0 R T 0 R T 0 M(.)

T E 0 c p 0 c p 0 c p 0 c p R I u RX 1 1 1 1 0 SROU -1 NOR 3 1 1 1 1 IRI 1/C 4,6,7, 2,4 6 4 4 2 10 MAJ 8,9 6 3 2 2 1 TS 2,5 2 0 2 2 RX 1 1 1 1 0 SROU -2 NOR 3 1 1 1 1 IRI 1/C 4,6,7, 2,4 6 4 4 2 10 MAJ 8,9 6 3 2 2 1 TS 2,5 2 0 2 2 RX 1 4 2 1 1 0 SROU -3 NOR 3 1 2 1 1 1 IRI 1/C 4,6,7, 2,3,5 8 4 4 2 10 7 MAJ 8,9 6 3 2 2 1 TS 2,5 2,4 4 0 2 2 RX 3 1 1 1 0 RO -1 NOR 3 1 1 1 1 IRI 1/C 6,7 1,5,7 6 4 4 2 8

MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 Instructions:

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 (1/C) malfunctions and one major transient, in the ATC position . If an Instant SRO additionally serves in the BOP position , one 1/C malfunction can be credited toward the two 1/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 1-for-1 basis.

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.

NUREG-1 021 , Revision 9 Supplement 1 Page 2 of 3 FENOC Facsimile Rev. 0

ES-301 Transient and Event Checklist Form ES-301-5 cility Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

A E Scenarios p v 1 2 3 4 Backup M p E T I N

L CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 N T

I T I c T A M A y s A B s A B s A B s A B L u N p R T 0 R T 0 R T 0 R T 0 M(.)

T E 0 c p 0 c p 0 c p 0 c p R I u RX 3 1 1 1 0 RO -2 NOR 3 1 1 1 1

[R1 1/C 6,7 1,5,7 6 4 4 2 8

MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 RX 3 1 1 1 0 R0-3 NOR 3 1 1 1 1

[R1 1/C 6,7 1,5,7 6 4 4 2 8

MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 RX 1 1 1 1 0 RO -4 NOR 1 1 1 1 1

[RI 1/C 4,10 2,4 2,5,7 7 4 4 2 MAJ 8,9 6 6 4 2 2 1 TS 0 0 2 2 RX 1 1 0 NOR 1 1 1 1/C 4 4 2 MAJ 2 2 1 TS 0 2 2 Instructions:

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 (1/C) malfunctions and one major transient, in the ATC position . If an Instant SRO additionally serves in the BOP position , one 1/C malfunction can be credited toward the two 1/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 1-for-1 basis .

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.

NUREG-1021, Revision 9 Supplement 1 Page 3 of 3 FENOC Facsimile Rev. 0

ES-401 PWR Examination Outline Form ES-401-2 rr=======================~~~~~~~~~~========~~~~~~===9 Facility: D Date ofExam 6/3 4 2013 Points SRO ONLY Points Tier Group K K K A A A G TOTAL A2 G* TOTAL 1 2 3 2 3 4

• 1 3 3 2 3 18 6 1.

Emergency 2

& 1 2 1 1 9 4 Abnormal Plant Tier Totals 4 5 3 4 27 10 Evolutions 1

2.

3 2 3 3 3 2 2 3 28 5 Plant Systems 2 1 1 1 1 2 1 1 1 1 10 3 Tier Totals 4 3 4 5 4 3 3 4 38 8

3. Generic Knowledge and Abilities 2 3 4 1 2 3 4 10 7 Category 2 3 t1- c..eYISf>t. re s+. II 141riHt".,.. ,. I!M ~tt"'ll~"rro*...,

Note: , tt[~ t-... ~ I +o ***:G*I\vu&r..4!' EAptc..,t:.1h .... tA~,.. ~jf!'1f"cl ~As.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i .e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two) .

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 +/-1 from that specified in the table based on NRC revisions . The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions 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/evolutions that are not included on the outline should be added . Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible ; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those KIAs 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. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level , and the point totals (#) 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 #1 does not apply) . Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics 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 KIAs that are linked to 10 CFR 55.43.

- ~====================================~

NUREG-1 021, Revision 9 Supplement 1 RO Page 1 of 9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 612013 Emergency and Abnormal Plant Evolutions- Tier 11Group 1(RO)

• EIAPE #I Name I Safety Function K K K A A G KIA Topic(s) IR Points 1 2 3 1 2 000008 Pressurizer (PZR) Vapor Space AK1.01 Knowledge of the operational implications 3.2 1 Accident X of the following concepts as they apply to a Question 1 Pressurizer Vapor Space Accident:

Thermodynamics and flow characteristics of open or leaking valves (CFR 41 .8 141.10 I 45.3) 000009 Small Break LOCA EK2.03 Knowledge of the interrelations between 3.0 1

}(

Question 2 the small break LOCA and the following : S/Gs (CFR 41.7 I 45.7) 000011 Large Break LOCA EA2.10 Ability to determine or interpret the 4.5 1

}(

Question 3 following as they apply to a Large Break LOCA:

Verification of adequate core cooling (CFR 43.5 I 45.13) 000015/000017 Reactor Coolant Pump 2.4.11 Knowledge of abnormal condition 4.0 1 (RCP) Malfunctions X procedures.

Question 4 (CFR: 41 .10 I 43.5 I 45.13) 000022 Loss of Reactor Coolant Makeup AK3 .02 Knowledge of the reasons for the following 3.5 1 X responses as they apply to the Loss of Reactor Question 5 Coolant Makeup: Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging ,

and abnormal charging (CFR 41 .5, 41 .10 I 45.6 I 45.13) 000025 Loss of Residual Heat Removal AA 1.01 Ability to operate and I or monitor the 3.6 1

}(

(RHRS) following as they apply to the Loss of Residual Heat 6 Removal System : RCS/RHRS cooldown rate (CFR 41 .7 I 45.5 I 45.6) 000026 Loss of Component Cooling Water AA 1. 07 Ability to operate and I or monitor the 2.9 1

}(

(CCW) following as they apply to the Loss of Component Question 7 Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components (CFR 41 .7 I 45.5 I 45.6) 000027 Pressurizer Pressure Control AK2 .03 Knowledge of the interrelations between 2.6 1 System (PZR PCS) Malfunction X the Pressurizer Pressure Control Malfunctions and Question 8 the following: Controllers and positioners (CFR 41 .7 I 45.7) 000029 Anticipated Transient Without EK2.06 Knowledge of the interrelations between 2.9* 1 Scram (ATWS) X the and the following an ATWS : Breakers, relays, Question 9 and disconnects (CFR 41 .7 I 45.7) 000038 Steam Generator Tube Rupture EA2 .12 Ability to determine or interpret the 3.9* 1 (SGTR) X following as they apply to a SGTR : Status of MSIV Question 10 activating system (CFR 43.5 I 45.13) 000040 Steam Line Rupture - Excessive

}( 2.1.7 Ability to evaluate plant performance and 4.4 1 Heat Transfer make operational judgments based on operating Question 11 characteristics, reactor behavior, and instrument interpretation .

(CFR: 41.5 I 43.5 I 45.12 I 45.13)

Loss of Main Feedwater (MFW) AA2 .01 Ability to determine and interpret the 4.3 1

}(

1estiot 12 following as they apply to the Loss of Main Feedwater (MFW) : Occurrence of reactor and/or turbine trip (CFR: 43.5 I 45.13)

NUREG-1 021, Revision 9 Supplement 1 RO Page 2 of 9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Emergency and Abnormal Plant Evolutions- Tier 1/Group 1(RO) Continued EIAPE #I Name I Safety Function K K K A A G KIA Topic(s) IR Points

~Loss 1 2 3 1 2 of Offsite and Onsite Power EA 1.06 Ability to operate and monitor the following 4.1 1 (Station Blackout) X as they apply to a Station Blackout: Restoration of Question 13 power with one EDIG (CFR 41 .7 145.5 I 45.6) 000056 Loss of Offsite Power AK1 .01 Knowledge of the operational implications 3.7 1 X of the following concepts as they apply to Loss of Question 14 Offsite Power: Principle of cooling by natural convection (CFR 41 .8 141 .10 I 45.3) 000062 Loss of Nuclear Service Water AK3 .01 Knowledge of the reasons for the following 3.2* 1 X responses as they apply to the Loss of Nuclear Question 15 Service Water: The conditions that will initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers (CFR 41.4, 41 .8 I 45.7~

000077 Generator Voltage and Electric Grid AK1 .03 Knowledge of the operational implications 3.3 1 Disturbances X of the following concepts as they apply to Question 16 Generator Voltage and Electric Grid Disturbances:

Under-excitation (CFR : 41.4 , 41~41 . 7 41 . 10145~

BWIE04 Inadequate Heat Transfer- Loss EA 1.1 Ability to operate and I or monitor the 4.4 1 Of Secondary Heat Sink :X following as they apply to the (Inadequate Heat Question 17 I"' Transfer) Components, and functions of control and safety systems, including instrumentation , signals, interlocks, failure modes , and automatic and manual features .

(CFR* 41 .7145.5145.6)

BW/E10 Post-Trip Stabilization 2.1.19 Ability to use plant computers to evaluate 3.9 1

X system or component status.

Question 18 (CFR: 41 .10 I 45.12)

KIA Category Point Totals : 3 3 2 4 3 3 Group Point Total : 18 NUREG-1021 , Revision 9 Supplement 1 RO Page 3 of9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Emergency and Abnormal Plant Evolutions -Tier 1/Group 2(RO)

EIAPE #I Name I Safety Function Points

~

K K A A G KIA Topic(s) IR 1 3 1 2 000036 Fuel Handling Incidents AK1 .03 Knowledge of the operational implications 4.0 1 X of the following concepts as they apply to Fuel Question 19 Handling Incidents : Indications of approaching Criticality (CFR 41 .8 141 .10 I 45.3) 000051 Loss of Condenser Vacuum 2.2.44 Ability to interpret control room indications to 4.2 1 X verify the status and operation of a system , and Question 20 understand how operator actions and directives affect plant and system conditions.

(CFR: 41 .5 I 43.5 I 45.12) 000059 Accidental Liquid Radwaste AK2.01 Knowledge of the interrelations between 2.7 1 Release X the Accidental Liquid Radwaste Release and the following: Radioactive-liquid monitors Question 21 (CFR 41 .7 145.7) 000060 Accidental Gaseous-Waste AA2 .06 Ability to operate and I or monitor the 3.6* 1 Release X following as they apply to the Accidental Gaseous Radwaste : Valve lineup for release of radioactive Question 22 gases (CFR 41 .7 145.5 I 45.6) 000061 ARM System Alarms AK3 .02 Knowledge of the reasons for the following 3.4 1 X responses as they apply to the Area Radiation Question 23 Monitoring (ARM) System Alarms : Guidance contained in alarm response for ARM system (CFR 41 .5,41 .10 I 45.6 I 45.13)

~~:"'~~r Loss of Containment Integrity X AA 1.03 Ability to operate and I or monitor the following as they apply to the Loss of Containment 2.8 1

.... Jestion 24 Integrity: Fluid systems penetrating containment (CFR 41 .7 145.5 I 45.6)

BWIA01 Plant Runback AA2 .1 Ability to determine and interpret the 3.0 1 X following as they apply to the (Plant Runback)

Question 25 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5145.13)

BWIA02 Loss of NNI-X AK2.2 Knowledge of the interrelations between the 3.8 1 X (Loss of NNI-X) and the following : Facility's heat Question 26 removal systems, including primary coolant, emergency coolant, the decay heat removal systems , and relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7 145.7)

BWIE13 EOP Rules EA 1.3 Ability to operate and I or monitor the 3.4 1 X following as they apply to the (EOP Rules) Desired Question 27 operating results during abnormal and emergency situations.

(CFR: 41 .7 I 45.5 I 45.6)

KIA Category Point Totals : 1 2 1 2 2 1 Group Point Total : 9 NUREG-1021 , Revision 9 Supplement 1 RO Page 4 of9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems -Tier 2/Group 1(RO)

• System #I Name 003 Reactor Coolant Pump System (RCPS)

Question 28 003 Reactor Coolant Pump K

1 ~

K K 3 4

)(

K 5 ~

A 1

A 2

A 3

)(

A 4

G KIA Topic(s)

A3 .02 Ability to monitor automatic operation of the RCPS, including: Motor current (CFR: 41 .7 I 45.5)

K3 .01 Knowledge of the effect that a loss or 2.6 3.7 IR Points 1

1 System (RCPS) malfunction of the RCPS will have on the Question 29 following : RCS (CFR: 41 .7 I 45.6) 004 Chemical and Volume )( K4 .14 Knowledge of CVCS design feature(s) 2.8* 1 Control System and/or interlock(s) which provide for the following : Control interlocks on letdown Question 30 system (letdown tank bypass valve)

(CFR: 41 .7) 005 Residual Heat Removal K6 .03 Knowledge of the effect of a loss or 2.5 1 System (RHRS)

X malfunction on the following will have on the RHRS : RHR heat exchanger Question 31 (CFR: 41 .7 I 45.7) 006 Emergency Core Cooling K6 .02 Knowledge of the effect of a loss or 3.4 1 System (ECCS)

X malfunction on the following will have on the ECCS: Core flood tanks (accumulators)

Question 32 (CFR: 41 .7 /45 .7) 007 Pressurizer Relief )( K3 .01 Knowledge of the effect that a loss or 3.3 1 Tank/Quench Tank System malfunction of the PRTS will have on the (PRTS) following : Containment 33 (CFR: 41 .7 I 45.6) 008 Component Cooling Water A2 .01 Ability to (a) predict the impacts of the 3.3 1 System (CCWS)

X following malfunctions or operations on the CCWS, and (b) based on those predictions, Question 34 use procedures to correct, control , or mitigate the consequences of those malfunctions or operations: Loss of CCW pump (CFR: 41 .5 I 43.5 I 45.3 I 45.13) 010 Pressurizer Pressure 2.2.39 Knowledge of less than or equal to 3.9 1

)(

Control System (PZR PCS) one hour Technical Specification action Question 35 statements for systems.

(CFR: 41 .7 I 41 .10 I 43.2 I 45.13) 01 0 Pressurizer Pressure K4 .02 Knowledge of PZR PCS design 3.0 1

}(

Control System (PZR PCS) feature(s) and/or interlock(s) which provide Question 36 for the following : Prevention of uncovering PZR heaters (CFR: 41 .7) 012 Reactor Protection System A2 .07 Ability to (a) predict the impacts of the 3.2* 1

}(

(RPS) following malfunctions or operations on the Question 37 RPS ; and (b) based on those predictions ,

use procedures to correct, control , or mitigate the consequences of those malfunctions or operations: Loss of de control power (CFR: 41 .5 I 43 .5 I 45.3 I 45.5)

NUREG-1 021 , Revision 9 Supplement 1 RO Page 5 of9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems -Tier 2/Group 1(RO) Continued e System #I Name K 1 ~

K 3 ~

K 5 ~

A 1

A 2

A 3

A 4

G KIA Topic(s) IR Points 013 Engineered Safety Features K1.07 Knowledge of the physical 4.1 1 Actuation System (ESFAS)

X connections and/or cause effect relationships between the ESFAS and the Question 38 following systems: AFW System (CFR: 41 .2 to 41 .9 I 45.7 to 45.8) 022 Containment Cooling A 1.04 Ability to predict and/or monitor 3.2 1 System (CCS)

X changes in parameters (to prevent exceeding design limits) associated with Question 39 operating the CCS controls including:

Cooling water flow (CFR: 41 .5 I 45.5) 004 Chemical and Volume 2.4.4 Ability to recognize abnormal 4.5 1 Control System X indications for system operating parameters that are entry-level conditions for emergency Question 40 and abnormal operating procedures.

(CFR: 41 .10 I 43.2 I 45.6) 062 AC Electrical Distribution K1 .02 Knowledge of the physical 4.1 1 System X connections and/or cause/effect relationships between the ac distribution Question 41 system and the following systems: ED/G (CFR: 41.2 to 41.9) 026 Containment Spray System K2 .02 Knowledge of bus power supplies to 2.7* 1 (CSS)

X the following : MOVs 42 (CFR: 41 .7)

Main and Reheat Steam K5 .08 Knowledge of the operational 3.6 1 System (MRSS) X implications of the following concepts as the apply to the MRSS : Effect of steam removal Question 43 on reactivity (CFR: 441 .5 I 45.7) 059 Main Feedwater (MFW) A 1.07 Ability to predict and/or monitor 2.5* 1 System X changes in parameters (to prevent Question 44 exceeding design limits) associated with operating the MFW controls including: Feed Pump speed, including normal control speed for ICS

.. (Q_FR : 41 .5 I 45.5) 059 Main Feedwater (MFW) A4.01 Ability to manually operate and 3.1* 1 System X monitor in the control room : MFW turbine Question 45 trip indication (CFR: 41 .7 I 45.5 to 45.8) 061 Auxiliary I Emergency X A2 .06 Ability to (a) predict the impacts of the 2.7 1 Feedwater (AFW) System following malfunctions or operations on the AFW; and (b) based on those predictions, Question 46 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Back leakage of MFW (CFR: 41 .5 I 43.5 I 45.3 I 45.13) 062 AC Electrical Distribution X A3.04 Ability to monitor automatic operation 2.7 1 of the ac distribution system , including:

~=~;~n 47 Operation of inverter (e.g., precharging synchronizing light, static transfer)

(CFR: 41 .7 I 45.5)

NUREG-1021 , Revision 9 Supplement 1 RO Page 6 of 9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 1(RO) Continued Points

~ ~

• System #I Name K K K K K A A A G KIA Topic(s) IR 1 2 3 4 6 2 3 4 063 DC Electrical Distribution X A 1.01 Ability to predict and/or monitor 2.5 1 System changes in parameters associated with operating the DC electrical system controls Question 48 including : Battery capacity as it is affected by discharge rate (CFR: 41 .5/ 45.5) 063 DC Electrical Distribution X A4.02 Ability to manually operate and/or 2.8* 1 System monitor in the control room : Battery voltage indicator Question 49 (CFR: 41 .7 I 45.5 to 45.8) 064 Emergency Diesel X K4 .03 Knowledge of ED/G system design 2.5 1 Generator (ED/G) System feature(s) and/or interlock(s) which provide for the following : Governor valve operation Question 50 (CFR: 41 .7) 073 Process Radiation )( K5 .01 Knowledge of the operational 2.5 1 Monitoring (PRM) System implications as they apply to concepts as they apply to the PRM system : Radiation Question 51 theory, including sources , types, units, and effects (CFR: 41 .5 I 45.7) 076 Service Water System X K2 .04 Knowledge of bus power supplies to 2.5* 1 (SWS) the following : Reactor building closed cooling water Question 52 (CFR: 41.7)

Instrument Air System (lAS) )( K1 .05 Knowledge of the physical 3.4* 1 connections and/or cause-effect 53 relationships between the lAS and the following systems: MSIV air (CFR: 41 .2 to 41 .9 I 45.7 to 45.8) 103 Containment System X 2.1.28 Knowledge of the purpose and 4.1 1 function of major system components and Question 54 controls.

(CFR: 41 .7) 103 Containment System X K3.02 Knowledge of the effect that a loss or 3.8 1 malfunction of the containment system will Question 55 have on the following : Loss of containment integrity under normal operations (CFR : 41 .7/45.6)

KIA Category Point Totals : 3 2 3 3 2 2 3 3 2 2 3 Group Point Total : 28 NUREG-1021 , Revision 9 Supplement 1 RO Page 7 of9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 2(RO)

System #I Name K K K K K A A KIA Topic(s)

~

K A G 1 2 3 4 5 6 2 3 4 IR Points 002 Reactor Coolant System }( K1 .03 Knowledge of the physical 3.8 1 (RCS) connections and/or cause-effect relationships between the RCS and the Question 56 following systems: Borated water storage tank (CFR: 41 .2 to 41 .9/45.7 to 45.8) 014 Rod Position Indication }( K4 .03 Knowledge of RPIS design feature(s) 3.2 1 System and/or interlock(s) which provide for the following: Rod bottom lights Question 57 (CFR: 41 .5/45.7) 015 Nuclear Instrumentation }( A4.01 Ability to manually operate and/or 3.6* 1 System monitor in the control room : Selection of Question 58 controlling NIS channel (CFR: 41 .7 I 45.5 to 45.8) 034 Fuel Handling Equipment }( A3 .01 Ability to monitor automatic operation 2.5* 1 System of the Fuel Handling System , including:

Travel limits Question 59 (CFR : 41 .7 I 45.5) 055 Condenser Air Removal }( K3 .01 Knowledge of the effect that a loss or 2.5 1 System malfunction of the CARS will have on the following : Main condenser Question 60 (CFR : 41 .7 /45 .6) 068 Liquid Radwaste System X A2.02 Ability to (a) predict the impacts of the 2.7* 1 following malfunctions or operations on the

,. estion 61 Liquid Radwaste System; and (b) based on those predictions , use procedures to correct, control , or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release (CFR: 41 .5 I 43.5 I 45.3 I 45.13) 072 Area Radiation Monitoring }( A 1.01 Ability to predict and/or monitor 3.4 1 System changes in parameters (to prevent exceeding design limits) associated with Question 62 operating the ARM system controls including: Radiation levels (CFR: 41 .5 I 45.5) 075 Circulating Water System }( K2 .03 Knowledge of bus power supplies to 2.6* 1 the following : Emergency/essential SWS Question 63 pumps (CFR: 41 .7) 079 Station Air System }( 2.4.2 Knowledge of system set points , 4.5 1 interlocks and automatic actions associated Question 64 with EOP entry conditions .

(CFR: 41 .7 I 45.7 I 45.8) 086 Fire Protection System }( K6 .04 Knowledge of the effect of a loss or 2.6 1 (FPS) malfunction on the Fire Protection System following will have on the : Fire , smoke, and Question 65 II heat detectors

l. KIA Category Point Totals : 1 1 1 0 0 2 1 1 1 1 (CFR: 41.7 I 45.7)

Group Point Total : 10 NUREG-1021 , Revision 9 Supplement 1 RO Page 8 of 9 FENOC Facsimile Rev. o

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 l~ty: Davis-Besse R 0 Date of Exam 6/3 thru 6/14 2013 RO SROOnly Category KJA# Topic IR Points IR Points

1. 2.1.40 Knowledge of refueling administrative requirements. (CFR: 41.10 I 43.5 I 2.8 1 Conduct 45.13) of Operations Question 66 2.1.45 Ability to identify and interpret diverse indications to validate the 4.3 1 response of another indication. (CFR: 41 .7 143.5145.4)

Question 67 Subtotal 2

2. 2.2 .36 Ability to analyze the effect of maintenance activities, such as degraded 3.1 1 Equipment power sources, on the status of limiting conditions for operations. (CFR:

Control 41 .10 143.2 145.13)

Question 68 2.2.7 Knowledge of the process for conducting special or infrequent tests . 2.9 1 (CFR: 41.10143.3 I 45.13)

Question 69 2.2.35 Ability to determine Technical Specification Mode of Operation. (CFR: 3.6 1 41 .7 I 41 .10 I 43.2 I 45.13)

Question 70 Subtotal 3

3. 2.3.4 Knowledge of radiation exposure limits under normal or emergency 3.2 1 Radiation conditions . (CFR: 41 .12 I 43.4 I 45.10)

Control Question 71 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation 2.9 1 monitors and alarms , portable survey instruments, personnel monitoring equipment, etc. (CFR: 41 .11 I 41 .12 I 43.4 I 45.9)

Question 72 2.3.13 Knowledge of radiological safety procedures pertaining to licensed 3.4 operator duties, such as response to radiation monitor alarms ,

containment entry requirements , fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 I 43.4 I 45.9 I 45.10)

Question 73 Subtotal 2

4. 2.4.31 Knowledge of annunciator alarms, indications, or response procedures. 4.2 1 Emergency (CFR: 41 .10 I 45.3)

Procedures/

Question 74 Plan 2.4.35 Knowledge of local auxiliary operator tasks during an emergency and the 3.8 1 resultant operational effects. (CFR: 41.10 I 43.5 I 45.13)

Question 75 Subtotal 3 Tier 3 Point Total 10 NUREG-1021 , Revision 9 Supplement 1 RO Page 9 of9 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 rr=======================~~~~~~~~~~==========~~~~~==~

Davis-Besse SRO Date of Exam 6/3 thru 6/14 2013 Points SRO ONLY Points Tier Group K K K A A A G TOTAL A2 G* TOTAL 1 2 3 2 3 4

• 1 18 3 3 6 1.

Emergency 2

& 9 2 2 4 Abnormal Plant Tier Totals 27 5 5 10 Evolutions 1

2.

28 3 2 5 Plant Systems 2 10 0 2 1 3 Tier Totals 38 5 3 8 1 2 3 4 1 2 3 4

3. Generic Knowledge and 10 7 Abilities Category 1 2 2 2 Note:

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i .e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two) .

2. The point total for each group and tier in the proposed outline must match that specified in the table . The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions . The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution .

5. Absent a plant-specific priority, only those KIAs 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. Refer to Section D.1.b of ES-401 for the applicable KIAs .

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) 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 #1 does not apply) . Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics 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 KIAs that are linked to 10 CFR 55.43.

-~====================================~

NUREG-1021 , Revision 9 Supplement 1 SRO Page 1 of 6 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 612013 Emergency and Abnormal Plant Evolutions- Tier 11Group 1(SRO) le EIAPE # 1 Name 1 Safety Function K 1

K 2 ~

A 1

A 2

G KIA Topic(s) IR Points 000056 Loss of Offsite Power .X 2.1.20 Ability to interpret and execute procedure 4.6 1 steps.

Question 76 (CFR: 41.10 I 43.5 I 45.12) 000038 Steam Generator Tube Rupture X EA2.01 Ability to determine and interpret thE? 4.7 1 (SGTR) following as they apply to SGTR: When to isolate one or more S/Gs Question 77 (CFR: 43.5 I 45.13) 000058 Loss of DC Power X AA2 .03 Ability to determine and interpret the 3.9 1 Question 78 following as they apply to the Loss of DC Power:

DC loads lost; impact on ability to operate and monitor plant systems (CFR : 43.5 I 45.13) 000065 Loss of Instrument Air .X 2.4.9 Knowledge of low power/shutdown 4.2 1 implications in accident (e.g., loss of coolant Question 79 accident or loss of residual heat removal) mitigation strategies.

(CFR: 41 .10 I 43.5 I 45.13)

BW/E10 Post-Trip Stabilization X EA2.1 Ability to determine and interpret the 4.0 1 following as they apply to the (Post-Trip Question 80 Stabilization) Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 45.13) r:~::::ansfer Steam Une R"P'"'" - E*cess;ve

.X 2.4.20 Knowledge of the operational implications of 4.3 1 EOP warnings , cautions, and notes .

.,.. ......;tion 81 (CFR: 41 .10 I 43.5 I 45.13)

KIA Category Point Totals : 0 0 0 0 3 3 Group Point Total : 6 NUREG-1 021 , Revision 9 Supplement 1 SRO Page 2 of 6 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 612013 Emergency and Abnormal Plant Evolutions -Tier 11Group 2(SRO)

Points

~

• EIAPE #I Name I Safety Function K K K A G KIA Topic(s) IR 1 2 3 1 000001 Continuous Rod Withdrawal :X AA2 .03 Ability to determine and interpret the 4.8 1 Question 82 following as they apply to the Continuous Rod Withdrawal : Proper actions to be taken if automatic safety functions have not taken place (CFR: 43.5 I 45.13) 000024 Emergency Boration X 2.2.42 Ability to recognize system parameters that 4.6 1 are entry-level conditions for Technical Question 83 Specifications. (CFR: 41 .7 I 41 .10 I 43.2 I 43.3 I 45.3) 000033 Loss of Intermediate Range :X AA2 .03 Ability to determine and interpret the 3.1 1 Nuclear Instrumentation following as they apply to the Loss of Intermediate Range Nuclear Instrumentation : Indication of blown Question 84 fuse (CFR: 43.5 I 45.13)

BWIA06 Shutdown Outside Control Room X 2.1.32 Ability to explain and apply system limits and 4.0 1 precautions.

Question 85 (CFR: 41.1 0 I 43.2 I 45.12)

KIA Category Point Totals : 0 0 0 0 2 2 Group Point Total: 4 NUREG-1 021 , Revision 9 Supplement 1 SRO Page 3 of 6 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 1(SRO)

• System #I Name 006 Emergency Core Cooling System (ECCS)

Question 86 K

1 ~

K 3 ~

K 5 ~

A 1

A 2

X A

3 A

4 G KIA Topic(s)

A2 .03 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control , or mitigate the consequences of those IR 3.7 Points 1

malfunctions or operations: System leakage (CFR: 41 .5 I 45.5) 013 Engineered Safety Features .X 2.4.21 Knowledge of the parameters and 4.6 1 Actuation System (ESFAS) logic used to assess the status of safety Question 87 functions, such as reactivity control , core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control , etc.

(CFR: 41 .7 I 43.5 I 45.12) 026 Containment Spray System X A2 .07 Ability to (a) predict the impacts of the 3.9 1 (CSS) following malfunctions or operations on the CSS ; and (b) based on those predictions, Question 88 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding),

or sump level below cutoff (interlock) limit (CFR: 41 .5 I 43.5 I 45.3 I 45.13)

Main and Reheat Steam X A2 .05 Ability to (a) predict the impacts of the 3.6 1 m (MRSS) following malfunctions or operations on the Question 89 MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Increasing steam demand, its relationship to increases in reactor power (CFR: 41 .5 I 43.5 I 45.3 I 45.13) 061 Auxiliary/Emergency .X 2.4.6 Knowledge of EOP mitigation 4.7 1 Feedwater (AFW) System strategies.

Question 90 (CFR: 41 .10 I 43.5 I 45.13)

KIA Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total : 5 NUREG-1 021 , Revision 9 Supplement 1 SRO Page 4 of 6 FENOC Facsimile Rev. o

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 2(SRO)

System # I Name KIA Topic(s)

~

K K K K K A A A A G 1 2 3 4 6 1 2 3 4 IR Points

" Pressurizer Level Control X A2 .07 Ability to (a) predict the impacts of the 3.3 System (PZR LCS) 1 following malfunctions or operations on the Question 91 PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of letdown (CFR : 41 .5 I 43.5 I 45.3 I 45.13) 015 Nuclear Instrumentation X A2 .01 Ability to (a) predict the impacts of the 3.9 1 System following malfunctions or operations on the NIS; and (b based on those predictions, use Question 92 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Power supply loss or erratic operation (CFR: 41 .5 I 43.5 I 45.3 I 45.5) 033 Spent Fuel Pool Cooling )( 2.1.20 Ability to interpret and execute 4.6 1 System (SFPCS) procedure steps.

Question 93 (CFR: 41 .10 I 43.5 I 45.12)

KIA Category Point Totals : 0 0 0 0 0 0 0 2 0 0 1 Group Point Total : 3 NUREG-1 021 , Revision 9 Supplement 1 SRO Page 5 of 6 FENOC Facsimile Rev. o

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 l*ty:

Category Davis-Besse KJA#

SRO Topic Date of Exam 6/3 thru 6/14 2013 RO SRO Only IR # IR #

1. 2.1.42 Knowledge of new and spent fuel movement procedures. (CFR: 41 .10 I Conduct 43.7 I 45.13) 3.4 1 of Operations Question 94 Subtotal 1

2. 2.2.1 Ability to perform pre-startup procedures for the facility, including Equipment operating those controls associated with plant equipment that could 4.4 1 Control affect reactivity. (CFR: 41 .5 I 41 .10 I 43.5 I 43.6 I 45.1)

Question 95 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization , 3.9 1 etc.(CFR: 41.10 I 43.5 I 45.13)

Question 96 Subtotal 2

3. 2.3.6 Ability to approve release permits. (CFR: 41.13 I 43.4 I 45.10)

Radiation Question 97 3.8 1 Control 2.3.15 Knowledge of radiation monitoring systems , such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring 3.1 1 equipment, etc. (CFR: 41 .12 I 43.4 I 45.9)

Question 98 Subtotal 2

4. 2.4.27 Knowledge of "fire in the plant" procedures. (CFR: 41 .10 I 43.5 I 45.13)

Emergency Question 99 3.9 1 Procedures/

Plan 2.4.44 Knowledge of emergency plan protective action recommendations.

(CFR: 41 .10 I 41.12 I 43.5 I 45.11) 4.4 1 Question 100 Subtotal 2 Tier 3 Point T a tal 7 NUREG-1 021 , Revision 9 Supplement 1 SRO Page 6 of 6 FENOC Facsimile Rev. o

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse Scenario No.: 1 Op Test No.: NRC 2013 Examiners: Operators: SRO ATC BOP Initial Conditions:

• 5% power

• Rod Control Panel in Auto

• MFPT 2 in service Turnover: Plant was shutdown for bushing replacement on the Main Transformer. Reactor startup is in progress and currently at 5%. Continue a plant startup per DB-OP-06901, starting at Step 3.42. Completed testing of both AFPTs for operability. Planned: Continue Reactor startup. In Progress: Line-ups for placing MDFP in AFW mode, complete venting of FW779 and FW780 Critical tasks: 1. Isolate SG 1 (CT17)

2. Initiate HPI Cooling (CT14)

3. Trip All Reactor Coolant Pumps (CT1)

Event Malf. Event Type* Event No. No. Description 1 R-ATC/SRO Continue Reactor startup from 5% to 10%. Stabilize at 10%

to perform NIP to HBP comparison 2 SRO (TS) MDFP Inoperable due to oil leak, Enter TS 3.7.5 Condition B 3 N-BOP/SRO Place Main Feed Reg Valves in service 4 C-ATC/SRO Pressurizer Spray Valve Fails Open 5 SRO (TS) RC TE3A6, RCS Hot Leg Temp to PAM fails high. Enter TS 3.3.17 Condition A 6 1-BOP/SRO Slow failure of Steam Generator 1 Startup Level Transmitter, LT SP984, to zero.

7 C- BOP/SRO Sheared shaft on Condensate Pump 1.

8 M-All Steam leak on AFPT 2 develops with MS 107A failed in the open position. Manual reactor trip required.

9 M-All Loss of all Feedwater due to a steam leak on AFPT 2 and AFPT 1 Governor overspeed trip. Motor driven feed pump breaker will not close. (oil leak on pump- event 2) 10 C-ATC/SRO Makeup Pump 1 does not start. Establish MU/HPI/PORV Cooling

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of2 FENOC Facsimile Rev. 0

DAVIS-BESSE 2013 NRC SCENARIO 1 The Crew will take the watch with power stabilized at approximately 5%. A Reactor startup is in progress following a shutdown for bushing replacement on the Main Transformer. Direction will be to increase power to 10%, stabilize for NIP to Heat Balance comparison and continue to 14% power During the power increase an Equipment Operator (EO) will be placing the Motor Driven Feed Pump (MDFP) in the Auxiliary Feedwater mode. The EO will call the Control Room and report the oil has leaked out of the MDFP. The SRO will declare the MDF Pump Inoperable and enter TS 3.7.5 Condition B.

An Equipment Operator will report the steps complete for venting the bonnets for the MFW Block Valves. The BOP RO will open the MFW Block Valves placing the Main Feedwater Control Valves in service. When the Main Feedwater Control Valves are in service the Pressurizer Spray Valve will slowly fail open. The ATC will close the Pressurizer Spray Block Valve. The SRO will enter DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATION, and verify the immediate actions complete and give direction for maintaining pressure manually.

Following the actions required in the Pressurizer System Abnormal Procedure the T Hot instrument input to the Subcooling margin meter will fail high which will bring in the loss of subcooling margin annunciator. The SRO will identify this as a Tech Spec required Post Accident Monitoring instrument and enter TS 3.3.17 Condition A.

LT SP984 will then slowly fail to zero which will cause Steam Generator 1 to overfeed.

The Crew will take the Steam Generator 1 startup and main Feedwater control valves to hand and restore level to 40 inches.

When Steam Generator level control is regained, Condensate Pump 1 will shear its shaft which will be recognized by low amps and a condensate header pressure annunciator.

The Crew will shutdown Condensate Pump 1 and start the standby Condensate Pump.

Following Condensate flow restoration a steam leak will develop at AFPT 2. DB-OP-02525, STEAM LEAKS, will be entered. The EO will report no personnel hazard. When isolation is attempted it will be discovered MS107A cannot be closed thus rendering the leak Unisolable.. The ATC will be directed to trip the reactor and initiate and isolate SFRCS.

A loss of all Feedwater will occur due to AFPT 1 overs peed trip since AFPT is isolated due to the steam leak and the MDFP is in the process of being shifted to the Auxiliary Feedwater mode. Specific Rule 4 will require the start of the standby makeup pump 1.

Makeup pump 1 will not start which will require the crew to immediately establish MU/HPI/PORV cooling.

Upon loss of subcooling, the crew will secure all RCPs. After all RCPs have been secured, the scenario will be terminated, at the Lead Evaluators discretion.

NUREG-1 021, Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 0

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse Scenario No.: 2 Op Test No.: NRC 2013 Examiners: Operators: SRO ATC BOP Initial Conditions:

• 100% power Turnover: Maintain 100% Power Critical Tasks: 1. Trip All Reactor Coolant Pumps (CT1)

2. Initiate LPI Event Malf. Event Type* Event No. No. Description 1 1-ATC/SRO SFAS Containment Pressure transmitter fails low (TS) 2 C-BOP/SRO High Pressure Feedwater Heater Tube Leak 3 R-ATC/SRO Controlled power reduction 4 1-BOP/SRO SAC 2 trips and SAC 1 fails to load, Emergency Instrument Air Compressor fails to AUTO start (Manual start available).

5 C-ATC/SRO Operating Makeup Pump 2 trips, Loss of Makeup capability (TS) 6 M-All Rapidly progressing RCS leak, Manual Reactor Trip required 7 C-ATC/SRO SFAS L3 Output Module Failure (CC1467 fails to re-position) 8 C ATC/SRO LPI Pump 1 trips requiring discharge cross connect

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of2 FENOC Facsimile Rev. 0

DAVIS-BESSE 2013 NRC SCENARIO 2 The crew will assume control with directions to maintain 100% power.

On cue from the Lead Evaluator, PT2003, Containment Pressure transmitter will fail low.

The crew should respond to alarm 5-4-8, SFAS CTMT PRESS LO FAIL, in accordance with DB-OP-02005, PRIMARY INSTRUMENTATION ALARM PANEL 5 ANNUNCIATORS. The SRO will enter the TS action and direct the RO to trip the channel by tripping the SFAS Channel4 Containment Pressure HI and SFAS Channel4 Containment Pressure HI-HI bistables.

After the containment pressure channel actions are complete, the Lead Evaluator can cue initiation of the HP FW Tube leak. The crew should respond in accordance with DB-OP-02013, CONDENSATE FEEDWATER ALARM PANEL 13 ANNUNCIATORS. DB-OP-02013 will direct them to DB-OP-06229, HIGH PRESSURE FEEDWATER HEATER SYSTEM OPERATION. DB-OP-06229 requires a power reduction to S95% prior to removing the heater from service. The Crew will reduce Rx power then remove High Pressure Feedwater Train 1 from service.

After High Pressure Feedwater Train 1 is removed from service, the Lead Evaluator can cue the trip of the running Station Air Compressor (SAC) 2. The standby SAC 1 will fail to load and the Emergency Instrument Air Compressor (EIAC) fails to automatically start.

The BOP Operator will manually start the EIAC. The SRO will implement DB-OP-02528, LOSS OF INSTRUMENT AIR, Section 4.3 for Air Compressor trip.

When the EIAC has been started and the plant is stabilized, the Lead Evaluator can cue loss of operating Makeup pump 2. The Crew will implement DB-OP-02512, MAKEUP AND PURIFICATION SYSTEM MALFUNCTIONS, due to the running makeup pump off.

Letdown and seal injection will be isolated by taking MU32 and MU19 to hand and closing. The standby Makeup pump will be started and letdown and seal injection will be restored. The SRO will declare makeup pump 2 non functional and enter TRM 8.1.1.

Condition A.

While the crew is performing DB-OP-02512 to restore seal injection, the Lead Evaluator can cue initiation of a progressive RCS leak. The crew should respond to indications/alarms and enter DB-OP-2522, SMALL RCS LEAKS. The SRO should direct a MANUAL reactor trip no later than PZR Level s1 00 inches. The leak will become a design basis LOCA when the reactor trip occurs.

The crew should enter DB-OP-02000. Coincident with the SFAS actuation, SFAS L3 Output Module will fail requiring the crew to manually open CC1467, CCW FROM DH CLR 1 VLV. Section 5,Loss of Subcooling Margin will be entered which will route to Section 10, LARGE LOCA. LPI Pump 1 will have tripped off and be unable to be started. 2 of DB-OP-02000 for cross connecting LPI discharge will be performed.

When Attachment 22 is complete the scenario can be terminated at the Lead Evaluators discretion.

NUREG-1021, Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 0

Appendix D Scenario Outline Form ES-D-1

• Facility:

Examiners:

Davis-Besse Scenario No.:

Operators:

3 Op Test No.: NRC 2013 SRO ATC BOP Initial Conditions:

• 50% Power Turnover: Planned to perform the Backup Overspeed trip test for the Main Turbine in accordance with DB-SS-04154, Turbine-Generator Backup Overspeed Trip Circuit Test Critical Tasks: 1. Establish AFW to SG (CT1 0)

2. Control HPI (CTS)

3. Isolate affected SG (CT22)

Event Malf. Event Type* Event No. No. Description 1 N-BOP/SRO Perform TG Overs peed Test, DB-SS-04154

• 2 3

4 C-All (TS) 1-ATC/SRO R-ATC/SRO RCS Pressure Instrument Selected for NNIInput Fails Low Seal injection flow instrument fails low SG 2 tube leak and plant shutdown (TS) 5 C-BOP/SRO Turbine High Vibrations - Manual Turbine trip required 6 M-All SG Tube Rupture - Manual Reactor trip required 7 C-BOP/SRO MFPT 2 speed lowers resulting in Loss of Main Feedwater, SFRCS Ch 1 fails to actuate (auto and manual)

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

• NUREG-1021, Revision 9 Supplement 1 Page 1 of 2 FENOC Facsimile Rev.O

• DAVIS-BESSE 2013 NRC SCENARIO 3 The crew will assume control with power at 50% power. Following turnover the crew will perform DB-SS-04154, Turbine-Generator Backup Overspeed Trip Circuit Test Following the completion of DB-SS-04154 the Lead Evaluator will cue the RCS Pressure Instrument Selected for NNI Input Fails Low. The Crew will recognize the failure by the RCS Low Pressure annunciator alarms, the RPS Channel 1 low pressure trip alarms along with all Pressurizer heaters energized and the narrow range pressure recorder failed to 1700 psig. The SRO will implement DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATl ON which will direct manual control of the Pressurizer heaters.

The crew will swap the NNI inputs selected in RPS Channel 2 to Channel1 and return heater control to auto. The SRO will declare RPS Channel 1 Inoperable and enter TS 3.3.1 Condition A.

Following TS declaration the Lead Evaluator will cue the FT MU 19, RCP Seal Injection Flow Transmitter low failure causing MU 19, RCP SEAL INJ FLOW CONTROLLER to open. MU 19 will have to be controlled manually.

When Seal Injection Flow is returned to normal the Lead Evaluator will cue the Steam Generator 1 Tube Leak (approximately 75 gpm). The crew should respond to annunciator 12-1-B, MN STM LINE 2 RAD HI, in accordance with DB-OP-06012, STM

• GEN/SFRCS Alarm Panel12 Annunciator and then enter DB-OP-02531, STEAM GENERATOR TUBE LEAK. The crew will evaluate the SG leakage and determine the leak rate is in excess of T.S. 3.4.13 and start a rapid shutdown.

During the power reduction Main Turbine bearing vibration levels will increase to the point annunciator 15-2-E T-G BEARING VIB HI will alarm. The crew will respond in accordance with DB-OP-02015, Turbine Alarm Panel Annunciators and manually trip the Main Turbine.

After the Main Turbine is tripped the Lead Evaluator will cue the increase in SG tube leakage. This leak size will be larger than Makeup capacity. Since the plant is on Low Level Limits, the Crew will manually trip the Reactor and enter DB-OP-02000, RPS SFAS, SFRCS Trip, or SG Tube Rupture After the reactor trip, the Main Feedwater Pump 2 speed will coast down leading to a loss of all Main Feedwater. SFRCS Channel 1 will not actuate either automatically or manually requiring the crew to reposition the SFRCS actuated valves.

The Crew will route to Section 8, SG Tube Rupture. The RCS will be cooled down and depressurized using the atmospheric vent valves. SG 2 will be isolated at 500 oF Thot and 1000 psig RCS pressure.

When SG isolation is complete the scenario can be terminated at the Lead Evaluators discretion .

• NUREG-1021, Revision 9 Supplement 1 Page 2 of 2 FENOC Facsimile Rev.O

Appendix D Scenario Outline Form ES-D-1 Facility: Davis-Besse Scenario No.: 4 Op Test No.: NRC 2013 Examiners: Operators: SRO ATC BOP Initial Conditions:

• 50% Power Turnover: Increase power to 100%, Add 200 gallons of water to the Makeup Tank Critical Tasks: 1. Shutdown Reactor- ATWS (CT24)

2. Establish AFW Flow (CT10)

3. Isolate Overcooling (CT17)

Event Malf. Event Type* Event No. No. Description 1 R-ATC/SRO Add 200 gal of water to the RCS Makeup tank 2 1-ATC/SRO Selected Pressurizer temperature instrument fails low 3 SRO (TS) EDG 2 low air start pressure 4 1-ATC/SRO Power range Nl5 fails high (TS) 5 1-BOP/SRO MFW control valve delta pressure instrument fails low 6 M-All Loss of Condenser Vacuum leads to turbine trip w/o Rx trip -

ATWS 7 C-BOP/SRO AFPT 1 Overspeed trip, MDFP manual start required 8 C-BOP/SRO MDFP target rock valve fails open

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 Supplement 1 Page 1 of 2 FENOC Facsimile Rev. 0

DAVIS-BESSE 2013 NRC SCENARIO 4 Add water to the Makeup Tank (MUT) in preparation for increasing power from 50% to 100%.

Following the water add the Lead Evaluator will cue the low failure of the PZR temperature input to the channel selected for level control. The crew will respond to level alarm(s) lAW DB-OP-2004, REACTOR COOLANT ALARM PANEL ANNUNCIATORS, and then enter DB-OP-02513, PRESSURIZER SYSTEM ABNORMAL OPERATION.

The ATC will place MU32 in hand, select the good temperature instrument and return MU32 to auto.

When MU32 is back in AUTO, the Lead Evaluator will cue Annunciator 1-2-K, EDG 2 Air Receiver Pressure Low alarm. The SRO will dispatch an operator locally. The EO will report both EDG 2 Air Receivers indicating 150 psig with compressors running. The SRO will refer to DB-OP-06316 for EDG 2 Operability. EDG 2 will be declared Inoperable and Tech Spec 3.8.1 Condition B will be entered.

When EDG 2 is declared Inoperable the Power range Nl 5 high failure can be cued. Rod control will be transferred to manual. The Reactor Demand station will be transferred to Hand. If Tave is greater than 2 degrees below setpoint, Feedwater Loop Demands will be taken to Hand. Tech Spec 3.3.1 will be entered. The SRO will direct placing RPS Channel 2 in Bypass and restoring ICS controls to Automatic.

The MFW control valve delta pressure transmitter PDT SP5B1 fails low can be initiated with controls still in manual from the Nl5 failure. The Main feed pump speeds up causing a SG overfill. MFP speed control is taken to HAND and a different instrument is selected for control. The MFP controls are returned to AUTO.

When the cue is given the condenser will rapidly lose vacuum and the main turbine will trip. The reactor will not trip from the manual pushbuttons requiring 480 VAC Buses E2 and F2 to be de-energized which will trip the reactor.

SFRCS will actuate on reverse valve delta pressure due to the loss of main feed pump due to loss of vacuum. AFPT 1 will overspeed trip. The MDFP will be placed in service to feed SG 1. AF6459, MDFP TO AUX FEED LINE 1 FLOW CONTROL will fail open and SG 1 will overfeed. The crew will route to the Overcooling Section and will close AF608.

When the overfeed of SG 1 is isolated the Crew should route to the supplemental section. The scenario can then be terminated at the Lead Evaluators discretion.

NUREG-1021, Revision 9 Supplement 1 Page 2 of2 FENOC Facsimile Rev. 0