ML13263A079

2013 Davis-Besse Initial License Examination Proposed Es 301-6 and Revised Outline Documents

ML13263A079
Person / Time
Site:	Davis Besse
Issue date:	04/12/2013
From:	NRC/RGN-III
To:
Michael Bielby
Shared Package
ML11354A431	List: ML13259A199 ML13263A077 ML13263A079 ML13263A102 ML13269A209
References
Download: ML13263A079 (28)

Text

ES-301 Competencies Checklist Form ES-301-6 Facility Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.: ___________

APPLICANTS RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 1,3,4 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 Interpret/Diagnosis 5,6,7 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 8,9 8 8 7,8,9 8 8 7,8,9 8 8 Events and Conditions 10 10 10 1,3,4 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 Comply With and 5,6,7 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 8,9 8 8 7,8,9 8 8 7,8,9 8 8 Use Procedures (1) 10 10 10 1,3,4 1,3,4 1,3,4 1,4,5 3,6,7 2,4,6 1,2,5 5,6,7 Operate Control 6,7,8 5,6,7 5,6,7 6,7,8 8,9 6,7 8 9,10 8 Boards (2) 1,3,4 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 Communicate and 5,6,7 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 8,9 8 8 7,8,9 8 8 7,8,9 8 8 Interact 10 10 10 1,2,3 1,3,4 1,3,4 1,3,4 1,2,3 1,3,4 1,3,4 1,3,4 Demonstrate 4,5,6 5,6,7 5,6,7 5,6,7 4,5,6 5,6,7 5,6,7 5,6,7 7,8,9 8 8 7,8,9 8 8 Supervisory Ability (3) 10 10 2,5 1,5 2,4 3,4 2,5 1,5 2,4 3,4 Comply With and Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

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

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

Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of D, R 2.1.43 (4.1)

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

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

Operations Ability to evaluate plant performance and make operational (RO A1.2) 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)

(RO 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 Perform radiation element administrative checks for a radioactive liquid release 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. 1

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

Administrative Type Describe activity to be performed Topic Code*

(See Note)

Conduct of N, R 2.1.43 (4.3)

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

JPM New Shift Manager Review of SDM calculation with Tave > 500 °F 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-In.

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 (> 1)

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

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

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

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / 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 SRO-I); (3 or 2 for SRO-U)

P1 Actions outside the control room of the primary side reactor D, E, R 8 operator for a serious control room fire (JPM 003) 068 AA1.21 3.9/4.1 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 / SRO-I / SRO-U (A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / > 1 (Control room system)

(L)ow-power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)

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

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

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / 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 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 SRO-I); (3 or 2 for SRO-U)

P1 Actions outside the control room of the primary side reactor D, E, R 8 operator for a serious control room fire (JPM 003) 068 AA1.21 3.9/4.1 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 / SRO-I / SRO-U (A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / > 1 (Control room system)

(L)ow-power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)

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

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

Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function 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 S7 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 SRO-I); (3 or 2 for SRO-U)

P1 Actions outside the control room of the primary side reactor D, E, R 8 operator for a serious control room fire (JPM 003) 068 AA1.21 3.9/4.1 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 / SRO-I / SRO-U (A)lternate Path 4-6 /4-6 /2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / > 1 (Control room system)

(L)ow-power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3/ 3 / 2 (randomly selected)

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

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.: _________

Initials

1. GENERAL CRITERIA a b* c#

a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.

c. The operating test shall not duplicate items from the applicants audit test(s) (see Section D.1.a).

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits.

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

2. WALK-THROUGH CRITERIA

a. Each JPM includes the following, as applicable:

• initial conditions

• initiating cues

• references and tools, including associated procedures

• reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time critical by the facility licensee

• specific performance criteria that include:

- detailed expected actions with exact criteria and nomenclature

- system response and other examiner cues

- statements describing important observations to be made by the applicant

- criteria for successful completion of the task

- identification of critical steps and their associated performance standards

- restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

3. SIMULATOR CRITERIA

a. The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.

Printed Name / Signature Date

a. Author ________________________________________________________ _________

b. Facility Reviewer (*) ________________________________________________________ _________

c. NRC Chief Examiner (#) ________________________________________________________ _________

d. NRC Supervisor ________________________________________________________ _________

NOTE:

• The facility signature is not applicable for NRC-developed tests.

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

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

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.: _____

QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.

2. The scenarios consist mostly of related events.

3. Each event description consists of

• the point in the scenario when it is to be initiated

• the malfunction(s) that are entered to initiate the event

• the symptoms/cues that will be visible to the crew

• the expected operator actions (by shift position)

• the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

7. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

8. The simulator modeling is not altered.

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.

10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position.

TARGET QUANTITATIVE ATTRIBUTES (PER SCENARIO; SEE SECTION Actual Attributes D.5.d)

1. Total malfunctions (5-8) 6 6 6 5

2. Malfunctions after EOP entry (1-2) 2 2 1 2

3. Abnormal events (2-4) 3 3 3 3

4. Major transients (1-2) 2 1 1 1

5. EOPs entered/requiring substantive actions (1-2) 1 1 1 1

6. EOP contingencies requiring substantive actions (0-2) 1 1 0 1

7. Critical tasks (2-3) 3 2 3 3 NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev.1

ES-301 Transient and Event Checklist Form ES-301-5 Facility 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 L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION O 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 O R T O R T O R T O M(*)

T E O C P O C P O C P O 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 I/C 4,6,7, 4,10 6,7 1,2,4 5,7 8 1,2,4 2,3,5 2,3 2,5,7 2,4,5 2,4, 5,7,8 4 4 2 T 10 5,7,8 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 1 1 1 1 1

I/C 4,10 1,2,4 2,5,7 11 4 4 2 5,7,8 MAJ 8,9 6 6 4 2 2 1 TS 1,5 2 0 2 2 RX 3 4 2 1 1 0 SROI-2 NOR 3 1 2 1 1 1

I/C 6,7 5,7 8 2,3,5 9 4 4 2 7

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

I/C 4,6,7, 1,2,4 2,3 9 4 4 2 10 MAJ 8,9 6 6 4 2 2 1 TS 2,5 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 (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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 applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility 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 L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION O 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 O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RX 1 4 2 1 1 0 SROU -1 NOR 3 1 2 1 1 1

I/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 1 1 1 1 0 RO -1 NOR 1 1 1 1 1

I/C 4,10 2,5,7 5 4 4 2 MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 RX 4 1 1 1 0 RO -2 NOR 3 1 1 1 1

I/C 6,7 2,3 4 4 4 2 MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 RX 1 1 0 NOR 1 1 1 I/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 (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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 applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

NUREG-1021, Revision 9 Supplement 1 Page 2 of 3 FENOC Facsimile Rev. 1

ES-301 Transient and Event Checklist Form ES-301-5 Facility 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 L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION O 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 O R T O R T O R T O M(*)

T E O C P O C P O C P O C P R I U RX 1 1 1 1 0 SROU -2 NOR 3 1 1 1 1

I/C 4,6,7, 4 4 4 2 10 MAJ 8,9 2 2 2 1 TS 2,5 2 0 2 2 RX 4 1 1 1 0 SROU -3 NOR 1 1 1 1 1

I/C 2,3,5 4 4 4 2 7

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

I/C 4,10 2,5,7 5 4 4 2 MAJ 8,9 6 3 2 2 1 TS 0 0 2 2 RX 4 1 1 1 0 RO -4 NOR 3 1 1 1 1

I/C 6,7 2,3 4 4 4 2 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 (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 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 applicants competence count toward the minimum requirements specified for the applicants license level in the right hand columns.

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

ES-401 Record of Rejected K/As Form ES-401-4 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

Tier / Randomly Reason for Rejection Group Selected K/A RO OUTLINE 1/1 000011 EA2.12 Question # 3 Davis Besse does not have a system for throttling or stopping reflux boiling spray. Randomly selected 000011 EA2.10 as a replacement.

1/1 000025 AK3.01 Question # 6 Davis Besse does not have an alternate RHR flowpath. Randomly selected 000025 AA1.01 as a replacement.

1/2 000059 AK2.01 Question # 21 Davis Besse does not have any gas monitors on the liquid waste discharge system. Randomly selected 000059 AK2.01 as a replacement.

2/1 025 2.4.4 Question # 40 Davis Besse does not have Ice Condensers. Randomly selected 004 2.4.4 as a replacement.

2/1 025 K1.02 Question # 41 Davis Besse does not have Ice Condensers. Randomly selected 062 K1.02 as a replacement.

2/1 064 K4.08 Question # 50 Davis Besse does not have any design features or interlocks for EDG fuel isolation valves. Randomly selected 064 K4.03 as a replacement.

2/1 073 K5.03 Question # 51 Unable to write a discriminatory question for the process radiation monitoring system that depicts the relationship between radiation intensity and exposure limits. Randomly selected 073 K5.01 as a replacement.

3 2.4.40 Question # 75 Unable to write an RO discriminatory question regarding SRO responsibilities during E-Plan implementation. Randomly selected 2.4.35 as a replacement.

2/2 034 A3.01 Question # 59. Deleted from the exam to achieve balance. There are too many fuel handling questions (5) already being addressed on this exam.

Discussed with chief examiner and determined that this K/A should be deleted to obtain a better balance. Randomly selected 041 A2.02 as a replacement.

SRO OUTLINE 2/2 027 A2.01 Question # 92 Davis Besse does not have an iodine removal system. Iodine is removed with the passive sodium triphosphate baskets. Randomly selected 015 A2.01 as a replacement.

1/1 057 AA2.16 Question # 77 Unable to write a discriminatory SRO level question for loss of vital AC impact on PZR level. Randomly selected 038 EA2.01 as a replacement.

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

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Exam Level: RO SRO Item Description Initial a b* c

1. Questions and answers technically accurate and applicable to facility

2. a. NRC K/As referenced for all questions

b. Facility learning objectives referenced as available

3. SRO questions are appropriate per Section D.2.d of ES-401

4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions are repeated from the last two NRC licensing exams, consult the NRR OL program office.)

5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

__ the audit exam was systematically and randomly developed; or

__ the audit exam was completed before the license exam was started; or

__ the examinations were developed independently; or

__ the licensee certifies that there is no duplication; or

__ other (explain)

6. Bank use meets limits (no more than 75 Bank Modified New percent from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) 16/0 0/0 59/25 at right.

(21.3%/0%) (0%/0%) (78.7%/100%)

7. Between 50 and 60 percent of the questions Memory C/A on the RO exam are written at the comprehension/analysis level; the SRO exam may exceed 60 percent If the randomly selected K/As support the higher 32/1 43/24 cognitive levels; enter the actual RO / SRO (42.7% / 4%) (57.3% / 96%)

question distribution(s) at right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors.

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the Tier to which they are assigned; deviations are justified

10. Question psychometric quality and format meet the guidelines in ES Appendix B.

11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with value on cover sheet Printed Name / Signature Date

a. Author ________________________________________________________ _________

b. Facility Reviewer (*) ________________________________________________________ _________

c. NRC Chief Examiner (#)________________________________________________________ _________

d. NRC Supervisor ________________________________________________________ _________

Note:

• The facility reviewer's initials/signature are not applicable for NRC-developed examinations.

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

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

ES-401 PWR Examination Outline Form ES-401-2 Facility: Davis-Besse RO Date of Exam 6/3 thru 6/14 2013 RO K/A Category Points SRO ONLY Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 6 1 2 3 4

• 1 3 3 2 4 3 3 18 6 1.

Emergency 2

& 1 2 1 2 2 1 9 4 Abnormal Plant Tier Totals 4 5 3 6 5 4 27 10 Evolutions 1

2.

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

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

1. Ensure that at least two topics from every applicable K/A 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 K/A 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 K/A 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 K/As 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 K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.

8. On the following pages, enter the K/A 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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

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

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

Question 1 Pressurizer Vapor Space Accident:

Thermodynamics and flow characteristics of open or leaking valves (CFR 41.8 / 41.10 / 45.3) 000009 Small Break LOCA EK2.03 Knowledge of the interrelations between 3.0 Question 2 X the small break LOCA and the following: S/Gs 1

(CFR 41.7 / 45.7) 000011 Large Break LOCA EA2.10 Ability to determine or interpret the 4.5 Question 3 X following as they apply to a Large Break LOCA:

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

1 Question 4 (CFR: 41.10 / 43.5 / 45.13) 000022 Loss of Reactor Coolant Makeup AK3.02 Knowledge of the reasons for the following 3.5 X responses as they apply to the Loss of Reactor 1

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 / 45.6 / 45.13) 000025 Loss of Residual Heat Removal AA1.01 Ability to operate and / or monitor the 3.6 System (RHRS) X following as they apply to the Loss of Residual Heat 1

Question 6 Removal System: RCS/RHRS cooldown rate (CFR 41.7 / 45.5 / 45.6) 000026 Loss of Component Cooling Water AA1. 07 Ability to operate and / or monitor the 2.9 (CCW) X following as they apply to the Loss of Component 1

Question 7 Cooling Water: Flow rates to the components and systems that are serviced by the CCWS; interactions among the components (CFR 41.7 / 45.5 / 45.6) 000027 Pressurizer Pressure Control AK2.03 Knowledge of the interrelations between 2.6 System (PZR PCS) Malfunction X the Pressurizer Pressure Control Malfunctions and 1

Question 8 the following: Controllers and positioners (CFR 41.7 / 45.7) 000029 Anticipated Transient Without EK2.06 Knowledge of the interrelations between 2.9*

Scram (ATWS) X the and the following an ATWS: Breakers, relays, 1

Question 9 and disconnects (CFR 41.7 / 45.7) 000038 Steam Generator Tube Rupture EA2.12 Ability to determine or interpret the 3.9*

(SGTR) X following as they apply to a SGTR: Status of MSIV 1

Question 10 activating system (CFR 43.5 / 45.13) 000040 Steam Line Rupture - Excessive 2.1.7 Ability to evaluate plant performance and 4.4 Heat Transfer X make operational judgments based on operating 1

Question 11 characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13) 000054 Loss of Main Feedwater (MFW) AA2.01 Ability to determine and interpret the 4.3 X following as they apply to the Loss of Main 1

Question 12 Feedwater (MFW): Occurrence of reactor and/or turbine trip (CFR: 43.5 / 45.13)

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

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1(RO) Continued E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 000055 Loss of Offsite and Onsite Power EA1.06 Ability to operate and monitor the following 4.1 (Station Blackout) X as they apply to a Station Blackout: Restoration of 1

Question 13 power with one ED/G (CFR 41.7 / 45.5 / 45.6) 000056 Loss of Offsite Power AK1.01 Knowledge of the operational implications 3.7 X of the following concepts as they apply to Loss of 1

Question 14 Offsite Power: Principle of cooling by natural convection (CFR 41.8 / 41.10 / 45.3) 000062 Loss of Nuclear Service Water AK3.01 Knowledge of the reasons for the following 3.2*

X responses as they apply to the Loss of Nuclear 1

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 / 45.7 )

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

Question 16 Generator Voltage and Electric Grid Disturbances:

Under-excitation (CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)

BW/E04 Inadequate Heat Transfer - Loss EA1.1 Ability to operate and / or monitor the 4.4 Of Secondary Heat Sink X following as they apply to the (Inadequate Heat 1

Question 17 Transfer) Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5 / 45.6)

BW/E10 Post-Trip Stabilization 2.1.19 Ability to use plant computers to evaluate 3.9 X system or component status.

1 Question 18 (CFR: 41.10 / 45.12)

K/A Category Point Totals: 3 3 2 4 3 3 Group Point Total: 18 NUREG-1021, Revision 9 Supplement 1 RO Page 3 of 9 FENOC Facsimile Rev. 1

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

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 000036 Fuel Handling Incidents AK1.03 Knowledge of the operational implications 4.0 X of the following concepts as they apply to Fuel 1

Question 19 Handling Incidents : Indications of approaching Criticality (CFR 41.8 / 41.10 / 45.3) 000051 Loss of Condenser Vacuum 2.2.44 Ability to interpret control room indications to 4.2 X verify the status and operation of a system, and 1

Question 20 understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) 000059 Accidental Liquid Radwaste AK2.01 Knowledge of the interrelations between 2.7 Release X the Accidental Liquid Radwaste Release and the 1

following: Radioactive-liquid monitors Question 21 (CFR 41.7 / 45.7) 000060 Accidental Gaseous-Waste AA2.06 Ability to operate and / or monitor the 3.6*

Release X following as they apply to the Accidental Gaseous 1

Radwaste: Valve lineup for release of radioactive Question 22 gases (CFR 41.7 / 45.5 / 45.6) 000061 ARM System Alarms AK3.02 Knowledge of the reasons for the following 3.4 X responses as they apply to the Area Radiation 1

Question 23 Monitoring (ARM) System Alarms: Guidance contained in alarm response for ARM system (CFR 41.5,41.10 / 45.6 / 45.13) 000069 Loss of Containment Integrity AA1.03 Ability to operate and / or monitor the 2.8 X following as they apply to the Loss of Containment 1

Question 24 Integrity: Fluid systems penetrating containment (CFR 41.7 / 45.5 / 45.6)

BW/A01 Plant Runback AA2.1 Ability to determine and interpret the 3.0 X following as they apply to the (Plant Runback) 1 Question 25 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13)

BW/A02 Loss of NNI-X AK2.2 Knowledge of the interrelations between the 3.8 X (Loss of NNI-X) and the following: Facilitys heat 1

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 / 45.7)

BW/E13 EOP Rules EA1.3 Ability to operate and / or monitor the 3.4 X following as they apply to the (EOP Rules) Desired 1

Question 27 operating results during abnormal and emergency situations.

(CFR: 41.7 / 45.5 / 45.6)

K/A Category Point Totals: 1 2 1 2 2 1 Group Point Total: 9 NUREG-1021, Revision 9 Supplement 1 RO Page 4 of 9 FENOC Facsimile Rev. 1

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

System # / Name K K K K K K A A A A G K/A Topic(s) IR Points 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump A3.02 Ability to monitor automatic operation 2.6 System (RCPS)

X of the RCPS, including: Motor current 1

Question 28 (CFR: 41.7 / 45.5) 003 Reactor Coolant Pump K3.01 Knowledge of the effect that a loss or 3.7 System (RCPS)

X malfunction of the RCPS will have on the 1

Question 29 following: RCS (CFR: 41.7 / 45.6) 004 Chemical and Volume K4.14 Knowledge of CVCS design feature(s) 2.8*

Control System X and/or interlock(s) which provide for the 1

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 System (RHRS)

X malfunction on the following will have on the 1

RHRS: RHR heat exchanger Question 31 (CFR: 41.7 / 45.7) 006 Emergency Core Cooling K6.02 Knowledge of the effect of a loss or 3.4 System (ECCS)

X malfunction on the following will have on the 1

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 Tank/Quench Tank System X malfunction of the PRTS will have on the 1

(PRTS) following: Containment Question 33 (CFR: 41.7 / 45.6) 008 Component Cooling Water A2.01 Ability to (a) predict the impacts of the 3.3 System (CCWS)

X following malfunctions or operations on the 1

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 / 43.5 / 45.3 / 45.13) 010 Pressurizer Pressure 2.2.39 Knowledge of less than or equal to 3.9 Control System (PZR PCS)

X one hour Technical Specification action 1

Question 35 statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13) 010 Pressurizer Pressure K4.02 Knowledge of PZR PCS design 3.0 Control System (PZR PCS)

X feature(s) and/or interlock(s) which provide 1

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*

(RPS)

X following malfunctions or operations on the 1

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 dc control power (CFR: 41.5 / 43.5 / 45.3 / 45.5)

NUREG-1021, Revision 9 Supplement 1 RO Page 5 of 9 FENOC Facsimile Rev. 1

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 1(RO) Continued System # / Name K K K K K K A A A A G K/A Topic(s) IR Points 1 2 3 4 5 6 1 2 3 4 013 Engineered Safety Features K1.07 Knowledge of the physical 4.1 Actuation System (ESFAS)

X connections and/or cause effect 1

relationships between the ESFAS and the Question 38 following systems: AFW System (CFR: 41.2 to 41.9 / 45.7 to 45.8) 022 Containment Cooling A1.04 Ability to predict and/or monitor 3.2 System (CCS)

X changes in parameters (to prevent 1

exceeding design limits) associated with Question 39 operating the CCS controls including:

Cooling water flow (CFR: 41.5 / 45.5) 004 Chemical and Volume 2.4.4 Ability to recognize abnormal 4.5 Control System X indications for system operating parameters 1

that are entry-level conditions for emergency Question 40 and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6) 062 AC Electrical Distribution K1.02 Knowledge of the physical 4.1 System X connections and/or cause/effect 1

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*

(CSS)

X the following: MOVs 1

Question 42 (CFR: 41.7) 039 Main and Reheat Steam K5.08 Knowledge of the operational 3.6 System (MRSS)

X implications of the following concepts as the 1

apply to the MRSS: Effect of steam removal Question 43 on reactivity (CFR: 441.5 / 45.7) 059 Main Feedwater (MFW) A1.07 Ability to predict and/or monitor 2.5*

System X changes in parameters (to prevent 1

Question 44 exceeding design limits) associated with operating the MFW controls including: Feed Pump speed, including normal control speed for ICS (CFR: 41.5 / 45.5) 059 Main Feedwater (MFW) A4.01 Ability to manually operate and 3.1*

System X monitor in the control room: MFW turbine 1

Question 45 trip indication (CFR: 41.7 / 45.5 to 45.8) 061 Auxiliary / 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 / 43.5 / 45.3 / 45.13) 062 AC Electrical Distribution X A3.04 Ability to monitor automatic operation 2.7 1 System of the ac distribution system, including:

Operation of inverter (e.g., precharging Question 47 synchronizing light, static transfer)

(CFR: 41.7 / 45.5)

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

ES-401 PWR Examination Outline Form ES-401-2 Davis-Besse 6/2013 Plant Systems - Tier 2/Group 1(RO) Continued System # / Name K K K K K K A A A A G K/A Topic(s) IR Points 1 2 3 4 5 6 1 2 3 4 063 DC Electrical Distribution X A1.01 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 / 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 X 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 / 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) 078 Instrument Air System (IAS) X K1.05 Knowledge of the physical 3.4* 1 connections and/or cause-effect Question 53 relationships between the IAS and the following systems: MSIV air (CFR: 41.2 to 41.9 / 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)

K/A 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 of 9 FENOC Facsimile Rev. 1

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

System # / Name K K K K K K A A A A G K/A Topic(s) 1 2 3 4 5 6 1 2 3 4 IR Points 002 Reactor Coolant System X 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 X 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 X 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 / 45.5 to 45.8) 041 Steam Dump System A2.02 Ability to (a) predict the impacts of 3.6 (SDS) and Turbine Bypass X the following malfunctions or operations 1 Control on the SDS; and (b) based on those predictions or mitigate the consequences Question 59 of those malfunctions or operations:

Steam valve stuck open (CFR: 41.5 / 43.5 / 45.3 / 45.13) 055 Condenser Air Removal X 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 Question 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 / 43.5 / 45.3 / 45.13) 072 Area Radiation Monitoring X A1.01 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 / 45.5) 075 Circulating Water System X 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 X 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 / 45.7 / 45.8) 086 Fire Protection System X 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 heat detectors (CFR: 41.7 / 45.7)

K/A Category Point Totals: 1 1 1 1 0 0 2 2 0 1 1 Group Point Total: 10 NUREG-1021, Revision 9 Supplement 1 RO Page 8 of 9 FENOC Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Davis-Besse RO Date of Exam 6/3 thru 6/14 2013 RO SRO Only Category K/A# Topic IR Points IR Points

1. 2.1.40 Knowledge of refueling administrative requirements. (CFR: 41.10 / 43.5 / 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 / 43.5 / 45.4)

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 / 43.2 / 45.13)

Question 68 2.2.7 Knowledge of the process for conducting special or infrequent tests. 2.9 1 (CFR: 41.10 / 43.3 / 45.13)

Question 69 2.2.35 Ability to determine Technical Specification Mode of Operation. (CFR: 3.6 1 41.7 / 41.10 / 43.2 / 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 / 43.4 / 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 / 41.12 / 43.4 / 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 / 43.4 / 45.9

/ 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 / 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 / 43.5 / 45.13)

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

ES-401 PWR Examination Outline Form ES-401-2 Facility: Davis-Besse SRO Date of Exam 6/3 thru 6/14 2013 RO K/A Category Points SRO ONLY Points Tier Group K K K K K K A A A A G TOTAL A2 G* TOTAL 1 2 3 4 5 6 1 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 K/A 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 K/A 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 K/A 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 K/As 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 K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A 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 K/As.

8. On the following pages, enter the K/A 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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

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

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 000056 Loss of Offsite Power X 2.1.20 Ability to interpret and execute procedure 4.6 1 steps.

Question 76 (CFR: 41.10 / 43.5 / 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 / 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 / 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 / 43.5 / 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)

BW/E05 Steam Line Rupture - Excessive X 2.4.20 Knowledge of the operational implications of 4.3 1 Heat Transfer EOP warnings, cautions, and notes.

Question 81 (CFR: 41.10 / 43.5 / 45.13)

K/A Category Point Totals: 0 0 0 0 3 3 Group Point Total: 6 NUREG-1021, Revision 9 Supplement 1 SRO Page 2 of 6 FENOC Facsimile Rev. 1

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

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR Points 1 2 3 1 2 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 / 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 / 41.10 / 43.2 / 43.3 /

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 / 45.13)

BW/A06 Shutdown Outside Control Room X 2.1.32 Ability to explain and apply system limits and 4.0 1 precautions.

Question 85 (CFR: 41.10 / 43.2 / 45.12)

K/A Category Point Totals: 0 0 0 0 2 2 Group Point Total: 4 NUREG-1021, Revision 9 Supplement 1 SRO Page 3 of 6 FENOC Facsimile Rev. 1

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

System # / Name K K K K K K A A A A G K/A Topic(s) IR Points 1 2 3 4 5 6 1 2 3 4 006 Emergency Core Cooling X A2.03 Ability to (a) predict the impacts of the 3.7 1 System (ECCS) following malfunctions or operations on the ECCS; and (b) based on those predictions, Question 86 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: System leakage (CFR: 41.5 / 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 / 43.5 / 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 / 43.5 / 45.3 / 45.13) 039 Main and Reheat Steam X A2.05 Ability to (a) predict the impacts of the 3.6 1 System (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 / 43.5 / 45.3 / 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 / 43.5 / 45.13)

K/A Category Point Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 NUREG-1021, Revision 9 Supplement 1 SRO Page 4 of 6 FENOC Facsimile Rev. 1

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

System # / Name K K K K K K A A A A G K/A Topic(s) 1 2 3 4 5 6 1 2 3 4 IR Points 011 Pressurizer Level Control X A2.07 Ability to (a) predict the impacts of the 3.3 1 System (PZR LCS) 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 / 43.5 / 45.3 / 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 / 43.5 / 45.3 / 45.5) 033 Spent Fuel Pool Cooling X 2.1.20 Ability to interpret and execute 4.6 1 System (SFPCS) procedure steps.

Question 93 (CFR: 41.10 / 43.5 / 45.12)

K/A Category Point Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 NUREG-1021, Revision 9 Supplement 1 SRO Page 5 of 6 FENOC Facsimile Rev. 1

ES 401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Davis-Besse SRO Date of Exam 6/3 thru 6/14 2013 RO SRO Only Category K/A# Topic IR # IR #

1. 2.1.42 Knowledge of new and spent fuel movement procedures. (CFR: 41.10 /

Conduct 43.7 / 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 / 41.10 / 43.5 / 43.6 / 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 / 43.5 / 45.13)

Question 96 Subtotal 2

3. 2.3.6 Ability to approve release permits. (CFR: 41.13 / 43.4 / 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 / 43.4 / 45.9)

Question 98 Subtotal 2

4. 2.4.27 Knowledge of fire in the plant procedures. (CFR: 41.10 / 43.5 / 45.13)

Emergency Question 99 3.9 1 Procedures/

Plan 2.4.44 Knowledge of emergency plan protective action recommendations.

(CFR: 41.10 / 41.12 / 43.5 / 45.11) 4.4 1 Question 100 Subtotal 2 Tier 3 Point Total 7 NUREG-1021, Revision 9 Supplement 1 SRO Page 6 of 6 FENOC Facsimile Rev. 1