ML030560730

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Nov/Dec 2002-301 Exam Administrative Documents
ML030560730
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 01/20/2003
From: Ernstes M
Operator Licensing and Human Performance Branch
To: Gasser J
Southern Nuclear Operating Co
References
50-424/02-301, 50-425/02-301, ES-201, ES-201-1 50-424/02-301, 50-425/02-301
Download: ML030560730 (49)
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Text

Administrative Documents VOGTLE EXAM 2002-301 50-424 AND 50-425 NOVEMBER 26, &

DECEMBER 2 - 13, 2002

1. -, Exam Preparation Checklist ....... .... ES-201-1
2. /Exam Outline Quality Checklist .... .... ES-201-2
3. 'ý Exam Security Agreement ........ *.... ES-201-3
4. '-Administrative Topics Outline (Final) S.... ES-301-1
5. *-Control Room Systems and Facility Walk-through Test Outline (Final) ...... .................. ............... ES-301-2
6. 1 Operating Test Quality Check Sheet ES-301-3
7. v Simulator Scenario Quality Check Sheet. *ES-301-4
8. - Transient and Event Checklist ......... ES-301-5
9. v Competencies Checklist .............. ES-301-6
10. -/Written Exam Quality Check Sheet .....
  • ES-401-7 9 1/4-Wrt-t~ew~xaataaviewwark~heetrteese~e~_ ,.-.. .- ESM4019.
12. VWritten Exam Grading Quality Checklist ES-403-1
13. ,-Post-Exam Check Sheet .................... ES-501-1

/%Q'o'CL < O/J; 40 W.- I rrC-' 4F X4-1A-( O14 rtI.T S

Form ES-201-1 fR8.S1)

Facility: Vootle Date of Examination: 11/26/02, 12/02 - 13/02 Examinations Developed by: Facility (Operating) / NRC (Written)

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

-180 1. Examination administration date confirmed (C.1.a; C.2.a & b) K O'D

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

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

-120 4. Corporate notification letter sent (C.2.d) K O'D

[-90] [5. Reference material due (C.l.e; C.3.c)] K O'D

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

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

-45 8. Proposed examinations, supporting documentation, and K O'D reference materials due (C.1 .e, f, g & h; C.3.d)

-30 9. Preliminary license applications due (C.1.1; C.2.g; ES-202) K O'D due and assignment sheet prepared K O'D

-14 10. Final C.2.g; applications (C.1.1;license ES-202)

-14 11. Examination approved by NRC supervisor for facility licensee K O'D review (C.2.h; C.3J)

-14 12. Examinations reviewed with facility licensee (C.1 .j; C.2.f & h; C.3.g) K OD

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

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

15. Proctoring/written exam administration guidelines reviewed with K O'D

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

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

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

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

Applies only to examinations prepared by the NRC.

ES-201 Examination Outline Form ES-201-2 (R8,S1)

Quality Checklist Facilify:Vogpte Date of Examination: 11/26/02, 12/02-13/02 Initials Item Task Description a b* c#

1. a. Verify that the outline(s) fit(s) the appropriate model per ES-401. K O'D W

R b. Assess whether the outline was systematically and randomly prepared in accordance with K O'D I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. 191,11 T

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. K O'D E

N d. Assess whether the justifications for deselected or rejected. K/A statements are appropriate. K O'D

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

S I b. Assess whether there are enough scenario sets (and spares) to test the projected number and KO'D M mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)*,

and scenarios will not be repeated over successive days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and KO'D quantitative criteria specified on Form ES-301-4 and described in Appendix D.
3. a. Verify that: KO'D (1) the outline(s) contain(s) the required number of control room and in-plant tasks, W (2) no more than 30% of the test material is repeated from the last NRC examination,

/ (3)* no tasks are duplicated from the applicants' audit test(s), and T (4) no more than 80% of any operating test is taken directly from the licensee's exam banks.

b. Verify that: KO'D (1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.
c. Verify that the required administrative topics are covered, with emphasis on performance- Al KO'D based activities.
d. Determine if there are enough different outlines to test the projected number and mix of KO'D applicants and ensure that no items are duplicated on successive days. ill v
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the 1,-Y KO'D appropriate exam section.

E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. §. KOD E c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. A - KOD R I KO'D A d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage. 2*1 KO'D

f. Assess whether the exam fits the appropriate job level (RO or SRO).--j.
  • KO'D Printed Name / Signature Date
a. Author (Written) Kathleen O'Donohue/ 9A&5&2 11/20/02 Author (Operatinq)AI Sweat / ___ 2-_
b. Facility Reviewer ( ()Operating) Dan Scukanec /
c. NRC Chief Examiner (#) (Written) George Hopper/ ,m7 NRC Chief Examiner (#) (Operating) Kathleen O'Donohue 1 11/22/02
d. NRC Supervisor Michael Ernstes/ , &-zzh-2 Note:
  • Not applicable for NRC-developed examinations.
  1. Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.

C (1 (

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination uk rio i I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of /A'-o as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC.Furthermore, I am aware of the physical security measures and requirements (as documnented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2. Post-Examination To the best of my knowjed e 1l jddnot divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of LWý... From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE - SIGNATURE (2) DATENOTE 1).

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NOTES:

NUREG-1021, Revision 8, Supplement 1 24 of 24 0 0

ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)

Facility: Voatle Date of Examination: 12/02/02 Examination Level (circle one): ISRO/ USRO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Manning Requirements CONDUCT OF K/A: G2.1.1, G2.1.4 OPERATIONS Calculate Boron Addition Following Reator Trip with 3 Stuck CONDUCT OF Control Rods OPERATIONS K/A: G2.1.23 A.2 Review Clearance for Containment Spray Pump "A" EQUIPMENT K/A: G2.2.13 CONTROL A.3 Question Topic - License Requirements for Conducting a Waste Release with Inoperable Instrumentation and Administrative RADIATION Controls Ensuring Requirements Met.

CONTROL K/A: G2.3.6 Question Topic - Selection Process for Individuals Performing Emergency Entries into Radiation Fields Resulting in Exceeding Permissible Exposure Limits.

K/A: G2.3.4 A.4 Perform an Emergency Action Level Classification and EMERGENCY Recommend Protective Actions PLAN K/A: G2.4.41, G2.4.44

ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)

Facility: Voqtle Date of Examination: 12/02/02 Examination Level (circle one): RO Operating Test Number:

Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Manning Requirement CONDUCTOF K/A: G2.1.1, G2.1.4 OPERATIONS Calculate Boron Addition Following Reactor Trip with 3 stuck CONDUCT OF Control Rods OPERATIONS K/A: G2.1.23 A.2 Review Clearance for Containment Spray Pump, Train "A" EQUIPMENT K/A: G2.2.13 CONTROL A.3 Calculate Worker Dose Using Survey Maps RADIATION K/A: G2.3.4 CONTROL A.4 Make Emergency Notifications with Failure of the ENN EMERGENCY K/A: G2.4.43 PLAN

ES-301 Control Room Systems Form ES-301-2 (R8, Si) and Facility Walk-Through Test Outline Facility: Voqtle Date of Examination: 12/02/02 Exam Level (circle one): USRO Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Code* Safety Function a.

b. Manually Initiate Containment Spray A, S, M 5 K/A: 026A2.03, 069AA2.02 C.
d. Spurious CIA Response S, N 2 K/A: 002A2.12 e.
f. Bypass Containment Hi-1 Following a Loss of Heat Sink CR,L, D 7 K/A: 012A4.04 g.

B.2 Facility Walk-Through

a. Control Pzr Pressure and S/G Level from Shutdown Panel A,N 8 K/A:, 068AA1.03, 068AA1.28 b.

c Locally Isolate RCP Seals D, R 4P K/A: 003A4.01

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

ES-301 Control Room Systems Form ES-301-2 (R8, Si) and Facility Walk-Through Test Outline Facility: Voqtle Date of Examination: 12/02/02 Exam Level (circle one): RO / SRO(l) Operating Test No.:

B.1 Control Room Systems System / JPM Title Type Code* Safety Function

a. D/G 1A Parallel Operating with Failure of LubeOil A, S, N, L 6 K/A: 064A2.01, 064A2.03,
b. Manually Initiate Containment Spray A, S, M 5 K/A: 026A2.03, 069AA2.02 C. Start a Reactor Coolant Pump A, S, M,L 4P K/A: 002A1.05
d. Spurious CIA Response S,N 2 K/A: 004A2.12
e. Initiate RCS Boration using BTRS D, S 1 K/A:004A4.07
f. Bypass Containment Hi-1 Following a Loss of Heat Sink CR, L, D 7 K/A: 012A4.04
g. Reduce Containment pressure following a CVI CR, S 8 K/A: 029A1.03 B.2 Facility Walk-Through
a. Control Pzr Pressure and S/G Level from Shutdown Panel A,N 8 K/A:, 068AA1.03, 068AA1.28
b. TDAFW Local Manual Control w/o DC power D 4S K/A: 061A2.03, 061A2.04 c Locally Isolate RCP Seals D, R 4P K/A: 003A4.01
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

11/22/02 FRI 10:20 FAX IZ002 OS-301 Operating Test Quality Checklist Form ES-301-3 (R8, Sl)

Fa'fIyl, VE0-P Date of Examination.; 01L ldQooperating Test Number.

0 Initials

1. GENERAL CRITERIA a b, ,
a. The operating test conforms with the previously approved outline; changes are consistent with A At 4) sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
b. Thers is no day-to-day repetition between this and other operating tests to be administered .

durin this examination.

0. The operalin test shall not duplicate items fram the aplicants' audit test(s)(see Section D* a).
d. Overlap with the written examination and between operating test categories is within acceptable Ilimits.

AlA £4O

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.
2. WALK-THROUGH (CATEGORY A & BDCRIlERIA -

a- Each JPM Includes the followlng. 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 Ifdeemed 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, ifapplicable b.

C.

The prescripted questions in Category A are predominantly open reference and meet the criteria inAttachment I of ES-301.

Repetition from operating tests used during the previous licensing examination Is within acceptable limits (30% for the walk-through) and do not compromise test integrity.

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d. At least 20 percent of the JPMS on each test are new or significantly modified. Al -

S. SIMULATOR (CATEGORY C) CRITERIA a, The associated simulator operating tests (scenario sets) have been reviewed inaccordance with Form ES-W01-4 and a copy Is attached.

Printed Name/ Signature Date a-Author 4( L e al rs-,-

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b. Faclity Revlewer(* O t tEL Sei4KA /a 4 / 2a01-0
c. -NRC Chief Exminer (#) Ia le,4 //2
d. NRC Supervisor Al : . c 1% /'* .* t NOTE:
  • The facility signature is not applicable for NRC-developed tests
  1. Independent NRC reviewer Initial items in Column "*;" chief examiner concurrence required.

(D 4 n rc-

FRI 10:20 FAX la003 11/22/02 ES-301 Simulator Scenario Quality Checklist Form ES-SO1- (R8, Si)

Fawily oW P Date of Exam: .J*ISC.. A2P ". .Scenario Numbers; /"/.Operating Test No.;

QUALITATIVE ATTRIBUTES Initials ritaonb utI o#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but It does not cue to operators into emcted events.
2. The scenarios consist mostly of related events.

S. Each event deascrip(on 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)

Awl the event termination point (ifapplicable)

4. No more than one non-mechanistlo failure (e.g., pipe break) is incorporated Into the scenario without a credible preceding incident such as a seismic event.
5. The and allows the examination team to obtain events are valid with regard to physics and thermodynamics.
0. Sequencing and timing of events Isroaaotable, complete evaluation results commensurate with the scenari o2jectives.
7. Iftime compression techniques are used, the scenario summary clearly so indicates. Operators time constraints. Cues are given.sufficient time to carry out expected activities without undue have

/

8. The simulator modeling is not altered. ___
9. The scenarios have been validated. Any open simulator performance deficiencies scenarios.

evaluated to ensure that functional fidelity is maintained while running the planned have been Al 10 Every operator will be evaluated usifl at least one new or significantly, modified scenario.

other scenarios have been altered in accordance with Section DA4 of ES-301. . ..

All 111. All individual operator competencties can be evaiuated, as verified using Form ES-301 .$.(Submit the form along with the simulator scenarios).

Al

12. -specified Each applicant will be on Form significantly ES-aOl involved Z*(submit the form withminimum inthe number the simulator of transients and events scenarios).

13, The level of difficulty is appro riate to support licensin decisions for each crew position. ____

r kRGET OUANTITAT1VE ATrRIBUTES (PER SCENARIO; SEE SECTION D.4.0) Actual Attributes ._ --

1. Total malfunctions (5-8) 6 1i 5' 9.. Malfunctions after tiOP entry (1-2) ________

S. Abnormal events (2-4)

/-U______

. Maiorftransienlts It1-2)

5. EOPs entered/requiring substantlve actions (1 -2) 1/ /
0. P con~ftlinencies requiilng ubstan§tive actions(0-)
7. Critical tasks (2-3)

11/22/02 FRI 10:21 FAX a004 M,-301 Simulator Scenario Quality Checidist Form ES-301-4 (R8, $1)

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

Xfnrtln* pl31p*."qi

--- Initial Exam S :PaQe (8 1 of 18 ES30 200nd0 Initit ExamstFr Trnsen OPERATING TEST NO Scenerio 1, Crew 1, Crew 2, Crew 5.

A.licant Ev.lution Minimum Scenario Number Sype iye Number y pBoP RO2BoP RO3BOP RO-BO Reactivity 1 1 0 Normal 1 1 0 RO1 Instrument/ 4 2 2 Component F Major 1 1 1 Reactivity 1 1 0 Normal 0 1 0 As RO Instrument 2 2 2 omp onent Major 1 1 1 SRO- 1 Reactivity 0 0 Normal 1 1 As SRO Instrument!/ 2 2 Component Major 1 1 Reactivity 0 Normal 1 SRO-U1 en 2 CotmrupMonern1 I Major Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: Dan Scukanec NRC Reviewer: Kathleen O'Donohue I

ES-30l Transient and Event Checklist Form ES-301-5 (R8, Si)

Vnntl. 2002-aol Initial Exam S :Pacie (8 2 of 18 ES30 200nd0 Initit ExamstFr Trnsen OPERATING TEST NO Scenario 2, Crew 3 Applicant Evolution Mimnim ur Scenario Number Iype Type Number RoI BOP 2

Ro 80P 3

Ro BOP RO*'BO Reactivity 1 1 Normal 1 1 R01 Instrument 4 2 1Component

__ _ __ _ _ Major 11 Reactivity 1 Normal 0 As RO Instrument /2 omp onent Major 1 SRO-l 1 Reactivity 0 0 Normal 1 1 As SRO lnstrument/ 2 2 Componentt Major 1 1 Reactivity 0 0 Normal 1 0 SRO-Ul Instruent/ 2 2 Major 1 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: Dan Scukanec NRC Reviewer: Kathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

Vogtle 2002-301 Initial Exam :Page 3 of 8 OPERATING TEST Scenario 2, Crew 1, Crew 2 Applican t Evlution ljn Scenario Number Io1 BOP no2Bop Ro3 BoP R0-BO Reactivity 1 0 Normal 1 0 RO1 Instrument / 4 2 Component A____ Major 1 1 Reactivity 1 1 Normal 0 1 As RO Instrument/ 2 2 omp onent Major 11 SRO-I 1 Reactivity 0 1 Normal 1 1 As SRO Instrument / 2 2 Component Major 11 Reactivity 0 Normal 1 SRO-U1 Instrumrent/ 2 omponant 1 I Major 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Wheneverpractical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: -Dan Scukanec I

NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

Vogtle 2002-301 Initial Exam :Page 4 of 8 OPERATING TEST Scenario 3 Crew 4.:

Applicant Evolution Minimum Scenario Number Type Type Number oo3BoP Ro4o nol01 BO no2aop R0B PR08 Reactivity 1 1 0 Normal 1 1 0 R01 Instrument 4 2 2 Component Major 11 1 Reactivity 1 Normal 0 As RO Instrument / 2 Component Major1 1

SRO-I Reactivity 0 Normal 1 As SRO Instrument/ 2 Component Major 1 Reactivity 0 0 Normal 1 1 SRO-Ul Instrument / 2 2 Component

__ _ _ _ __ Major11 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: Dan Scukanec I NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, S1)

Vogtle 2002-301 Initial Exam :Page 5 of 8 OPERATING TEST Scenario 3 Crew 2 Applicant Ev.lution urninum Scenario Number RolyoP gO2mRP RO3BOP RO*BO Reactivity 1 0 Normal 1 0 RO1 Instrument / 4 2 Component

____________ Major11 Reactivity 1 1 Normal 0 1 As RO Instrument / 2 2 Component Major 1 -- 1 SRO-I 1 Reactivity 0 0 Normal 1 1 As SRO Instrument / 2 2 Component Major 1 1 Reactivity 0 Normal 1 SRO-U1 Instrument/ 2 CotmrupMoneant 1 Major 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: -Dan Scukanec I

NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, S1)

Vogtle 2002-301 Initial Exam :Page 6 of,,

OPERATING TEST Scenario 3 Crew3 Applicant Evolution Minimum Scenario Number Type Type Number Oo3sOP 2 3 RO4BO Rol Bop Ro BOP I O B P f0 Reactivity 1 0 Normal 1 0 RO1 Instrument / 4 2 Component Major Reactivity 1 I1 Normal 0 1 As RO Instrument / 2 2 Component Major 1 1 SRO-l 1 Reactivity 0 Normal 1 As SRO Instrument / 2 Component

__ _ _ _Major 1 Reactivity 0 0 Normal 1 1 SRO-U1 Instrument/ 2 2 Component Major 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Wheneverpractical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: -Dan Scukanec NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, S1)

Vogtle 2002-301 Initial Exam :Page 7 of 8 OPERATING TEST Scenario 4 Crew 5 Applicant Evolution Minimum Scenario Number Iype Type Number 1o3Bop RO4BO nolsop no2aop noB PR00 Reactivity 1 1 Normal 1 1 RO1 Instrument / 4 2 Component Major 11 Reactivity 1 Normal 0 As RO Instrument / 2 Component Major 1 SRO-l 1 Reactivity 0 0 Normal 1 1 As SRO Instrument 2 2 Component Major 1 1 Reactivity 0 Normal 1 SRO-U1 Instrument! 2 Component Major 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: -Dan Scukanec NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

\Inntln POAP-."ol3 Initisil Exam S :Paqe (8 6 of18 ES30 200nd0 Initit Examst tiesen Fr OPERATING TEST Scenario 4 Crew 1 Aplicant Evolution Minimum Scenario Number Type Type Number 1O4o 2 3 R01 BOP no BoP Ro BOP R02 P

Reactivity 1 0 Normal 1 0 RO1 Instrument / 4 2 Component Major 1 Reactivity 1 1 Normal 0 1 As RO Instrument/ 2 2 Component Major 1 1 SRO-I 1 Reactivity 0 0 Normal 1 1 As SRO Instrument/ 2 2 Component Major 1 1 Reactivity 0 Normal 1 SRO-U1 Instrument/ 2 Component Major 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Wheneverpractical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: -Dan Scukanec NRC Reviewer: NKathleen O'Donohue

ES-301 Transient and Event Checklist Form ES-301-5 (R8, S1)

Vogtle 2002-301 Initial Exam :Pace 8 of 8 OPERATING TEST Scenario 4, Crew 4 Apflicant Ev..lution Mlnimum Scenario Number ype Ie Neumber Rol BOP RO2 20P RO3 BOP nC*ao Reactivity 1 1 0 Normal 1 1 0 RO1 Instrument/ 4 2 2 Component Major 111 Reactivity 1 Normal 0 As RO Igstrument 2 omp onent Major 1 SRO-I 1 Reactivity 0 Normal 1 As SRO Instrument/ 2 Component Major 1 Reactivity 0 0 Normal 1 1 SRO-U1 Instrent/ 2 2 Major 1 1 Instructions: (1) Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2) Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3) Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirement.

Author: Dan Scukanec NRC Reviewer: Kathleen O'Donohue

ES-301 Competencies Checklist Form ES-301-6 (R8, $1)

SRO RO BOP Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 4 5,6,7 Understand and Interpret 4 3 V 4,5,6.7 5.6.8 4,6,7 3,4,7 3,4,6,7 3,4,8 3,5,7 Annunciators and Alarms Diagnose Events 7 V 4,5,6,7 2,56 4,5,7 3,4 3,4,6,7 3,4,8 3,5,7 5,6 and Conditions 2,3.5, 2,5.6.

Understand Plant 3,4,5 1,2,4, 5,6,8 2,3,4, 6,7 2,3,6.

7 2.4,5,6

,7 1,25, 6,7,8 1,24 6.7 1,2,3 4,7 2,3,4,6

,7 3,4.7, a 7 7 and System Response 8 2 2 Comply W ith and 1,2.3.

4,5,5, 1.2.3, 4,5,5, 2.3,4, 5,6,7 2,4,5, 6,7 1.2 1,6.7.

8 1.2 1,2,3 2 Use Procedures (1) 7 5 Operate Control 1,2,4,5

.6,7 1,2,5, 7,8 1,2,4, 6,7 1,2,3 4,7 2,3,4,6 3,4.7. 2.3,5, 2,5,6,

,7 8 7 7 Boards (2)1 11 1 3,4,7. 2,3,5, 5,7 Communicate and 1,2,3.

4,5,6. 1:2:3:

4.5.7. 2.3A 5,6,7 2.3,4, 5,6,7 2,4,5,6

,7 1,2,5, 7,8 2,4,6.

7 1,2,3 4,7 2,3,4,6

.7 8 7 Interact With the Crew 7 8 Demonstrate Supervisory 1,2,3, 4,5,6, 1.2.3.

4.5.6.

2.3.4.

5,6,7 2.3.4, 5,6,7 Ability (3) 7 7. 6 1

Comply With and 3,4 2,3 6 4.5,6 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:

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

Author: rfa abulation) DAL) .c..ai. r NRC Reviewer: 14a4 Lp 1, at*)t LA ,/---

ES-401 Written Examination Form ES-401-7 (R8, Si)

Oualitv Checklist Facility:Vogtle Electric Generating Plant Date of Exam: 11/26/02 Exam Level: RO Initial

  • a b 4'/-b ,#

Item Description

1. Questions and answers technically accurate and applicable to facility
2. a. NRC K/As referenced for all questions C / *
b. Facility learning objectives referenced as available
3. RO/SRO overlap is no more than 75 percent, and SRO questions are appropriate (9 per Section D.2.d of ES-401 / 1
1. Question selection and duplication from the last two NRC licensing exams appears consistent with a systematic sampling process
5. Question duplication from the license screening/audit exam was controlled as inlicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; or exam was completed before the license exam was started; or

- the audit

- 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 modified); enter the actual question AC 13 __

distribution at right I`

7. Between 50 and 60 percent of the questions on Memory C/A the exam (including 10 new questions) are written at the comprehension/analysis level; 48 52 enter the actual question distribution at right
8. References/handouts provided do not give away answers nI/,
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 ES, Appendix B, guidelines ,
11. The exam contains 100, one-point, multiple choice items; the total is correct and cover sheet 63 /

agrees with value on Printed Name / nature Date

a. Author Kathleen O'Donohue/ .
b. Facility Reviewer (*) -2/,

z

c. NRC Chief Examiner (#),9eorge Hopper
d. NRC Regional Supervisor"V.&ichael Ernstes ,, /,

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.

ES-401 Written Examination Form ES-401-7 (R8, S$)

Quality Checklist Qualitv Checklist Facility:Vogtie Electric Generating Plant Date of Exam: 11/26/02 Exam Level: SRO Initial a b *c Item Description

1. Questions and answers technically accurate and applicable to facility j L
2. a. NRC K/As referenced for all questions
b. Facility learning objectives referenced as available 4*
3. RO/SRO overlap is no more than 75 percent, and SRO questions are appropriate per Section D.2.d of ES-401
1. Question selection and duplication from the last two NRC licensing exams appears consistent with a systematic sampling process
5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

Žthe 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, - I "

and the rest modified); enter the actual question 13 distribution at right A4_._

7. Between 50 and 60 percent of the questions on Memory C/A the exam (including 10 new questions) are written at the comprehension/analysis level; 44 56 enter the actual question distribution at rig ht
8. References/handouts provided do not give away answers
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 lustified
10. Question psychometric quality and format meet ES, Appendix B, guidelines
11. The exam contains 100, one-point, multiple choice items; the total is correct and agrees with value on cover sheet 0/1 rted NamDate
a. Author -Kathleen O'Donohue/ L/4- f -widO9ee,
b. Facility Reviewer (*) I. '  !,/.4 . I
c. NRC Chief Examiner (4t) GeorgeHopper 72
d. NRC Regional Supervisor 'hM tichael Ernstes/

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.

ES-403 Written Examination Grading Form ES-403-1 (R8, S1)

Quality Checklist Facility: Date of Exam: Exam Level: RO/SRO Initials Item Description a b c

1. Clean answer sheets copied before grading .. AL,.
2. Answer key changes and question deletions justified and documented 0
3. Applicants' scores checked for addition errors (reviewers spot check > 25% of examinations)
4. Grading for all borderline cases (80% +/- 2%) reviewed in detail - _
5. All other failing examinations checked to ensure that grades are justified
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants \/

Printed Name / Signature Date

a. Grader -

01- 0,1 n L /, // ____k.,

b. Facility Reviewer(*)
c. NRC Chief Examiner (*) "? F,,

'o'< J&o., ' //

d. NRC Supervisor (*) IG/I&C- E.a,,Vre/-,( ,.a //,d/oa

(*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

'ft/c ES-501 Post-Examination Check Sheet Form ES-501-1 (R8, S1)

Task Description Date Complete

1. Facility written exam comments or graded exams received and 1.4-2-10 2--

verified complete2

2. Facility written exam comments reviewed and incorporated and NRC grading completed, if necessary
3. Operating tests graded by NRC examiners 6+/-! 2Z.
4. NRC Chief examiner review of written exam and operating test grading completed 12-
5. Responsible supervisor review completed .2-6i 2
6. Management (licensing official) review completed 6 c
7. License and denial letters mailed __,
8. Facility notified of results e2
9. Examination report issued (refer to NRC MC 0610) /C
10. Reference material returned after final resolution of any appeals -/ _-/

ES-401 PWR RO Examination Outline ýoim £5-401-4 Facility: Vootle Date of Exam: SExam Level: RO ES-401tv Dat Exam:n ExammLevel:-4 PWRtl Eomiato K/A Category Points Tier Group Point K K2 K3I K4 IK K6I Al A3I A4I G Total 1

1. 1 2 3 4 0 15 2 16 16 Emergency & 3 17 17 Abnormal 2 4 3 1 5 11 Plant 3 1 0 1 1 0 0 3 3 Evolutions - -__

Tier 7 6 6 6 6 5 36 36 Totals 1 3 1 2 3 3 3 2 2 0 2 2 23 23 2.

Plant 2 131113 11 1 1 3 112 2 1 2 1 20 1 20 Systems 3 1 1 1 1 1 0 0 1 1 1 0 1 _ _ 8 1 8 Tier 7 3 6 5 5 4 5 4 3 4 46 51 51 Totals I .. .. .. ....... L.......-,L .i .. *I_______ ________

3. Generic Knowledge and Abilities Cat 1 Cat2 Cat3 Cat4 1 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6V The generic 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.

7. On the following pages,; enter the KJA numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

ES-401 PWR RO Examination Outline Form ES-401-4 ES-401 _Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 000005 Inoperable/Stuck Control Rod / 1 1 AK2.02 Knowledge of interrelationship between stuck rods and breakers, relays, 2.512.6 R disconnects, and control room switches (CFR 41.7, 45.7) 000015/17 RCP Malfunctions / 4 1 AK1.02 - Consequences of an RCPS failure(CFR 41.8 / 41.10 / 45.3) 3.7/4.1 B BW/EO9; CE/Al 3; W/E09&E10 Natural Circ. 4 1 EA2.2 - Adherence to appropriate procedures and operation within the 3.4/3.8 B limitations in the facility s license and amendments. (CFR: 43.5 / 45.13) 000024 Emergency Boration / 1 1 AK2.01 - Valves - (CFR 41.7 / 45.7) 2.7/2.7 B 000026 Loss of Component Cooling Water / 8 AK3.0l - Knowledge of the reasons for the following responses as they 3.2/3.5 B apply to the Loss of CCW: The conditions that will initiate the automatic opening 41.5,4T10 and/45.6 closing of the SWS isolation valves to the CCWS collers (CFR

/ 45.13) 000027 Pressurizer Pressure Control System 1 AK3.03 - Actions contained in EOP for PZR PCS malfunction (CFR 3.7/4.1 B Malfunction / 3 41.5,41.10 / 45.6 / 45.13) 000040 (BW/E05; CE/E05 W/E12) Steam Line 1 AG2.4.4 Ability to recognize abnormal indications for system operating 4.0/4.3 B Rupture - Excessive Heat transfer / 4 parameters which are entry level conditions for EOPs and AOPs (CFR 41.10, 43.2,45.6 CE/A1l; W/EO8 RCS Overcooling - PTS / 4 1 EA2.1 - Facility conditions and selection of appropriate procedures during 3.4/4.2 R abnormal and emergency operations.

(CFR: 43.5 / 45.13) 000051 Loss of Condenser Vacuum / 4 1 AA2.02 - Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 3.9/4.1 R 000055 Station Blackout / 6 1 EK3.02 - Actions contained in EOP for loss of offsite and onsite power (CFR 4.3/4.6 B 41.5 41.10/45.6/45.13) 000057 Loss of Vital AC Elec. Inst. Bus / 6 1 AA2.18 - Ability to determine and interpret the following as they apply to the 3.1/3.1 R Loss of Vital AC Instrument Bus: The indicator valve, breaker, or amper position which will occur on a loss of power (CAR: 43.5 / 45.13) 000062 Loss of Nuclear Service Water / 4 1 AG2A.24 - Knowledge of loss of cooling water procedures. (CFR: 41.10/ 3.3/3.7 B 45.13) 000067 Plant Fire On-site / 9 1 AK1.02 - Fire fighting (CFR 41.8 / 41.10 / 45.3) 3.1/3.9 B 000068 (BW/A06) Control Room Evac. / 8 1 AK3.18 - Knowled eof the reasons for the following responses as they 4.2/4.5 B apply to the ControT Room Evacuation: Actions contained in EOP for control room evacuation emergency task. (CFR 41.5,41.10 / 45.6 / 45.13) 000069 (W/E14) Loss of CTMT Integrity / 5 AK2.03 - Personnel access hatch and emergency access hatch (CFR 41.7 / 2.8/2.9 B 1 45.7) 000074 (W/E06&E07) Inad. Core Cooling / 4 1 EA2.2 - Ability to determine and interpret the following as they apply to the 3.3/3.9 R (Saturated Core Cooling) Adherence to appropriate procedures and operations within the limitations in the facility's license and amendments.

I (FR 43.5 / 45.13)

BW/EO31nadequate Suboýoling Margin / 4 000076 Hi ieac'tor latctv 9T I I I

ES-401 PWR R0 Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier l/Group 1 E/APE # / Name / Safety Function I K1 K2 K3 Al A2 G K/A Topic(s) I Imp. Points BW/At2&AOS Loss of NNiP IY /77 K/A Gategor Totals: 2 3 4 0 5 2 Group Point Total: 16 16

RO Examination Outline- Tier l /Group 2 Form ES-401-4 ES-401 Emergency andPWR Abnormal Plant Evolutions A2 G K/A Topic(s) Imp. Points E/APE # / Name / Safety Function K1 K2 K3 Al 3.5/3.8 B 000001 Continuous Rod Withdrawal / 1 1 AKI.05 - Knowledge of the operational implications of the foIlowina concepts as they apply to Continuos Rod Withdrawal: Effects of t irbine reactor power mismatch on rod control (CFR: 41.8/41-10/45.3) _

000003 Dropped Control Rod / 1 1 G2.4.49 - Ability to perform without reference to procedures those actions 4.0/4.0 B that require immediate operation of system components and controls. __

(CFR: 41.10/43.2/45.6)

?r 7 :BWzE02&Re1r CE02) Reactor Tip StbilliýT~a;*- ROe~wE r0* ;

8W/Aol Plant Runbackf 1 BW/A04Turbine Trip / 4 000008 Pressurizer Vapor Space Accident / 3 1 AK1.01 - Knowledge of the o erational implications of the following 3.2/3.7 B concepts as they apply to aoressurizer Vapor Spaceleaking Accident:

Thermodynamics and flow characteristics of open or valves (CFR 41.8 /41.10/ 45.3) interpret followlnaas the (CFR they apply to a 4.3/4.7 000009 Small Break LOCA 3 1 small

- Ability EA2.39break L CA: Adequate or to determine core colinge. 43.5 /45.13 1 EK2.02 Knowledge of the inter-relationship LB LOCA and pumps 2.6/2.7 B 000011 Large Break LOCA 3 W/E04 LaOC Outside Containment/ /3 systems, including primarp coolant, 3.7/4.0 B BW/E08; W/E03 LOCA Cooldown/Depress. / 4 1 EK2.2 emergency- Facility's coolant, theremoval heat decay heat removal systems, an relations betweente p roper operation of these systems to the operation of the facility. (CF R: 41.7 /Y45.7) 1 A - Desired operatina results during abnormal and emergency 3.7/4.2 B W/E1 1 Loss of Emergency Coolant Recirc. 4 situations. (CFR: 41.7 / 45.5/456 1 EK1.2 - Normal, abnormal and emergency operating procedures 3.4/4.0 R W/EO1 & E02 Rediagnosis & SI Termination / 3 associated with (Reactor Trip or Safcty Injection /yRdiagnoais). (CER:

41.8 /41.10/ 45.3) 000022 Loss of Reactor Coolant Makeup / 2 AG2. .32 - Ability to explain and apply all system limits and precautions. 3.4/3.8 B 0-00-0-2-2--- - ----- - - ---- - - - - - - -- - - u- C FR: 4 1.1 0 / 43 .2 / 4 5.1 2) 1 AK2.02 - LPI or Decay Heat Removal/RHR pumps (CFR 41.7 / 45.7) 3.2/3.2 B 000025 Loss of RHR System / 4 EA1.13 - Manual trip of main turbine (41.8/41.10/45.3) 4.1/3.9 B 000029 Anticipated Transient w/o Scram/ 1 of voltage changes on performance (CFR 41.8 / 41.10 / 2.5/3.1 B 000032 Loss of Source Range NI / 7 1 00--0--------------------------------- 45.3) - Effects AKi.01 000033 Loss of Intermediate Ran e NI / 71 AK3.07 - KnowledgeGeneratorof the reasons for the following responses as they 4.2/4.4 B 000037 Steam Generator Tube Leak / 3 Sapolv to the Steam Tube Leak: Actions contained in EOP for

/8 tube leak (CFR 41.5,41.10/45.6/45.13)

B LK 000038.SemG eao~b~utr/ 3.5/3.8 EG2.4.48 - Ability to interpret control room indications to veif thdtau 000054 (CE/E06) Loss of Main Feedwater / 4 and operation of system, and understand how 0 ertratin5n R 43.5/45.12) directives affect plant and svstem conditions.

PWR RO Examination Outline Form ES-401-41 ES-401 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points E/APE # / Name / Safety Function BW/E04; WIE05 Inadequate Heat Transfer - Loss 1 EA1.3 - Desired o eratinq results durng abnormal and emergency 3.8/4.2 B of Secondary Heat Sink uCFR

/,4-situations. 21.7/45.5/45.6 000058 Loss of DC Power/ 6 AAt.01 - Radioactive-liquid monitor (CFR 41.7 / 45.5 / 45.6) 3.5/3.5 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Re]. 9 000061 ARM System Alarms / 7 1 AA1.01 - Ability to operate and / or monitor the foliowng as they apply to 3.6/3.6 R the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation (CFR 41.7 / 45.5 45.6)

W/El6HighContainmentRada.o../.....

CEtE09 Functi'oIal R3e1ove1y 13 ro onetI 1_

,FK/A Category Point Totals: I 4 1 3Ii1 Ir1 r3 Group Point Total: T17 _____ F 171

PWR RO Examination Outline Form ES-401-4 ESI 0 ___________________________Emergency and Abnormal Plant Evolutions - Tier 1/Group3 G K/A Topic(s) Imp. Points E/APE # / Name / Safety Function K1 K2 K3 Al A2 000028 Pressurizer Level Malfunction / 2 /

000036 (BW/A08) Fuel Handling Accident 88 AK1.01 - Principle of cooling by natural convection CFR 41.8 /41.10 /45.3) 3.7/4.2 R 000056 Loss of Off-site Power//6

- Restoration of systems served by instrument air when pressure is lAA1.03 2.9/3.1 B 000065 Loss of Instrument Air/B regained (CFR 41.7 / 45.5/45.6)

BW/E13&E14 EOP Rules and Enclosures ]

BW/A05 Emergency Diesel Actuation 166 BW/AO7 Flooding/8 CE/A 6 Excess RCS Leakage/22 i 1 EK3.2 - Normal, abnormal and emergency peratin g procedures associated 2.9/3.3 R W/E1 3 Steam Generator Over-pressure / 4 with (Steam Generator Over pressure). (CFH:41.5/4110,45.6, 45.13)

W/E15 Containment Flooding / 5 K/A Category Point Totals: 1110 1 1 0I 0I GruuPoint Total:

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 001 Control Rod Drive 1 K1 .05 Knowled a of the physical connections 4.5/4.4 B and/or cause-effect relationship between the CRDS and the followinl systems: NIS and RPS (CFR 41.2 to 41.9"/45.7 to 45.8) 003 Reactor Coolant Pump A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a 3.7/3.9 R normal shutdown of an RCP (CFA: 41.5/

43.5/45.3 / 45/13) 004 Chemical and Volume Control K4.04 Knowledge of CVCS design features 3.2/3.1 R and interlocks that provide for manual/automatic transfers of controls (CFR 41.7) Ij 004 Chemical and Volume Control K5.04 Knowledge of the operational 2.8/3.2 R implications of 9e following concepts as they apply to the CVCS: Reason for hydrogen cover as in VCT (oxygen scavenge) (CFR:

41.5/ .7) 004 Chemical and Volume Control A2.12 Ability to (a) predict the impacts of the 4.1/4.3 B following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those malfunctions or operations: CIAS, SIAS (CFR: 41.5 / 43.5/

4.3 / 45.5) 004 Chemical and Volume Control manually operate and/or A4.07Abilitv tocontrol 3.9/3.7 B monitor in e room: Boration/dilution.

(CFR: 41.7 / 45.5 to 45.8) 013 Engineered Safety Features Actuation K6.01 Knowledie of the effect of a loss or 2.7/3.1 R malfunction on the sensors and detectors will have on the ESFAS (CFR 41.7, 45.5 to 8) 013 Engineered Safety Features Actuation K2.01 ESFAS/safeguards equipment control 3.6/3.8 B (CPR: 41.7) 015 Nuclear Instrumentation 1 G2.2.12 Knowledge of surveillance 3.0/3.4 R 015--------------------tion- procedures (CFR 41.10,45.13) 015 Nuclear Instrumentation K4.06 Reactor trip bypasses (CFR: 41.7) 3.9/4.2 B 015 Nuclear Instrumentation 1 K5.04 Knowledge implication of the operational of the following concepts as they 2.6/3.1 B apply to the NIS: Factors affecting accuracy and reliability of calorimetric calibrations.

(CFR: 41.5/45.7) 017 In-core 017 Temperature Monitor In-core Temperature--Mon-tor K3.01 Natural circulation indications (CFR: 41.7 / 45.6) 3,5/3.7 B 022 Containment Cooling o25lce Condenser------------------------ - - -___

ES-40t PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 025 Ice Condenser -1 I 1 K1.03 - MFW (CFR: 41.2 to 41.9 / 45.7 to 2.6/2.6 B 056 Condensate 45.8) 059 Mai Feedwater K6.09 Effect of loss of MFW pump and flow 2.4/2.6 B regulating valves 059 Main Feedwater interlocks of and / orKnowledge K4.19 thatMFW provide for Features design automatic 3.2/3.4 R feedwater isolation of MFW (CFR 41.7)

A4.1 1 - Recovery from automatic feedwater 3.1/3.3 isolation (CFR: 41.7/45.5 to 45.8) 061 Auxiliary/Emergency Feedwater K5.01 Knowledge the operational of teofrelationship between AFW 3.6/3.9 R implications flow and RCS heat transfer (41.5, 45.7) 061 Auxiliary/Emergency Feedwater A1.04 - Ability to predict and/or monitor 3.9/3.9 B changes in parameters (to prevent exceeding desn limits) associate with operating the AFV ontrols including: AFW source tank level. (CFR: 41.5/45.5) 068 Liquid Radwaste K1.07 - Sources of liquid wastes for LRS 2.7/2-9 B (CFR: 41.2 to 41.9 / 45.7 to 45.8) 068 Liquid Radwaste K6.10 Knowledge of the effect of a loss or 2.5/2,9 R malfunction on the following will have on the Radwaste System: Radiation monitors.

L(CFR:i 41.7 1 45.7) 071 Waste Gas Disposal K3.05 Knowledae of the effect that aARM loss of 3.2/3.2 B the waste gas disposal will have on and PRAM (CFR41.7,45.6)

A1.01 Predict/monitor changes in radiation 3.4/3.6 B 072 Area Radiation Monitoring levels to prevent exceeding design limits (CFR 41.5, 45.5) 072 Area Radiation Monitoring 1 G2.1.28 Knowledge of the purpose andand 3.2/3.3 B function of major system components controls. (CFR41.7

__ _ __8__ _ _ _ EI 3D I 9737I i 7 12I0 I 1u 2 Point Tota1: 23 I 1 2371 a&

PWR RO Examination Outline Form ES-401-4 ES-401 Plant Systems - Tier 2/Group 2 K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) [MD. Points System # / Name 002 Reactor Coolant K5.10 Operational implications of relationship 3.614.1 B between reactor power and RCS differential temperature (CFR 41.5, 45.7) 006 Emergency Core Cooling K1.07 cause-neatofrelationship and/or Knowledge connections the physicalbetween the 2.9/3.3 B ECCS and the followin systems: MFW system.

(CFR 41.2 to 41.9/453' to 45.8) 006 Emergency Core Cooling A1.11 Ability to predict and/or monitor changes 3.1/3.4 B in parameters (to prevent exceeding design imits) associated with operating the ECCS controls including: Boron concentration. (CFR 41.5 /45.5) 010 PrRssurizer Pressure Control K3.01 Knowledge of the loss of PZR PCS on 3.8/3.9 B FPS(CFR 41.7, 45.6) 011 Pressurizer Level Control A3.03 Ability to monitor automatic operation of 3.2/3.3 B PZR LCS including: Charging and letdown (CFR 41.7 / 45.5) 012 Reactor Protection K6.10 RPS (CFR of loss Effect41.7, of permissive circuits on 45.5) 3.3/3.5 B 014 Rod Position Indication A4.01 Rod selection control (CFR: 41.7 / 45.5 3.3/3.1 B to 45.8) 1 016 Non-nuclear Instrumentation 1 016-------------------------- (K3.02Knowledge of the effect that a loss or 3.4/3.5 R

- malfunction of the NNIS has on PZR LCS 026 Containment Spray . 1 predict and/or monitor A1 .01 - Ability to prevent exceeding design changes 3.9/4.2 B in parameters (to limits) associated with operating the CSS controls including: Containmentpressure (CFR:

41.5/45.5)

K1.02 Knowledge of the physical connections 3.6/3.8 029-Containment Purge and/or cause-effect relationship between the Containment Purge System and the following systems: Containment radiation monitor 1 G2.4.18 Knowledge of the specific bases for 2.7/3.6 R 033 Spent Fuel Pool Cooling EOPs (CFR 41.1 0/45.13) 035 Steam Generator K1.09 Cause / effect between S/0 and RCS 3.8/4.0 B

(CFR 41.2 - 9, 45.7 - 8) 039 Main and Reheat Steam A1.03 Ability to predict and/or monitor changes 2.6/2.7 B in parameters (to prevent exceeding desig limits) associated with operating the iM-R9 controls including: Primary system temperature indications, and required valves, during main steam system warm-up. (CFR41.5 / 45.5) 055 Condenser Air Removal K3.01 Knowledge malfunction of the of the effect CARS will have the or a loss that on 2.5/2.7 R

- following: Main ondenser. (CFR 41.7 / 45.6)

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 062 AC Electrical Distribution A3.05 Ability to monitor automatic operation of 3.5/3.6 B the ac distribution system, including: Safety related indicators and controls. (4 .7 / 45.5) 063 DC Electrical Distribution 064 Emergency Diesel Generator K2.03 Knowledge control power power supplies 3.6/3.9 B (CFR41.7) 073 Process Radiation Monitoring A2.01 Ability to (a) predict the impacts of the 2.5/2.9 R following malfunc ions or operations on the PRM system; and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply. (CFR:

41.5/43.5 / 45.3 / 45.13) 075 Circulating Water 1 A4.01 Ability to operate/monitor emergency/

essential SWS pumps (CFR41.7, 45.5- 8) 3.2/3.2 B 079 Station Air K4.01 Knowledge of SAS design feature and 2.9/3.2 cross-connection with lAS MCFR4 .7) 086 Fire Protection 1 G2.4.25 Knowledge of fire protection procedures 2.9/3.4 B aICG F R P oi nt T -2 2 01 K/A Category Point Totals: 3 1 [3 I 11 11 3 I 1 2 2 2 Group Point Total: 20 2

PWR RO Examination Outline Form ES-401-4 ES-401 Plant Systems - Tier 2/Group 3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points System # / Name K1 K2 K3 K503 Operational effects of reactivity 2.9/3.1 005 Residual Heat Removal 005------------------------ effects of RHR fill water (CFR41.5, 45.7) 007 Pressurizer Relief/Quench Tank K1.02 Knowledge of the physical 3.3/3.4 008 Component Cooling Water connections an or cause-effect and the relationship between the CCWS followini systems: Loads to cooled by CCWS.

-CFR: 4.to 41.9 / 46.7 45.9) 027 Containme ntiodine Removal RecoroIbiner and Purget Control-____

028 Hydro-gein 034 Fuel Handling Equipment 1 K4.01 Design features and interlocks which 2.6/3.4 B provide fuer protection from binding and dropping (CFR41.7) 041 Steam Dump/Turbine Bypass Control 1 K3.04 Effect of a malfunction of the SDS 3.5/3.4 B has on reactor power (CFR41.7, 45.6) 045 Main Turbine Generator A3.05 Ability to monitor auto operation of 2.6/2.9 B the MT/G system, including:

Electrohydraulic control. (CFR 41.7 / 45.5)

K2.08 MOV (CFRPower41.Wp7) ESF-actuated suplies tooES 3.1/3.3 076 Service Water 078 Instrument Air 1 G2.4.11 Knowledge of abnormal conditions 3.4/3.6 R

-procedures (CFR 41.10, 43.5, 45.13) 103 Containment A2.033 Predict impact and use procedures 3.5/3.8 R to address malfunction of phase A and B isolation (CFR 41.5, 43.5, 45.3,45.18)

I K/AoCategory Point Totals: 1 '11FtI1I o o t t oJI1 Group Point Total: 85 Plant-Specific Priorities Reason Points System /Topic Recommended Replacement for...

Plant-Specific Priority Total: (limit 10) 1 I

Facility-. .... Date of Exam: - Exam Level:R0 Category K/A # Topic Imp. Points 2.1.3 Knowledge of shift turnover practices 3.0/3.4 B 2.1.2 Knowledge of operator responsibility during all modes of 3.0/4.0 B Conduct of operation Operations 2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 B 2.1.

2.1.

Total 3 2.2.3 Knowledge of the design, procedural and operational differences 3.1/3.3 B between Units Equipment 2.2.12 Knowledge of surveillance procedures 3.0/3.4 B Control _____________________________________

2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4/4.1 B Total 3 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control 2.6/3.0 B requirements 2.3.4 Knowledge of radiation exposure limits and contamination control 2.5/3.1 B Radiation Control including permissible levels in excess of those authorized 2.3.9 Knowledge of the process for performing a containment purge 2.5/3.4 B Total 3 2.4.1 Knowledge of EOP entry conditions and immediate action steps 4.3/4.6 B 2.4.14 Knowledge of general guidelines for EOP flowchart use 3.0/3.9 B Emergency Procedures/ Plan 2.4.8 Knowledge of how the event-based emergency/abnormal 3.0/3.7 B operating procedures are used in conjunction with the symptom based EOPs 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 B Total 4 Tier 3 Point Total 13 RO 12

.1 -4 Facility: Vogtle Date of Exam: Exam Level: SRO Tier__ Group__ K/A Category Points Point K3 K4 K5 K6 Al A4 G Total K1 K2

1. 1 4 3 4 424 Emergency &

Abnormal 2 2 2 216 Plant 3 1 0 1 1 0 3 3 Evolutions Tier 7 5 7 10 6 43 43 Totals 1 3 1 2 1 1 1 3 2 2 19 19

2. 17 1 1 2 1 1 2 2 2 1 2 17 Plant 2 2 Systems 3 0 1 1 0 1 0 0 0 1 0 0 4 4 Tier 5 3 4 3 3 2 5 4 3 4 4 40 40 Totals _I]_ I I I I I
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 4 5 4 117 14 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

relevant to the applicable V.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be evolution or system.

for the SRO license level, and

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings of plant-specific priorities. Enter the tier totals the point totals for each system and category. K/As below 2.5 should be justified on the basis for each category in the table above.

C.n CCAAIS ES-401 Irmarnonr',onPWR A=tSRO Examination hnnrnloi uutiine Pi~nt Pvnhiitinn* . Ti~r llnroun 1 Form ES-401-3 Ki K2 K3 At A2 G K/A Topic(s) Imp. Points E/APE # / Name / Safety Function 000001 Continuous Rod Withdrawal / 1 1 AKt.05 - Knowledge of the operational implications of the following concepts as 3.5/3.8 B they apply to Continuos Rod Withdrawal: Effects of turbine-reactor power mismatch on rod control (CFR: 41.8/41.10/45.3) 1 G2.4.49 - Ability to perform without reference to procedures those actions that 4.0/4.0 B 000003 Dropped Control Rod / I immediate euire 41.10 (CFR: operation of system components and controls.

/43.21F45.6) 000005 Inoperable/Stuck Control Rod 1 AK3.02 Knowledwe of the reason for the following responses as they apply to the 3.3/3.7 S Dropped Control od: Reactor runback with a dropped control rod (CFR 41.5,41.10 / 45.6 / 45.13) 000011 Large Break LOCA / 3 1 EK2.02 knowledge of the inter-relationship LB LOCA and pumps 2.6/2.7 B 000011 Large Break LOCA / 31 EA1.04 - ESF actuation system in manual (CFR 41.7/45.5/45.6) 4.4/4.4 S W/E04 LOCA Outside Containment / 3 1 EA2.1 - Facility conditions and selection of aropriate procedures dunng abnormal 3.4/4.3 S and emergency operations. (CFR: 43.5 / 45.13)

W/EO1 &E02 Rediagnosis & SI Termination / 3 EK1 .2 - Normal, abnormal and emergency operatinp procedures associated with 3.4/4.0 S (Reactor Trip or SafetyInjection/Rediagnosis). (CFH:41.8 / 41.10 / 45.3) 000015/17 RCP Malfunctions / 4 1 AKI.02 - Consequences of an RCPS failure(CFR 41.8 / 41.10 /45.3) 3.7/4.1 B BW/E09; CE/A13; W/EOY&E1O Natural Cir. / 4 1A2.2 - Adherence to a propriate procedures and d eration within the limitations in 3.4/3.8 B the facilitys license andamendments. (CFR: 43.R/45.13) 000024 Emergency Boration / 1 1 AK2.01 - Valves - (CFR 41.7 / 45.7) 2.7/2.7 B 000026 Loss of Component Cooling Water / 8 1 AK3.01 - Knowledge of the reasons for the following responses as they apply to the 3.2/3.5 B Loss of CCW: The conditions that will initiate the automatic opening and cosing of the SWS isolation valves to the CCWS collers (CFR 41.5,41.10 / 45.6 / 45.13) 000029 Anticipated Transient w/o Scram / 1 EA1.13- Manual trip of main turbine (41.8/41.10/45.3) 4.1/3.9 B 00040 (BW/Eo5- CE/E05*W/E12) Steam Line 1 AG2.4.4 ability to recognize abnormal indications for system operating parameters 4.0/4.3 B Rupture- Elass~ve Heat transfer / 4 which are entry level conditions for EOPs and AOPs (CFR 41.10, 43.2, 45.6 1 EA2.1 - Facility conditions and selection of appropriate procedures during abnormal 3.4/4.2 S CE/Al1; W/E08 RCS Overooling - PTS / 4 and anýerency operations.

(F:.4.51/5.13) 1 AA2.02 - Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 3.9/4.1 S 000051 Loss of Condenser Vacuum / 4 000055 Station Blackout / 6 1 EK3.02 - Actions contained in EOP for loss of offsite and onsite power (CFR 41.5 / 4.3/4.6 B 41.10/45.6/45.13) 1 AA2.19 - Ability to determine and interpret the following as they apply to the Loss of 4.0/4.3 S 000057 Loss of Vital AC Elec. Inst. Bus / 6 Vital AC Instrument Bus: The the plant automatic actions that will occur on a loss of a vital ac electrical instrument bus (CFR: 43.5 / 45.13)"

ES-401 PWR SRO Examination Outline Form ES-401-31 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 I E/APE # / Name / Safety Function (K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000059 Accidental Liquid RadWaste Rel. / 9 1 AA1.01 - Radioactive-liquid monitor (CFR 41.7 / 45.5 / 45.6) 3.5/3.5 B 000062 Loss of Nuclear Service Water / 4 1 AG2.4.24 - Knowledge of loss of cooling water procedures. (CFR: 41.10 / 45.13) 3.3/3.7 B 000067 Plant Fire On-site / 9 1 AK1.02 - Fire fighting (CFR 41.8 / 41.10 / 45.3) 3.1/3.9 B 000068 (BW/AO6) Control Room Evac. / 8 1 AK3.18 - Knowledge of the reasons for the following responses as they apply to the 4.2/4.5 B Control Room Evacuation: Actions contained in EOCfor control room evacuation emergency task. (CFR 41.5,41.10 / 45.6 / 45.13) 000069 (V/E1 4) Loss of CTMT Integrity / 5 1 AK2.03 - Personnel access hatch and emergency access hatch (CFR 41.7 / 45.7) 2,8/2-9 B 000074 (W/E06&E07) Inad. Core Cooling / 4 1 EA2.1 - Ability to determine and interpret the following as they apply to the 3.2/4.0 S (Saturated Core Cooling) Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR 43.5 / 45.13)

BEW/EO3 Inadequate Subcooling Margin / 4 000076 High Reactor Coolant Activity / 9 1 AA2.02 Ability to determine and interpret the following as they apply to the High 2.8/3.4 S Reactor Coolant Activity: Corrective actions requiredror high fission product activity in RCS. (CFR: 43.5/43.13)

BW/A02&Ao3 Loss of NN4-XiY 17 IK/A CategoryTotals: 4~ 3 j4 ~3 j7 3 Group Point Total: 24 _ _J 24

ES-401 PWR SRO Examination Outline Form ES-401-3 ES-401 _ _Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000007 (BW/E02&E10; CE/E02) Reactor Trip - 1 EA1.03 - RCS pressure and temperature (CFR 41.7 /45.5 /45.6) 4.214.1 S Stabilization- Recovery / 1 6BW/Ao Plant Runback / I

-BW/A04 Turbine Trip /4 000008 Pressurizer Vapor Space Accident / 3 1 AK1 .01 - Knowledge of the operational implications of the following concepts as 3.2/3.7 B they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow charactenstics of open or leaking valves (CFR 41.8 / 41.10 / 45.3) 000009 Small Break LOCA / 3 1 LOCA: for throttlingoror

- Ability to determine EA2.34 Conditions interpret following stoppingtheHPI. (OFR as they apply to a small break 43,5/45.13) 3.6/4.2 S BW/EO8; W/E03 LOCA Cooldown - Depress. / 4 1 EK2.2 - Knowledge of the operational implicationsFacility's heat removal systems, 3.7/4.0 B including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper ation o these systems to the operation of the facility. (CFR: 41.7 / 45.e)

W/E1 1Loss of Emergency Coolant Recirc. / 4 1 EA1,3 - Ability to monitor / operate to obtain the desired operating results during 3.7/4.2 B abnormal and emergency situations during a loss of emerg cool recirc. (CFR: 41.7 /

45.5/45.6) 000022 Loss of Reactor Coolant Makeup / 2 1 AG2.1.32 - Ability to explain and apply all system limits and precautions. (CFR: 3.4/3.8 B 41.10 / 43.2/45.12) 000025 Loss of RHR System / 4 1 AK2.02- Knowledge of the interrelationship of the LPI or Decay Heat RemovaVRHR 3.2/3.2 B pumps during a loss ofRHR (CFR 41.7 / 45.7) 000027 Pressurizer Pressure Control System AK3.03 - Knowledge of the actions contained in EOP for PZR PCS malfunction 3.7/4.1 B Malfunction /3 41.5,41. 0/145.6/45.13) 4CFR 000032 Loss of Source Range NI / 7 1 AK1.01 - Knowledge of the operational implications of the effects of voltage changes on performance during a loss of SR NI (CFR 41.8 /41.10 /45.3) 2.5/3.1 B 000033 Loss of Intermediate, RagN 17.

000037 Steam Generator Tube Leak / 3 1 AK3.07 - Knowledge of the reasons for the following responses as they apply to the 4.2/4.4 B Steam Generator Tube Leak: Actions contained in EOP for S/G tube leak (CFR 41.5, 41.10 / 45.6 / 45.13) 000038 Steam Generator Tube Rupture / 3 EA1.04- Ability to operate and monitor the following as they al to a SGTR: PZR 4.3/4.1 S spray, to reduce coolant system pressure. (CFR 41.7 / 45.5/45.6) 000054 (CE/E06) Loss of Main Feedwater / 4 1 EG2.4.48 - Ability to interpret control room indications to verify the status and 3.5/3.8 B operation of system, and understand how operator actions and directives affect plant and sys em conditions. (CFR: 43.5 7 45.12)

BW/E04; W/EOS Inadeqluate Heat Transfer Loss 1 EA .3 - Ability to obtain desired operating results during abnormal and emergency 3.8/4.2 B of Secondary Heat Sink / 4 situations. (CFR: 41.7 / 45.5 / 45.6) 0 e Loss of DC Powor/ .... _ _ _,__ _ _ _ _

_ 7.....

ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 000060 Accidental Gaseous Radwaste Rel. / 9 1 AA2.04 - Ability Accidental to determine Gaseous andThe Radwaste: interret effeotsthe on following the powerasplant they ofapply to thea given isolating 2.6/3.4 S radioactive-gas leak (CFR: 43.5 /45.13) 000061 ARM System Alarms / 7 W/E16 High Containment Radiation / 9 1 2.3.10 - Ability to perform procedures to reduce excessive levels of radiation and 2.9/3.3 S guard against personnel exposure. (CFR: 43.4 / 45.10) 000065 Loss of Instrument Air / 8 1 AA1.03 - Ability ot conduct restoration of systems served by instrument air when pressure is regained (CFR 41.7 / 45.5 / 45.6) 2.9/3.1 B OE/Eos Functionals2eGovera Groupal:

_________________________ 16 I 'C6 K/A Category Point Totals: j [2 J2Ž 5S 2 3 Group Point Total: 16 11 16 1 C

ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier I/Group 3 E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 000028 Pressurizer Level Malfunction / 2 1 AA2.12 - Ability to determine and interpret the following as they apply to the 3.1/3.5 S Pressurizer Level Control Malfunctions: Cause for PZR level deviation alarm:

controller malfunction or other instrument malfunction. (CFR: 43.5 /45.13)

'000036 (BW/A08) Fuel Handling Accident/ 8 000056 Loss of Off-site Power / 6 1 AK1.01 - knowledge of the operational implications of the Principle of cooling by 3.7/4.2 S natural convection as it applas to LOSP_(CFR 41.8/41.10/45.3)

S.

  • BW/E13&El4 BOP Rules and. Enclosures .......... . ..I .. . .. . .. . . . . l I I . .. . . -_. . ..

BW/AOS Emergency:Diesel Actuationl/6 __________________________________

BW/A07 Flooding/ 8________________________________

CE/Al Excess RCS Leakage/ 2 W/E13 Steam Generator Over-pressure / 4 1 EK3.2 -Knowledge of the normal, abnormal and emergency operating procedures 2.9/3.3 5 associated with Steam Generator Overpressure). (CFR: 41.5 /41.10, 45.6,45.13)

WIE1 5 Containment Flooding /5.

K/A Category Point Totals: 1 0 11 0 J1 01 Group Point Total: 3 I

ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System # /Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 001 Control Rod Drive 1 K1.05 Knowled e of the physical connections and/or 4.5/4.4 B cause-effect relationship between the CRDS and the following 45..7 to 45.systems:

) NIS and RPS (CFR 41.2 to 41.9 /

003 Reactor Coolant Pump 1 A2.02 Ability to predict the impact of the following 3.7/3.9 S malfunction or operation on the RCPS :

Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP (CFR: 41.5 / 43.5/45.3 / 45/13) 004 Chemical and Volume Control 1 A2.12 Ability to (a) predict the impacts of the following 4.1/4.3 B malfunctions or operations on the CVCS; and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those malfunctions or operations: CIAS, SIAS (CPR: 41.5 / 43.5 / 45.3 / 45.5) 004 Chemical and Volume Control 1 A4.07Ability to manually operate and/or monitor in the 3.9/3.7 B control room: Boration/dilution. (CFR: 41.7 / 45.5 to 45.8) 013 Engineered Safety Features Actuation 1 K2.01 Knowledge of the power supplies of the 3.6/3.8 B ESFAS/safeguards equipment control (CFR: 41.7) 014 Rod Position Indication 1 A4.01 Ability to manually operate or monitor in the CR 3.3/3.1 B the rod selection contro[ (CFR: 41.7 / 45.5 to 45.8) 015 Nuclear Instrumentation 1 K4.06 Knowledge of the NIS design features and 3.9/4.2 B interlocks provided for Reactor trip bypasses (CFR:

41.7) 015 Nuclear Instrumentation 1 K5.04 Knowledge of the operational implication of the 2.6/3.1 B following concepts as they apply to the NIS: Factors affecting accuracy and re lab!i ity of calorimetric calibrations. (CFR: 41.5 / 45.7) 017 In-core Temperature Monitor 1 K3.01 Knowledge of the effect of loss of Natural 3.5/3.7 B circulation indications (CFa: 41.7 / 45.6) 022 Containment Cooling 1 G2.1.27 - Knowledge of system purpose and function. 2.8/2.9 B (CFR: 41.7) 025 Ice Condenser 025 Ice Condenser 026 Containment Spray A1.01 - Ability to predict and/or monitor changes in 3.9/4.2 B parameters (to prevent exceeding design limits) associated with operating the CS controls incluing:

Containment pressure (CFR: 41.5 / 45.5)

ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System # Name K1 K2 K3 K4 K5 K6 Al A2. A3 A4 G K/A Topic(s) Ina Points 056 Condensate 1 K1.03 -Knowledge of the physical connection or cause- 2.6/2.6 B effect relationship between condensate system and the MFW (CFR: 41.2 to 41.9/ 45.7 to 45.8) 059 Main Feedwater 1 K6.09 Knowledge of the effect of loss of MFW pump 2.4/2.6 B and flow regulating valves 059 Main Feedwater I A4.11 - Recovery from automatic feedwater isolation 3.1/3.3 B (CFR: 41.7 /45.5 to 45.8) 061 Auxiliary/Emergency Feedwater A1.04 - Ability to predict and/or monitor changes in 3.9/3.9 B parameters (to prevent exceeding design limits) associated with operating the AN controls including:

AFW source tank level. (CFR: 41.5 / 45.5) 063 DC Electrical Distribution 068 Liquid Radwaste 1Ki.07 - Knowledg of the sources of li uid wastes for 2.7/2-9 B LRS (CFR: 41.2 to 41.9/45.7 to 45.83 071 Waste Gas Disposal 1 K3.05 Knowled e of the effect that a loss of the waste 32/3.2 B

____________________________gas disposal will have on ARM and PAM (CFR 41.7, 072 Area Radiation Monitoring 1 A1.01 Predict/monitor changes in radiation levels to 3.4/3.6 B prevent exceeding design limits CFR41.5, 45.5) 072 Area Radiation Monitoring 1 G2.1.28 Knowledge of the purpose and function of 3.2/3.3 B major system componentsand controls. (CFR41 .7)

IKA Category Point Totals z i 13 I1 2 1I1 13 2 0 13 2 1jGroup Point Total: 19 19

ES-4Ol PWR Plant SRO Examination Outline Systems - Tier 2/Group 2 Form ES-401-3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 006 Emergency Core Cooling 1 K1.07 Knowledge of the physical connections and/or cause-effect relationship between the ECOS 2.9/3.3 B fo oweng systems: MFW system. (CFR 41.2 to and the 41 9 /

- 45.7 to 45.8) 006 Emergency Core Cooling A1.11 Ability to predict and/or monitor changes in 3.1/3.4 B parameters (to prevent exceeding design limits) associated with operating the ECCS controis ncluding:

Boron concentration. (CF R 41.5 / 45.5) 010 Pressurizer Pressure Control K3.01 Knowledge of the loss of PZR PCS on RCS (CFR 3.8/3.9 B 41.7,.45.6) 011 Pressurizer Level Control A3.03 Ability to monitor automatic operation of PZR LOS 3.2/3.3

-- including:Carging and letdown (CFR 41.7/45.5)

B 012 Reactor Protection K6.1 0 Knowledge of the effect of loss of permissive 3.3/35 B

-circuits on RPS (CFR 41.7, 45.7) 016 Non-nuclear InsItrumentiation 027 Containment Iodine Removal H 4r ge obinerand Purge Control.

-029- Contarinment urge6ý 033 Spent Fuel Pool Cooling 1 G2.4.18 Knowledge of the specific bases for EOPs 2.7/3.6 S (CFR 41.1 0/ 451.3 034 Fuel Handling Equipment K4.01 Knowledge of the design features and intedocks 2.6/3.4 B which provide fuel protection from binding and dropping

__(CPA 4T17) 035 Steam Generator K1.09 Knowledge of the cause / effect between S/G and 3.8/4.0 B RCS (CFR 41 - 9,457-8) 039 Main and Reheat Steam A1.03 Ability to predict and/or monitor changes in 2.6/2.7 B parameters (to prevent exceeding design limits) associated with operating the MRSS controls including Primary system temperature indications, and requiredf valves, during main steam system warm-up. (CFR 41.5 /

-- 45.5) 055-Condlenser Air Removal 062 AC Electrical Distribution A3.05 Ability to monitor automatic operation of the ac 3.5/3.6 B distribution system including: Safety related indicators and controls. (41J /45.5) 064 Emergency Diesel Generator 1 12.03 Knowledge control power power supplies (CFA 41.7) 3.2/3.6 B 073 Process Radiation Monitoring 1A2.01 Ability to (a) predict the impacts of the following 2.5/2.9 S malfunctions or operations on the PRM system; and (b) based on those predictions, use procedure to correct, control or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply. (CFR: 41.5 / 43.5 / 45.3 / 45.13)

ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System # Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 075 Circulating Water 1 A4.01 Ability to opeate/monitor emergency/ essential 3.2/3.2 B SWS pumps (CFR 41.7, 45.5 -7 8 079 Station Air 1 K4.01 Knowledge of SAS design feature and cross 2.9/3.2 B Connection withlAS (CFR41 .' u 086 Fire Protection 1 2.4.25 Knowledge of fire protection procedures (CFR 2.9/3.4 S 41.0, 43.5, 45.5) 103 Containment A2.03 Ability to predict impact and use procedures to 3.5/3.8 S address malfunction of phase A and B isolation (CFR 41.5, 43.5, 45.3,45.13)

IA Category PointTotals: 2 1 12 1 1 2 2 2 1 2 GroupPointTotal: 17 I17

ES-401 PWR SRO Examination Outline Form ES401-3

- Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 005 Residual Heat Removal 1 K5.03 Knowledge reactivity effects ofofRHR the oflwater erational imp lcations of (CFR41.5, 45.7) 2.9/3.1 S 00VPessurizer Relief /Quench ITank 008 Component Cooling Water _______________________

041 Steam Dump/Turbine Bypass Control K3.04 Knowledge of the effect of a malfunction of the 3.5/3.4 B 045-------------------ator SDS has on reactor power (BFR41.7, 45.6) 045 Main Turbine Generator I A3.05 Ability to monitor auto operation of the MT/G 2.6/2.9 B

_sytem, including: Electrohydraulic control. (CFR 41.7 /

076Seric Waer.5) 076 Serce Water iK(2.08 Knowledge of the power supplies to ESF-

actuated MOV (CFR 41.7)B 3.1/3.3 078 Instrument Air K/A Category Point Totals: lolJ 0 1o lolH t o io GroupPointTotal: 4 _ __ 4 Plant-Specific Priorites System / Topic Recommended Replacement for... Reason Points

  • iI

+ 4 1____

t I.

E. I I I.

Plant-SPecific Prioritv Total: (limit 10i PatS eii c Pro "t Total: (imi 1....

.)

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, Si)

Facility. Date of Exam: Exam Level: SRO Category K/A # Topic Imp. Points 2.1.3 Knowledge of shift turnover practices 3.0/3.4 B 2.1.2 Knowledge of operator responsibility during all modes of 3.0/4.0 B Conduct of operation Operations 2.1.14 Knowledge of system status criteria which require the notification 2.5/3.3 S of plant personnel 2.1.32 Ability to explain and apply all system limits and precautions 3.4/3.8 B 2.1.

2.1.

Total 4 2.2.3 Knowledge of the design, procedural and operational differences 3.1/3.3 B between Units 2.2.8 Knowledge of the process for determining if the proposed 1.8/3.3 S Equipment change, test, or experiment involves an unreviewed safety Control - question.

2.2.12 Knowledge of surveillance procedures 3.0/3.4 B 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4/4.1 B 2.2.29 Knowledge of SRO fuel handling responsibilities 1.6/3.8 S 2.2. ___________________________ _

Total 5 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control 2.6/3.0 B requirements 2.3.4 Knowledge of radiation exposure limits and contamination control 2.5/3.1 B Radiation - including permissible levels in excess of those authorized Control 2.3.9 Knowledge of the process for performing a containment purge 2.5/3.4 B 2.3.8 Knowledge of the process for performing a planned gaseous 2.3/3.2 S release 2.3.

2.3.

Total 4 2.4.1 Knowledge of EOP entry conditions and immediate action steps 4.3/4.6 B 2.4.14 Knowledge of general guidelines for EOP flowchart use 3.0/3.9 B Emergency Procedures/ 2.4.8 Knowledge of how the event-based emergency/abnormal 3.0/3.7 B Plan operating procedures are used in conjunction with the symptom based EOPs 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 B 2.4.

Total 4 Tier 3 Point Total (RO/SRO) 17 12

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