ML14084A044

Iinitial Exam 2013-302 Final Administrative Documents

ML14084A044
Person / Time
Site:	Oconee
Issue date:	03/21/2014
From:	NRC/RGN-II
To:	Duke Energy Corp
References
50-269/13-302, 50-270/13-302, 50-287/13-302, ES-201, ES-201-1 50-269/13-302, 50-270/13-302, 50-287/13-302
Download: ML14084A044 (54)

Text

sr I 0?0r9-srrn I -fi[al-fornr s-nrs.doc E5-Z0T----------Eramination Preparation Checklist Form ES-201-1 Facility: Oconee Date of Examination: 121912013 Developed by: Written - Facility x NRC E tt Operating - Facility x NRC E Target Date" Task Description (Reference)

Chief Examiner's lnitials

-1 80 1

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

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-120 NRC examiners and facility contact assigned (C.1.d; C.2.e) 2.

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-120 3.

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

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-120 4.

Corporate notification letter sent (C.2.d)

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t5 Reference material due (C.1.e; C.3.c; Attachment 3)l 8t rols/rr t-75) 6 lntegrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1t2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)

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

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(-45]

8 Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

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-30 Preliminary license applications (NRC Form 398's) due (C.1.1; C.2.9; ES-202) 9.

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-14 Final license applications due and Form ES-20'l-4 prepared (C.1.l; C.2.i; ES-202) 10.

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-14 Examination approved by NRC supervisor for facility licensee review (C.2.h;C.3.0 11.

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-14

12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

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

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-7 Final applications reviewed', 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204) 14.

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-7 Proctoringlwritten exam administration guidelines reviewed with facility licensee (C.3.k) 15.

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

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• Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Oconee Date of Examination: 12/09/2013 Initials Item Task Description a

b*

c#

1.

a.

Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

R b.

Assess whether the outline was systematically and randomly prepared in accordance with I

Section D.1 of ES-401 and whether all KJA categories are appropriately sampled.

T c.

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

ZV.._..

d.

Assess whether the justifications for deselected or rejected K/A statements are appropriate.

2.

a.

Using Form ES-3d -5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, j

S and major transients.

M b.

Assess whether there are enough scenario sets (and spares) to test the projected number A)

U and mix of applicants in accordance with the expected crew composition and rotation schedule L

without compromising exam integrity, and ensure that each applicant can be tested using A

at least one new or significantly modified scenario, that no scenarios are duplicated T

from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

c.

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

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

AJ 3.

a.

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

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W

distributed among the safety functions as specified on the form I

(2) task repetition from the last two NRC examinations is within the limits specified on the form T

(3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria 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 (2) at least one task is new or significantly modified (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.

4.

a.

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

W E

b.

Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

23 c.

Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

P d.

Check for duplication and overlap among exam sections.

L e.

Check the entire exam for balance of coverage.

jf f.

Assess_whether_the_exam_fits_the_appropriate_job_level_(P0_or_SRO).

a. Author

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b. Facility Reviewer (*)

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c. NRC Chief Examiner (#)

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d. NRC Supervisor

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

Not applicable for NRC-prepared examination outlines

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 12/09/13 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations GEN 2.1.25 (3.9/4.2)

(27 min)

N,R Admin-143, Manually Calculate Core Tilt due to Loss of the OAC (RO Only)

Conduct of Operations GEN 2.1.37 (4.3/4.6)

(20 min)

M, R Admin-145, Calculate Run Time for Deborating Demineralizer (Both)

Equipment Control

[KA G2.2.14 (3.9/4.3)]

(30 min)

M, R Admin-212 Determine LTOP Requirements (RO Only)

Radiation Control G2.3.12 (3.2/3.7)

(10 min)

D, R Admin-307, Determine Posting and Access requirements of the LPI Room Based on Plan View (Both)

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)

X

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 12/09/13 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations GEN 2.1.25 (3.9/4.2)

(35 min)

N,R Admin-144, Manually calculate Core Tilt due to Loss of the OAC and determine any required actions and completions times (SRO Only)

Conduct of Operations GEN 2.1.37 (4.3/4.6)

(20 min)

M, R Admin-145, Calculate Run Time for Deborating Demineralizer (Both)

Equipment Control

[KA G2.2.18 (2.6/3.9)]

(25 min)

M, R Admin-241, Complete Plant Configuration Sheet (Time to Core Boil) (SRO Only)

Radiation Control G2.3.12 (3.2/3.7)

(10 min)

D, R Admin-307, Determine Posting and Access requirements of the LPI Room Based on Plan View (Both)

Emergency Plan G2.4.38 (2.4/4.4)

(20 min)

M,R Admin-413, Determine Emergency Classification and Complete the Emergency Notification Form (SRO Only)

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)

X

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 12/09/13 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 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

a. CRO-115, Withdraw Control Rod Group One to 50%

OP/1/A/1105/019 (Control Rod Drive System) Encl. 4.3 (Withdrawal Of Safety Rod Group to 50%)

[KA: 001 A4.06 (2.9/3.2)] (14 min)

M, L, S 1

b. CRO-223, Bypass ES Subsystem 2 OP/1/A/1105/014 Encl. 4.9 (Removal and Restoration of ES Channels)

[KA: SYS 013 A4.02 (4.3/4.4)] (10 min)

D, S 2

c. CRO-404, Alignment of Condensate Recirc Unit 1 EOP Encl. 5.23 (Alignment of Condensate Recirc)

[KA: APE 054 G2.1.20 (4.6/4.6)] (10 min)

D, A, S, E, L 4S

d. CRO-414, Swapping LPI Modes - High Pressure Mode to LPI Normal Decay Heat Mode OP/1/A/1104/004, Enclosure 4.15 (Swapping LPI Modes -

High Press Mode to LPI Normal Mode)

[KA: 005 A4.01 (3.6*/3.4)] (15 min)

D, L, S 4P

e. CRO-508, ES Channels 5 and 6 Recovery Unit 1 EOP Encl. 5.41 (ES Recovery)

[KA: 103 A4.04 (3.5*/3.5*)] (10 min)

N, EN, L, S 5

f.

CRO-606, Energize Main Feeder Buses from CT-5 Unit 1 EOP Encl. 5.38 (Restoration of Power)

[KA: EPE 055 EA2.03 (3.9/4.7)] (15 min)

M, A, L, S 6

g. CRO-803, Perform Required Actions For a Turbine Building Flood AP/10 (Uncontrollable Flooding of Turbine Building)

[KA: APE BW/A07 AA1.3 (3.3/3.5)] (15 min)

D, A, L, S 8

h. CRO-903, Release GWD Tank OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release)

[KA: 071 A4.26 (3.1/3.9) (20 min)

M, A, S 9

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

i.

NLO-400, Station ASW Pump Alignment EOP Encl. 5.10 Station ASW Pump Alignment

[KA: BW/E04 EA1.1 (4.4/4.2)] (16 min)

D, R, E, L 4S

j.

CRO-607, Activate the SSF From the SSF Control Room AP/25 (SSF EOP)

[KA: 062 A2.11 (3.7/4.1)] (12 min)

D, E, L 6

k. NLO-700, Restoration of ICS AUTO Power AP/023 (Loss of ICS Power) Encl. 5.2 (Restoration of ICS AUTO Power)

[KA: BW/A02 AA1.3 (3.4/3.6)] (16 min)

D, A, E 7

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 12/09/13 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 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

a. N/A

b. N/A

c. N/A

d. N/A

e. CRO-508, ES Channels 5 and 6 Recovery Unit 1 EOP Encl. 5.41 (ES Recovery)

[KA: 103 A4.04 (3.5*/3.5*)] (10 min)

N, EN, L, S 5

f.

CRO-606, Energize Main Feeder Buses from CT-5 Unit 1 EOP Encl. 5.38 (Restoration of Power)

[KA: EPE 055 EA2.03 (3.9/4.7)] (15 min)

M, A, L, S 6

g. N/A

h. CRO-903, Release GWD Tank OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release)

[KA: 071 A4.26 (3.1/3.9) (20 min)

M, A, S 9

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

i.

NLO-400, Station ASW Pump Alignment EOP Encl. 5.10 Station ASW Pump Alignment

[KA: BW/E04 EA1.1 (4.4/4.2)] (16 min)

D, R, E, L 4S

j.

N/A

k. NLO-700, Restoration of ICS AUTO Power AP/023 (Loss of ICS Power) Encl. 5.2 (Restoration of ICS AUTO Power)

[KA: BW/A02 AA1.3 (3.4/3.6)] (16 min)

D, A, E 7

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Oconee Date of Examination: 12/09/2013 Operating Test Number: 1 Initials

1. General Criteria 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 0.1.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 operationally important 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 The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.

=

Printed Name] Signture Date a.

Author L4h/L&J Ii-.313 b.

Facility Reviewer(*)

,,d;,

c.

NRC Chief Examiner (#)

d.

NRC Supervisor Al i

NOTE:

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

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

Target Quantitative Attributes (Per Scenario; See Section D.5.d)

Actual Attributes ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Oconee Date of Exam: 12/09/13 Scenario Numbers; 1 I 2 I 3 I 4 Operating Test No.: 1 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.

tY 9.

The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator vL/

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 j 4./

(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.

7 1.

Total malfunctions (58) 2.

Malfunctions after EOP entry (12) 3.

Abnormal events (24) 4.

Major transients (12) 5.

FOPs entered/requiring substantive actions (12) 6.

FOP contingencies requiring substantive actions (02) 7.

Critical tasks (23)

\\

1 4

1 12 3

0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Oconee Date of Exam: 12/09/13 Operating Test No.:

1 A

E Scenarios P

V 1

2 3

4 T

M P

E I

L N

CREW CREW CREW CREW T

N I

T POSITION POSITION POSITION POSITION I

_A M

L S

A B

S A

B S

A B

S A

B L

u A

T R

T 0

A T

0 R

T 0

A T

0 M(*)

N y

0 C

P 0

C P

0 C

P 0

C P

T P

R IU E

RO RX 110 X

NOR 1

1111 SRO-l I/C 1,2,4 2,3 2,5,5 3,5 4

4 2

SRO-U MAJ 7

7 7

7,8 2

2 1

TS 022 cO NOR 111 SRO-l I/C 3,5 4,5 4,6 2,4,6 4

4 2

D SRO-U MAJ 7

7 7

7,8 2

2 1

D TS 022 NOR 11111 I/C 1,2,3 2,3,4 2,3,4 2,3,4 4

4 2

SRO-U 4,5 5,6 5,6 5,6 X

MAJ 7

7 7

7,8 221 TS 1,6 3,4 2,5 2,5 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-i 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.

ES-301 ComDetencies Checklist Form ES-301-6 Facility: Oconee Date of Examination: 12/09/13 Operating Test No.: 1 APPLICANTS RO X

RO X

RO P0 SRO-I D

SRO-l D

SRO-l D

SRO-l D

SRO-U D

SRO-U D

SRO-U X

SRO-U D Competencies NAJO SCENAFUO CENARKD 12341 23412341 234 Interpret/Diagnose Events 2,3 4,5 1,4 2,4 1,2 1,2, 2,3 1,3 1,2, 1,2 1,2, 1,2, 45 67 67 67 46 37 57 57 34 34 34, 34 and Conditions 6

8 8

7,8 8

8 5,6, 5,6 5,6, 5,6, 7,8 7,8 7

7,8 Comply With and 3,5 2,4 1,3, 2,4 1,2 1,2 2,3 1,3 1,2, 1,2 1,2, 1,2, 6,7 56 4,5, 67 3,4 37 5,7 56 3,4, 34 3,4, 3,4, Use Procedures (1) 8 7,8 6,7, 8

6,7 8

7,8 5,6, 5,6 5,6, 5,6, 8

7,8 7,8 7

7,8 Operate Control 3,5 2,4 1,3, 2,4 1,2 1,2 2,3 1,3

-4 6,7 5,6 4,5, 6,7 3,5 3,7 5,7 5,6 Doarus )

8 7,8 6,7 8

6,7 8

7,8 8

Communicate 1,2 1,2 1,2, 1,2 1,2 1,2, 1,2, 1,2 1,2, 1,2 1,2, 1,2,

-4 I

4 4

3,4 3,4 3,4 3,4, 3,4 3,,

s, 3,4, 3,4, anu InLeraci 5,6 5,6 5,6, 5,6 5,6 5,6 5,6 5,6 5,6, 5,6 5,6, 5,6, 7,8 7,8 7

7,8 7,8 7,8 7

7,8 7,8 7,8 7

7,8 Demonstrate Supervisory 1,2, 1,2 1,2, 1,2, 3,4, 3,4 3,4, 3,4, Ability (3) 5,6 5,6 5,6, 5,6, 7,8 7,8 7

7,8 Comply With and 1,6 3,5 2,5 2,5 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 applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected KA Reason for Rejection 1 / 1 APE022 AK3.07 Q(5) B&W design does not isolate makeup pumps on loss of RC makeup 1 / 1 EPE029 EA1.07 Q(9) B&W design does not operate recirc valve switch on the makeup pump.

1 / 2 APE001 AK3.02 Q(19) No link in rod operability and continuous rod withdrawal in B&W digital rod system 1 / 2 APE037 AA1.03 Q(21) Oconee has no loop isolation valves 1 / 2 APE059 AA1.02 Q(22) ONS Operations does not do anything with liquid readioactive discharges. No actions for ARMs assocaited with discharge.

1 / 2 BWA08 2.4.34 Q(26) ROs have no duties outside the CR for lowering refuiling canal level 2 / 1 SYS004 A1.05 Q(29) A/G level and poressure controlled by ICS based upon plant load. Not operated manually.

2 / 1 SYS076 K3.02 Q(42) Service water is not connected to Secondary Closed Cooling Water 2 / 2 SYS028 2.2.12 Q(46) ONS no longer has this system 2 / 1 SYS061 K5.02 Q(73) Essentially the same as T1/G1 007EK1.06 2 / 1 SYS003 A2.05 Q(89) ONS seal leakoff does not go to LDST (VCT) it goes to Quench Tank therefore no connection between LDST pressure and seal leakoff.

2 / 1 SYS039 A2.02 Q(89) Prevent oversampling 3 / 0 GEN2.2 2.2.41 Q(97) Unable to write an SRO level question to this KA

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:

Oconee Nuclear Station Date of Exam:

12/9/2013 Exam Level:

RO SRO Initial Item Description a

b*

c*

1.

Questions and answers are technically accurate and applicable to the facility.

2.

a.

NRC K/As are referenced for all questions.

b.

Facility learning objectives are referenced as available.

3.

SRO questions are appropriate in accordance with Section D.2.d of ES-401 4.

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

4 tq 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 v the licensee certifies that there is no duplication; or other (explain)

6.

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

23 / 2 10 I 4 42 / 19 cpj 7.

Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 33 I 5

42 I 20 the actual RO / SRO 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; kJL deviations are justified.

1)i...) k}\\

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; 9

the total is correct and agrees with the value on the cover sheet.

Printed Name / Signature te

a. Author

b. Facility Reviewer (*)

Z/zpi4

)

/2/31/3

c. NRC Chief Examiner (#)

Dc 4. L,: /4XJ t C. rj 4

R 1

A

/z/y/,

1

d. NRC Regional Supervisor lA.Q&/JJ Note:

• The facility reviewers initials/signature are not applicable for NRC-developed examinations.

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

ES-401, Rev. 9 Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 1

H 3

N S

EPE007 EK1.06; Reactor Trip - Knowledge of the operational implications of the relationship of emergency feedwater flow to S/G and decay heat removal following reactor trip as they apply to the reactor trip.

K/A is met.

2 H

2 B

S APE008 AK1.01; Pressurizer (PZR) Vapor Space Accident (Relief Valve Stuck Open) -

Knowledge of the operational implications of the thermodynamics and flow characteristics of open or leaking valves as they apply to a Pressurizer Vapor Space Accident.

K/A is met.

This is GFE information, but OK with specific plant data.

Choice A not plausible. Cant be <212 if above 0 psig. Why not use building press as one option?

Added RB pressure = 0 and made answer 212F. OK.

3 F

3 B

S EPE009 EK2.03; Small Break LOCA - Knowledge of the interrelations between the small break LOCA and The S/Gs.

K/A is met.

4 F

3 N

S APE015/017 2.4.45; Reactor Coolant Pump (RCP) Malfunctions - Ability to prioritize and interpret the significance of each annunciator or alarm.

K/A is met.

5 H

3 B

S EPE011 EA1.14; Large Break LOCA - Ability to operate and monitor the Subcooling margin monitors as they apply to a Large Break LOCA.

K/A is met.

6 H

3 B

S APE025 AK1.01; Loss of Residual Heat Removal System - Knowledge of the operational implications of the loss of RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System.

K/A is met.

7 F

3 B

S APE026 AK3.03; Loss of Component Cooling Water - Knowledge of the reasons for guidance actions contained in EOP for Loss of CCW as they apply to the Loss of Component Cooling Water.

K/A is met.

8 H

3 M

E APE027 AK2.03; Pressurizer Pressure Control System (PZR PCS) Malfunction -

Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and the controllers and positioners.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only Plausibility of responding as expected is low. Could the second question be rephrased such that the answers are Bank 2 should be energized or Bank 2 will energize at XXX psig?

Modified as suggested. SAT.

Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1)Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2)Enter the level of difficulty (LOD) of each question using a 1 B 5 (easy B difficult) rating scale (questions in the 2 B 4 range are acceptable).

3)Check the appropriate box if a psychometric flaw is identified:

4)The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

5)The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

6)The answer choices are a collection of unrelated true/false statements.

7)The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

8)One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

9)The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

10)The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

11)The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

12)The question requires reverse logic or application compared to the job requirements.

5.Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6.Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

7.At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401, Rev. 9 2

Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 9

H 3

N S

BWE04 EK3.1; Inadequate Heat Transfer -

Knowledge of the reasons for facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics as they apply to Inadequate Heat Transfer.

K/A is met.

When is rule 4 required? It sounds like the lowest number given would be correct regardless.

Not true. If you changed pressure to 2255, the answer would not change. This was changed to 2255. Required is underlined.

Change to 2255. Complete now SAT.

10 F

2 N

S EPE038 2.2.38; Steam Generator Tube Rupture - Knowledge of conditions and limitations in the facility license.

K/A is met.

Isnt this a little bit of minutia. Dont the CFT tanks have an alarm for low press or high level? Why would you require anyone to know this from memory?

Licensee expects the RO to know these numbers. Discussed with licensee. They stated this is the plant standard and they feel this is an acceptable question.

11 H

3 N

S APE054 AA1.04; Loss of Main Feedwater-Ability to operate and / or monitor HPI, under total feedwater loss conditions as they apply to the Loss of Main Feedwater.

K/A is met.

Not sure what is gained on this question by using the actual displays?

This makes the match with the K/A better.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 12 H

3 X

N E

EPE055 EA2.03; Loss of Offsite and Onsite Power - Ability to determine or interpret the actions necessary to restore power as they apply to a Station Blackout.

K/A is met.

D is a possible answer. Need to add detail to the stem such as Assuming no other failures describe the first method how power will.

Corrected as suggested and added per procedure.

Add IAW enclosure. This has been added. SAT.

13 H

3 N

S APE056 AA2.43; Loss of Offsite Power - Ability to determine and interpret the occurrence of a turbine trip as it applies to the Loss of Offsite Power.

K/A is met.

The second part may cause the applicant to assume trip is expected.

I agree, need to ensure there is wording given to infer that both questions are totally independent of each other.

Second question added asking what ICS uses to control the bypass valve.

Question is now SAT.

14 H

3 N

S APE057 AA1.06; Loss of Vital AC Electrical Instrument Bus - Ability to operate and / or monitor the Manual control of components for which automatic control is lost as they apply to the Loss of Vital AC Instrument Bus.

K/A is met.

15 F

3 N

U APE065 AA2.05; Loss of Instrument Air -Ability to determine and interpret when to commence plant shutdown if instrument air pressure is decreasing as it applies to the Loss of Instrument Air.

K/A is met.

C and D plausibility is weak. Why not use 70# and 65 # and alternate the correct reason and the fact that pneumatic valves reach fully closed and therefore they lose all ability to control flows and pressures.

Corrected as suggested. This is now SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 16 H

2 B

E APE077 AK2.03; Generator Voltage and Electric Grid Disturbances -

Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and sensors, detectors, indicators.

K/A is met.

For second part just make the answers Will automatically trip and will NOT automatically trip.

Corrected as suggested. SAT.

17 F

2 N

S BWE02 2.2.3; Vital System Status Verification - (multi-unit license)

Knowledge of the design, procedural, and operational differences between units.

K/A is met.

18 F

3 N

E BWE05 EK3.2; Excessive Heat Transfer - Knowledge of the reasons for the normal, abnormal and emergency operating procedures associated with Excessive Heat Transfer as they apply to Excessive Heat Transfer.

K/A is met.

I cant find where the EOP references using either indicator. Step 47 does state that if Tcold approaches 400 F ensure less than 4 RCPs operating.

This question would be OK if I can get verification that it is correct.

Logically you would want to use qualified instruments if MSLB inside containment, but this is not a given.

Step 7 of Rule 5 requires use of CETs. You go back to Tcs in step 13.

This is acceptable. SAT.

19 H

3 B

S APE076 2.3.5; High Reactor Coolant Activity - Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A is met.

20 F

2 B

S APE032 AK3.01; Loss of Source Range Nuclear Instrumentation -

Knowledge of the reasons for startup termination on source-range loss as it applies to the Loss of Source Range Nuclear Instrumentation.

K/A is met.

How was this modified?

This is a Bank question.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 21 H

3 B

S APE037 AA1.11; Steam Generator (S/G) Tube Leak - Ability to operate and / or monitor the PZR level indicator as it applies to the Steam Generator Tube Leak.

K/A is met.

A2 and C2 not plausible. No adjustment is required for this. This is normal operating level criteria.

Both are given bands out of SG tube leak AP. 220 is normal but if loss of auto control occurs then band would be 220 plus or minus. SAT.

22 F

2 N

S BWA04 AA1.2; Turbine Trip - Ability to operate and / or monitor the operating behavior characteristics of the facility as they apply to the Turbine Trip.

K/A is met.

Changed C due to not plausible (only one active trip signal exists). SAT.

23 H

3 B

S APE060 2.2.36; Accidental Gaseous-Waste Release - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

K/A is met.

D plausibility? Immediately closes but you dont have to isolate for up to one hour?

First question changed to should the second part will ask if not already isolated or words to that affect. Now SAT.

24 H

2 B

S BWA03 AK1.3; Loss of NNI-Y - Knowledge of the operational implications of the Annunciators and conditions indicating signals, and remedial actions associated with the Loss of NNI-Y as they apply to the Loss of NNI-Y.

K/A is met.

25 H

3 N

S BWA05 AA2.1; Emergency Diesel Actuation -Ability to determine and interpret the facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the Emergency Diesel Actuation.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 26 H

2 N

S BWE08 EK3.1; LOCA Cooldown - Knowledge of the reasons for the facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics as they apply to the LOCA Cooldown.

K/A is met.

27 H

3 N

S BWE03 EK2.1; Inadequate Subcooling Margin - Knowledge of the interrelations between the Inadequate Subcooling Margin and components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A is met.

28 H

3 X

N U

SYS003 K5.02; Reactor Coolant Pump System (RCPS) -

Knowledge of the operational implications of the effects of RCP coastdown on RCS parameters as they apply to the RCPS.

K/A is met.

All part 1 answers are true statements and would correctly answer the question. Probably why they are good distractors. This leads to two correct answers.

Changed first part to what the design purpose is. Now SAT.

29 F

2 X

N U

SYS004 A1.06; Chemical and Volume Control System - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including VCT level.

K/A is met.

40 inches is always less than 55 inches, therefore never incorrect.

Recommend that the second part be rephrased into a question asking at which level will HP-24 and 25 first open. Then the answers could be 52 inches or 38 inches.

Changed as recommended. This is now SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 30 H

3 X

M E

SYS005 K6.03; Residual Heat Removal System (RHRS) - Knowledge of the effect of a loss or malfunction on the RHR heat exchanger will have on the RHRS.

K/A is met.

A is not plausible. Series implies more than one.

Rewrote question to use a two part question. Used two plausible distractors for first answer and second part is based on unit difference between Unit 2 and 3 allowable pressures. SAT.

31 H

2 X

N E

SYS006 2.4.45; Emergency Core Cooling System (ECCS) - Ability to prioritize and interpret the significance of each annunciator or alarm.

K/A is met.

Why is NOT running Rule 4 plausible? I question answer A and answer B as being plausible.

Pressure and level could cause it. This is SAT.

32 H

2 N

S SYS007 2.2.36; Pressurizer Relief Tank/Quench Tank System (PRTS) -

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

K/A is met.

33 H

3 M

S SYS007 K3.01; Pressurizer Relief Tank/Quench Tank System (PRTS) -

Knowledge of the effect that a loss or malfunction of the PRTS will have on the containment.

K/A is met.

34 F

3 N

S SYS008 A2.04; Component Cooling Water System (CCWS) - Ability to (a) predict the impacts of the PRMS alarm on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

Doesnt appear the bullets are needed to answer the question. Does this meet the KA?

RCS leakage procedure has a section for CCW leak. Therefore K/A is met. Bullets make it clear that you are in the AP. SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 35 F

2 B

S SYS010 K4.03; Pressurizer Pressure Control System (PZR PCS) -

Knowledge of PZR PCS design feature(s) and/or interlock(s) which provide for over pressure control.

K/A is met.

36 H

3 M

E SYS012 A2.05; Reactor Protection System (RPS) - Ability to (a) predict the impacts of faulty or erratic operation of detectors and function generators on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

A2 & C2 plausibility? Two RPS Channels in BYPASS?

Rewrote question to make a two by two asking what RPS functions are affected and if it requires the channel to trip. Now SAT.

37 F

2 N

S SYS012 K4.09; Reactor Protection System (RPS) - Knowledge of RPS design feature(s) and/or interlock(s) which provide for separation of control and protection circuits.

K/A is met.

Check definitions. Does median require a minimum of 3? If so, A is not plausible.

Rewriting to put wide range and two narrow range instead of other way around. This makes the three instruments more visible.

38 H

3 M

S SYS013 A3.02; Engineered Safety Features Actuation System (ESFAS) -

Ability to monitor automatic operation of the ESFAS including operation of actuated equipment.

K/A is met.

39 H

3 N

S SYS064 K1.04; Emergency Diesel Generator (ED/G) System - Knowledge of the physical connections and/or cause-effect relationships between the ED/G system and the DC distribution system.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 40 H

3 N

E SYS073 A1.01; Process Radiation Monitoring (PRM) System - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including radiation levels.

K/A is met.

Does this question help in answering question 23? If there is any possibility of this, then one of these 2 needs to be rewritten.

C2 & D2 plausibility? Why would the ABN have system realignment steps for aligning a release pathway?

Rewrote number 40 due to overlap. New question is SAT.

41 F

2 M

S SYS073 K3.01; Process Radiation Monitoring (PRM) System -

Knowledge of the effect that a loss or malfunction of the PRM system will have on radioactive effluent releases.

K/A is met.

42 F

2 N

S SYS076 K3.01; Service Water System (SWS) - Knowledge of the effect that a loss or malfunction of the SWS will have on closed cooling water.

K/A is met.

43 F

2 B

S SYS078 K2.02; Instrument Air System (IAS) -

Knowledge of bus power supplies to the emergency air compressor.

K/A is met.

44 H

3 N

S SYS103 A4.04; Containment System - Ability to manually operate and/or monitor in the control room phase A and phase B resets.

K/A is met.

45 H

2 N

S SYS016 A3.02; Non-Nuclear Instrumentation System (NNIS) - Ability to monitor automatic operation of the NNIS, including the relationship between meter readings and actual parameter value.

K/A is mostly met.

Changed due to question 72 overlap. New question is SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 46 F

3 N

E SYS015 2.2.12; Nuclear Instrumentation System (NIS) - Knowledge of surveillance procedures.

K/A is met.

Wording is confusing. Make the first question What is the highest power at which TS limits on Reactor Power Imbalance do NOT apply?

The second question would be better if it stated How does OP/1/A/1105/014 (Control Room Instrumentation Operation and Information) determine if Imbalance limits specified in the COLR have been exceeded?

The answer would be by use of the CR indicators or by performing the PT.

Changed as recommended. SAT.

47 F

2 B

S SYS034 A4.02; Fuel Handling Equipment System (FHES) - Ability to manually operate and/or monitor in the control room neutron levels.

K/A is met.

48 H

3 N

S SYS041 K4.11; Steam Dump System (SDS)/Turbine Bypass Control -

Knowledge of SDS design feature(s) and/or interlock(s) which provide for the T-ave./T-ref. program.

K/A is met.

Added the word additional to 1301 information. SAT.

49 H

3 B

S SYS056 A2.04; Condensate System - Ability to (a) predict the impacts of the loss of condensate pumps on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences. loss of condensate pumps.

K/A is met.

50 F

3 N

E SYS068 K6.10; Liquid Radwaste System (LRS) - Knowledge of the effect of a loss or malfunction on the radiation monitors will have on the Liquid Radwaste System.

K/A is met.

Are you certain that you want to test on a note in the procedure?

Ops Representative state that this is acceptable and ROs would be expected to know this. SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 51 F

2 N

S SYS071 K3.04; Waste Gas Disposal System (WGDS) - Knowledge of the effect that a loss or malfunction of the Waste Gas Disposal System will have on the ventilation system.

K/A is met.

52 F

2 N

S SYS072 A1.01; Area Radiation Monitoring (ARM) System - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ARM system controls Including radiation levels.

K/A is met.

53 F

2 B

S SYS075 K2.03; Circulating Water System - Knowledge of bus power supplies to the emergency/essential SWS pumps.

K/A is met.

54 F

2 B

S SYS079 K1.0; Station Air System (SAS) - Knowledge of the physical connections and/or cause-effect relationships between the SAS and the IAS.

K/A is met.

55 F

2 B

S GEN2.1 2.1.26 ; Conduct of Operations - Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

K/A is met.

56 F

3 N

S GEN2.1 2.1.34; Conduct of Operations - Knowledge of primary and secondary plant chemistry limits.

K/A is met.

57 F

2 B

S GEN2.1 2.1.37; Conduct of Operations - Knowledge of procedures, guidelines, or limitations associated with reactivity management.

K/A is met.

58 F

2 B

S GEN2.2 2.2.13; Equipment Control - Knowledge of tagging and clearance procedures.

K/A is met.

59 F

2 N

S GEN2.2 2.2.12;- Equipment Control - Knowledge of surveillance procedures.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 60 H

2 B

S GEN2.2 2.2.37; Equipment Control - Ability to determine operability and/or availability of safety related equipment.

K/A is met.

61 H

3 N

E GEN2.3 2.3.11; Radiation Control - Ability to control radiation releases.

K/A is met.

Will this provide information for question 41?

The tested concepts are different. This is SAT.

62 H

2 N

S GEN2.3 2.3.7; Radiation Control - Ability to comply with radiation work permit requirements during normal or abnormal conditions.

K/A is met.

63 H

3 N

E GEN2.4 2.4.22; Emergency Procedures / Plan -Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

K/A is met.

B2 is not very plausible. Since the reason to stop the RCPs is to the phase separation issue, use that. That should still make A correct, but B would then be plausible.

Rewrote B2 to give reason as HPI injection required prior to exceeding void fraction. Not true but first part is true within 10 minutes second part is true for securing RCPs. SAT.

64 F

2 N

S GEN2.4 2.4.4; Emergency Procedures / Plan -Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

K/A is met.

65 F

3 M

S SYS013 K2.01; Engineered Safety Features Actuation System (ESFAS) -

Knowledge of bus power supplies to the ESFAS/safeguards equipment control.

K/A is met.

66 F

3 N

S SYS022 A4.04; Containment Cooling System (CCS) - Ability to manually operate and/or monitor in the control room valves in the CCS.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 67 H

3 M

S SYS022 K2.01; Containment Cooling System (CCS) - Knowledge of power supplies to the Containment cooling fans.

K/A is met.

68 H

3 N

E SYS026 A3.02; Containment Spray System (CSS) - Ability to monitor automatic operation of the CSS, including verification that cooling water is supplied to the containment spray heat exchanger.

K/A is met.

A is not very plausible. How about A could be to ensure valve fully opened And then change D to ensure valve throttle and is supplying 3000 gpm.

A changed as suggested C and D changed to throttle positions. SAT.

69 H

3 B

S SYS039 A3.02; Main and Reheat Steam System (MRSS) - Ability to monitor automatic operation of the MRSS, including isolation of the MRSS.

K/A is met.

70 H

2 N

E SYS039 K5.08; Main and Reheat Steam System (MRSS) -

Knowledge of the operational implications of the effect of steam removal on reactivity as it applies to the MRSS.

K/A is met.

This is GFE as written. Why not put plant specific data in like how much they would expect power to change for a single valve.

Not GFES. Depends on ICS demand. SAT.

71 F

2 N

S SYS059 A1.03; Main Feedwater (MFW) System - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including power level restrictions for operation of MFW pumps and valve.

K/A is met.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 72 H

2 M

E SYS059 K1.04; Main Feedwater (MFW) System - Knowledge of the physical connections and/or cause-effect relationships between the MFW and the S/GS water level control system.

K/A is met.

This contains similar information as question 45.

Question 45 was changed. SAT.

73 F

2 N

S SYS061 K5.05;Auxiliary / Emergency Feedwater (AFW) System

- Knowledge of the operational implications of feed line voiding and water hammer as they apply to the AFW.

K/A is met.

74 H

3 M

S SYS062 K1.02; AC Electrical Distribution System - Knowledge of the physical connections and/or cause-effect relationships between the ac distribution sys-tem and the ED/G.

K/A is met.

75 H

2 B

S SYS063 K4.01; DC Electrical Distribution System - Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the manual/automatic transfers of control.

K/A is met.

76 F

2 N

S APE008 2.2.37; Pzr Vapor Space Accident - Ability to determine operability and/or availability of safety related equipment.

K/A is met 77 H

2 X

N E

APE015/017 AA2.10; RCP Malfunctions - Ability to determine and interpret when to secure RCPs on loss of cooling or seal injection as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow).

K/A is met.

Not sure what the physics would be to continue to drive the stator temperature up if the pump was tripped at 260 °F. This might lead the applicants to ignore the lower temperature. Instead ask at what temperature should the pump be tripped and what actions should be entered.

Since a single pump can be operated in a loop in this mode, why would any applicant think that you require 2 pumps to be available to be considered operable Changes made as recommended.

Delete last time info. Question is SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 78 H

3 N

S APE025 2.4.45; Loss of Residual Heat Removal System (RHRS) - Ability to prioritize and interpret the significance of each annunciator or alarm.

K/A is met.

79 H

3 M

S APE 054 AA2.03; Loss of Main Feedwater (MFW) - Ability to determine and interpret the conditions and reasons for AFW pump startup as they apply to the Loss of Main Feedwater (MFW).

K/A is met.

80 H

3 X

B E

APE058 AA2.01 - Loss of DC Power: Ability to determine and interpret the following as they apply to the Loss of DC Power: That a loss of dc power has occurred; verification that substitute power sources have come on line.

K/A is met.

I need to see a drawing but I dont see how you could reasonably think that D is credible? If power alignment is needed to restore power to 1KVID as stated in D1 why would it be energized as stated in D2 prior to the alignment This is not an exact K/A match. It does not verify that an restoration of power occurs. This tests the concept of what to expect on a loss of DC.

SAT.

81 H

2 M

S BWE10 2.4.31; Knowledge of annunciator alarms, indications, or response procedures.

K/A is met.

82 H

2 X

N U

APE 005 AA2.03; Inoperable/Stuck Control Rod - Required actions if more than one rod is stuck or inoperable.

K/A is met.

Instead of dropping the one of the rods, could it ratchet down 10 inches?

This should be treated as a dropped rod.

Not sure why anyone would choose the 40% option. Would just ordering the tip setpoints changed make more sense?

Changes made as recommended. This is now SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 83 H

2 X

X N

U APE 067 2.1.20; Plant fire on site - Ability to interpret and execute procedure steps.

K/A is met.

If the applicant doesnt know what a challenging fire is he can still delete two possible answer without knowing anything else. If it affects cables, then you will isolate things associated with having power. Likewise if it doesnt, why touch these? Also why would you ever isolate your TDEFW pump for a fire in this area? Therefore without knowing anything B, C, and D can be eliminated.

Changed part 2 to ask what indication would be used per AP/50. Detailed knowledge of procedures. This is now SAT.

84 F

3 N

S APE 068 2.4.3; Control Room Evacuation - Ability to identify post-accident instrumentation.

K/A is met.

85 H

3 X

N E

BW A01 AA2.1; Ability to determine and interpret the facility conditions and selection of appropriate procedures during abnormal and emergency operations. as they apply to a Plant Runback.

K/A is met.

Could it be argued that using the Operations at Power procedure is NOT prohibited and therefore allowed? If so there would be two correct answers.

AP1 directs you to use AP1. Therefore doing elsewhere would be a procedural violation. SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 86 H

2 X

X X

N U

SYS 004 2.2.3; Chemical and Volume Control System; Knowledge of the design, procedural, and operational differences between units.

K/A is NOT met.

This does not appear to be a unit difference question. It is basically asking the power supply for HP-25 which is the same on each unit.

This is not SRO level. With an ES bus tied to an alternate bus, an RO would know that TS 3.8.1 should be entered and that Mode changes are not allowed.

Replaced question. Used unit difference in seal rejection requirements on HPI pump. Used supporting equipment operability determination to get SRO. The new question is SAT.

87 H

3 X

N E

SYS 005 2.4.47; Residual Heat Removal System; Ability to diagnose and recognize trends in an accurate and timely manner l utilizing the appropriate control room reference material.

K/A is met.

For question 1, do not specify the time range. Also provide some RCS pressure > 50 psig for the entire evolution to eliminate anyone trying to use Table 3.4.3-2 note c.

Changed as recommended. SAT.

88 H

2 N

S SYS 012 A2.06; Reactor Protection System - Ability to (a) predict the impacts of the failure of RPS signal to trip the reactor or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

89 H

2 X

X X

N U

SYS003 A2.02; Reactor Coolant Pump System - Ability to (a) predict the impacts of the conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

The second question implies that the correct answer for the first question is off.

Also, since there is no information given, what in the stem would let the applicant know that the plant is not aligned via backcharge of the main transformer? You state that this is one of the normal configurations.

This does not appear to be SRO only. The first part is plant knowledge and the ROs would have a general idea of what is contained in the EOP tabs.

Significantly changed second part to ask allowed CDR per the procedure.

Add IAW EOP. This is now SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 90 H

2 N

S SYS103 2.1.31; Containment System - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

K/A is met.

91 H

2 N

E SYS002 2.2.40; Reactor Coolant System - Ability to apply Technical Specifications for a system.

K/A is met.

Provide plant mode for completeness.

General comment: Do you want to provide equipment names with their ID numbers? Not required.

Mode added. Equipment names are not desired. AOPs and EOPs do not use the noun names at ONS. Ops agreed with this. SAT.

92 H

2 N

E SYS014 A2.06; Rod Position Indication System - Ability to (a) predict the impacts of the loss of LVDT on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is kind of met.

You really are not using your procedures to mitigate the consequences when you are just determining the frequency of the required surveillance.

A better tack might be to have this occur 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after a major up-power with the controlling rods still inserted. Give data that shows they meet SDM. Later give data that shows that you dont meet SDM. Then ask ask what to do.

Question reworded. Now second part now requires the decision on what procedures to use. SAT.

93 H

3 N

E SYS072 2.4.41; Area Radiation Monitoring System - Knowledge of the emergency action level thresholds and classifications.

K/A is met.

Editorial comment: sheared, seals, and saturated do not need to be capitalized.

Corrected as recommended. SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 94 F

2 X

N E

GEN 2.1.18; Ability to make accurate, clear, and concise logs, records, status boards, and reports.

K/A is met.

A better first part of the question might be to ask who can correct a log entry. (Step 5.15.2.d). As written is weak. A RO would know the answer.

Corrected as suggested.

Typo. Corrected. SAT.

95 H

2 N

S GEN 2.1.32; Ability to explain and apply system limits and precautions.

K/A is met.

96 F

2 M

E GEN 2.2.19; Equipment Control - Knowledge of maintenance work order requirements.

K/A is met.

Change it such that it requires an Air Operated valve as a tagout boundary. This should make it OM approval required.

Still looking for new second part. Rewrote question. Now SAT.

97 F

2 N

E GEN 2.2.7; Equipment Control - Knowledge of the process for conducting special or infrequent tests.

K/A is met.

Consider changing CRS to Reactor Engineering Supervisor (or equivalent.

Not someone considered senior management).

Corrected as suggested. Added clarification to ensure that lower member of crew cant perform if OM is present. Also revised to ask lowest level of authorization.

Change to should and lowest level of management. SAT.

98 H

3 B

S GEN 2.3.15; Radiation Control - Knowledge of radiation monitoring systems, such as fixed radiation monitors and l alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A is met.

Add to say the audible alarm associated with on response D.

Revised as suggested. SAT.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only 99 H

2 N

S GEN 2.4.1; Emergency Procedures/Plan - Knowledge of EOP entry conditions and immediate action steps.

K/A is met.

100 H

2 M

E GEN 2.4.50; Emergency Procedure/Plan - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

K/A is met.

AP-32 is not entered until Letdown is actually lost. Therefore it is not plausible.

Letdown isolates at 135 F. Given is 138 F. SAT.

SRO RO UNSAT Questions 4 / 16%

3 / 4%

Bank Questions 2 / 8%

23 / 31%

Modified Questions 4 / 16%

10 / 13%

New Questions 19 / 76%

42 / 56%

Memory Questions 5 / 20%

33 / 44%

C/A Questions 20 / 80%

42 / 56%

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility:

Oconee Nuclear Station Date of Exam:

12/18/13 Exam Level: RO/SRO Initials Item Description a

b c

1.

Clean answer sheets copied before grading N/A 2.

Answer key changes and question deletions justified and documented 1t.

3.

Applicants scores checked for addition errors (reviewers spot check > 25% of examinations)

4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail

5.

All other failing examinations checked to ensure that grades are justified r

6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of (if

\\L questions_missed by half or more of the_applicants Printed Name/Signature Date

a. Grader Ken Schaaf / Q, 67

b. Facility Reviewer(*)

NA

c. NRC Chief Examiner (*)

Dad Lanyi /

d. NRC Supervisor (*)

Malcolm Widmann /

(*)

The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-201, Rev. 9 Examination Outline Quality Checklist Form ES-201-2 Facility:

Oconee Unit 1,2, and 3 Date of Examination: December 2013 Initials Item Task Description

a b*

c#

a.

Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

b.

Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

T c.

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

d.

Assess whether the justifications for deselected or rejected K/A statements are appropriate.

2.

a.

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

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 M

compromising exam integrity, and ensure that each applicant can be tested using at least one new or U

significantly modified scenario, that no scenarios are duplicated from the applicants= audit test(s), and L

that scenarios will not be repeated on subsequent days.

T 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.

3.

a.

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

1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among W

the safety functions as specified on the form I

2) task repetition from the last two NRC examinations is within the limits specified on the form T

3) no tasks are duplicated from the applicants= audit test(s) 4)

the number of new or modified tasks meets or exceeds the minimums specified on the form 5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria 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

2) at least one task is new or significantly modified 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.

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

exam sections.

F4

G b.Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

E N

cEnsure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

d.Check for duplication and overlap among exam sections.

e.Check the entire exam for balance of coverage.

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

Printed Name/Signature Date

a. Ahor

. C L%

4 A /4 c24

b. Facility Reviewer (*)

.L/i4-

c. NRC ChiefExaminer#)t.

Note:# Independent NRC reviewer initial items in Column Acs; chief examiner concurrence required.

ES-401 PWR Examination Outline Form ES-401-2 Facility:

Date of Exam:

RD K/A CaoyPomts

SRO-Dnly_Points Tier Group T

K K

K K

K KAAAA G

A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total 1.

1 3

3 3

3 3

3 18 3

3 6

Emergency &

Abnormal 2

+/- j_ 1.

N/A I

N/A 2

9 2

2 4

Plant Evolutions Tier Totals 4

4 5

5 4

5 27 5

5 10 1

33332232322 28 2

3 5

2.

Plant 2

1 1

1 1

0 1

1 1

1 1

1 10 1

0 2

3 Systems Tier Totals 4

4 4

4 2

3 4

3 4

3 3

38 3

5 8

3. Generic Knowledge and Abilities 1

2

[

3 4

10 1

2 3

4 7

Categories I

3 L

2 2

2 2

1 2

Note:

1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RD 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 RD 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 RD and SRO ratings for the RD 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 RD and SRD-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 SRD selections to K/As that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

- Tier 1/Group 1 (RO I SRO)

E/APE # / Name / Safety Function K

K K

A A2 G

K/A Topic(s)

IR 1231

007EK1.06; Knowledge of the operational 000007 (BW/E02&E1 0; CE/E02) Reactor X

implications of the relationship of emergency Trip

- Stabilization

- Recovery / I feedwater flow to S/C and decay heat removal following reactor trip as it applies to the reactor trip.

OO8AK1.01; Knowledge of the operational 000008 Pressurizer Vapor Space X

implications of the thermodynamics and flow 3.2 Accident / 3 characteristics of open or leaking valves as they apply to a Pressurizer Vapor Space Accident.

X OOBAG2.2.37; Ability to determine operability 4.6 and/or availability of safety related equipment.

009EK2.03; Knowledge of the interrelations 000009 Small Break LOCA / 3 X

between the small break LOCA and the S/Cs.

30

O11EA1.14; Ability to operate and monitor the 000011 Large Break LOCA / 3 X

Subcooling margin monitors as they apply to a Large Break LOCA.

000015/17 RCP Malfunctions/4 X

015AG2.4.45; Ability to prioritize and interpret 4.1 the significance of each annunciator or alarm.

015AA2.10; Ability to determine and interpret 3.7 When to secure RCPs on loss of cooling or seal injection as it applies to the Reactor Coolant Pump Malfunctions (Loss of RC Flow).

000022 Loss of Rx Coolant Makeup / 2

025AK1.01; Knowledge of the operational 000025 Loss of RHR System 14 X

implications of the loss of RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System.

025AG2.4.45; Ability to prioritize and interpret X

the significance of each annunciator or alarm.

4.1 026AK3.03; Knowledge of the reasons for the 000026 Loss of Component Cooling X

guidance actions contained In EOP for Loss of 4.0 Water / 8 CCW as they apply to the Loss of Component Cooling Water.

027AK2.03; Knowledge of the interrelations 000027 Pressurizer Pressure Control X

between the Pressurizer Pressure Control 2.6 System Malfunction / 3

Malfunctions and Controllers and positioners.

000029 ATWS/1

038EG2.2.38; Knowledge of conditions and 000038 Steam Gen. Tube Rupture) 3 X

limitations in the facility license.

BEO5EK3.2; Knowledge of the reasons for 000040 (BW/E05; CE/E05; W/E12)

X normal, abnormal and emergency operating 3.5 Steam Line Rupture

- Excessive Heat procedures associated with (Excessive Heat Transfer / 4 Transfer) as they apply to the (Excessive Heat Transfer).

000054 (CE/E06) Loss of Main X

054AA1.04; Ability to operate and / or monitor 4.4 Feedwater / 4 HPI, under total feedwater loss conditions as it applies to the Loss of Main Feedwater (MFW).

054AA2.03; Ability to determine and interpret x

the conditions and reasons for AFW pump 4.2 startup as they apply to the Loss of Main Feedwater (MFW).

=

055EA2.03; Ability to determine or interpret 000055 Station Blackout / 6 X

Actions necessary to restore power as they 39 apply_to_a_Station_Blackout.

056AA2.43; Ability to determine and interpret 000056 Loss of Off-site Power / 6 X

the Occurrence of a turbine trip as it applies to 39 the Loss of Offsite Power.

057AA1.06; Ability to operate and / or monitor 000057 Loss of Vital AC Inst. Bus/6 X

Manual control of components forwhich automatic control is lost as they apply to the Loss_of Vital_AC_Instrument_Bus.

O5BAA2.01; Ability to determine and interpret 000058 Loss of DC Power / 6 X

that a loss of dc power has occurred and 4.1 verification that substitute power sources have come on line as it applies to the Loss of DC Power.

000062 Loss of Nuclear Svc Water! 4

065AA2.05; Ability to determine and interpret 000065 Loss of Instrument Air! 8 X

when to commence plant shutdown if instrument air pressure is decreasing as it applies_to_the_Loss_of_Instrument Air.

W!E04 LOCA Outside Containment / 3

W!E1 1 Loss of Emergency Coolant Recirc./4

BW!EO4EK3.01; Knowledge of the reasons for BW!E04; W!E05 Inadequate Heat X

the facility operating characteristics during Transfer - Loss of Secondary Heat Sink! 4 transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics as they apply to the Inadequate Heat_Transfer.

077AK2.03; Knowledge of the interrelations 000077 Generator Voltage and Electric X

between Generator Voltage and Electric Grid 3.0 Grid Disturbances / 6 Disturbances and sensors, detectors, indicators.

BE1OEG2.4.31; Knowledge of annunciators BE1O Post-Trip Stabilization X

alarms, indications or response procedures.

42 B/EO2EG2.2.3; (multi-unit license) Knowledge B!E02 Vital System Status Verification X

of the design, procedural, and operational 3.8 differences between units.

K/A Category Totals:

3 3

3 3

3/3 3/3 Group Point Total:

18/6

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnorm Plant Evolubons -Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K

K K

A A2 G

K/A Topic(s)

IR 1

231 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1

000005 Inoperable/Stuck Control Rod / 1 005AA2.03; Ability to determine and interpret the required actions if more than one rod is stuck or inoperable as they apply to the Inoperable /

Stuck Control Rod.

000024 Emergency Boration / 1 000028 Pressurizer_Level_Malfunction_/_2 000032 Loss of Source Range NI / 7 032AK3.01; Knowledge of the 3.2 reasons for startup termination on source-range loss as it applies to the Loss of Source Range Nuclear Instrumentation.

000033 Loss of Intermediate Range NI / 7

000036 (BW/A08) Fuel Handling Accident / 8

000037 Steam Generator Tube Leak / 3 037AA1.11; Ability to operate and /

or monitor pressurizer level indication as it applies to a Steam Generator Tube Leak.

000051 Loss of Condenser Vacuum 14 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X

060AG2.2.36; Ability to analyze the 3.1 effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for

operations.

00006 1 ARM System Alarms / 7 000067 Plant Fire On-site /8 X

067 AG2. 1.20: Ability to execute 4.6 procedure steps.

000068 (BW/A06) Control Room Evac. / 8 X

068AG2.4.3: Ability to identify post-3.9 accident instrumentation.

000069 (W/E14) Loss of CTMT Integrity / 5 000074 CJV/E06&E07) Inad. Core Cooling / 4

000076 High Reactor Coolant Activity / 9 076G2.3.5: Ability to use radiation 2.9 monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E1 3 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BAO1AA2.1; Ability to determine and interpret the facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the (Plant Runback).

BW/A02&A03 Loss of NNI-XIY / 7 X

BA03AK1.3; Knowledge of the 3.0 operational implications of annunciators and conditions indicating signals, and remedial actions associated with the (NNI-Y)

as they apply to the (Loss of NNI-Y).

BW/A04 Turbine Trip / 4 BWA04A1.92; Ability to operate 3 2 and / or monitor the operating behavior characteristics of the facility

as they apply to the Turbine Trip.

BW/A05 Emergency Diesel Actuation /6 X

BAO5AA2.l ; bilit to determine and interpret facility conditions and selection of appropriate procedures during abnormal and emergency operations as they apply to the

(Emergency Diesel Actuation).

BW/A07 Flooding / 8 BW/A08 Refueling Canal Level Decrease /8 BW/E03 Inadequate Subcooling Margin /4 X

BEO3EK2. 1; Knowledge of the interrelations between the (Inadequate Subcooling Margin) and Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BW/E08; W/E03 LOCA Cooldown

- Depress. / 4 BWEO8EK3.01; Knowledge of the reasons for the facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics as they apply to the LOCA Cooldown.

BW/E09; CE/Al 3; W/E09&El0 Natural Circ. /4 BW/E13&E14 EOP Rules and Enclosures CE/All; W/E08 RCS Overcooling

- PTS /4 CE/Al 6 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:

1 1

2 2

1/2 Group Point Total:

9/4

ES-401 4

Form ES-.401-2 ES-401 PWR Examination Outline Form ES-401-2

Dt Systems -ller2/Grqypj/ SRO)

=

System # / Name K

K K

K K

K A

A2 A

A G

K/A Topic(s)

IR 234561 34 003K5.02; Knowledge of the 003 Reactor Coolant Pump X

operational implications of effects of 2.8 RCP coastdown on RCS parameters as they apply to the RCPS.

003A2.02; Ability to (a) predict the x

impacts of the effects of conditions 39 which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP:

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

004A1.06; Ability to predict and/or 004 Chemical and Volume X

monitor changes in parameters 3.0 Control (to prevent exceeding design limits) associated with operating the CVCS controls including VCT level.

004G2.2.3; (multi-unit license)

X Knowledge of the design, procedural 3.9 and operational differences between units.

005K6.03; Knowledge of the effect of 005 Residual Heat Removal X

a loss or malfunction on the RHR 2.5 heat exchanger will have on the RHRS.

X 4.2 005G2.4.47; Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

006G2.4.45; Ability to prioritize and 006 Emergency Core Cooling X

interpret the significance of each 4.1 annunciator_or_alarm.

007G2.2.36; Ability to analyze the 007 Pressurizer Relief/Quench X

effect of maintenance activities, such 3.1 Tank as degraded power sources, on the status of limiting conditions of operations.

X 007K3.01; Knowledge of the effect 3.3 that a loss or malfunction of the PRTS_will_have_on_containment.

008A2.04; Ability to (a) predict the 008 Component Cooling Water X

impacts of the PRMS alarm on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

01 0K4.03; Knowledge of PZR PCS 010 Pressurizer Pressure Control X

design feature(s) and/or interlock(s) 3.8 which provide for Over pressure control.

012A2.05; Ability to (a) predict the impacts of Faulty or erratic operation of detectors and function generators on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

012K4.09; Knowledge of RPS design feature(s) and/or interlock(s) which provide for separation of control and protection circuits.

012A2.06; Ability to (a) predict the impacts of failure of RPS signal to trip the reactor on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

012 Reactor Protection x

x x

3.1 2.8 4.7 013A3.02; Ability to monitor 013 Engineered Safety Features X

automatic operation of the ESFAS 4.1 Actuation including Operation of actuated equipment.

X 3.6 01 3K2.01; Knowledge of bus power supplies to ESFAS/safeguards

equipment control.

022 Containment Cooling X

022A4.04; Ability to manually 3.1 operate and/or monitor in the control room valves in the CCS.

X 022K2.01; Knowledge of power 3.0 supplies to the containment cooling 025 Ice Condenser 026 Containment Spray X

automatic operation of the CSS, 3.9 including verification that cooling water is supplied to the containment spray_heat_exchanger.

039 Main and Reheat Steam X

039A3.02; Ability to monitor 3.1 automatic operation of the MRSS, including isolation of the MRSS.

039K5.08; Knowledge of the 3 6 X

operational implications of the effect of steam removal on reactivity as it applies to the MRSS.

059A1.03; Ability to predict and/or 059 Main Feedwater X

monitor changes in parameters 2.7 (to prevent exceeding design limits) associated with operating the MFW controls including Power level restrictions for operation of MFW pumps and valves.

059K1.04; Knowledge of the physical 3.4 connections and/or cause-effect X

relationships between the MFW and the S/GS water level control system.

061 Auxiliary/Emergency X

061 K5.05, Knowledge of the 2.7 Feedwater operational implications of feed line voiding and water hammer as they apply to the AFW.

062K1.02; Knowledge of the physical 062 AC Electrical Distribution X

connections and/or cause-effect 4.1 relationships between the ac distribution system and the EDIG.

063K4.01 Knowledge of DC 063 DC Electrical Distribution X

electrical system design feature(s) 2.7 and/or interlock(s) which provide for manual/automatic transfers of control.

064K1.04; Knowledge of the physical 064 Emergency Diesel Generator X

connections and/or cause-effect 3.6 relationships between the ED/G system and the DC distribution system.

073A1.01; Ability to predict and/or 073 Process Radiation X

monitor changes in parameters 3.2 Monitoring (to prevent exceeding design limits) associated with operating the ARM system controls including radiation levels.

073K3.01; Knowledge of the effect X

that a loss or malfunction of the ARM 3.2 system will have on the containment ventilation isolation.

076K3.01; Knowledge of the effect 076 Service Water X

that a loss or malfunction of the SWS 3.4 will have on the closed cooling water system.

078 Instrument Air X

078K2.02; Knowledge of bus power 3.3 supplies to the Emergency air

compressor.

103 Containment X

103A4.04; Ability to manually 3.5 operate and/or monitor in the control room phase A and phase B resets.

103G2.1.31; Ability to locate control X

room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

F KJA Category Point Totals:

f3

[ 2 [ 2 [

2/2 f2 [ 2/3 f Group Point Total:

[ 28/5

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 PlanL Systems

- Tier 2/Group 2 (RO / SRO)

System # / Name K

K K

K K

K A

A2 A

A G

K/A Topic(s)

IR 1

234561 34 001 Control Rod Drive 002 Reactor Coolant X

002G2.2.40; Ability to apply technical 4.7

specifications for a system.

011 Pressurizer Level Control 014A2.06; Ability to (a) predict the 014 Rod Position Indication X

impacts of the loss of LVDT on the 3.0 RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the

consequences.

015 Nuclear Instrumentation X

015G2.2.12; Knowledge of 3.7 surveillance procedures.

016 Non-nuclear Instrumentation X

016A3.02; Ability to monitor 2.9 automatic operation of the NNIS, including relationship between meter readings and actual parameter value.

017 In-core Temperature Monitor

027 Containment Iodine Removal 028 Hydrogen Recombiner andPurgeControl

029 ContainmentPurge

033 Spent Fuel Pool Cooling

034 Fuel Handling Equipment X

034A4.02; Ability to manually 3.5 operate and/or monitor in the control room neutron levels.

035 Steam Generator 041 K4.1 1; Knowledge of SDS design 041 Steam Dump/Turbine X

feature(s) and/or interlock(s) which 2.8 Bypass Control

provide for the T-aveiT-ref. program.

045 Main Turbine Generator 055 Condenser Air Removal 056A2.04; Ability to (a) predict the 056 Condensate X

impacts of the loss of condensate 2.6 pumps on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate_the_consequences.

068K6.10; Knowledge of the effect of 068 Liquid Radwaste X

a loss or malfunction on the radiation 2.5 monitors will have on the Liquid Radwaste_System.

071K3.04; Knowledge of the effect 071 Waste Gas Disposal X

that a loss or malfunction of the 2.7 Waste Gas Disposal System will have on the Ventilation system.

072A1.01; Ability to predict and/or 072 Area Radiation Monitoring X

monitor changes in parameters (to 3

prevent exceeding design limits) associated with operating the ARM system controls including radiation levels.

4.6 072G2.4.41; Knowledge of the X

emergency action level thresholds and classifications.

075 Circulating Water X

075K2.03; Knowledge of bus power 2.6 supplies to emergency/essential p

p

079K1.01; Knowledge of the physical 079 Station Air X

connections and/or cause-effect 3.0 relationships between the SAS and the lAS.

086 Fire Protection K/A Category Point Totals:

1 [

1 [

I 1

0 1

1 1/1 [

1 1

1/2 Group Point Total:

10/3

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

Form ES-401-3 LFacility:

Date of Exam:

Category KIA#

Topic RO SRO-OnIy IR IR Knowledge of industrial safety procedures (such as 2.1.26 rotating equipment, electrical, high temperature, high pressure, 1

caustic, chlorine, oxygen and hydrogen).

Conduct 2.1.34 Knowledge of primary and secondary chemistry limits 2.7 of Operations Knowledge of procedures, guidelines or limitations associated with reactivity management Ability to make accurate, clear and concise logs, records, status 2.1.18 boardsandreports.

3.8 2.1.32 Ability to explain and apply all system limits and precautions.

4.0 2.1.

Subtotal 3

2 2.2.13 Knowledge of tagging and clearance procedures.

4.1 2.2.12 Knowledge of surveillance procedures.

3.7 2

2 2 37 Ability to determine operability and/or availability of safety related 3 6 equipment.

Equipment Control 2.2.19 Knowledge of maintenance work order requirements.

3.4 Knowledge of the process for conducting special or infrequent 2.2.7 tests.

3.6 2.2.7 Subtotal 3

2 2.3.11 Ability to control radiation releases.

3.8 Ability to comply with radiation work permit requirements during 2.3.7 normal or abnormal conditions.

3.

2.3.15 Knowledge of radiation monitoring systems.

3.1 Radiation Control 2.3.

2.3.

2.3.

Subtotal 2

1 Knowledge of the bases for prioritizing safety functions during 2.4.22 abnormal/emergency operations.

3.6 Ability to recognize abnormal indications for system 4.

2.4.4 operating parameters which are entry-level conditions for Emergency emergency and abnormal operating procedures.

Procedures I Knowledge of EOP entry conditions and immediate action steps.

Plan

.4.

i 4.8 Ability to verify system alarm setpoints and operate controls 2.4.50 identified in the alarm response manual.

4.0 2.4.

2.4.

Subtotal 2

2 Tier3PointTotal 10 10 7

7

ES-401 Record of Reicted K!As Form ES-401-4 Tier /

Randomly Reason for Rejection Group Selected K/A 2/1 022K2.02 No containment chillers in plant.

2/2 056K5.02 No K/A importance value specified (< 2.5).

1/1 022AK3.07 B&W design does not isolate makeup pumps on loss of RC makeup.

1/1 029EA1.07 B&W design does not operate recirc valve switch on the makeup pump.

1/2 059AA1.02 Oconee Operations does not do anything with radioactive discharges. Not even signing the permit. No actions for ARMs associated with discharge.

1/2 037AA1.03 Oconee has no ioop isolation valves.

1/2 001AK3.02 No link in rod operability and continuous rod withdrawal in B&W digital rod system.

1/2 BAO8AG2.4.34 ROs have no duties outside the CR for lowering refueling canal level.

2/1 004A1.05 S/G level and pressure controlled by ICS based upon plant load.

Not operated manually.

2/1 061K5.02 Essentially the same as T1/G1 OO7EK1.06.

2/1 076K3.02 Service water is not connected to Secondary Closed Cooling Water.

2/1 039A2.02 Prevent oversampling. Requested by licensee as a difficult question to make at SRO level.

2/2 028G2.2. 12 Hydrogen recombiner has been removed.

3 2.2.41 Unable to write an SRO level question to this K/A.

2/1 003A2.05 RCPs seal leakoff does not go to VCT. Unable to match K/A