ML12304A012

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Initial Exam 2012-301 Final Administrative Documents
ML12304A012
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/13/2012
From:
NRC/RGN-II
To:
Virginia Electric & Power Co (VEPCO)
References
50-280/12-301, 50-281/12-301
Download: ML12304A012 (35)
v • d • e


Text

ES-201 Examination Preparation Checklist Form ES-201-1 August 13, Facility: Surry Nuclear Station Date of Examination: 2012 cilit NRC Examinations Developed by:

Writte I Operating Test Written / Operating Test T ae Chief Task Description (Reference) Examiners Initials

-180 1. Examination administration date confirmed (C.1.a; C.2.a and b) RSB

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

-120 3. Facility contact briefed on security and other requirements (C.2.c) RSB

-120 4. Corporate notification letter sent (C.2.d) RSB

[-901 [5. Reference material due (C.1.e; C.3.c; Attachment 2)1 RSB

{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES 301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-112, ES-401-3, and ES-401-4, as RSB applicable (C.1.e and f; C.3.d)

{-70) {7. Examination outline(s) reviewed by NRC and feedback provided to facility RSB licensee (C.2.h; C.3.e)}

{ -45 } 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, RSB ES-301-5, ES-30l-6, and ES-401-6), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202) RSB

-14 10. Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202) RSB

-14 11. Examination approved by NRC supervisor for facility licensee review RSB (C.2.h; C.3.f)

-14 12. Examinations reviewed with facility Licensee (C.1.j; C.2.f and h; C.3.g) RSB

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

-7 14. Final applications reviewed; 1 or 2 (if>10) applications audited to confirm qualifications I eligibility; and examination approval and waiver letters sent RSB (C.2.i;_Attachment 4;_ES-202,_C.2.e;_ES-204)

-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee RSB (C.3.k)

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

  • 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.

HNAL ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Surry Power Station Date of Examination: 8/2012 Initials Item Task Description a b* c#

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. Jk !vIh AlA R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

T -

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, C6 S and major transients.
b. Assess whether there are enough scenario sets (and spares) to test the projected number 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 y.

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 . ,-

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 W

/

T (2) task repetition from the last two distributed among the safety functions as specified on the form NRC examinations is within the limits specified on the form (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

---c in the appropriate exam sections.

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

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

R d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO). 6

, Printed tltq/Sgnature , Date

a. Author ?c Ic. Ok i

4

?- 3i3j7_

b. Facility Reviewer (*) P 1..ii4I 2t / 7 76 /Z.
c. NRC Chief Examiner (#) IIMC ,. 2e1
d. NRC Supervisor gUhr Lc..ft1 a Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines Nec. c(qd M wI 4

iuiiJ FINAL

ES-201 Examination Outline Quality Checklist FINAL Form ES-201-2 Facility: Surry Date of Examination: 8/28/2012 Initials Item Task Description

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

NA NA

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 S transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number and U 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 at A least one new or significantly modified scenario, that no scenarios are duplicated from the T 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 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 W 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.

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

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d. Check for duplication and overlap among exam sections.

L 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. Author (9 /

(*) /

b. Facility Reviewer
c. NRC Chief Examiner (#)
d. NRC Supervisor I

I 4 ft Note: # Independent NRC reviewer initial items in Colu , clief examiner concurrence required.

Examination Security Agreemert Form ES-201 -3 ES-201

1. Pre-Examination 2

acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 1t Iii. as of the date of my signature. agree that 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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 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.

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of , a,t.. as of the date of my signature. 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 (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees 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 knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ofAyJ_rFrom the date that I entered into this security agreement until the completion of examination administration, I did not 7

instruct, evaluate, or procide 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) DATE NOTE

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ES-201 Examination Security Agreemert Form ES-201-3

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of

,4 7°R-.-. 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 administratio n, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicato r is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and action against me or understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement 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 administered To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations From the date that I entered into this security agreement until the completion of examination administratio n, I did not during the week(s) of/ 4 .2o/2.

, except as specifically noted instruct, evaluate, or prO<iide performance feedback to those applicants who were administered these licensing examinations below and authorized by the NRC.

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

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NOTES c2D Sd X 4cQLco-4 f

ES-301 Administrative Topics Outline FINAL Form ES-301-1 Facility: Surry Power Station Date of Examination: 8/20 12 Examination Level: SRO Operating Test Number: I Administrative Topic Type Describe activity to be performed (KA)

(see Note) Code*

. R/M Perform an At-Power Shutdown Margin with a Partially Dropped Conduct of Operations Control Rod G2.1 .25 Ability to Interpret Reference Materials, Such as Graphs, Curves, Tables, etc. (3.9/4.2)

Conduct of Operations Determine Final Pressure for a Waste Gas Decay Tank and RIM determine T.S. time limitations G2.1 .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.4/4.7)

. RIN Perform a SRO Review of a Surveillance Procedure and Equipment Control Determine Tech Spec Applicability 2.2.12 Knowledge of surveillance procedures (4.1)

. . R/M Calculate Dose and Best Work Method Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7)

Emergency Plan RIM SRO Classify SAE SRO- 2.4.41 (Knowledge of the emergency action level thresholds and classifications) (4.8)

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; for SROs & RO retakes)

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

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

ES-301 FINAL Administrative Topics Outline Form ES-301-1 Facility: Surry Power Station Date of Examination: 8/2012 Examination Level: RO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (KA)

(see Note) Code*

. RIM Perform an At-Power Shutdown Margin with a Partially Dropped Conduct of Operations Control Rod G2.1 .25 Ability to Interpret Reference Materials, Such as Graphs, Curves, Tables, etc. (3.9/4.2)

. Determine Final Pressure for a Waste Gas Decay Tank Conduct of Operations R. D G2.1 .7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.4/4.7)

. . R/M Calculate Dose and Best Work Method Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7)

R/D Complete EPIP-2.01, Attachment 3 Update Message.

Emergency Plan 2.4.39 (Knowledge of RO responsibilities in emergency plan implementation (3.9)

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; for SROs & RO retakes)

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

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

FINAL ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO X - SRO-I SRO-U Operating Test No.: I 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. Manually Align Alternate High Head Safety Injection Flowpath A/SID/LIEN 2
b. Isolate a Leaking Recirc Spray Heat Exchanger SIMIL 9
c. Respond to a Spurious SI <350°F S/DIL 3
d. Perform AP-3.00 to Emergency Borate the RCS A/S/N 1
e. Adjust the PRNIs in accordance with 1-OPT-RX-001 A/SIN 7
f. Place the Containment H2 Analyzer in Service SIDIL 5
g. Perform 1-FR-H.3 for SG High Level A/S/NIL 4
h. Place the AAC Diesel on the IJ Emergency Bus SIDIL 6 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
i. Isolate Flooding in #5 MER A/DIE 4
j. Align Turbine Building IA to Containment D/R 8
k. Locally Isolate the Secondary System (E-3, Attachment 1) EID 3

@ All RO and SRO-l 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 RO Actual Criteria Met?

(A)lternate path 4-6 5 Yes (D)irect from bank 9 7 Yes (E)mergency or abnormal in-plant 1 2 Yes (EN)gineered safety feature (L)ow-Power / Shutdown 1 6 Yes (N)ew or (M)odified from bank including I (A) 2 4 Yes (P)revious 2 exams (randomly selected) 3 0 Yes (R)CA 1 1 Yes (S)imulator I (C)ontrol room FINAL

ES-301 FINAL Control Roomlln-Plant Systems Outline Form ES-301 -2 Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO SRO-I - SRO-U Operating Test No.: I Control Room Systems© (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including I ESF)

System / JPM Title Type Code* Safety Function

a. Manually Align Alternate High Head Safety Injection Flowpath AIS/D/L/EN 2
b. Isolate a Leaking Recirc Spray Heat Exchanger S/M/L 9
c. Respond to a Spurious SI <350°F S/D/L 3
d. Perform AP-3.00 to Emergency Borate the RCS A/SIN 1
e. Adjust the PRNIs in accordance with 1-OPT-RX-001 A/SIN 7
f. Place the Containment H2 Analyzer in Service S/D/L 5
g. Perform 1-FR-H.3 for SG High Level A/S/NIL 4 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Isolate Flooding in #5 MER A/DIE 4
j. Align Turbine Building IA to Containment D/R 8
k. Locally Isolate the Secondary System (E-3, Attachment 1) E/D 3

@ All RO and SRO-l 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 SRO-I SRO-I Actual Criteria Met?

(A)lternate path 4-6 5 Yes (D)irect from bank 8 6 Yes (E)mergency or abnormal in-plant 1 2 Yes (EN)gineered safety feature (L)ow-Power I Shutdown 1 5 Yes (N)ew or (M)odified from bank including 1(A) 2 4 Yes (P)revious 2 exams (randomly selected) 3 0 Yes (R)CA I I Yes (S)imulator / (C)ontrol room ANAL

ES-301 ANAL Control Roomlln-Plant Systems Outline Form ES-301 -2 Facility: Surry Power Station Date of Examination: 08/2012 Exam Level: RO SRO-I SRO-U- X Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System I JPM Title Type Code* Safety Function

a. Manually Align Alternate High Head Safety Injection Flowpath AIS/D/L/EN 2
b. Isolate a Leaking Recirc Spray Heat Exchanger S/M/L 9
c. Respond to a Spurious SI <350°F S/D/L 3 d.

e.

f.

g.

h.

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

i. Isolate Flooding in #5 MER A/DIE 4
j. Align Turbine Building IA to Containment D/R 8 k.

@ 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 SRO-U SRO-U Actual Criteria Met?

(A)lternate path 2-3 2 Yes (D)irect from bank 4 4 Yes (E)mergency or abnormal in-plant 1 1 Yes (EN)gineered safety feature 1 1 Yes (L)ow-Power I Shutdown 1 3 Yes (N)ew or (M)odified from bank including 1 (A) 1 1 Yes (P)revious 2 exams (randomly selected) 2 0 Yes (R)CA 1 1 Yes (S)imulator / (C)ontrol room ANAL

FINAL ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Surry Power Station Date of Examination: 8/2012 Operating Test Number: 201 2-001 Initials

1. General Criteria a b*
a. The operating test conforms with the previously approved outline; changes are consistent with ,._.

sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 a.)

ci. 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 IL.-

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 4L-1 c.-X Form ES-301-4 and a copy is attached.

Printed Name / Signature Date

a. Author 7f()
b. Facility Reviewer(*) -zfr i-i
c. NRC Chief Examiner (#)c v4 1

/ /J

d. NRC Supervisor f NOTE: The facility signature is not applicable for NRC-developed tests.
  1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ANAL

ES-301 FINAL Simulator Scenario Quality Checklist Form ES-301 -4 Facility: Surry Power Station Date of Exam: 8/2012 Scenario Numbers: 1/2/3/4 Operating Test No.: 2012-001 QUALITATIVE ATTRIBUTES Initials a b* f

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. .-1
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. C,4
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
7. If time compression techniques are used, the scenario summary clearly so indicates.

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

Cues are given.

8. The simulator modeling is not altered.
9. The scenarios have been validated. Pursuantto 10 CFR55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated 1- 6 to ensure that functional fidelity is maintained while running the planned scenarios.
10. Every operator will be evaluated using at least one new or significantly modified scenario. .

All other scenarios have been altered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios).
12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301 -5 (submit the form with the simulator scenarios).
13. The level of difficulty is appropriate to support licensing decisions for each crew position.

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

1. Total malfunctions (58) 7 / 8 / 11 / 8 c.(
2. MalfunctionsafterEOPentry(12) 4/3/7/2
3. Abnormal events (24) 4/5/4/5 ,...

9 4JJ

4. Major transients (12) 3I I I3/I
5. EOPs entered/requiring substantive actions (12) 3/2/2I1
6. EOP contingencies requiring substantive actions (02) 1 /1 /1 /1 i -
7. Critical tasks (23) 4 I 3/2 / 2 i.

ANAL

ES-301 TrEeItNA LJjQckIist Form ES-301-5 Facility: Surry Power Station Date of Exam: 8/2012 Operating Test No. I A E Scenarios P V P E 1 2 3 4 T M CREW CREW CREW CREW c POSmON POSfl1ON POSmON A A T S A B S A B S A B S A B L u N R T 0 R T 0 R T 0 R T 0 T M(*

P 0 C P 0 C P 0 C P 0 C P E R IU RX 4 5 1 2 **

NOR 1 RO I/C 3,5,6 2,6, 3,4,5 3,6,7 4

,8 7 ,6,7 MAJ 6,7,9 6 6,7, 7 2 9

TS **

0 RX NOR 1,4 3,5 1,3 2 RO I/C 2,8 1,4,7 2,8 4,5,8 **

(BOP) MAJ 6,7, 6 6,7, 7 **

9 9 TS RX 4 5 1 2 **

NOR 1 3 3 2 **

SROI I/C 2,3,5 1,2,4 2,3,4 3,4,5 **

4 us

6,8 ,6,7 5,6, 6,7,8 7,8 MAJ 6,7,9 6 6,7, 7 **

2 9

TS 2,3 1,2,4 3,4 1,5 **

2 5

RX 4 5 1 2 **

1 NOR **

1 SROI I/C 3,5,6 2,6, 3,4,5 3,6,7 **

4 RO

,8 7 ,6,7 MAJ 6,7,9 6 6,7, 7 **

2 9

TS RX 4 5 1 2 0 NOR 1 3 3 2 SROU I/C 2,3,5 1,2,4 2,3,4 3,4,5 **

2 us 6,8 ,6,7 5,6, 6,7,8 7,8 MAJ 6,7,9 6 6,7, 7 9

T5 2,3 1,2,4 3,4 1,5 **

2 5

    • Scenario Sets verified to meet or exceed minimum event types. All combinations will resute I ac ity vent, 1 normal, 4 instrumentation/control events, 2 major events, and 2 technical specification events.

NA L

Instructions:

I. Check the applicant level and enter the operating test number and Form ES-D-l 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 SOP 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.

ANAL Scenario Sets verified to meet or exceed minimum event types. All combinations will result in at least 1 reactivity event, 1 normal, 4 iistrumentationIcontrol events, 2 major events, and 2 technical specification events.

FINAL ES-301 Competencies Checklist Form ES-301-6 Facility: Surry Power Station Date of Examination: 8/2012 Operating Test No.: 2012-001 APPLICANTS RO SROl SRO-U Competencies JO_ JJO_

12341234123 41234 Interpret/Diagnose 35 2,5, 3,4, 1,3, 3,5, 2,5, 3,4, 1,3, 3,5, 2,5, 3,4, 1,3,

.. 67 6,7 56 67 67 67 56 67 67 67 56 67 Events and Conditions 8,9 7,9 89 7,9 89 79 Comply With and All All All All All All All All All All All All Use Procedures (1)

Operate Control 3,4, 2,5, 1,3, 2,3, 3,4, 2,5, 1,3, 2,3, N/A N/A N/A N/A 6,7, 6,7 4,5, 6,7 6,7, 6,7 4,5, 6,7 B oarus 8,9 6,7, 8,9 6,7, 9 9 Communicate All All All All All All All All All All All All and Interact Demonstrate N/A N/A N/A N/A All All All All All All All All Supervisory Ability (3)

Comply With and N/A N/A N/A N/A 2,3 1,2, 3,4 1,5 2,3 1,2, 3,4 1,5 4,5 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 even, applicable competency for even, applicant.

HNAL

ES-401, Rev. 9 Record of Rejected KJAs Form ES-401-4 SURRY NUCLEAR POWER STATION AUGUST 2012 EXAMINATION Tier I Randomly Selected Reason for Rejection Group K/A NO KAs WERE REQUEST BY LICENSEE TO CHANGE

FINAL ES-401 Written Examination Quality Checklist Form ES-401-6 L Facility: Surry Date of Exam: 8/28/20 12 Exam Level:

Initial Item Description b c

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

ZQIE j- z

a. NRC KJAs are referenced for all questions.

2.

b. Facility learning objectives are referenced as available. L 4-
3. SRO questions are appropriate in accordance with Section D.2.d ofES-401 iV
4. If more than four RO and two SRO questions are repeated from the last two NRC licensing exams, the facility licenseeUs sampling process was random and systematic. (k A 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 5 the audit exam was completed before the license exam was started

/ the examinations were developed independently the licensee certifies that there is no duplication (explain)

Bank use meets limits (no more than 75 percent from Bank Modified New

6. the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question distributions(s) at right.

i / o7 a.i, / 2 2 (i+ i72 Between 50 and 60 percent of the questions C/A

. Memory on the RO exam are written at the comprehension!

7. analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question q7 / 1.07, 57 1, /

distribution(s) at right.

References/handouts provided do not give away answers 8.

or aid in the elimination of distractors.

3Jk 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.

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

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

Printed Name / Signature Date 7),, ZL

a. Author &L/LOO.rA4O
b. Facility Reviewer (*) t
c. NRC Chief Examiner (#) G k4/ $1
d. NRC Regional Supervisor /JJilfj[jjT. JtD(.M4JAJ.,,/

Note:

  • The facility reviewerLis initials/signature are not applicable for NRC-developed examinations.
  1. Independent NRC reviewer initial items in Column UcU; chief examiner concurrence required.

FINAL

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

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) U/EIS Explanation Stem Cues T/F Job- Minutia #/ Back- Q SRO Focus Link units ward K/A Only SURRY POWER STATION WRITTEN EXAM 2012 WAS DEVELOPED BY THE NRC

- NO COMMENTS -

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.

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

3. Check the appropriate box if a psychometric flaw is identified:
  • The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
  • The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

Check the appropriate box if a job content error is identified:

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).

  • 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).
  • The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
  • The question requires reverse logic or application compared to the job requirements.
5. Check ciuestions 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).

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?

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

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q SRO U/E/S Explanation Focus Dist. Link units ward K/A Only i[ I I I I I I I I [

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Surry 2012 Date of Exam: August 28, 2012 Exam LeveK Initials Item Description a b c

1. Clean answer sheets copied before grading NA frZI
2. Answer key changes and question deletions justified and documented NA
3. Applicants scores checked for addition errors (reviewers_spot_check_>_25%_of_examinations) NA
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail NA
5. All other failing examinations checked to ensure that grades are justified NA
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of NA questions_missed_by_halt or more of the_applicants Printed Name/Signature Date
a. Grader Kenneth D. -zS-iz
b. Facility Reviewer(*) N/A
c. NRC Chief Examiner (*) Richard S.
d. NRC Supervisor (*) MarkFranke/

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

ES-401 PWR Examination Outline Form ES-401-2 Facility: Surry Date of Exam: August 2012 RO K/A CaoPts_ SRO-Only_Points Tier Group 1 1 1 G*

K K 1(1K K KIA A A A GI A2 Total

=

1 =

2 314

-=

5 611= 2 3 4

= =

  • iTotal
1. 1 3 18 3 3 6 Emergency &

Abnormal 2 i N/A a. N/A 9 2 2 4 Evoluons Tier Totals 4 5 5 4 5 4 27 5 5 10 1 222333333 22 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 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 RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, iRs, arid point totals (#) on Form ES-401-3. Umit SRO 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 / SRO)

E/APE #) Name! Safety Function K K K A A G KJA Topic(s) lR #

1_g_._i_L_

EK2 Knowledge of the interrelations between a 000007 (BW/E02&E10; CE/E02) Reactor R reactor trip and the following: 2.6 1 Trip Stabilization Recovery / 1 (CFR 41.7 / 45.7)

EK2.02 Breakers, relays and disconnects AK1. Knowledge of the operational implications of 000008 Pressurizer Vapor Space R the following concepts as they apply to a 3.2 2 Accident /3 Pressurizer Vapor Space Accident:

(CFR 41.8! 41.10/ 45.3)

AK1 .01 Thermodynamics and flow characteristics of open or leaking valves 2.1.19 AbIlity to use plant computers to 000009 Small Break LOCA /3 S evaluate system or component status. 3.8 76 (CFR: 41.10145.12)

EA1 Ability to operate and monitor the following as 000011 Large Break LOCA /3 R they apply to a Large Break LOCA: 4.3 3 (CFR 41.7! 45.5 / 45.6)

EA1.09 Core flood tank initiation AA2. Ability to determine and interpret the 000015/17 RCP Malfunctions? 4 S following as they apply to the Reactor coolant 35 77 Pump Malfunctions (Loss of RC Flow):

(CFR: 435/45.13)

AA2.08 When to secure RCPs on high bearing temperature AA2. Ability to determine and interpret the following 000022 Loss of Rx Coolant Makeup! 2 R as they apply to the LOSS of Reactor Coolant 3.2 4 Makeup:

. (CFR43.5145.13)

AA2.02 Charging pump problems 2.4.31 Knowledge of annunciator alarms, 000025 Loss of RHR System / 4 R indications, or response procedures. 4.2 5 (CFR: 41.10 / 45.3)

AA2. Ability to determine and interpret the following 000026 Loss of Component Cooling R as they apply to the Loss of Component Cooling 28 6

Water /8 Water 2 .9 (CFR:43.5!45.13)

AA2.Ol Location of a leak in the C Aew4eeempene before that component-may-be amagod AK2. Knowledge of the interrelations between the 000027 Pressurizer Pressure Control R Pressurizer Pressure Control 2.6 7 System Malfunction /3 Malfunctions and the following:

(CFR 41.7/ 45.7)

AK2.03 Controllers and positioners 2.1.23 Ability to perform specific system and A 78 integrated plant procedures during all modes of plant operation.

EA1 Ability to operate and monitor the following as 000029 ATWS! 1 A they apply to a ATWS: 3.4 8 (CFR41.7/45.5/45.6)

Al.03 Ability to op. & monitor t e 01 OW n as the apply to an ATWS:

barging pmp suction vlvs from vc GGUVO EK3 Knowledge of the reasons for the following 000038 Steam Gen. Tube Rupture /3 A responses as the apply to the SGTR: 4.1 9 (CFR 41.5/41.10145.6/45.13)

EK3.01 Equalizing pressure on primary and secondary sides of ruptured S/G WE1 2 EK2. Knowledge of the interrelations between 000040 (BW/E05; CEIEO5; W/E1 2) R the (Uncontrofled Depressurization of all Steam 3.4 10 Steam Line Rupture - Excessive Heat Generators) and the following:

Transfer / (CFR: 41.7 / 45.7)

WE1 2 EK2.1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

s WEI 2 EA2. Ability to determine and Interpret the following as they apply to the (Uncontrolled Depressurizatlon of all Steam Generators)

(CFR: 43.5 I 45.13)

WE1 2 EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

000054 (CEJEO6) Loss of Main Feedwater / 4 EK1 Knowledge of the operational implications of 000055 Station Blackout /6 R the following concepts as they apply to the Station 4.1 11 Blackout:

(CFR41.8/41.10/45.3)

EK1 .02 Natural circulation cooling 2.4.9 Knowledge of low power/shutdown Implications in accident (e.g., loss of coolant 4.2 80 accident or loss of residual heat removal) mitigation strategies.

(CFR: 41 .10143.5145.13) 000056 Loss of Off-site Power! 6 AK3. Knowledge of the reasons for the following 000057 Loss of Vital AC Inst. Bus /6 responses as they apply to the Loss of Vital AC 4.1 12 instrument Bus:

(CFR 41.5,41.10 / 45.6/45.13)

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus AA1. Ability to operate and / or monitor the following 000058 Loss of DC Power! 6 R as they apply to the Loss of DC Power 34 13 (CFR 41.7 / 45.5 / 45.6)

AA1 .01 Cross-tie of the affected do bus with the alternate supply AA2. Ability to determine and interpret the following 000062 Loss of Nuclear Svc Water / 4 R as they apply to the Loss of Nuclear Service Water: 2.9 14 (CFR: 43.5/45.13)

AA2.01 Location of a leak in the SWS 2.1.31 Ability to locate control room switches, 000065 Loss of Instrument Air! 8 R controls, and indications, and to determine that they 4.6 15 correctly reflect the desired plant lineup.

= (CFR:41.10!45.12)

2.4.45 Ability to prioritize and interpret the WIEO4 LOCA Outside Containment! 3 R significance of each annunciator or alarm. 1 1 16 (CFR:41.10!43.5145.3/45.12)

EK1. Knowledge of the operational implications of WIE1 1 Loss of Emergency Coolant R the following concepts as they apply to the (Loss of 3.6 17 Recirc. 14 Emergency Coolant Recirculation)

(CFR: 41.8! 41.10 / 45.3)

EK1 .2 Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).

WEO5 EK3. Knowledge of the reasons for the BW/E04; W/E05 Inadequate Heat R following responses as they apply to the (Loss of 3.7 18 Transfer - Loss of Secondary Heat Sink / 4 Secondary Heat Sink)

(CFR: 41.5/41.10, 45.6, 45.13)

WEO5 EK3.2 Normal, abnormal and emergency operating procedures associated with (Loss of

. Secondary Heat Sink).

AA2. Ability to determine and Interpret the 000077 Generator Voltage and Electric S following as they apply to Generator Voltage and 35- 81 Grid Disturbances / 6 Electric Grid Disturbances: (CFR: 41.5 and 43.51 . B 45.5 45.7, and 45.8)

AGeReratofrequeney4Im#atlone A2.O5 Operational status of offsite circ it

= = = =

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18

- - - - ii

ES-401 3 Form ES-401 -2 ES-401 PWR Examination Outline Form ES-401 -2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

EJAPE #1 Name / Safety Function K K K A A G K/A Topic(s) lB #

000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 AK3. Knowledge of the reasons for the R 3.8 19 following responses as they apply to the Dropped Control Rod:

(CFR 41.5,41 .10 / 45.6 / 45.13)

AK3.07 Tech-Spec limits for T-ave 000005 Inoperable/Stuck Control Rod / 1 AK2. Knowledge of the interrelations 000024 Emergency Boration / 1 R between Emergency Boration and the 2.6 20 following:

(CFR 41.7 / 45.7)

AK2.03 Controllers and positioners 000028 Pressurizer Level Malfunction /2 AK2. Knowledge of the interrelations R 2.6 21 between the Pressurizer Level Control Malfunctions and the following:

(CFR 41.7 / 45.7)

AK2.02 Sensors and detectors 000032 Loss of Source Range NI / 7 AK1. Knowledge of the operational 000033 Loss of Intermediate Range NI /7 R 2.7 22 implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation:

.. (CFR41.8/41.10/45.3)

. AK1.01 Effects of voltage changes on performance 000036 (BW/A08) Fuel Handling Accident/S 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum /4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. /9 AA2. Ability to determine and Interpret S 34 82 the following as they apply to the Accidental Gaseous Radwaste:

(CFR: 43.5/45.13)

A2.O5 That the automatic safety actions ia e cc ri d as a result of a high ARM system signa 4.2

  • AA2O1A radiation-level-alarm, as-to whether-the-cause-was-due-to-a-gradual (in.

the-use of strip-chart recorders meter and-alarm-observations 000061 ARM System Alarms / 7 2.4.11 Knowledge of abnormal condition 000067 Plant Fire On-site! 8 S 4.2 83 procedures.

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

WE1 4 EK3. Knowledge of the reasons for 000069 (W/E14) Loss of CTMT Integrity /5 H the following responses as they apply to the (High Containment Pressure)

(CFR: 41.5/41.10, 45.6, 45.13)

WE1 4 EK3.4 RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

000074 (W/E06&E07) mad. Core Cooling /4 000076 High Reactor Coolant Activity /9 W/EO1 & E02 Rediagnosis & SI Termination /3 W/E13 Steam Generator Over-pressure /4 R EA1. Ability to operate and / or monitor the 31 24 following as they apply to the (Steam Generator Overpressure)

(CFR: 41.7 / 45.5 / 45.6)

EA1 .1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

W/E15 Containment Flooding / 5 S G2.4.l8 Knowledge of the specific bases o E 4. 0 (CFR:41.10I43.5145.13)

EA2. Ability to determine and interpret the W/E1 6 High Containment Radiation! 9 R 3.0 25 following as they apply to the (High Containment Radiation)

(CFR: 43.5 / 45.13)

EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 8W/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation /6 BW/A07 Flooding /8 BW/E03 Inadequate Subcooling Margin /4 2.1.20 Ability to interpret and execute BW/E08; W/E03 LOCA Cooldown - Depress. /4 H 4.6 26 procedure steps.

(CFR: 41.10/43.5 / 45.12)

BW/E09; CE/Al 3; W/E09&E1 0 Natural Circ. /4 S 39 interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS)

(CFR: 43.5 145.13)

WE1O EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

BW/E13&E14 EOP Rules and Enclosures = =

= = = =

CE/Al 1; W/E08 RCS Overcooling PTS / 4 WEO8 EA2. Ability to determine and interpret

- R 35 27 the following as they apply to the (Pressurized Thermal Shock>

(CFR: 43.5/45.13)

WEO8 EA2.2 Adherence to appropriate procedures and operation within the limitations in the Facilitys license and amendments.

CE/Al 6 Excess RCS Leakage /2 CE/E09 Functional Recovery K/A Category Point Totals: 112 T 1 Group Point Total: J9 11212

=11_________

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 -2 Pnt Systems 1ier2/GrouojjRO / SRO)

System # I Name 1< K K K K K A A A A G K/A Topic(s) IR #

1234561234 K6 Knowledge of the effect of a loss or 003 Reactor Coolant Pump R malfunction on the following will have on 2.7 28 the RCPS:

(CFR: 41.7 / 45/5)

K6.02 RCP seals and seal water supply R A3 Ability to monitor automatic operation 3.2 29 of the RCPS, including:

(CFR: 41.7/ 45.5)A3.03 A3.03 Seal D/P A2 Ability to (a) predict the impacts of 004 Chemical and Volume S the following malfunctions or 4.2 86 Control operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5! 43/5 145/3! 4515)

A2.O1 RCS pressure allowed to exceed limits A2 Ability to (a) predict the impacts of the following malfunctions or operations 3.6 30 on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of

. those malfunctions or operations:

(CFR: 41.5/43/5/45/3/45/5)

A2.1 3 Low RWST 2.4.2 Knowledge of system set points, R interlocks and automatic actions 31 associated with EOP entry conditions.

(CFR: 41.7 / 45.7 I 45.8)

K5 Knowledge of the operational 005 Residual Heat Removal R implications of the following concepts as 3.4 32 they apply the RHRS:

(CFR: 41.5 / 45.7)

K5.02 Need for adequate subcooling R 2.2.42 Ability to recognize system 3.9 33 parameters that are entry-level conditions for Technical Specifications.

= = =

(CFR:41.7/41.10/43.2/43.3145.3) = =

A2 Ability to (a) predict the impacts of 006 Emergency Core Cooling S the following malfunctions or 3.5 87 operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41,51 45.5)

A2.05 improper amperage to the pump motor A4 Ability to manually operate and/or R 3.8 34 monitor in the control room:

(C FR: 41.7 / 45.5 to 45.8)

A4.i0 Safety parameter display system 1(4 Knowledge of PRTS design 007 Pressurizer Relief/Quench IR feature(s) and/or interlock(s) 2.6 35 Tank which provide for the following:

(CFR: 41.7)

K4.01 Quench tank cooling R A3 Ability to monitor automatic operation 27 36 of the PRTS, including:

(CFR: 41.7 / 45.5)

A3.01 Components which discharge to the PRT A2 Ability to (a) predict the impacts of 008 Component Cooling Water R the following malfunctions or operations 3*3 37 on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5/43.5/45.3/45.13)

A2.04 PRMS alarm K2 Knowledge of bus power supplies to 010 Pressurizer Pressure Control R the following: 2.5 38 (CFR: 41.7) 1(2.02 Controller for PZR spray valve Al Ability to predict and/or monitor R changes ri parameters (to prevent 3.6 39 exceeding design limits) associated with operating the PZR PCS controls including:

(CFR: 41.5/ 45.5)

Al .04 Effects of temperature change during solid operation 1(6 Knowledge of the effect of a loss or 012 Reactor Protection R malfunction of the following will have on 3.1 40 the RPS:

(CFR: 41.7 / 45/7) 1(6.03 Trip logic circuits S 2.2.38 Knowledge of conditions and 4.5 88 limitations in the facility license.

= = = =

(CFR:41.7!41.10I43.1I45.13)

= = = = = = = = = = = = =-

K1 Knowledge of the physical 013 Engineered Safety Features R connections and/or cause effect 4.1 41 Actuation relationships between the ESFAS and the following systems:

(CFR: 412 to 41.9 / 45.7 to 45.8)

K1.12 ED/G K5 Knowledge of the operational R implications of the following concepts 2.9 42 as they apply to the ESFAS:

(CFR: 41.5/ 45.7)

K5.02 Safety system logic and reliability K4 Knowledge of CCS design feature(s) 022 Containment Cooling R and/or interlock(s) which provide for the 2.6 43 following:

(CFR: 41.7) 1<4.05 Containment cooling after LOCA destroys ventilation ducts 025 Ice Condenser Not applicable to Surry K3 Knowledge of the effect that a loss or 026 Containment Spray R malfunction of the CSS will have on 4.2 44 the following:

. (CFR: 41.7 / 45.6)

K3.02 Recirculation spray system A4 Ability to manually operate and/or 039 Main and Reheat Steam R monitor in the control room: 3.8 45 (CFR: 41.7/ 45.5 to 45.8)

A4.04 Emergency feedwater pump turbines Ki Knowledge of the physical 059 Main Feedwater R connections and/or cause-effect 3.4 46 relationships between the MFW and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

Ki .02 AFW system 1<2 Knowledge of bus power supplies to 061 Auxiliary/Emergency R the following: 3.2 47 Feedwater (CFR: 41.7) 1<2.01 AFW system MOVs K5 Knowledge of the operational R implications of the following concepts 3.2 48 as the apply to the AFW:

(CFR: 41.5/ 45.7)

K5.02 Decay heat sources and magnitude KS-Knowledge-of--the effect that-a less-er 062 AG-Eleetr4eal-Distcibution R #tia--ati 37 49 078 Instrument Air System system-wHI-liave-en-the-folIowing 3 4 .

417 b4&

K3.02 Systems having pneumatic a1ve & co trol,

= = = = = = =

= K3;03DGsysteni

K4 Knowledge of DC electrical system 063 DC Electrical Distribution A design feature(s) and/or interlock(s) 2.9 50 which provide for the following:

(CFR: 41.7)

K4.02 Breaker interlocks, permissives, bypasses and cross-ties.

Al Ability to predict and/or monitor changes in parameters 2.5 51 associated with operating the DC electrical system controls including:

(CFR: 41.5 / 45.5)

Al .01 Battery capacity as it is affected by discharae rate K6 Knowledge of the effect of a loss or 064 Emergency Diesel Generator R malfunction of the following will have on 2.7 52 the ED/G system:

(CFR: 41.7 I 45.7)

K6.07 Air receivers A2 Ability to (a) predict the impacts of 073 Process Radiation R the following malfunctions or operations 2.5 53 Monitoring on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the

  • consequences of those malfunctions or operations:

(CFR: 415/4&5/45.3/45.13)

A2.01 Erratic or failed power supply A2 Ability to (a) predict the impacts of the following malfunctIons or S operatIons on the PRM system; and 2.9 89 (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5/ 43.5 / 45.3145.13)

A2.03 CalIbration drift Al Ability to predict and/or monitor 076 Service Water A changes in parameters (to prevent 2.6 54 exceeding design limits) associated with operating the SWS controls including:

(CFR: 41.5 / 45.5)

Al .02 Reactor and turbine building closed cooling water temperatures. -

2.1.7 Ability to evaluate plant 078 instrument Air S performance and make operational 4.7 90 judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5/43.5145.12 I 45.13)

A3 Ability to monitor automatic operation 103 Containment A of the containment system, including: 3.9 55 (CFR: 41.7 / 45.5)

= = = = = =

A3.01 Containment isolation

=

K/A Category Point Totals: 2 2j 2 3 3 3 3 3 3 2 2 Group Point Total: 28

= = L

= =

3

-= =

2

5

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 -2 Pnt Systems Ticr2/Group2 (AC I SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IA #

1234561234 K2 Knowledge of bus power supplies to the 001 Control Rod Drive R following: 2.7 56 (CFR: 41.7)

K2.03 One-line diagram of power supplies to logic circuits 002 Reactor Coolant K3 Knowledge of the effect that a loss or 011 Pressurizer Level Control R malfunction of the PZR LCS 3.2 57 will have on the following:

(CPA: 41.7/45.6)

K3.01 CVCS 014 Rod Position indication A2 02 au t o e ra Ic oj :r ti n f detectors or compensating compol mts 3.1 3.5 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation K6 Knowledge of the effect of a loss or 017 In-core Temperature Monitor R malfunction of the following irM system 2.7 58 components:

(CFR: 41.7/ 45.7)

K6.01 Sensors and detectors K1 Knowledge of the physical connections 027 Containment Iodine Removal R and/or cause-effect relationships between 34 59 the CIRS and the following systems:

(CFR: 41.2 to 41.9/ 45.7 to 45.8)

  • K1 .01 CSS 2.1.28 Knowledge of the purpose and 028 Hydrogen Recombiner R function of major system components and 4.1 60 and Purge Control controls.

(

(CFR: 41.7)

A4 Ability to manually operate and/or 029-Containment-Purge A monitor in the control room: 61 041 SDCS A4.02 Ability 0 ai a ly op ra e 11 /0 m ni or in the MCR the cooldown valves 2.7 A404-Containrnent-evaouation-signal 033 Spent Fuel Pool Cooling K4 Knowledge of design feature(s) 034 Fuel Handling Equipment S and/or interlock(s) which provide for the 3.3 91 following:

(CFR: 41.7)

K4.03 Overload protection A3 Ability to monitor automatic operation of 035 Steam Generator A the S/G including: 4.0 62 (CFR: 41.7 / 45.5)

A3.01 SIG water level control 041 Steam Dump/Turbine BypassControl 24274(nowledge-of-system-pwpose 045 Main Turbine Generator S and/or-function. 4.0 92

- = = = = = = = = = =

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation

= = = = = = = = = =

055 Condenser Air Removal A2 Ability to (a) predict the impacts of the 056 Condensate R following malfunctions or operations on the 2.6 63 Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.04 Loss of condensate pumps

.. cHemf 088+/-iqut&Radwaste- the-4oliowingaHunctloas..or operatIonson-4he-Liqul4-Radwasta-Syemtn4hose-pFedIetlonsusepreeedures-to-eorrect, ehe shesme#un operaons:

liuumsoHon Al Ability to predict and/or monitor 071 Waste Gas Disposal R changes in parameters(to prevent 2.5 64 exceeding design limits) associated with Waste Gas Disposal System operating the controls including:

(CFR: 41.5/ 45.5)

Al .06 Ventilation system K5 Knowledge of the operational 072 Area Radiation Monitoring B implications of the following 2.7 65 concepts as they apply to the ARM system:

(CFR: 41.5 / 45.7)

K5.01 Radiation theory, including sources, types, units, and effects 075 Circulating Water 079 Station Air 086 Fire Protection

=

K/A Category Point Totals: 1 1 1 0 1 1 1 1 1 1 1 Group Point Total: 10

=1 1 1 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO_____ SRO-Only FR lR 2.1.1 2.1.1 Knowledge of conduct of operations requirements. 3.8 66 (CFR: 41.10/45.13) 2.1.8 2.1.8 Ability to coordinate personnel activities outside the 3.4 67 C d t control room.

of° p rations (CFR: 41.10 / 45.5 / 45.12 / 45.13) 2.1.26 2.1.26 Knowledge of industrial safety procedures (such 3.4 68 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

(CFR: 41 .10/45.12) 2.1.34 2.1.34 Knowledge of primary and secondary plant 3.5 94 chemistry limits.

(CFR:_41.10/43.5/45.12) 2.1.13 2.1.13 Knowledge of facility requirements for controlling 3.2 95 vital/controlled access.

(CFR:_41.10/43.5/45.9/45.10)

Subtotal 3 2 2&4 22A-m{ti-unftHeense)-AbiIityto-expIain-the-variatiens-in- 3.6 69 2 2 35 contrel-bearti/ContrOl-foom-4ayoutSTsyStemSI-insffiimentatien-anproeeduraI-aetiens-between-uflits-at a-faeility-Abilicy to determine Technical Specificat on Mod of Ope ation.

2 ment (GFR: 41.6/41.7-/-41.10/45.1 /4543)

Control 2.2.44 2.2.44 Ability to interpret control room indications to verify 4.2 70 the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR:_41.5/ 43.5 / 45.12) 2.2.11 2.2.11 Knowledge of the process for controlling temporary 3.3 96 design changes.

(CFR: 41.10/43.3/45.13) 2.2.12 2.2.12 Knowledge of surveillance procedures. 4.1 97 (CFR: 41.10 / 45.13)

Subtotal 2 2 2.3.7 2.3.7 Ability to comply with radiation work permit 3.5 71 requirements during normal or abnormal conditions.

(CFR: 41.12/45.10) 3 2.3.12 2.3.12 Knowledge of radiological safety principles 3.2 72 Radiation pertaining to licensed operator duties, such as Control containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR:41.12/45.9/45.10) 2,3.13 2.3.13 Knowledge of radiological safety procedures 3.8 98 pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

(CFR: 41.12/43.4/45.9/45.10)

Subtotal 2 1 2.4.5 2.4.5 Knowledge of the organization of the operating 3.7 73 procedures network for normal, abnormal, and 4.

emergency evolutions.

Emergency (CFR: 41.10/43.5/45.13)

Procedures! 2.4.20 2.4.20 Knowledge of the operational implications of EOP 3.8 74 Plan warnings, cautions, and notes.

(CFR: 41.10/43.5/45.13) 2.4.37 2.4.37 Knowledge of the lines of authority during 3.0 75 implementation of the emergency plan.

(CFR: 41.10 / 45.13) 2.4.16 2.4.16 Knowledge of EOP implementation hierarchy and 4.4 99 coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

(CFR: 41.10/43.5/45.13) 2.4.30 2.4.30 Knowledge of events related to system 4.1 100 operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

(CFR: 41.10/43.5/45.11)

Subtotal 3 2 Tier 3 Point Total 10 7

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