ML102780341

Initial Exam 2010-301 Final Administrative Documents

ML102780341
Person / Time
Site:	Surry
Issue date:	09/14/2010
From:	NRC/RGN-II
To:	Virginia Electric & Power Co (VEPCO)
References
50-280/10-301, 50-281/10-301
Download: ML102780341 (23)

Text

ES-201 Examination PreDaration Checklist Form ES-201-1 Target Chief Date*

Task Description (Reference)

Examiners Initials

-180 1.

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

/743

-120 2.

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

-120 3.

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

[fl13

-120 4.

Corporate notification letter sent (C.2.d) 1Y

[-90]

[5.

Reference material due (C.1.e; C.3.c; Attachment 3)]

fl113

(-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-1 s, ES-401 -1/2, ES-401 -3, and ES-401-4, as applicable (C.1.e and f; C.3.d)

{-70)

{7.

Examination outline(s) reviewed by NRC and feedback provided to facility 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, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d)

-30 9.

Preliminary license applications (NRC Form 398s) due (C.1.1; C.2.g; ES-202)

-14 10.

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

-14 11.

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

-14 12.

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

-7 13.

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

-7 14.

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

-7 15.

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

-7 16.

Approved scenarios, job performance measures, and questions distributed to 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.

Facility:

i4 Date of Examination:

Developed by: Written

- Facility El NRC II Operating

- Facility V NRC El ES-201, Page 25 of 28

\\-rr ES-201 Examination Outline Quality Checklist Form ES-201 -2 Facility:

5 o//

Date of Examination:

JL 7

?o/ 0 Initials Item Task Description

1.

a.

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

A 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.

7

/,1 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, instwment and component failures, technical specifications, S

and major transients.

M 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 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 j

j W

distributed among the safety functions as specified on the form I

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

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

(4) the number of new or modified tasks meets or exceeds the minwnixns specified on the form (5) the number of altemate 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.

n 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.

ii R

d.

Check for duplication and overlap among exam sections.

3 L

e.

Check the entire exam for balance of coverage.

f.

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

a Author

/f/*/947,ft99_

b. Facility Reviewer (*)

N J14 N/A

c. NRC Chief Examiner (#)

ARL A.

/ YYL. CET 12/18/tM

d. NRC Supervisor

--/.z_d 7

Note:

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

Not applicable for NRC-prepared examination outlines

FmItL,p m 1

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Surry Power Station Date of Examination:

7/26/2010 Initials Item Task Description

a b*

f 1.

a.

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

N/il ji)- N/j w

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, (j

S and major transients.

M 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 0)

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

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

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

c.

To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix 0.

I 3.

a.

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

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

distributed among the safety functions as specified on the form cI

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.

1 b.

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

E c.

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

4J R

d.

Check for duplication and overlap among exam sections.

C/

L e.

Check the entire exam for balance of coverage.

c_I 4_ li.,

f.

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

Cl L2_.

Printed Name/S iaoat Date

a. Author Cat e1,d32 / /Y

} 11

b. FacilityReviewer()

Pctc l-J.jj2.__

c. NRC Chief Examiner (#)

VPd-i,E4i5/

/cL

d. NRCSupervisor OfZ1/IO 7

Note:

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

Not applicable for NRC-prepared examination outlines

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 7/26/10, 8/2/10. 8/9/10 and 8-1-61tOas 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) of 7/26/10, 8/2/10. 8/9/10 and 8/16/10.

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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NOTES:

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DATE SIGNATU (2

DATE NOTE I I L1J /

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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 7/26/10, 8/2/10. 8/9/10 and 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 (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 7/26/10, 8/2/10. 8/9/10 and 8/16/10. 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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13. RC.3OiEI) 14:T Ottt k.,)k04 NOTES:

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PRINTED NAME 1.

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i-I JOB TITLE / RESPONSIBILITY trfl I) kI.1 5

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i,.siopAr SIGNATURE (1)

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DATE SIGNATURE (2)

DATE NOTE

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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 7/26/10, 8/2/10. 8/9/10 and

.L?1-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 (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 7/26/10, 8/2/10. 8/9/10 and 8/16/10. From the date that I entered into this security agreement until the completion of examination admiristration, 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.

SIGNATURE (1) 1.

2.

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3. 0 4.

W c7 5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

NOTES:

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PRINTED NAME JOB TITLE I RESPONSIBILITY

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DATE SIGNATURE(2)

DATE NOTE

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ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Surry Power Station Date of Examination:

07/26/10 Examination Level:

RO SRO Operating Test Number:

301 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Perform 1-OP-RX-010 (Documentation of Reactivity Parameters during Power Operations)

Conduct of Operations R/D GEN 2.1.37 (4.3/4.6)

==

Description:==

Calculate the reactivity parameters for a given time in core life and boric acid concentration.

Complete 1-OPT-RC-10.0 (Reactor Coolant Leakage

Computer Calculated)

Conduct of Operations GEN2.1.23 (43/4.4)

==

Description:==

Given plant leak rate data, complete 1-OPT-RC-10.0 and determine if the PT is SAT or UNSAT.

Generate a tagout to ensure a safe working boundary.

Equipment Control R/ M

==

Description:==

Generate a tagout utilizing controlled prints GEN2.2.13 (4.1/4.3) to ensure a safe working boundary exists.

Determine Stay Time.

Radiation Control R I M

==

Description:==

Given current dose and dose rates in an GEN2.3.4 (3.2/3.7) area, determine stay times.

Emergency Procedures/Plan NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (3 for ROs; 4 for SROs & RO retakes)

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Surry Power Station Date of Examination:

07/26/10 Examination Level:

RO LI SRO Operating Test Number:

301 Administrative Topic Type Describe activity to be performed (see Note)

Code*

Title:

Determine containment partial pressure following a loss of containment cooling (SRO only).

Conduct of Operations GEN 2.1.20 (4.6/4.6)

==

Description:==

Calculate containment partial pressure detectors during a loss of containment cooling and verify associated Technical Specifications are met.

Title:

Complete 1 -OPT-RC-1 0.0 (Reactor Coolant Leakage Computer Calculated).

Conduct of Operations RIN GEN2.1.23 (4.3/4.4)

==

Description:==

Given plant leak rate data, complete 1-OPT-RC-1 0.0 and determine if the PT is SAT or UNSAT. Determine if a Technical Specification violation exists.

Title:

Review a performance test to determine system operability (SRO only).

Equipment Control R / N GEN2.2.37 (3.6/4.6)

==

Description:==

Given a completed performance test, review the test for possible errors and identify any system operability concerns.

Title:

Determine Stay Time.

Radiation Control R / M

==

Description:==

Given current dose and dose rates in an GEN2.3.4 (3.2/3.7) area, determine stay times.

Title:

Classify an event in accordance with EPIP-1.01 R I M (SRO only).

Emergency Procedures/Plan GEN2.4.41 (2.9/4.6)

==

Description:==

Modified facility JPM that will result in a Site Area Emergency due to loss of power or control room evacuation.

NOTE:

All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (3 for ROs; 4 for SROs & RO retakes)

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

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

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Surry Power Station Date of Examination:

07/26/10 Exam Level: RD SRO-l SRO-U El Operating Test No.:

301 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.

Recover a dropped rod. APEOO3.AA1.02 (3.6/3.4)

D / S I

b. Depressurize the RCS with Normal Spray lAW 1 -AP-24.01.

N/S/A III 010.A4.01 (3.7/3.5)

c. Respond to a loss of Decay Heat Removal lAW AP-27.

M/S/A/L IV P

005.A4.01 (3.6/3.4)

d. Establish feed flow from the condensate system lAW FR-H.1.

M/S/A/L IV

- S EPEEO5.EA1.1 (4.1/4.0)

e. Respond to a spurious CS Actuation. 026.A4.01 (4.5/4.3)

D/S/A/EN V

f.

Align the Emergency Busses lAW AP-10.07 Attachment 4.

M/S/L VI 064A2.05 (3.1/3.2)

g. Isolate a WGDT release. 071.A3.03 (3.6/3.8)

N/S IX

h. Pressurizer level channel fails low. 01 1.A2.1 1 (3.4/3.6)

M/S II In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for S RD-U) i.

Isolate Charging Crosstie lAW ECA-0.2. APEO22.AA1.01 (3.4/3.3)

M/P/E/R II j.

Trip Unit 1 Reactor Locally (EPEO29EA1.12 (4.1/4.0)

M/P/E/A 1

k.

Fill the CC Head Tank using 1-BC-P-2. 008.A2.02 (3.2/3.5)

N/P VIII All RD and SRD-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRD-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RD / SRD-l I SRD-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature

- I

/

(control room system)

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

(R)CA 1 I 1 I 1 (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Surry Power Station Date of Examination:

07/26/10 Exam Level: RO Li SRO-l SRO-U Li Operating Test No.:

301 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.

Recover a dropped rod. APEOO3.AA1.02 (3.6/3.4)

D / S I

b. Depressurize the RCS with Normal Spray lAW 1-AP-24.01.

N/S/A III 010.A4.01 (3.7/3.5)

c. Respond to a loss of Decay Heat Removal lAW AP-27.

M/S/A/L IV P

005.A4.01 (3.6/3.4)

d. Establish feed flow from the condensate system lAW FR-Hi.

MIS/A/L IV

- S EPEEO5.EA1.1 (4.1/4.0)

e. Respond to a spurious CS Actuation. 026.A4.01 (4.5/4.3)

D/S/A/EN V

f.

Align the Emergency Busses lAW AP-10.07 Attachment 4.

M/S/L VI 064A2.05 (3.1/3.2)

g. Isolate a WGDT release. 071.A3.03 (3.6/3.8)

N/S IX h.

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

Isolate Charging Crosstie lAW ECA-0.2. APEO22.AA1.01 (3.4/3.3)

M/P/E/R II j.

Trip Unit 1 Reactor Locally. EPEO29EA1.12 (4.1/4.0)

M/P/E/A 1

k.

Fill the CC Head Tank using 1-BC-P-2. 008.A2.02 (3.2/3.5)

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

Type Codes Criteria for RO / SRO-l / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)mergency or abnormal in-plant 1 / i / 1 (EN)gineered safety feature

- /

/

(control room system)

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

(R)CA 1 / 1 I i (S)imulator

1 9N/ft 7 Sr ES-301 Operating Test Quality Checklist Form ES-301-3 Facility:

Surry Power Station Date of Examination:

7/26/2010 Operating Test Number: 2010-301 Initials

1. General Criteria a

b*

ff a.

The operating test conforms with the previously approved outline; changes are consistent with c..j 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 cf during this examination.

C-LII c.

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

4 d.

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

e.

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

=

=

2. Walk-Through Criteria

a.

Each JPM includes the following, as applicable:

initial conditions initiating cues references and tools, including associated procedures D

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 critena 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 f

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 y

ft9 Form ES-301-4 and a copy is attached.

b

Printed Name! Signature Date a.

Author Cqv r7.v,i /

7--- -i b.

Facility Reviewer()

c.

NRC Chief Examiner (#)

/.

13i73//2ZiC d.

NRC Supervisor LL.i&T. Wlb) LJ/

NOTE:

The facility signature is not applicable for NRC-develope a.

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

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

Actual Attributes I/3 ii(

i1i3

.a ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Surry Power Station Date of Exam: 7/26/10 Scenario Numbers: //3 Operating Test No.:2010-301 QUALITATIVE ATTRIBUTES lnials

a b*

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, 42 3.

Each event description consists of the point in the scenario when it is to be initiated

,413 the malfunction(s) that are entered to initiate the event I

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.

7 t 40 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.

C/ c.. 2 9.

The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated

(.Oi..)

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).

1 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).

I 13.

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

t/

1.

Total malfunctions (58) 2.

Malfunctions after EOP entry (12) 3.

Abnormal events (24) 4.

Major transients (12) 5.

EOPs entered/requiring substantive actions (12) 6.

EOP contingencies requiring substantive actions (02) 7.

Critical tasks (23) c,7/g.

-c

/j/f

_2L3___%

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Surry Power Station Date of Exam: 7/26/10 Scenario Numbers:Y/!

Operating Test No.:2010-301 QUALITATIVE ATTRIBUTES lnials

a b*

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 scenanos consist mostly of related events.

3.

Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable) 4.

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

7

/

5.

The events are valid with regard to physics and thermodynamics.

7 ifl 6.

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

7.

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

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

Cues are given.

8.

The simulator modeling is not altered.

9.

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

/

performance deficiencies or deviations from the referenced plant have been evaluated

(,

to ensure that functional fidelity is maintained while running the planned scenarios.

10.

Every operator will be evaluated using at least one new or significantly modified scenario.

U 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).

/1 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).

V

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 /

2.

Malfunctions after EOP entry (12)

/ (4 / L4

3.

Abnormal events (24)

Lf / 4

/

4.

Major transients (12) 2 / a /3 5.

EOPs entered/requiring substantive actions (12)

/. /

6.

EOP contingencies requiring substantive actions (02) 1

/ I

/ I 7.

Critical tasks (23)

/ I /

fijz LP7(

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility: Surry Power Station Date of Exam: 7/26/10 Scenario Numbers:? /

/

Operating Test No.2010-301 QUALITATIVE ATTRIBUTES lnftials

a b*

c#

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

2.

The scenarios consist mostly of related events.

3.

Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew U

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.

I 5.

The events are valid with regard to physics and thermodynamics.

6.

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

7.

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

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

Cues are given.

8.

The simulator modeling is not altered.

CC 9.

The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated D

to ensure that functional fidelity is maintained while running the planned scenarios.

N 10.

Every operator will be evaluated using at least one new or significantly modified scenario.

,f J

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

I.

Total malfunctions (58) 7 /

/

-,f 2.

Malfunctions after EOP entry (12) 3 /

I 3.

Abnormal events (24) 5 /

/

4.

Major transients (12) p /

/

._i:_

5.

EOPs entered/requiring substantive actions (12)

I

/

/

c.7 6.

EOP contingencies requiring substantive actions (02)

/

1 ci/

7.

Critical tasks (23) 2 i

/

Y

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Surry Power Station Date of Exam: 7/26/2010 Operating Test No.: 2010-301 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

4 T

O T

A L

M I

N I

M U

M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

RO SRO-I SRO-U RX 5

5 4

5 1

1 0 NOR 1

1 1 1 I/C 3,6,7 2,4, 7,8 3,5 3,6,7 4

4 2 MAJ 7,9 6

6,7,9 6,8 2

2 1 TS 0

2 2 RO SRO-I SRO-U RX 5

5 4

5 1

1 0 NOR 1

1 1

1 1

1 1 I/C 2,4, 8

3,7 2,3,8 2,4,7 **

4 4 2 MAJ 7,9 6

6,7,9 6,8 2

2 1 TS 0

2 2 RO SRO-I SRO-U RX 5

5 4

5 1

1 0 NOR 1

1 1

1 1

1 1 I/C 2,3,4 6,7,8 2,3,4 7,8 2,3,5 8

2,3,4 6,7 4

4 2 MAJ 7,9 6

6,7,9 6,8 2

2 1 TS 2,4 3,5 1,2 4,5 0

2 2 RO SRO-I SRO-U RX 5

5 4

5 1

1 0 NOR 1

1 1 1 I/C 3,6,7 2,4, 7,8 3,5 3,6,7 4

4 2 MAJ 7,9 6

6,7,9 6,8 2

2 1 TS 0

2 2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

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

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Surry Power Station Date of Exam: 7/26/2010 Operating Test No.: 2010-301 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 5

6 7

T O

T A

L M

I N

I M

U M(*)

CREW POSITION CREW POSITION CREW POSITION CREW POSITION S

R O

A T

C B

O P

S R

O A

T C

B O

P S

R O

A T

C B

O P

S R

O A

T C

B O

P R

I U

RO SRO-I SRO-U RX 2

1 5

1 1 0 NOR 1

1 1 I/C 4,5,9 3,4,6, 8

2,4,6 8

4 4 2 MAJ 7,9 6,7,9 7,9 2

2 1 TS 0

2 2 RO SRO-I SRO-U RX 2

1 5

1 1 0 NOR 2,6 3

1 1

1 1 I/C 3,8 2,5,8 2,3,8 4

4 2 MAJ 7,9 6,7,9 7,9 2

2 1 TS 0

2 2 RO SRO-I SRO-U RX 2

1 5

1 1 0 NOR 2,6 3

1 1

1 1 I/C 3,4,5 8,9 2,3,4 5,6,8 2,3,4 6,8 4

4 2 MAJ 7,9 6,7,9 7,9 2

2 1 TS 1,5 2,3 2,4 0

2 2 RO SRO-I SRO-U RX 2

1 5

1 1 0 NOR 1

1 1 I/C 4,5,9 3,4,6, 8

2,4,6 8

4 4 2 MAJ 7,9 6,7,9 7,9 2

2 1 TS 0

2 2 Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

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

ES-301 Competencies Checklist Form ES-301-6 Facility: Surry Power Station Date of Examination: 7/26/2010 Operating Test No.: 2010-301 APPLICANTS RD BOP

[1 RD RD El SRO-I El SRO-I SRO-I El SRO-I SRO-U El SRO-U El SRO-U El SRO-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1

2 34 1

2 34 567 56 7

Interpret/Diagnose Events 2,3, 2,3, All 2,3, 2,3, 2,3, All 2,3, 1,2, All 2,3, 1,2, All 2,3, and Conditions

4,5, 4,5, 3,4, 45 6,7, 6,7, 6,7, 6,7, 6,7, 6,7, 5,7, 6,7, 5,7, 6,7, 8,9 8

8 8,9 8

8 8,9 8,9 8,9 8,9 Comply With and All All All All All All All All All All All All All All Use Procedures (1)

Operate Control All All All All N/A N/A N/A N/A All All All N/A N/A N/A Boards (2)

Communicate All All All All All All All All All All All All All All and Interact Demonstrate Supervisory N/A N/A N/A N/A All All All All N/A N/A N/A All All All Ability (3)

Comply With and N/A N/A N/A N/A 2,4 3,5 1,2 4,5 N/A N/A N/A 1,5 2,3 2,4 Use Tech. Specs. (3)

Notes:

(1)

Includes Technical Specification compliance for an RD.

(2)

Optional for an S RD-U.

(3)

Only applicable to SROs.

Instructions:

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

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

Group Randomly Selected K/A Reason for Rejection 1/2 000059AA1.02 The K/A focused on the ability to operate or monitor the Area Radiation Monitor (ARM) system as it applies to the Accidental Liquid Radwaste Release. Could not develop a question on this topic because the ARM system at Surry does not monitor the Liquid Radwaste areas or lines. Replaced with 000059AA1.01 (Radioactive-liquid monitor - RO -3.5).

2/1 061K5.03 The K/A focused on the knowledge of the operational implications of pump head affects when the control valve is shut as it applies to the Auxiliary Feedwater (AFW) System. Could not develop a question that was plant-specific and discriminating. Replaced with 061K5.05 (Feed line voiding and water hammer - RO -2.7).

2/1 061A3.04 The K/A focused on the ability to monitor automatic operation of the AFW system, including automatic AFW isolation. Could not develop a question on this topic because the AFW system at Surry employs flow restricting venturis in the supply lines to limit flow during a line break rather than isolation valves that automatically close on high supply line flow. Replaced with 061A3.03 (AFW S/G level control on automatic start).

2/1 (KDS) 103 K3.03 The K/A focused on the effect that a loss or malfunction of the containment system will have on containment integrity under refueling operations. Per Surry Tech Spec, Containment Integrity is not required below 200 degrees F. Replaced with 103 K3.01 (Loss of containment integrity under shutdown conditions).

2/2 (MAB) 056A2.05 Could not write an SRO-only question for selected K/A. Randomly selected 086A2.01.

1 /2 (KDS) 024G2.4.20 Could not write an SRO-only question for selected K/A. Randomly selected 024G2.4.11.

2/2(MKM) 075K2.03 The selected K/A requires knowledge of electrical bus power supplies to Emergency/essential SWS pumps. At Surry, the Emergency/essential SWS pumps are powered from individual diesels, therefore the K/A does not apply to Surry. Randomly and systematically replaced with K/A 015K2.01 (Knowledge of bus power supplies to NIS channels, components, and interconnections).

2/2(MKM) 068K6.10 The selected K/A topic (effect of radiation monitors on liquid radwaste system) when applied to the Surry process radiation monitor system excessively overlaps with another K/A, 059AA1.01, which is dealing with an inadvertent liquid radwaste release and radiation monitors. Randomly and systematically replaced with K/A 041K6.03 (Knowledge of the effect of a loss or malfunction on the following will have on the Steam Dump System: Controller and Positioners, including ICS, S/G, CRDS).

1/1 (KDS) 062AK3.04 Could not develop an operationally valid question (loss of CCWs affect on Service Water discharge header). NRC randomly selected replacement K/A 062AK3.02).

ES-401 Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws

4. Job Content Flaws

5. Other

6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

1. /

units Back-ward Q=

K/A SRO Only No comments. Surry 2010-301 was written by the NRC.

Instructions

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

1.

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

2.

Enter the level of difficulty (LOD) of each question using a 1 - 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).

4.

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 questions that are sampled

6.

Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

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

7.

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?

8.

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

/Att 2fPfr.1 ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:, (J2s.4 Date of Exam: elc oç-

Exam Level: RD t SRD Li o8/og/o, initial Item Description a

b*

1.

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

N il fl3 2.

a.

NRC KJAs are referenced for all questions.

b.

Facility learning objectives are referenced as available.

3.

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

4.

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

5.

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

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently, or the licensee certifies that there is no duplication; or other (explain) 6.

Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest

new or modified): enter the actual RD / SRO-only ff i3 /

9,,,

(.4.5 question distribution(s) at right.

1 qq,

7.

Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; the SRD exam may exceed 60 percent if the randomly Go selected K/As support the higher cognitive levels; enter

/

the actual RD / SRD question distribution(s) at right.

8.

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

9.

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

10.

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

11.

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

j Ppted Name / Signature Date

a. Author p

.3

b. Facility Reviewer ()

/2

c. NRC Chief Examiner (#)

A.

/

d. NRC Regional Supervisor JL(?)t1XTJJ1C)iAkI&1/

Note:

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

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

ES-401, Page 29 of 33

The Final Written Exam Sample Plan consists of the combination of the Draft Written Exam Sample Plan and the ES-401-4.

ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility:

Surry Date of Exam: 10AUG2010 Exam Level: RO x SRO x Initials Item Description a

b c

1.

Clean answer sheets copied before grading t_

t4/,

Y1)3 2.

Answer key changes and question deletions justified and_documented 3.

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

!y NJ1 4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80, as_applicable,_+/-4%_on_the_SRO-only)_reviewed_in_detail 5.

All other failing examinations checked to ensure that grades N

are justified J

14 6.

Performance on missed questions checked for training deficiencies and wording problems; evaluate validity I$

443 of questions missed_by half or more of the_applicants Printed Name/Signature Date

a. Grader Ccek

b. Facility Reviewer(*)

c. NRC Chief Examiner (*)

A. /

1 JC.7-

d. NRC Supeisor (*)

(*)

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