ML080720485

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NRC Examination Report Nos. 05000327-08-301 and 05000328-08-301
ML080720485
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 01/31/2008
From: Widmann M
Division of Reactor Safety II
To:
References
Download: ML080720485 (59)


See also: IR 05000327/2008301

Text

1.

2.

3.

4.

5.

6.

7.

ADMINISTRATIVE DOCUMENTS

(Yellow Paper)

E

P

.

C

ES-201-1/'

xam

reparation

hecklist

.

/

Exam Outline Quality Checklist. J:>:u=:

ES-201-2

Exam Security Agreement(s)

ES-201-3./

Administrative Topics Outline (Final)

ES-301-1 /

C~ntrol Room Systems & Facility Walk-through Test Outline

./

(Final)

ES-301-2

/

Operating Test Quality Check Sheet

ES-301-3

J

Simulator Scenario Quality Check Sheet

ES-301-4

8.

Transient and Event Checklist

.

9.

Competencies Checklist

.

10.

Written Exam Quality Check Sheet

.

I

ES-301-5

/

ES-301-6

.

/

ES-401-6

11.

Written Exam Review Worksheet

ES-401-9

12.

Written Exam Grading Quality Checklist

ES-403-1 ./

13.

Post-Exam Check Sheet

ES-501-1/'

14.

Facility Submittal Letter.s ( 0

SE{}uoyAH

oZO~8-JL)/

[]

~.

ES*201

Examination Preparation Checklist

Form ES*201*1

Facility:

<: lVlAO;! rW

Date of Examination: -:r4-N. &'OClC~

Developed by: Written - Facility ~NRC 0

II

Operating - Facility MNRC 0

Target

Chief

Date"

Task Description (Reference)

Examiner's

Initials

-180

1.

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

IJifS

-120

2.

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

r~

-120

3.

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

r0kP

-120

4.

Corporate notification letter sent (C.2.d)

y11f>

[-90]

[5.

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

!Y~

{-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-O-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

tms

licensee (C.2.h; C.3.e)}

{-45}

8.

Proposed examinations (including written, walk-through JPMs, and

scenarios, as applicable), supporting documentation (including Forms

m$>

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 398's) due (C.1.1; C.2.g;

I~

ES-202)

-14

10.

Final license applications due and Form ES-201-4 prepared (C.1.1; C.2.i;

/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)

'rn!b

-7

13.

Writt~n exam~ons and oper~tests approved by NRC supervisor

(C.2.1; C.3.h)

-7

14.

Final applications reviewed; 1 or 2 (if >10) applications audited to confirm

flI4IP

qualifications / eligibility; and examination approval and waiver letters sent

(C.2.i; Attachment 5; ES-202, C.2.e; ES-204) ],w-s;..v--et'::,-,,) :2 G..K!~"""'-l.£v;....J

-7

15.

Proctoring/written exam administration guidelines reviewed

mrs

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.

ES-201, Page 25 of 28

ES*201

Examination Outline Quality Checklist

Form ES*201*2

c#

b'

a

~1ZJrwP

~7ZJIMP

-~ 'llJ r#b

Initials

Date of Examination: 1/;)..00?:j'

Task Description

d.

Assess whether the justifications for deselected or rejected KIA statements are appropriate.

a.

Verify that the outline(s) fit(s) the appropriate model, in accordance with ESA01.

f--.--*-*--------------------------------+--t-'-~+_~__11

b.

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

--2..,,:cOon 0.1 of ES-401 ar:.d whether all KIA cateqories are appropriately sampled.

c.

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

Item

I----+-*--------------------------------t-::..-j-..:;:--t-~I

1.

W

R

I

T

T

E

N

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.

a.

Using Form E$-301-5, verify that the proposed scenario sets cover the required number

of normal evolutions, instrument and component failures, technical specifications,

and major transients.

f--*-------------'-----------------------;---;f-<--t---il

b.

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

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

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

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

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

2.

I

M

U

L

A

To

R

s

Ir----I-*--*-~----------------------------_t_-+_-+--_il

3

W

I

T

a.

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

(1)

the outlir&(s) contain(s) the required number of control room and in-plant tasks

distributed among the safety functions as specified on the form ./'

(2)

task repetition from the last two NRC examinations is within the limits specified on the fonrn ......

(3)

no tasks are duplicated from the applicants' audit test(s)./

1~."11

J fY\\tS

(4)

the number of flew or modified tasks meets or exceeds the minimums specified on the form ,/

.

/!II./ I

(5)

the number of alternate path, low-power, emergency, and RCA tasks meet the criteria.>

on the form.

-;~tZ..

Iv~

15 '1?J ifVIfJ

i1'~ 1lJ 1~

f0~'iv~

-j-:) 7lJ \\\\rR>

Assess whether the 10 CFR55,41 143 and 55,45 sampling is appropriate.

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

e.

Check the entire exam for balance of coverage.

d.

Check for duplication and overlap among exam sections.

b.

1-*-*-----------------....:..--:..-..:....:....:....:..-----------j-!:~+"u::.'9-'~-i1

c.

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

G

E

N

E

R

p.,

L

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

0/'

,..--.-

of applicants and ensure that no items are duplicated on subsequent days.

4.

R.

Assess whether plant-specific priorities (including PRA and IPE insights) are covered

in the appropriate exam sections.

Note:

Date

j 1/7(t/'8

I JI7/~

Q2 /0.4bM'-,

t'-7{l5'I",

a. Author

b. Facility Reviewer (')

c. NRC Chief Examiner (if)

d. NRC Supervisor

IJA.II'Fn..l./~\\nll.Uf..:,/

~

II-'

--Ifll.<::~~.,/Y 'L

  1. Independent NRC reviewer initial items in Colbmrr"C"; ctlref examiner concurrence required.
j,; >:>>.:,c,;c 'z... .,f<:'., ... ,'

",.; 11;;',;!:>;['

);V,':".

E8-201, Page 26 of 28

ES-201

Examination Outline Quality Checklist

DIll

7

Form ES-201-2

(

(

Facility:

Date of Examination:

Initials

Item

Task Description

b*

c#

a

1.

a.

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

~ V

~

W

./

R

b.

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

-IS .#J.... '01{S

I

Section 0.1 of ES-401 and whether all KiA cateqories are appropriately sampled.

T

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

--1) .,~ *

T

c.

E

d.

Assess whether the justifications for deselected or rejected KiA statements are appropriate.

~ I-ra)

N

NJ6

2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number

~ 1Y

of normal evolutions, instrument and component failures, technical specifications,

M$

S

and major transients.

I

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 ~ ~ r1£

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 testis). and that scenarios will notbe repeated on subsequent days.

0

c.

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

p

R

and quantitative criteria specified on Form ES-301-4 and described in AppendiX2Ctt -tlcn

Irv ~

-

30

'

u.h

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,'U

wl-\\'

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{)IIVII~

W(V.[\\SI".fL "i-iAS

~,IA

~'1'v)k-\\t: .

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

r<<V

/

(2)

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

76 rr

T

(3)

no tasks are duplicated from the applicants' audit testis)

(4)

the number of new or modified tasks meets or exceeds the minimums 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

7!J ~

(ff6

(2)

at least one task is new or significantly modified

(3)

no more than one task is repeated from the last two NRC licensinq examinations

c.

Determine if there are enough different outlines to test the projected number and mix

15,iJ ~

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

76 ~ tI1t

in the appropriate exam sections.

G

b.

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

.~ ~ tWP

E

N

c.

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

76 .<lJ ~

E

d.

Check for duplication and overlap among exam sections.

76 .<tJ ~

R

A

e.

Check the entire exam for balance of coverage.

76 4r/ \\'\\Xb

L

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

o>> ~v..I 'f\\\\t5

f.

7"1omitS -:s:::

Printed Na

...' JO

ioltcPJih

a. Author

O"V'" .:>

~

~~

b. Facility Reviewer (*)

TJJ& I""" "'~

0

cJA If.."

e,

/-- Y

"' r. trJ/

jV//? (07

c. NRC Chief Examiner (#)

M.AI\\~ A- 'B4-r£5 I ~ ~ L/ J O<.:t.':is

"'/fltlo7

d. NRC Supervisor

J IIUI'N 1.(1:\\\\IfT)dlHIi-! / tfb'

1

{I/N!lJ1

(

-,

r

....

Note:

  1. Independent NRC reviewer initial items in Coiwr;n "c"; chief examiner concurrence required.
  • ()(C~'h\\trl.s

CU'- i1cted

d'Y1

L1'Mf\\'\\eJ."\\1- 'S"'~-\\-.

ES-201, Page 25 of 27

ES-201

Examination Security Agreement

Form ES-201-3

1.

Pre-Examination

J/:< elog ike!

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of ,7/?I/o(f

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

licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an

enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or

suggestions that examination security may have been compromised.

2.

Post-Examination

To the best of my kno~ledg2~1

id not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered

during the week(s) of !h9 -

i'~ O:9From 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.

.

JOB TITLE / RESPONSIBILITY

szl14E

DP~Tlo~

ES-201, Page 26 of 27

ES-201

Examination Security Agreement

Form ES-201-3

1.

Pre-Examination

/

/

I

I

'2.~{ o?f t"~v

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of ;2./ 'lJ(0'if 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

licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an

enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or

suggestions that examination security may have been compromised.

2.

Post-Examination

To the best of my knowled~e I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered

during the week(s) of ~~ - Y'f'OG' 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.

JOB TITLE / RESPONSIBILITY

kD

Ifo

~ogo

/20

ES-201, Page 26 of 27

DATE

SC-&>>fY#/

l:-£JOf"

ES~201

Examination See!~tl-A-8-ree-m-l!-n-t-F-crm-------------f-o-nn""(~s-2ft1*3

Pre-Exarnin:atfon

)!;z.r;/t;?

~wV

I ackrlo.edge that Ehave acquirHdspecialized knowledgeabout the-tIRe Ijc;ensing examillations t.cheduled for the week(s) of ?j~10 "l

as of the

date o.fmy signaturtr. I agree that I will no'! knowin{ly divulge any infurmation about these examinaoons to aly per-mns who haw not been authnrized

by the NRC chief examinet'". I urtde:rsland t'lat I ern £101to instruc;l. evaluate, or provide performeoce feedback 10thoseapj;li[;Clnls scheduled to be

admil'iisteled these licensing examinatlO1l$. from this dat.eunlil c:omplel:ion of examination administniliorl, except as specificalit noted oolow and

aultlorized byttle NRC (e.g., acting as a simt.Jator boot!

h 'Opef~or or eemmurlicatOl' is aooeptableif 111 iii indi\\lidLSlI does not select the fJainingCOnient or

llfovide direct a'" indirec1 feedback). Furthemllre. I aIrI aware of !tie physical security measures aJ1d rE!q\\lirernel11s (as documented fl the facjlil~

lit:erJsee's procecb'es) and understand thai vio!a1ionof the conditions of thks agreem enJ. mayrestflt in carnl!Dalion (If the elo:aminatioos and/or an

enfDlcement action agains1 me or lhefaGilitv licensee. Iw. immEdialelyreport to facility managemeritOf tire NRC chief examio@r 8rIY indications Dr

suggesfons that eKaminal~on o.ewrity may ha\\19 been compromised.

1.

2_

Post-E nmination

To tf1ebest of my lfficMtIedge. td id not divLIIgeto any un<llJthorlzed persons any irforrnatiQn ooncemiog the NRC Ii-cerlsing exarnillaticns admTiistered

dlJri1g the week(s) of

. From the dale that I entered into this sewlil1' agreemeflt unlil ttle compleliort of e:xami1ation admi1istratioo. rtid oot

instrudl. evaluale, or provide pelfurmance feedback m thase applicants who were administered these licensi"lg elC3minations, ext:ept as spef;ifically

noted beJow:and authorized by the NRC

.

ES-201, Page 26 of27



JOB rrns I RESPONSIBILITY

fS. \\J !ef'JPR

PRlmED!'WAE~

SIGNAT~

DJ}T~. ~."

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{

VA E

TE

1:~s8'H M.$G..*Jb(

.f-~-Fli../L-:o,..t

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  • _~iLE:.!LQ.7~~Z* Jl oK

2.

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3.

.

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4.

.

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5.

.

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6.

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7.

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9.

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10.,

_

11.,

.

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12.,

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13,,

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14.

15_,-='


NOTES:

C

0-

ES-301

Administrative Topics Outline

Form ES-301-1

(

(

Facility:

Sequoyah 1 & 2

Ro9

Date of Examination:

1/2008

Examination Level (circle one):

Operating Test Number:

NRC

Administrative Topic

Type Code*

Describe activity to be performed

(see Note)

Conduct of Operations

2.1.1

Knowledge of conduct of operations requirements. (CFR:

N,R

41.10/45.13)

3.7/3.8

Determine license status

Active / Inactive

Conduct of Operations

2.1.33

Ability to recognize indications for system operating

parameters which are entry-level conditions for technical

D,S

specifications. (CFR: 43.2 /43.3/45.3)

3.4 / 4.0

Perform Shift Log SI-2 SG Level Instrumentation (JPM

176)

2.2.18

Knowledge of the process for managing maintenance

Equipment Control

activities during shutdown operations.

N,R

(CFR: 43.5/45.13)

3.6

Containment Closure Time

Radiation Control

2.3.10

Ability to perform procedures to reduce excessive levels of

radiation and guard against personnel exposure. (CFR:

D,R

43.4 / 45.10)

2.9/3.3

Survey Map (JPM 166)

Emergency Plan

2.4.41

Knowledge of the emergency action level thresholds and

classifications.(CFR: 43.5/45.11)

4.1

D,S

Classify the REP Degraded Core with Possible Loss of

Coolable Geometry and Likely Cntmt Failure (JPM 109)

NOTE:

All items (5 total are required for SROs.

RO applicants require only 4 items unless they are retaking

only the administrative topics, when 5 are required.

  • Type Codes & Criteria:

(C)ontrol room

Class(R)oom

(D)irect from bank (:S: 3 for ROs; :s: for SROs & RO retakes)

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

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

(S)imulator

NUREG-1021

Revision 9

ES-301

Administrative Topics Outline

SRO Admin JPM Summary

Form ES-301-1

(

A1a

The applicant will evaluate the status of licensed operators work history to determine if license is active or

inactive.

A1b

The applicant will be required to recognize a required Technical Specification entry while completing and a

portion of the daily shift surveillance instruction.

A2

The applicant will evaluate a request to open a containment penetration during a refuel outage and determine

the requirements.

A3

The applicant will use a survey map to determine anti-contamination clothing requirements, stay time, and

radiation levels in area.

A4

The applicant will evaluate conditions for entry into the E-Plan, determine the proper classification, protection

action recommendation, and make required notifications.

NUREG-1021

Revision 9

ES-301

Control Room/In-Plant Systems Outline

Form ES-301-2

(

Facility:

Sequoyah 1 & 2

Date of Examination:

1/2008

-

Exam Level (circle one):

R~SRO~I SRO (U)

Operating Test No.:

NRC

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

System I JPM Title

Type Code*

Safety

Function

a.

W/E14 High Containment Pressure

(EA-1.1 )

3.7 I 3.7

D,A,S

5

Respond to High Containment Pressure (JPM 057AP1)

b.

003 Reactor Coolant Pump System

(A2.01 )

3.5 I 3.9

N,L,S

4P

Respond to a #1 RCP Seal Failure

c.

001 Control Rod Drive System

(A3.05)

3.5 I 3.5

M,A,L,S

1

Shutdown Bank Withdrawal

d.

004 Chemical and Volume Control System (A4.06)

3.6 13.1

N,L,S

2

Fill and Vent Excess Letdown

e.

038 Steam Generator Tube Rupture (EA1.32 )

4.6 14.7

D,A,S

3

SG tube rupture with MSIV fails to Close (JPM 075AP)

f.

015 Nuclear Instrumentation System (A1.01) 3.5 I 3.8

D,A,S

7

Calibrate Power Range Nuclear Instrumentation (JPM 22-AP2)

g.

064 Emergency Diesel Generator (ED/G) System (A4.06)

3.9 I 3.9

M,D,S

6

Shutdown the Diesel Generator (1A-A and 1B-B) (JPM 046-1)

h.

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

i.

061 Auxiliary I Emergency Feedwater System

(A2.04)

3.4 I 3.8

D,A,E,R

4S

Operate the TO AFW Pump Locally (JPM 74-2AP)

j.

004 Chemical and Volume Control System

(A2.25)

3.8 14.3

D,R

1

Uncontrolled Dilution Flow Path Isolation (O-SI-OPS 063-214.0)) (JPM 40-2)

k.

062 AC Electrical Distribution

(A2.10)

3.0 13.3

D,A

6

Transfer 480v SO Board 2A1-A from Normal to Alternate (JPM 061AP2)

@

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.

NUREG-1021

Revision 9

ES-301

Control Room/In-Plant Systems Outline

Form ES-301-2

\\,

~

  • Type Codes

Criteria for RO / SRQl-1 j SRO-U

" --

(A)lternate path

4-6/4-0'/2-3

iJJ

(C)ontrol room

ff!:<;47

(D)irect from bank

'5,9 /

(E)mergency or abnormal in-plant

1 /

1"1:?: 1 \\

(L)ow-Power / Shutdown

<:: 1 /

11:'?:1 .:>

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

2/'?2"1'2:1-1

(P)revious 2 exams

3/

3/

2 (randomly selected) 0

(R)CA

1 /

1/<:: 1 .......-

(S)imulator

JPM Summary

JPMA

JPM B

JPM C

JPM D

JPM E

(

'-

JPM F

JPM G

JPM I

RHR spray will be established in accordance with FR-Z.1, High Containment Pressure. This is a Bank

Alternate Path JPM.

An RCP seal failure will be diagnosed and the Abnormal Operating Instruction used to remove the pump

from service. This is a new low power/shutdown JPM

A failure of the step counter will occur during the withdrawal of Shutdown Rods requiring a reactor trip.

This is a new alternate path low power/shutdown JPM.

Excess letdown system will be filled and vented from the control room using the system operating

instruction. This is a new low power/shutdown JPM.

A Main Steam Isolation valve will fail to close during the isolation of steam side of a ruptured steam

generator will be isolated.. This is a Bank Alternate Path JPM.

Power Range nuclear instruments will be adjusted in accordance with the surveillance instruction O-SI-OPS-

092-078.0. This is a Bank Alternate Path JPM.

Unit 1 Diesel Generators will be shutdown per EA-82-1. This is a Bank modified JPM.

Plant JPM -The trip and throttle valve will not open electrically while TDAFW pump is being placed in

service locally. This is an Alternate path Bank JPM using emergency abnormal procedure performed inside

the RCA.

JPM J

Dilution flow path will be isolated using O-SI-OPS 062-214.0.

This is a Bank JPM performed inside the

RCA using an Appendix contains in a surveillance instruction.

JPM K

Plant JPM - A breaker will fail to operate while a transfer of a 480v Shutdown Board is being attempted.

This is a Bank Alternate Path JPM.

NUREG-1021

Revision 9

ES-301

Control Room/In-Plant Systems Outline

Form ES-301-2

(

Facility:

Sequoyah 1 & 2

Date of Examination:

1/2008

-

Exam Level (circle one):

RO I SRO(I)(:;RO (uij

Operating Test No.:

NRC

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

System I JPM Title

Type Code*

Safety

Function

a.

W/E14 High Containment Pressure

(EA-1.1 )

3.7 I 3.7

D,A,S

5

Respond to High Containment Pressure (JPM 057AP1)

b.

003 Reactor Coolant Pump System

(A2.01)

3.5 I 3.9

N,L,S

4P

Respond to a #1 RCP Seal Failure

c.

001 Control Rod Drive System

(A3.05)

3.5 I 3.5

M,A,L,S

1

Shutdown Bank Withdrawal

d.

e.

f.

g.

h.

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

i.

061 Auxiliary I Emergency Feedwater System

(A2.04)

3.4 I 3.8

D,A,E,R

4S

Operate the TD AFW Pump Locally (JPM 74-2AP)

j.

004 CI,eli lieal alld 'v'olUilie Conti 01 Systel Ii

(AZ.25)

3.8/4-:&-

D,R

'---1--

Ulieo'iti~IIedDilution Flow Patll IS9Iatiol~I-OPS0,6~+4:&)7~('"d'~!\\11~40'"2>>-~

~'f.

tl143 "I ~3/z~~n,

C-Y-tc.<,;"",<'d

'?e-t-

p/~.;,,,r

"-G'v-.t-_<:.~

<-..~

~(A.

'.

k ..A,,-(.j..*W,J. 1:::>, s<:..."""",t ... / L,="'-

k.

D(PJ. /tc EIe..G\\-t-\\c::..",J, 1:);sk\\"Du-Hc"" (A J, 10) :,.0/3,.3

D 1 ri

0

-Y;:-e",v5k ~v 'SD ~e.....J. 2.;11-1-14

~.iVv\\. (Vct1'f"'oC...(, ~ i41~ok(W(t

O~ I /l.p2.)

@

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.

NUREG-1021

Revision 9

ES-301

Control Room/In-Plant Systems Outline

Form ES-301-2

(

(

(

  • Type Codes

Criteria for RO / SRO-I / SRO-U

(A)lternate path

4-6 / 4-6 / 2-3 :>

(C)ontrol room

(D)irect from bank

~9/:':;8/

4],

(E)mergency or abnormal in-plant

1 /

1/:2::1\\

(L)ow-Power / Shutdown

1 /

1 / 21

7-

(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 /

1/21!fJ

(S)imulator

JPM Summary

JPM A

RHR spray will be established in accordance with FR-Z.1, High Containment Pressure. This is a Bank

Alternate Path JPM.

JPM B

An RCP seal failure will be diagnosed and the Abnormal Operating Instruction used to remove the pump

from service. This is a new low power/shutdown JPM

JPM C

A failure of the step counter will occur during the withdrawal of Shutdown Rods requiring a reactor trip.

This is a new alternate path low power/shutdown JPM.

JPM I

Plant JPM -The trip and throttle valve will not open electrically while TDAFW pump is being placed in

service locally. This is an Alternate path Bank JPM using emergency abnormal procedure performed inside

the RCA.

JPM J

Dilution flow path will be isolated using O-SI-OPS 062-214.0.

This is a Bank JPM performed inside the

RCA using an Appendix contains in a surveillance instruction.

NUREG-1021

Revision 9

ES-301

Operating Test Quality Checklist

Form ES-301-3

(

(

(

Facility:

Sequoyah 1 & 2

Date of Examination:

1/28/2008

Operating Test Number:

NRC

1. GENERAL CRITERIA

Initials

a

b*

c#

a.

The operating test conforms with the previously approved outline; changes are consistent

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

'/6 -;LJ t~~

distribution).

b.

There is no day-to-day repetition between this and other operating tests to be administered -rs

lyK!?

during this examination.

-rZJ

c.

The operating test shall not duplicate items from the applicants' audit test(s) (see Section

/'~

\\ri:7

D.1.a).

,7ZJ

d.

Overlap with the written examination and between different parts of the operating test is

/0

t~

within acceptable limits.

rzJ

e.

It appears that the operating test will differentiate between competent and less-than-

~

~ifv

competent applicants at the designated license level.

JZ---'

2. WALK-THROUGH CRITERIA

-

-

-

a.

Each JPM includes the following, as applicable:

initial conditions .,..

initiating cues ./

references and tools, including associated procedures v

reasonable and validated time limits (average time allowed for completion) and specific

designation if deemed to be time-critical by the facility licensee /"

17--~

operationally important specific performance criteria that include:

76

- detailed expected actions with exact criteria and nomenclature v

- 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

~

f7J {~

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

~ -n: .~

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

Printed Name / Signa~Q.

Date

.---r/'

~rvz'-5 /-:~~,

/1--

//;7108

a.

Author

7 hOl11ffS

b.

Facility Reviewer (*)

~,

i.)tlJLc.~

-:>>:

Iff 7/0 4

. I

...."'"'- '-'

.1-_ ./~~~..I~

c.

NRC Chief Examiner (#)

't-f\\ MUl A"'v':) AIK7 '/n~..~/l fti. 1l1'::1f:--.-..

o i /1"3!~trJB

d.

NRC Supervisor

J).AtG(jJJ...l.\\V If)MJJ.JAJ I 7!:.mlor

....-.--

t'i!lJ/!",

\\ " \\

.~

NOTE:

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

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

NUREG-1021

Revision 9

ES-301

Simulator Scenario Quality Checklist

Form ES-301-4

(

(

Facility:

Sequoyah 1 & 2

Date of Exam:

1/28/2008

Scenario Numbers:

1,2,3,4

Operating Test No.:

NRC

QUALITATIVE ATTRIBUTES

Initials

a

b*

c#

1.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of

73

service, but it does not cue the operators into expected events.

10 W$

2.

The scenarios consist mostly of related events.

-J~ "J'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

1~

/~ JV

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 '70

1'~

a credible preceding incident such as a seismic event.

7Z/

5.

The events are valid with regard to physics and thermodynamics.

7~ -IZ..-

\\~

6.

Sequencing and timing of events is reasonable, and allows the examination team to obtain complete '76

'j~

evaluation results commensurate with the scenario objectives.

-rt>>

7.

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

Operators

/'-5 Jl;

\\,,~

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

8.

The simulator modeling is not altered.

?~ ri- ~

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

/~ 71J ~

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

7~

~

scenarios have been altered in accordance with Section 0.5 of ES-301.

1V

11.

All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the

-/:5

.~

form along with the simulator scenarios).

jJ../

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).

TL/

13.

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

76 ~ '{'(lD

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

Actual Attributes

-

-

-

1

2

3

4

1.

Total malfunctions (5-8)

8/

16""' 7/ '16/ -;f~ -;L; Mf:,

2.

Malfunctions after EOP entry (1-2)

2""'

1...-- 72/ ;2/ /~

-rc; ~

3.

Abnormal events (2-4)

3""-

3"

4/

3/

.~

"T/.J

l~~

4.

Major transients (1-2)

1/

1v

1 /

1/ /,:) /L

i:~ID

5.

EOPs entered/requiring substantive actions (1-2)

1,/

1/

1/

1/ ?5

'17- "rib

6.

EOP contingencies requiring substantive actions (0-2)

1v

0,/

1/

1/ 7'7

7tr- ~

7.

Critical tasks (2-3)

2/

3v 2/

2/ 7~ -rt- vWJ3

NUREG-1021

Revision 9

ES-301

Transient and Event Checklist

Form ES-301-5

(

(

(

Facility:

Sequoyah 1 & 2

Date of Exam:

1/28/2008

Operating Test No.:

NRC

A

E

Scenarios

P

V

P

E

1

2

3

4

T

M

L

N

Spare

0

I

I

T

T

N

CREW

CREW

CREW

CREW

C

POSITION

POSITION

POSITION

POSITION

A

I

A

T

L

M

N

Y

U

T

P

M(*

E

S

A

B

S

A

B

S

A

B

S

A

B

R

I

U

R

T

0

R

T

0

R

T

0

R

T

0

0

C

P

0

C

P

0

C

P

0

C

P

RX

0",,-

1

1

1

1

0

NOR

1/

I

0

1

1

1

1

SROU

I/C

,\\5/

Z

3

8

4

4

2

MAJ

1/

i

0

1

2

2

1

TS

3/

c

0

3

0

2

2

RX

1/

0/

1

1

1

0

NOR

Ov

1/

1

1

1

1

SROI-1

I/C

3/

5/

8

4

4

2

0

MAJ

1v

1 v

2

2

2

1

TS

0

3/

3

0

2

2

RX

0

1/

0

1

1

1

0

NOR

I

0"

1

1

1

1

1

SROI-2

I/C

Y

4/

7

11

4

4

2

MAJ

f

1 v

2

3

2

2

1

TS

~

Ov

2

2

0

2

2

0

1

0

1

1

1

0

1

0

1

2

1

1

1

NA

7

5

3

15

4

4

2

1

1

1

3

2

2

1

2

0

0

2

0

2

2

1

1

0

1

1

1

4

4

2

2

2

1

0

2

2

NUREG 1021

Revision 9

ES-301

Transient and Event Checklist

Form ES-301-5

(

Facility:

Sequoyah 1 &2

Date of Exam:

4/9/2007

Operating Test No.:

NRC

A

E

Scenarios

P

V

P

E

1

2

3

4

T

M

L

N

Spare

0

I

I

T

T

CREW

CREW

CREW

CREW

N

C

POSITION

POSITION

POSITION

POSITION

A

I

A

T

L

M

N

Y

U

T

P

M(*

E

S

A

B

S

A

B

S

A

B

S

A

B

R

I

U

R

T

0

R

T

0

R

T

0

R

T

0

0

C

P

0

C

P

0

C

P

0

C

P

1

1

0

1

1

1

4

4

2

2

2

1

0

2

2

1

1

0

1

1

1

4

4

2

2

2

1

0

2

2

1

1

0

1

1

1

4

4

2

2

2

1

0

2

2

Instructions:

1.

Circle 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 service in both the "at-the-controls (ATC)" and

"balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or

component (I/C) malfunctions and one major transient, in 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 applicant's competence count toward the minimum requirements

specified for the applicant's license level in the right-hand columns.

This matrix assumes that Scenario 3 is used as the spare. If scenario 3 is used in combination with any

other scenario, the minimum requirements are still met for each applicant.

NUREG 1021

Revision 9

ES-301

Competencies Checklist

Form ES-301-6

(

(

Facility: Sequoyah 1 & 2

Date of Exam:1/28/2008

Operating Test No.: NRC

SRO

RO (ATC)

BOP/CRO

Competencies

SCENARIO

SCENARIO

SCENARIO

1

2

3

4

1

2

3

4

1

2

3

4

Interpret/Diag-

2,3,6,

3,4,5,

3,4,5,

2,5,6,

1,2,3,

2,5,6,

3,4,5,

nose Events

2-9

1-7,9

2-9

2-9

9

6,7,9

6,8,9

7,8

4-8

4,7,8

7

9

and Conditions

Comply With

1,2,3,

3,5,6,

1,3,4,

1,2,5,

1,4,5,

1,2,3,

1,2,6,

1,3,4,

and Use

ALL

ALL

ALL

ALL

6,8,9

9

5,6,8,

6,7,8

6,8

5,7

7

5,6,7,

Procedures (1)

9

9

Operate

1,2,3,

3,5,6,

1,3,4,

1,2,5,

1,4,5,

2,3,5,

1,2,6,

1,3,4,

Control Boards

N/A

N/A

N/A

N/A

6,8,9

9

5,6,8,

6,7,8

6,8,7

7

7

5,6,7,

(2)

9

9

Communicate

1,2,3,

1,3,4,

1,3,4,

and

ALL

ALL

ALL

ALL

6,8,9

3,4,5,

5,6,8,

1,2,5,

1,4,5,

1,2,3,

1,2,5,

5,6,7,

6,7,9

6,7,8

6,8,7

4,7,8

6,7

Interact

9

9

Demonstrate

Supervisory

ALL

ALL

ALL

ALL

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

Ability (3)

Comply With

and Use Tech.

2-4

1,2,4

3,4

2,3

N/A

N/A

N/A

N/A

N/A

N/A

N/A

N/A

Specs. (3)

Notes:

(1)

Includes Technical Specification compliance for an RO.

(2)

Optional for an SRO-U.

(3)

Only applicable to SROs.

Instructions:

Circle the applicants' license type and enter one or more event numbers that will allow the

examiners to evaluate every applicable competency for every applicant.

NUREG-1021

Revision 9

ES-401

Written Examination Quality Checklist

Form ES-401*6

~-CilitY:5(~~uoyah u s:

Date of Exam: 1/;1.008

Exam Level' RO .:*iSRO~1

..

Initial

Item Description

a

b*

c'

--;15

-

1

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

71r-J ~

2.

o .

NRC KJAs are referenced for all questions.

-;s

J}--/ rrIf?

b.

Facility learning objectives are referenced as available.

3.

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

--J6

-rz,J

v'v'R>

-

....

4

The sampling process was random and systematic (If more than 4 RO or 2 SRO questions

% 1P ~

were repeated from the last 2 NRC licensmp exams, consult the NRR OL program office).

5.

Question duplication from the license screening/audit exam was controlled

as indicated below (check the item that applies) and appears appropriate:

_

the audit exam was systematically and randomly deveioped; or

_

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

76 JZJ ~

__ the examinations were developed independently; or

"Jf.- the licensee certifies that there is no duplication; or

__ other (explain)


_._-

Ban:-r Mcditied

6.

Bank use meets limits (no more than 75 percent

New

from the bank, at least 10 percent new, and the rest

5/~-r;3 ~

25

/'6 "f1J fYIf;>

new or modified); enter the actual RO / SRO-only

,J,7 I IS

r----

question distribution(s) at right.

7.

Between 50 and 60 percent of the questions on the RO1MClnory

CIA

exam are wntten at the comprehension/ analysis level,

-15

the SR.O exam may exceed 60 percent If the randomly

-n> ~

selected K/As support the hiqhe: cognitive levels, enter

3 c;

/ 7

i70

/ la

the actual RO I SRO question distributiorus) at light

J

8.

References/handouts provided do not give away answers

-;:5 7lr/ IVS

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;

/6 .-fl-/

/'if:>

~.

deviations are justified.

10.

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

-/~

--y1--

1W1S

11

The exam contains the required number of one-point, multiple choice items;

-D 11P ~~

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

____

Printed Name / ~nat~~

Date

a. Author

210mm

O:'IV~'> / '/L/

-

v----:=:-

//1/ot'

b. Facility Reviewer (*J

-Z;Z~~...

/././/6'-

/~~ /'.;, /Z

fft;

c. NRC Chief Examiner (#)

~ It BtrT$/ ff;["J (j, I '" .J;:-:...

d

NRC Regional Supervisor

J..!J4<AUJ---r:. WttiJ)NV.t>J /

~

.

~

(

.

"----'"

"

Note:

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

ES-401, Page 30 of 34

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

BIW

GENERAL COMMENTS

B= Bank 1M=Modified 1N-New 1F-Fundamental Level (I.E. Memory) 1H-Higher Cognitive Level (I.E. CIA)

I

For All BANK questions: swap the order of the answer choices so that applicants cannot rely on recall of the correct answer location.

ROEXAM

I

007EAl.08

N

H

2

B

Can the first two bullets be replaced with the following single bullet:

"Unit I was at 10% power when both MFPTs tripped."

S

First bullet revised. Second bullet not changed. The teaching in the

second bullet does not affect the a11SWerS to this question or any other

questions. OK MAB 02/04/2008

Can the third bullet read as follows:

"Stearn generator levels dropped to a minimum of##% and then began to

rise." - (use a level that is a couple ofpercent above the AFW start signal)

Incorporated. OK MAB 02/0412008

l

.'

Is there an extra space in the correct answet between "controlled" and

"manually"? Fixed OK MAB 02/0412008

Is there an extra space in "A" and "B" between "required" and "to"?

Fixed OK MAB 02/04/2008

2

008AA2.29

N

H

2

B

Be consistent with periods in answer choices. Fixed. OK MAB

02/0412008

S

Does the cause of the lowering RCS pressure affect which answer is

correct? Is it important to state that pzr pressure is inadvertently lowered

with pzr sprays or that the safety leakage rises, etc? If the pressure drop

results from a problem elsewhere, then the level behavior may change.

Discuss with licensee.

Licensee agreed. Comment incorporated. OK

MAB 02/04/2008

3

009EA2.24

N

H

2

B

There is no point in stating the reason why the RCPs are required to be

tripped. Consider the following suggestion for the answer choices:

S

A.

ALL RCPs are required to be tripped.

Page I of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KJA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KJA

Only

S

Dis!

Dis!

BIW

B.

ONLY RCP #1 and #3 are required to be tripped.

C.

ONLY RCP #1 is required to be tripped.

D.

ONLY RCP #3 is required to be tripped.

Incorporated. OK MAB 02/04/2008

4

01lEK3.13

B

F

2

B

Change answer choices to:

A.

Realigns the ECCS suction path from the RWST to the

S

contairunent sump.

B.

No change needed

C.

No change needed

D.

Realigns the ECCS flow to prevent boron precipitation.

Incorporated for "D". Licensee and CE agreed on change for "A". OK

MAB 02/0412008

5

015/017

B

H

2

S

Suggest making slight modification to "C" and "D":

AK2.08

C.

The RCP stator windings will overheat.

D.

The RCP motor bearings will overheat.

Incorporated. OK MAB 02/04/2008

6

022AA2.03

B

H

2

X?

B

Have licensee explain the mechanism for "A" to occur. I need to better

understand the failure mechanism that can cause the charging to go to 120

S

gpm and then retum to normal with pressurizer level also returning to

nonna!.

Licensee modified "A" based on comment. OK MAB 02/04/2008

7

025AK2.05

M

H

2

X?

Y

"B" and "D" plausibility: Why would it be plausible for an applicant to

ii

+

believe that spray pumps would be drawing suction from the sump when

,

there is 68% remaining in the RWST? Also, why would an applicant

S

believe that suction for the spray pumps would be from the sump when

they are in ECA-I.I. If adequate level existed in the sump and spray

pumps are operating why would they be in ECA-I.I ?

Parameters in the stem changed to address these concerns. The changes to

the parameters also caused the correct answer to change. OK MAB

02/04/2008

This question contains overlap flaws with questions on the SRO exam.

This question provides information that indicates that E-Ois entered upon a

reactor trip. I think this comment could alleviate itself ifthe issues on the

SRO exam are resolved. Concern addressed on SRO exam. OK MAB

02/0412008

Add a period after the sentence at 08:0 l. Fixed. MAB 02/04/2008

Does the information in the stem preclude an applicant from assuming that

containment pressure could have been greater than 12 psid and has now

decreased to 9.7 psid? Ifthis is an assumption that the applicants are

Page 2 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

B/W

forced to make, would it change the correct answer. Is there a possible

argument that there are two correct answers to this question based on

forcing the applicant to make assumptions? Qnestion statement has been

enhanced to preclnde an assnmption that conld make two answers correct.

There is enough info in the stem to preclnde applicants having a need to

make any assumptions on containment pressure. OK MAB 02/04/2008

8

026AK3.03

B

F

2

x

E

"B" and "C" are really the same distractor. They both state to reduce heat

load, or minimize heat load. "C" implies that RCPs must not be needed if

S

they are not cooled to maintain CCS within design capability.

One ofthese two distractors should be modified/replaced. "B" has been

changed to address concem. OK MAB 02/04/2008

9

027AAI.02

B

H

2

E

"start" should be plural in the answer choices. Fixed. OK MAB

02/04/2008

S

Delete the piece of each answer choice that states that heaters ENERGIZE

or DEENERGIZE. This is not needed to make answer choices unique. I.E.

A. Pressurizer Pressure HI alarm annunciates. Actual pressurizer pressure

starts to rise.

Etc. for the rest ofthe answer choices.

Incorporated. OK

MAB 02/04/2008

10

038G2.1.3

N

F

2

E

Technical accuracy of "A" and "B": Is there a requirement to cool the

plant prior to tumover? The supporting documentation does not support

S

this. The supporting documentation supports that the cooldown is not

J.!

permitted to be performed by an operator who is simultaneously

"

conducting tumover. This is different than requiring that the cooldown

take place prior to tumover. TIle more precise way to phrase this would be

to state the converse ofwhat is stated in "C" and "D". I.E. An operator is

not permitted to simultaneously tumover and perform the cooldown.

Incorporated. OK MAB 02/04/2008

First part of "C" and "D" also needs wording enhancements because

OPDP-I would not provide direction to cooldown while ccncurrently

performing tumover. OPDP-I provides Administrative guidance, not

guidance that is specific to the SGTR accident. Consider: An operator is

permitted to simultaneously turnover and perform the cooldown.

Incorporated. OK MAB 02/04/2008

II

040AKI.03

B

F

2

x

y

KIA Match: The IvA requires testing knowledge of operational

implications of RCS shrink and depressurization as they apply to steam

S

line break. This question tests knowledge ofbrittle failure which stems

from an RCS cooldown and subsequent pressurization.

New Q written. OK MAB 02/04/2008

Page 3 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focns

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

This question has other issues with distractors, but because ofthe above

comment, there is no need to address these comments at this time.

New Q written. OK MAB 02/04/2008

12

055G2.4.29

N

F

I-

x

.y

Is the 19:30 bullet worded correctly?

2

Q replaced. OK MAB 02/04/2008

S

Punctuation in answer does not appear to be correct,

Q replaced. OK MAB 02/04/2008

KIA not Matched: The KIA requires a SBO. Does this question test

knowledge ofa SBO, or just knowledge of a security threat? The way I

read this question is that you could delete all the information in the stem

and simply state that there is a credible insider security t1ueat and it is

necessary to dispatch an operator to the EDG room.

In other words, the

LOOP appears to be irrelevant.

Q replaced. OK MAB 02/04/2008

13

056AKI.03

B

H

I-

x

.g

Be consistent with periods after bullets. Fixed. OK MAB 02/04/2008

2

S

Replace "D" with the logical error that would result from subtracting 15 psi

from 2085.

Incorporated. OK MAB 02/04/2008

Consider combining the subtraction of 15 psi and tile use ofThot to replace

"e".

Incorporated. OK MAB 02/04/2008

Technically this question could be rated as U, but the fix is simple enough

that it is being rated as E. The above comment incorporation will help to

make the LOD more acceptable. As written, two distracters are not

plausible. It is not reasonable for a licensed operator to use Tcold or Tave

in a subcooling calculation.

Noted. Issues addressed. OK MAB 02/04/2008

14

058AK1.01

B

H

2

.g

After 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> would the batteries be discharged? Or is there a requirement

that only states that the batteries will not be discharged prior to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />?

S

We need to ensure that the aIISWer choices accurately represent the status

ofthe batteries. Concems addressed by changing the wording. OK MAB

02/04/2008

15

062AA1.01

M

F

2

S

Q is SAT.

16

W/E04

B

F

I-

x

X?

.g

Be consistent with periods in the aIISWer choices. Fixed OK MAB

G2.4.28

2

'I

02/04/2008

Page 4 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Nou

Partial

Miu

Q-

SRO

E

Explanation

N

K

D

Focus

Crcd

Crcd

KIA

Only

S

Dist

Dist

B/W

S

Distractor "A" is not plausible. ECCS flow is an indirect parameter, which

will follow RCS pressure, which is answer choice "DO'. It does not have

the procedure guidance to monitor the indirect parameter (ECCS flow)

when the direct parameter is available (RCS P).

Concern addressed. OK MAE 02/04/2008

I also have some issues with "B" because subcooling is calculated from

RCS pressure. It makes no sense to monitor the calculated parameter when

the direct parameter is available. Concern addressed. OK MAB

02/04/2008

The only thing that makes "A" and "B" incorrect is that the procedure does

not state these parameters, but they would work as a method for

determining ifthe leak was isolated. Noted.

MAB 02/04/2008

The KIA does not restrict this question to be written to test leak isolation.

Noted.

MAB 02/0412008

17

W/E05

B

F

2

X?

E

How is "A" different from "D"? Are these unique answer choices? It

EK3.1

should be possible to modify the wording ofthese two distractors to ensure

S

that they are unique, I.E., "A" could be pertaining to high temperatures

and "DO' could speak to cold water on dry tubes as is suggested in the

distractor analysis. Wording in "DO' enhanced to ensure uniqueness of

answer choice. OK MAB 02/04/2008

18

W/Ell

M

H

1

x

Y

Question does not discriminate at the licensed operator level. This is a

EK2.2

h

question that, when provided the reference, almost anyone could arrive at

REF

S

the correct answer.

i

Following suggestion incorporated. OK MAB 02/04/2008

Suggestion to improve question:

Use most of the same items in the stem. Some can be deleted if they

become unnecessary,

Q: Which one ofthe following correctly describes the flow rate that meets

the intent of ECA-l.1, Step 20 RNO?

A.

Establish 325 gpm ECCS flow. ECCS pumps may be started

and stopped as necessary to accomplish the desired flow rate.

B.

Establish 325 gpm ECCS flow. ECCS pumps are not permitted

to be started and stopped as necessary to accomplish the desired

flow rate.

C.

Establish 400 gpm ECCS flow. ECCS pumps may be started

and stopped as necessary to accomplish the desired flow rate.

D.

Establish 400 gpm ECCS flow. ECCS pumps are not permitted

to be started and stopped as necessary to accomplish the desired

flow rate.

This suggestion raises the plausibility ofthe distractors and still tests

Page 5 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

whether the applicants understand the intent of the procedure step.

Suggestion incorporated. OK MAB 02/04/2008

19

001AK2.05

M

H

1-

B

Be consistent with periods behind bulleted phrases. Fixed. OK MAB

2

02/04/2008

S

Would the question be enhanced if one ofthe Thot or Tcold instruments

were to fail instead ofthe Tavg auctioneering unit? Discuss with licensee.

Decided not to make a change on temp inst. OK MAB 02/04/2008

20

033G2.4.2l

M

F

2

S

Q is SAT

21

036AKl.Ol

N

F

2

S

Maintain past tense in third bullet. Somewhat incorporated, but it does not

affect technical accuracy of question. OK MAB 02/04/2008

Question is written in the "NOT' format, which is discouraged by

NUREG-l02l. This question can remain in its current form as long as the

licensee agrees that the question being in this format will not affect

applicant performance. In other words, their applicants have seen

questions in this format and would not get the incorrect answer for any

other reason than a knowledge weakness.

Noted. OK MAB 02/04/2008

22

060AAl.02

M

F

2

X?

x

lei

KIA Match: Have the licensee provide an explanation ofhow the KIA is

matched. The KIA requires testing knowledge ofhow to operate or

S

monitor ventilation systems during an accidental gaseous radwaste release.

1'

How is a ventilation system being monitored? Rad Mntr is part ofthe

ventilation system. KIA match is OK. MAB 02/04/2008

When would the Waste Gas Rad Monitor not detect a leak from a Waste

Gas Decay Tank? Changed stem to a flange leak which would not cause

the Waste Gas Rad Mntr to alarm. OK MAB 02/0412008

23

069G2.4.45

N

H

2

B

Technical accuracy ofthe question is a concern because they do not have

to restore integrity within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Ifthey do not restore integrity within 1

S

hour, then they are required to shutdown. TIle answer choices need to be

more precise in order to be technically correct.

Wording enhancements made to specifically ask for what the Action

Statement states. OK MAB 02/04/2008

24

074EK3.07

B

F

1

x

lei

LOD= 1: Distractors are not plausible. Due to the non-credible distractors,

this question does not discriminate at the appropriate level to make a

S

licensing decision. Changed distractors. OK MAB 02/04/2008

Reflux boiling is a cooling method used when RCPs are off.

How would it be reasonable for an operator to think that starting an RCP

Page 6 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KJA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cnes

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KJA

Only

S

Dist

Dist

B/W

would keep pressure from rising?

Changed distractor. OK MAB 02/04/2008

2S

076AK2.01

B

H

I

x

tf

A pinhole leak of a fuel assembly would be evident in RCS samples that

are analyzed for various isotopes; however, small leaks will not necessarily

S

result in rising radiation monitor trends. There are concerns with "B"

being an altemate correct answer because the size of the leak is not

defined. Also, the RCS leakage locations are not defmed, so there are also

concems about whether a small RCS leak would result in a rising rad

monitor reading.

"Significant increase in RCS activity" added to stem. OK MAB

02/04/2008

LOD= I: Distractors are not plausible. Due to the non-credible distractors,

this question does not discriminate at the appropriate level to make a

licensing decision.

Question is on the cusp ofbeing unacceptable due to low LOD. Noted.

MAB 02/04/2008

Consider writing a question that has a plant nip and a SGTL. This will

allow testing MSL monitors as well as Condenser Off Gas Monitors. This

idea may help to raise the question to a level where it could be used to

discriminate between a competent and less than competent licensed

operator.

Not incorporated. Allowed by CEo The rest ofthe exam is at an

acceptable level to not warrant a change to this question. OK MAB

02/04/2008

26

W/E09

B

H

2

B

The "repressurization" piece of "A" and "B" should be deleted. It does not

EA2.1

add information that is needed to make these answer choices unique.

S

Discuss with licensee. Deleted. OK MAE 02/04/2008

Consider rewording the question as follows:

Which one ofthe following correctly states the procedure that maximizes

the allowable cooldown rate for the provided circumstances and the

maximum cooldown rate allowed by that procedure?

A.

Use ES-0.2, Natural Circulation Cooldown. The cooldown

limit is SOF/hr.

B.

Use ES-0.2, Natural Circulation Cooldown. The cooldown

limit is 100F/hr.

C. / Use ES-O.3, Natural Circulation Cooldown with Steam Voids in

Vessel (with RVLSI). The cooldown limit is SOF/hr.

D.

Use ES-O.3, Natural Circulation Cooldown with Steam Voids in

Vessel (with RVLSI). The cooldown limit is SOF/hr

Incorporated. OK MAE 02/04/2008

Page 7 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psvchometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

27

W/EI4

B

F

2

S

Q is SAT.

EA2.2

28

003K3.04

B

H

2

S

Q is SAT.

29

003G2.3.10

N

F

2

S

Q is SAT.

30

004K5.26

N

H

2

S

Q is SAT.

31

004A3.08

B

H

I-

X

B

"D": it is not credible for an applicant to make this error. There is no

2

division needed in this calculation.

S

Consider making "D" 60%. Discuss with licensee

Incorporated. OK MAB 02/04/2008

32

005A4.03

B

H

I-

x

y

"RCS cooldown rate is too high" - what does this mean? It may not

2

matter, but it would be better to provide the applicant with information that

S

they would normally have available to them, such as an actual temperature

at two different times. It may also be necessary to state that SRO gave

them direction to cooldown at a certain value. The question piece would

need to change slightly to ask for the actions needed to comply with the

SRO's directions. (These changes will make "C" plausible)

Q replaced. OK MAB 02/04/2008

Question should be tied to the procedure. I.E. Which one of the following

..... CONSTANT RHR flow, in accordance with 0-SO-74-1, "procedure

title"?

Q replaced. OK MAB 02/04/2008

"A" and "B" do not contain credible misconceptions to discriminate

between competent and less than competent licensed operators.

Q replaced. OK MAB 02/04/2008

33

006KI.02

M

F

2

B

Is there an extra space between "SSPS" and "if' in the stem?

Fixed. OK MAB 02/04/2008

S

Have licensee walk me through the technical aspects of the question. I

may be OK with the question with a couple of minutes of discussion.

Q is SAT. MAB 02/04/2008

34

007K3.01

B

H

2

x

B

Is there an extra space in "D" between "..4," mId "failed"?

Fixed. MAB 02/0412008

S

"C" not plausible because there is no relationship with the PRT.

The following change would correct the distractor plausibility issue:

A.

  1. 2 seal on RCP #4 failed; Pressurizer Safety Valve, 1-68-568,

failed open; Reactor Head Vent Valve, I-FCV-68-394, Failed

Page 8 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

BIW

Open

B.

  1. 2 seal on RCP #4 failed; Pressurizer Safety Valve, 1-68-568,

failed open; Reactor Head Vent Valve (I-FCV-68-394, Failing

Open, could not cause the stated conditions)

C.

Pressurizer Safety Valve, 1-68-568, failed open; Reactor Head

Vent Valve, I-FCV-68-394, Failed Open (#2 seal on RCP #4

failing could not cause these conditions)

D.

Pressurizer Safety Valve, 1-68-568, failed open (Pressurizer

Safety Valve, 1-68-568, failing open could not cause the stated

plant conditions AND Reactor Head Vent Valve, I-FCV-68-

394, Failing Open could not cause the stated plant conditions.)

Discuss the above change with thelicensee, If we can get this change to

work, then the question may be SAT.

Worked with licensee to develop plausible distractors. OK MAB

02/04/2008

35

007G2.1.1

N

F

2

x

B

Is fourth bullet worded correctly? Fixed. MAB 02/04/2008

S

"A" and "B" are not mutually exclusive, which harms their plausibility. In

other words, If"B" were true, it will still makes sense to do "A". The

problem is that ifthe applicant determines that the alarm is valid, adjusting

level will always be correct.

"A" and "B" corrected. MAB 02/04/2008

Is there an extra space in "C" and "D" between "level" and "alarm"?

They neglected to correct this; however, the extra space appears in the

~! '

correct answer as well as a distractor, so it will not adversely affect

r'

plausibility. OK MAB 02/04/2008

The question should be specific to the answer choices provided:

Which one ofthe following correctly states the validity ofthe PRT level

alarm and the required actions as a result ofthe alarm?

Incorporated. OK MAB 02/04/2008

I would prefer to have "A" and "B" read as follows:

A. The PRT level alarm is valid. (need a better second halfofdistractor)

B. The PRT level alarm is valid. 0-SI-OPS-068-137.0, RCS Water

Inventory, is required to be performed.

A version ofthis comment was incorporated. AOP-R.05 was used. OK

MAB 02/04/2008

I would prefer the second halfof"C" and "D" to read such that it

specifically states the information being tested. I.E.:

C. The PRT level alarm is false. According to OPDP-4, the maximum time

that Maintenance has to correct the condition causing the invalid alarm is 7

days, at which time the alarm is required to be cleared/disabled.

Page 9 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

D. The PRT level alarm is false. According to OPDP-4, the maximum

time that Maintenance has to correct the condition causing the invalid

alarm is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, at which time the alarm is required to be

cleared/disabled.

Incorporated. OK MAB 02/04/2008

36

008K4.07

N

F

2

x

E

Is there an extra space between "CCS" and "Pump" in the stem?

(I am beginning to think that it just may be the way it prints out and that

there may not be an extra space - but it is free to ask.)

S

Fixed. MAB 0210412008

Would it be possible to test the RED light on the throwover switch for the

first part of every answer choice. I think this would be a better test ofthe

actual plant indications. I.E. Either the red light is ON or OFF. Discuss

with licensee.

I think this could help the plausibility of "B".

Did not incorporate after discussions with licensee. MAB 02/04/2008

37

010K6.03

M

H

2

S

Be consistent with periods after bullets. Fixed. MAB 02/04/2008

Simplify the answer choices as follows:

A.

Master controller output would increase. PZR pressure would

be maintained above the reactor trip setpoint.

B.

Master controller output would increase. PZR pressure would

decrease to the reactor trip setpoint.

C.

Master controller output would decrease. PZR pressure would

be maintained above the reactor trip setpoint.

  • c

D.

Master controller output would decrease. PZR pressure would

"

be maintained above the reactor trip setpoint

Incorporated. MAB 02/0412008

38

012K4.04

N

H

2

X?

f

"A" and "D" are not plausible because the last bullet in the stem leads the

applicant to only consider answer choices where RTA "A" is different than

S

RTA "B" UV and Shunt coils. Simply using psychometrics, and applicant

can eliminate these two answer choices. Discuss with licensee.

Answer choices simplified. Issue resolved. OK MAB 02/04/2008

39

013K2.01

B

H

2

S

Potential overlap issues with 006Kl.02 should be discussed. Ifit is

determined that there is no overlap, then question may be SAT.

Overlap issue resolved. OK MAB 02/04/2008

40

022A2,04

N

H

2

X?

f

Is the wording correct in the second paragraph, "Compare the effects on of

the .."? Fixed. OK MAB 02/04/2008

S

Have the licensee explain the plausibility of additional cooling units being

placed in service. Are there additional cooling units that would be

available at any time in order to reduce temp? If there are additional

Page 10 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

BIW

cooling units that could be used, under what conditions would they

typically be used?

Additional cooling units are available one ofthe units. Unit differences

make the distractors plausible. OK MAB 02/04/2008

41

025K5.02

M

F

2

B

Is the incorrectness ofthis answer choice based entirely on the word

"each"? This needs to be discussed to ensure only one correct answer.

S

Distractors reworked to ensure only one correct answer. OK MAB

02/04/2008

42

026K4.07

M

F

2

B

The licensee needs to explain why the II% level requirement is because of

the I-FCV-74-3 interlock. I am not sure that the attached reference

S

material supports this. Maybe the supporting documentation is in another

print or lesson plan. Also as part ofthis discussion, the wording ofthe

question should be reviewed to ensure that it is accurate and will elicit the

answer.

Licensee explained the level requirement. OK MAB 02/04/2008

43

026G2.4.48

M

H

2

x

lei

Are there extra spaces in "A" and "B"? Fixed. MAB 02/04/2008

S

Will the terminology "loading room" confuse any ofthe applicants?

Should this be defmed with more precise terminology?

"loading room" deleted. OK MAB 02/04/2008

Is the wording of "A" and "B" precise enough? The pump did not (failed

to) auto start - this is a fact. I would prefer more precise terminology such

'1'[

as: "Pump did not auto start even with an auto start signal present."

Altemative similar wording would work as well.

Incorporated. OK MAB 02/04/2008

Should the answer choices contain commas or periods between the two

answer parts. It looks like two complete sentences are separated by

commas.

Two sentences used. OK MAB 02/04/2008

Second set ofbullets should be introduced with a colon, vice semi-colon.

Fixed. MAB 02/04/2008

Time in the stem is only provided to the minute, yet 14:05:00 is almost a

full 4 minutes from 14:07:59. The clock in the control room may read the

same, but this is greater than 180 seconds. Discuss whether this question

needs to be more precise to elicit the correct answer.

More precise times are not needed - I made an error with my math when

this comment was made. OK MAB 02/04/2008

"A" and "B" are not mutually exclusive because it may never be wrong to

Page II of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

verify that there is room on the EDG prior to manually placing a load on

the EDG. If "A" is correct, the "B" will also be correct,

Wording revised to ensure unique answer choices. OK MAB 02/0412008

When did the containment pressure reach 2.81 psig? Discuss whether this

is important information to contain in the stem.

Q stem is precise enough. OK MAB 02/0412008

"A" and "B" plausibility: Ifthe pump was supposed to auto start, then I

know, just using common sense, that the EDG is desigoed to have room to

start the pump (assuming that the sequencer has timed out). Ifthe

sequencer has not timed out, then it would not be smart to start the pump

anyway. "A" wording revised.

"B" determined to be OK with the change

to "A". OK MAB 02/04/2008

44

039Al.09

N

H

2

x

.g

KIA Match: The KIA requires testing knowledge ofmonitoring main

steam line radiation monitor parameters associated with operating the

S

MRSS controls to prevent exceeding design limits. How does this question

test the knowledge required by the KIA? How is knowledge ofthe

radiation monitor indications being tested in relation to how those

indications are used to avoid exceeding design limits?

Q replaced. OK MAB 02/04/2008

The question asks for the condition that is causing the alarm. Is there a

possibility that another condition, such as an actual high rad condition

could cause the alarm? High rad may not cause the other conditions, but

,1

could it cause the alarm? The wording ofthe question may need some

minor revision to ensure that the correct answer is elicited.

Q replaced. OK MAE 02/0412008

Are the second parts ofthe answer choices worded correctly? The subject

ofthe sentence appears to be implied. It would be better to state the noun.

Q replaced. OK MAE 02/04/2008

No reference is being suggested. Are the time requirements a closed book

knowledge item at SQ?

Q replaced. OK MAB 02/0412008

45

059A2.07

N

H

2

x

?

B

What conditions would automatically close the 2B MFPT Cond FCVs?

Valve operation depends on power being above or below 60%. OK MAB

S

02/0412008

"A" Plausibility: What is the logic behind the FCVs being re-opened in the

AOP? This distractor may not be plausible. It may not be credible for an

operator to think that they would re-open valves that automatically closed.

Discussed with licensee.

OK MAB 02/0412008

Page 12 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cnes

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

B/W

The stem and answer choice talks about some AOP that has been entered.

Is there a reason that the AOP that the operators are performing is not

mentioned in the stem or the answer choices? Discuss the possibility of

adding the AOP to tighten the question and tie the answers to a specific

AOP. AOP-S.OI added to the stem. OK MAB 02/04/2008

46

059A4.01

M

H

2

S

Second to last bullet: I assume the SG level is below setpoint, but this

needs to be specific. Fixed. MAB 02/04/2008

Last Bullet: is it necessary to state that the dumps are armed?

No - "armed" deleted. OK MAB 02/04/2008

47

061K5.01

B

H

2

S

Typos in 5th bullet. Fixed. MAB 02/04/2008

Trends are provided for all parameters except for SG levels.

Added. MAE 02/04/2008

48

062KI.02

B

F

2

B

Too many items are being iterated on in the answer choices. This provides

the applicants with multiple ways to eliminate distractors. Discuss with

S

licensee. Discussed. OK MAB 02/04/2008

Consider the following:

A.

After 1.25 seconds, all EDGs will auto start .

B.

After 1.25 seconds, only the IB-B EDG will start.

C.

After 300 seconds all EDGs will autostart.

c

D.

After 300 seconds only the IB-B EDG will statio

Incorporated. OK MAB 02/04/2008

49

063K2.01

N

H

2

?

+

Distractor analysis states that an applicant may think that control power for

the breaker is supplied from the EDG battery. Why would an applicant

S

think this. Do the EDG batteries supply control power to other buses or to

this bus under different plant conditions? I need to understand the credible

misconception a little better.

Answer choices revised to correct issue. OK MAE 02/04/2008

50

064K6.08

B

F

2

x

x

.y

"B" is not plausible: TIle entire reason for having a standby pump is to

have it backup the lead pump. The second pump is not referred to in the

S

distractor as the standby pump, but it is strongly implied by the stem

stating that there is a lead pump. A manual alignment does not appear to

make sense.

Distractors revised. OK MAB 02/04/2008

"C" is not plausible because the stem provides a cue that these pumps start

on tank level. "C" allowed this distractor to stay on exam after discussions

with licensee. OK MAB 02/04/2008

Page 13 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cnes

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

0

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

BIW

"A" is the obvious answer because the stem states that these pumps start on

low tank level. It would also be common sense to assume that the standby

pump would not stilt at the same time or level as the lead pump, which is

why it is a standby pump. After discussion with licensee, decided to allow

this distractor. OK MAB 02/04/2008

If possible, place the conditions of the plant in the stem, rather than making

the answer choices conditional. A specific tank level and switch position

for the backup pump should be placed in the stem.

It is not prohibited to place conditions in answer choices, therefore Q was

not changed. OK MAB 02/04/2008

Consider the following:

Initial plant conditions:

-

2A-A EDG running

-

Fuel oil day tank level = ##%

-

Lead fuel oil transfer pump is running

-

The backup fuel oil transfer pump control switch is in AUTO

Current plant conditions:

-

Lead fuel oil transfer pump shaft completely shears

Which one of the following correctly describes the operation of the backup

fuel oil transfer pump?

A.

The backup pump will be running due to a start signal on low

discharge pressure.

B.

The backup pump will be running due to a start signal on low

tanklevel.

C.

The backup pump will not be running and will not start at

anytime as tank level lowers.

D.

The backup pump will not be running, but will start as tank

level lowers with no discharge pressure on the lead pump.

Allowed Qto remain with only minor revision. OK MAB 02/0412008

51

073AI.01

N

II

2

x

g

Is second bullet worded correctly? Fixed. MAB 02/04/2008

F

S

Be consistent with periods behind bullets. Licensee did not incorporate

this comment, but does not affect the technical accuracy of the question,

OK MAE 02/0412008

This question is really written at the (Fnmdamental knowledge level.

It

appears like there may be infonnation in the stem that does not add value

to the question. The question really does not ask anything more than:

What automatic actions occur as a result of2-RM-90-123A alarming on

high radiation? Licensee did not incorporate comment, TIley are in the

middle ofthe band for CIA and F questions, therefore designating this

question in either category will not cause all exam metric to be encroached

Page 14 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

n

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

BIW

upon. I would have required this to be fixed if it affected the adherence to

the higher cog criteria. OK MAE 02/04/2008

"B" is not plausible: What information in the stem would lend credibility

to this distractor. It is very basic that there is an auto isolation ofthe surge

tank. It is not enough to simply test whether an auto isolation exists. I

agree with the plausibility that you have built into the other two distrators.

Is there any way to improve this distractor by requiring the applicants to

know a little more than whether or not an auto isolation exists?

"B" replaced. MAB 02/04/2008

Does "C" contain grammatical errors in both sentences?

Fixed. MAB 02/04/2008

"D": when possible, always word questions and answers for what is

required to be done, not what an operator will or may do. This is because

operators may do anything, but we want to test what they are required to

do.

Revised. OK MAE 02/04/2008

52

076A2.02

N

H

2

y

Typo in second bullet. Fixed. MAE 02/0412008

S

Is there enough information in the stem to elicit the correct answer?

During the review in Atlanta we will need to pull prints and do a detailed

review of the information in the stem, detennine if the stem permits

applicants, or forces applicants to make assumptions on the location of the

.j(

leak, on how and where the leak is isolated, and whether there are credible

"

arguments for no correct answers or mnltiple correct answers. Plausibility

ofthe distractors will also need to be discussed.

OK. We pulled prints during IP and question is sat. MAB 02/04/2008

This question will be rated as unsat, pending the detailed review that will

take place with the licensee.

Q OK MAB 02/04/2008

53

076A4.02

M

F

2

E

Is there an extra space between "following" and "the"?

Q simplified. Corrected. MAE 02/04/2008

S

"A": Would it be more plausible for I-FCY-67-146 to be "Auto" and 2-

FCY-67-146 to be "Manual"? This qnestion is being asked because on the

surface it may make sense for the valve on the unit with the SI to auto

reposition, rather than the other unit's valve? This may be due to my

unfamiliarity with SQ. Discuss with licensee.

Corrected. MAB 02/04/2008

Is there any possibility that EA-67-1 allows operators to reposition O-FCY-

Page 15 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

B/W

67-152, thus bringing into question the possibility that Manual would be

the correct response for all three valves?

Q revised. Corrected. MAB

02/04/2008

The stem contains a lot of words. Are we simply asking the following:

Which one ofthe following correctly describes the following valve

responses to a Unit I safety injection?

0-FCV-67-152

I-FCV-67-146

2-FCV-67-146

A. Auto repositions

Auto repositions

Does NOT auto reposition

B. etc.

Incorporated, OK MAB 02/04/2008

54

078K3.01

M

F

I-

S

Question is right at the cusp ofbeing acceptable. When all other changes

2

to the exam have been made, an overall evaluation ofthe exam will be

performed. Q is OK. MAB 02/04/2008

55

103A3.01

M

H

I-

X

g

"C" and "D" plausibility: There are no indications in the stem that would

2

lead an applicant to believe that CVI should only have occurred on one

S

train. Are rad monitors train specific for CVI? If so, add values for both

the "A" and "B" monitors, with the "B" at a lower value.

Specific rad monitor information added. OK MAB 02/04/2008

56

011K6.05

N

H

2

?

g

Be consistent with periods after bullets. Fixed. 02/04/2008

S

'f

What credible misconception would lead an applicant to believe that I-LT-

68-321 would have an impact on pzr level control when I-LT-68-320 is

I

S

selected?"

Licensee revised answer choices to correct. OK MAB 02/04/2008

AJ:e the cold cal instruments ever used for pzr level control?

Cold Cal instruments deleted from answer choices. OK MAB 02/04/2008

57

015K2.01

M

F

I-

x

Y

"B" and "C" are not plausible: These two choices can be eliminated just

2

by knowing that even channels are powered by the same bus and the odd

S

channels are powered from the same bus (or at least the same division of

power). The mixing of even and odd NI numbers make these two

distractors not plausible.

Distractors revised to correct concem. OK MAB 02/04/2008

58

016K1.10

M

F

2

S

Q is SAT.

59

o17K4.03

B

F

I

x

Y

Remaining "in" limits, or "within" limits? Either way - it just depends on

how you want your applicants to read the question. Fixed. MAB

S

02/04/2008

What does "limits" mean in the stem? Is this specific enough to elicit the

Page 16 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KJA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KJA

Only

S

Dist

Dist

BIW

correct answer? I understand what it means only by reading the question

analysis, which the applicants will not have. Wording enhancements

made. OK MAE 02/04/2008

The question should also be tied to the procedure. Incorporated. MAB

02/04/2008

"C" and "D" are not plausible. The magnitude of these two answer choices

make them completely non-credible.

Distractors revised. OK MAB 02/04/2008

Are there any other choices that have meaning at your plant? 600F?

700F? nOF? 750F? Different values were agreed upon with licensee.

OK MAE 02/04/2008

60

045K5.17

N

H

I-

x

Y

"A" is not plausible. This is not a method which is directed by plant

2

procedures, which does not create a plausible distractor.

S

Qand distractor revised to address concem. OK MAE 02/04/2008

"D" is not plausible. Two variables, the two parameters being analyzed,

moving is not plausible. Q and distractor revised to address concem. OK

MAB 02/04/2008

This question is pure GFE. Applicants have already passed a GFE. This is

the Site Specific written exam. Steam header pressure incorporated, which

makes the question more plant specific. OK MAB 02/04/2008

.

Will the correct answer be correct under all plant conditions that can be

assumed with the information provided in the stem? To be safe, does a

bumup need to be provided in the stem as well? Answer will always be

correct at 50% power. OK MAB 02/04/2008

This question can be brought to an acceptable level by making it plant

specific. Maybe iterating on "B" and "C" and then adding a second half to

the distractors would accomplish plausibility and allow for a plant specific

question. Qrevised. OK MAB 02/04/2008

61

055A3.03

N

H

2

x

g

"C": lacks a period. Fixed. MAB 02/04/2008

S

"B" is not plausible. The reason in "B" is not tied to conditions that are

provided in the stem. Compare to "A" - where "A" contains a reason that

corresponds to an alarm that is provided in the stem. To raise the

plausibility of"B", the reason needs to be tied to a condition in the stem.

Simplified to only tie to high pressure, vice rad inst malfunction. OK

MAE 02/04/2008

Page 17 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

PsvchometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

62

068A4.02

M

F

2

S

Q is SAT. TIle chosen wording does not appear to be the easiest to

interpret, but the Q is OK ifyou want to go with the current wording. If

you would like your applicants to see this question worded slightly

different, I am OK with that too.

OK MAB 02/0412008

63

071K3.04

M

H

2

S

Q is SAT.

64

075G2.2.1 I

N

H

2

g

Grammar issue in first bullet.

Q replaced. OK MAB 02/04/2008

S

The stem ofthe question is vague with respect to how the design will be

changed. It is implied, that the change will cause the valve to

automatically close. Is it important to state this. Will it be possible for an

applicant to assume a change that would affect the answer choices?

Q replaced. OK MAB 02/04/2008

Do you want to ask this question to all RO? Do you have ally RO learning

objectives associated with temp changes? Is this knowledge part of the RO

ILT program? Discuss with licensee.

Q replaced. OK MAB 02/04/2008

If licensee can produce documentation that this is OK to ask an RO, then

the question is SAT.

Q replaced. OK MAB 02/04/2008

65

086AI.OI

N

F

'5.

x

Y

Answer choices need some "the'ts added between "trip" and "pump".

Qrevised. OK MAB 02/04/2008

S

KIA not matched: The KIA requires testing the ability to monitorlpredict

changes in parameters as they relate to operating controls to prevent

exceeding design limits (fire header pressure). This question only tests

knowledge of existence of design features. The question does not test the

ability to monitor changes in parameters to prevent from exceeding design

limits.

Q revised. OK MAE 02/04/2008

66

G2.I.3

N

F

2

S

Question is written as a NOT question, which is discouraged by the

NUREG. I will allow this format ifthe licensee does not have an issue

with presenting the question to the applicants in this format.

Noted. MAB 02/04/2008

Repeated the word "during" in the stem. Fixed. MAE 02/0412008

67

G2.I.27

B

H

2

S

Third bullet: "start" should be plural. Fixed. MAB 02/04/2008

Page 18 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q-

SRO

E

Explanation

N

K

D

Focns

Cred

Cred

KiA

Only

S

Dist

Dist

B/W

Fourth bullet: "level" should be plural. Fixed. MAB 02/04/2008

Be consistent with tense in all answer choices. Consider:

A.

Arming conditions for AMSAC were not present.

B.

AMSAC actuated.

C.

Arming conditions were present, but actuation conditions were

not present.

D.

AMSAC has not actuated, but will actuate after the appropriate

time delay if SG levels stabilize at their current values.

Fixed. MAB 02/04/2008

68

G2.1.28

M

F

2

x

.g

"C" and "D" plausibility: ERCW pumps are the same type ofpump

performing the same function.

If an applicant had a misconception that

S

they were both sequenced on the bus, why would it make any difference

which pump starts first? Are there other pumps in the plant that both get

sequenced on a bus and the order of that sequence is determined by a

switch position that is manipulated by the operators? Discuss with

licensee. Ifthere is more plausibility here than I realize, then this question

may be SAT.

Qreplaced. OK MAB 02/04/2008

"C' and "D" should have an "in which" added.

Qreplaced. OK MAB 02/04/2008

The second part of"A" and "C" appears to be a little cryptic. Is this easily

understandable?

T

Q replaced. OK MAB 02/04/2008

69

G2.2.26

N

H

2

S

Qis SAT.

REF

70

G2.2.33

B

H

2

B

Is there an extra space between "and" and "the"? Corrected. MAB

02/0412008

S

"B" is not plausible. With dumps open and rods inserting it is not credible

for an applicant to have a misconception that temperature will go up.

Consider changing the temperature to something lower than 559 F, but

plausible. Answer choices changed to iterate on temps and speed. OK

MAB 02/04/2008

71

G2.3.2

N

H

2

S

Q is SAT.

72

G2.3.9

B

F

2

S

Be consistent with periods behind bullets. Fixed. MAB 02/04/2008

Q is SAT.

73

G2.3.l0

B

F

I

x

x

x

.g

"A" is not plausible. If"A" is correct, then any of the others would be

Page 19 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

also. TIle question asks for which would be correct to exit the RCA. If it

S

is correct to simply exit, then doing anything above and beyond that would

not be wrong. Q replaced. OK MAB 02/04/2008

"B" is not plausible. PCM-IB monitors alarm quite often. Can you

imagine how many whole body counts would be needed if this were true?

How many times have these applicants had a PCM-IB alarm?

Q replaced. OK MAB 02/04/2008

This question does not discriminate at the appropriate level. An RO

applicant getting tins question correct does not provide useful information

in making a license decision. Q replaced. OK MAB 02/04/2008

74

G2.4.16

B

H

2

S

Typo in "D": E-O? vice E-O. Fixed. MAB 02/04/2008

Typo "D": should "exist" be plural? Licensee failed to correct. It does not

affect tec1micalaccuracy ofquestion. I would make them change it if it

appeared only in a distractor. OK

MAB 02/04/2008

This question looks very familiar. No response needed from licensee - I

am just noting this. Noted. MAB 02/04/2008

75

02.4.22

N

F

2

S

Why is "Larger" capitalized in "A' and "D"? Corrected. MAB

02/04/2008

SROEXAM

76

008G2.4.49

NJH

2

II

"C": Is there an extra space between "and" and "immediately"?

~

Q and KIA changed. OK MAB 02/04/2008

S

"D": Is there an extra space between "in" and "E-O"?

Q and KIA changed. OK MAB 02/04/2008

What pressure causes phase B to actuate?

Would it be incorrect for the SRO to direct starting of the EDG? Is this an

automatic action that should have occurred? Does SQ have all Admin

procedure that states that it is permissible to manually perform an auto

action that should have occurred?

Q and KIA changed. OK MAB 02/04/2008

If this question is determined to require knowledge of procedure selection,

i.e. beyond general rules of procedure usage, then it will be acceptable as

an SRO question. Discuss SRO-only learning objectives that may be

available to support this question as SRO only.

Q and KIA changed. OK MAB 02/04/2008

It is my knowledge that a general Westinghouse rule of usage is that

Page 20 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

BIW

operators do not exit E-O until E-O instructs them to exit. I would view this

as RO knowledge unless there is some plant documentation that would

state otherwise.

Q and KiA changed. OK MAB 02/04/2008

77

029EA2.09

M

H

2

x

Y

Discuss deleting parameters at the time oftransition. They do not add

plausibility to "turbine not tripped"; therefore, they may not be necessary

S

information.

PRT values deleted. OK MAB 02/04/2008

Change feed water flow to something that is just over the limit. Like 120

gpm to each SG. Heat sink requirements are 440 gpm total. Discuss with

licensee.

FW flow values revised. OK MAB 02/0412008

Not SRO-only: ROs are required to know status trees. Therefore, the

question can be answered by knowing that H.l is not required to be entered

and that the turbine is tripped. Both of these knowledge items are required

RO-knowledge.

(G2.4.21 has an RO importance rating of 3.7)

Q revised. OK MAB 02/04/2008

78

054AA2.05

N

H

2

x

Y

Not SRO-only: Question requires systems knowledge for response ofthe

MFW B/P Reg Valve, which is RO knowledge. Question also requires

S

knowledge ofAOP and EOP entry conditions, which is also RO

knowledge. Furthermore, the applicant can use systems knowledge to

I

determine that the reactor will not trip and that not SI is present, thereby,

allowing the applicant to eliminate going to E-O, "Reactor Trip or Safety

Injection."

(2.4.1 and 2.4.4 have RO importance ratings of4.3 and 4.0 respectively)

Q revised to make SRO only. OK MAB 02/04/2008

Are the applicants required to go to the AOP? Would an operator be

wrong if the AOP was not entered?

Q revised. OK MAB 02/04/2008

79

057AA2.17

N

H

2

x

y

Is punctuation in second bullet correct?

Q revised. OK MAB 02/04/2008

S

Not SRO-only: Both parts ofthe answer choices can be analyzed using

RO required knowledge. Systems knowledge is required by ROs;

therefore, this question does no require any knowledge that is specific only

to the SRO position.

Q revised. OK MAB 02/04/2008

80

065AA2.01

N

H

2

E

Wording on LCO 3.0.3 is too loose. LeO 3.0.3 is always applicable and

Page 21 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

BIW

licensees are always required to comply with 3.0.3. Change the wording

S

to: Required Actions ofLCO 3.0.3 are required to be performed, OR not

required to be performed. This will not change the meaning of what is

being asked, but it will be more direct and more technically correct to

phrase the second part of each answer choice in this manner.

Incorporated. MAB 02/04/2008

Delete the air pressure in the stem. The ala1111 annunciates, which is

enough to inform the operator that pressure is below 68 psig. Discuss with

licensee. Allowed air pressure to remain. OK MAB 02/0412008

The piece of each answer choice that discusses that fuel movement is

required to be suspended does not add value since it is the same in each

answer choice. The answer choices should only contain the information

needed to make them unique answer choices:

A.

ABGTS Train A remains OPERABLE until Train A

Containment Air Isolation Valve automatically closes, at which

time LCO 3.0.3 required actions would NOT be required to be

taken.

B.

ABGTS Train A remains OPERABLE until Train A

Containment Air Isolation Valve automatically closes, at which

time LCO 3.0.3 required actions would be required to be taken.

C.

Both trains of ABGTS would immediately be INOPERABLE

with the current conditions.

LCO 3.0.3 required actions would

NOT be required to be taken.

D.

Both trains of ABGTS would immediately be INOPERABLE

with the current conditions.

LCO 3.0.3 required actions would

be required to be taken

Incorporated. OK MAB 02/04/2008

81

W/Ell

B

H

I-

x

X?

B

Be consistent with punctuation after bulleted items.

Fixed. MAB

G2.4.48

2

02/04/2008

S

Transfer to RHR containment sump is not plausible. The stem clearly

states that a LOCA Outside Containment is occurring. This distractor must

be replaced. Corrected. OK MAB 02/04/2008

Is there a way to provide some indications in the stem that are indicative of

a LOCA outside containment without telling them that the operators are in

ECA-1.2 due to a WCA in the Aux Bid. Is there a less obvious way to

provide indications ofabnormal radiation in the aux building - i.e. and

ala1111? Containment sump level added. OK MAB 02/04/2008

The easiest fix for this question may be to use the two best answer choices

and then iterate on operator actions, etc. I.E. Iterate on ECA 1.I and E- I

AND then operator actions. Incorporated. MAB 02/04/2008

Page 22 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

TIF

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dis!

B/W

-

Another possible fix may be to test procedure path for two transitions.

Operators would go to ECA-I.I, then to ...

Distractors revised. OK MAB 02/0412008

82

W/EI2

B

H

2

x

E

Questions testing knowledge of what operators "should" do are too

G2.I.32

ambiguous to ask. Questions must ask what operators are required to do.

S

This may just be a phrasing issue with the question statement, but

questions need to test requirements.

Corrected. OK MAB 02/0412008

Distractor "B": Not plausible because there is not a credible

misconception that could lead an applicant to stop terminating SI but

remain in the same procedure. At least with the procedure transition they

need to evaluate ifthey are to stop the SI termination in order to make the

transition. Corrected. MAB 02/04/2008

Modify the stem slightly to place the operators at Step 14 where they are

monitoring for SI termination criteria and provide them the criteria that are

indicative of them proceeding to step 15. Answer choices could be

something like:

A.

Terminate SI in ECA-2. I, then transition to E-2

B.

Transition to E-2, then terminate SI

C.

Remain in ECA-2. I. SI termination criteria are not currently

met.

D.

Transition to E-2, SI termination criteria are not currently met.

Discuss this option with licensee.

Incorporated. OK MAB 02/04/2008

83

003G2.2.22

N

F

I

x

x

.y

Can the stem state that the control rod drops to the middle ofthe core?

Otherwise, a rod dropping to the bottom makes "B" non-plausible because

S

there would not be any axial concerns for a rod that falls to the bottom.

Added. OK MAB 02/04/2008

"D" is a correct statement and could successfully be argued as correct by

an applicant. The accident analysis will remain valid at 75% power.

Corrected. MAB 02/0412008

Is there a more specific option to use for "A"? Any reactivity 1power

redistribution issue is going to be a fuel integrity concern.

"A" allowed to remain. OK MAB 02/04/2008

A more specific choice for "A" and replacement of"D" could result in a

satisfactory question.

"D" revised and "A" allowed to remain with the

other changes made to the question. OK MAB 0210412008

Page 23 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Ouly

S

Dist

Dist

B/W

84

005AA2.03

N

H

2

X

X

.y

Delete "causing a runback from the stem".

Applicants should have

enough information with the plant at 86% and a MFP trip to understand

S

that a runback will occur. Discuss with licensee to ensure that this is the

case.

Deleted. OK MAB 02/04/2008

Is second bullet worded corrected?

Corrected. MAB 02/04/2008

Not SRO-only knowledge: ROs are required to know reactor trip criteria.

Q revised and allowed for SRO due to location oftrip criteria. MAB

02/04/2008

Is "D" a subset of"C"? Is (ripping the reactor a means of removing the

Unit from service within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />? This may be able to be alleviated by

changing the wording of the question to ask for the specific requirements

as stated in AOP-C.OI. Corrected. MAB 02/0412008

85

051AA2.02

M

H

2

X

.y

Is second bullet worded correctly? Corrected. MAB 02/04/2008

S

Delete all unnecessary information in answer choices. In other words,

delete the information that is not needed to make the answer choices

unique.

All ofthe extraneous procedure entry information is not needed to

make the answer choice unique. I.E.:

A.

Manual turbine trip criteria is currently met.

B.

Manual reactor trip criteria is currently met.

C.

Manual turbine trip criteria will be met ifcondenser pressure

I

exceeds 2.7 psia and cannot be restored within 5 minutes.

D.

Manual turbine trip criteria will be met ifcondenser pressure

exceeds 2.7 psia and cannot be restored within 5 minutes.

Extra info deleted from answer choices. MAB 02/0412008

Question should be worded in the plural fonn. Currently it is worded for

singular (or plural), but each answer choice has more than one item.

Corrected. MAB 02/0412008

Not SRO-only: Reactor Trip criteria is RO knowledge. The above

comments will be irrelevant unless the SRO-only issue is corrected.

(G2.1.7 and G2.4.l have RO IRs of3.7 and 4.3 respectively)

Allowed for SRO exam due to knowledge of being able to stay in AOP to

address vacuum problem for 5 minutes. MAB 02/04/2008

86

W/E02

N

H

I

x

.y

Should "Safety" be capitalized in second bullet? "Injection" is also now

EA2.2

capitalized. OK MAB 02/04/2008

S

"B" and "D": This reviewer does not understand how the conditions in the

Page 24 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

V

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

stem result in LCO 3.0.3 being plausible. There is not a reasonable

misconception that would lead an applicant to thinking that LCO 3.0.3.

Corrected. MAB 02/04/2008

"C" and "0": Nothing has really occurred in the stem except for an

inadvertent SI. There is no reasonable misconception that would lead an

applicant to E-I for a LOCA.

Condition in the stem revised and distractors changed. OK.MAB

02/04/2008

TIle lack of plausibility in the distractors results in an LOD= I, which does

not allow this question to discriminate between a competent and less than

competent SRO. Q revised to bring to acceptable level. OK MAB

02/0412008

87

W/EI6

M

H

2

x

B

Can "The reactor is in Mode 6 with" be deleted from first bullet?

G2.2.31

2

Deleted. MAB 02/0412008

S

Not SRO-only: ROs are licensed to move fuel and therefore are required

to know how to handle a loss ofrefueling water event.

TIns is snpported

by KIA 036AAI.04, which has an RO IR of 3.7. Lowering water level is a

fuel handling incident, which is supported by AOP-M.04, Refueling

Malfunctions.

See comment below. OK MAB 02/0412008

This was a modified question. TIle reviewer would like to see a copy of

the source question, from which this one was modified. Provided. MAB

02/0412008

Do ROs currently move fuel at SQ? Ifnot, when was the last time an RO

moved irradiated fuel at SQ?

Is there an SRO-only leaming objective to

support tins being SRO-only knowledge? Based on the above reasoning

tins falls into the category of an RO question; however, ifsufficient

justification can be provided it may be permissible to allow this on the

SRO exam.

Licensee provided sufficient justification for SRO only level. MAB

02/04/2008

88

008A2.09

M

H

2

x

y

Reactor Physics and systems knowledge are the only requirements for

answering this question. Plant response to a controller failure is systems

S

knowledge that is required of an RO. Determining whether a temp change

adds positive or negative reactivity is basic GFE reactor physics

knowledge. This question can be answered only by knowing GFE

knowledge. No SRO-only knowledge is required to answer this question.

Q replaced. OK MAB 02/04/2008

89

0IOG2.4.38

N

F

I

x

y

"A" and "0": 5 minutes is not plausible. Leading to a LOD

I.

Page 25 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psvchometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

Q revised to address concern. OK MAE 02/0412008

S

Question LOD would be acceptable if the acceptable ODS notification

requirement is tested, instead ofthe 15 minute to declare. Test whether the

requirement to notify ODS is 5 minutes from the event or 5 minutes from

making the declaration. This will test knowledge of whether the ODS

notification is required to be made prior to or after event declaration.

Incorporated. OK MAB 02/0412008

90

013A2.05

N

H

2

x

Y

Question is not SRO-only: Can this question be answered using only

systems knowledge?

The first piece of each answer choice can be

S

answered by knowing what the cause ofthe condition could be, which is

systems knowledge. This limits the potential answer choices to "C" and

"D" using RO knowledge. Applicants can also determine that the pumps

will not start manually based on the physical configuration of the plant, I.E.

systems knowledge. Therefore, this question can be answered by an

applicant without needing to use any SRO-only level knowledge.

Concerns addressed. Distractors and stem revised. OK MAB 02/04/2008

91

103G2.2.l4

N

F

2

S

Tie the second halfof the question to the procedure just as you did with

when Containment Closure Control is required to be implemented. I.E.

...who will maintain the listing ofthe Containment Closure Exceptions in

effect in accordance with 0-GO-15.

Incorporated, MAB 02/04/2008

92

029G2.4.46

N

H

3

x

x?

E

Question is backward logic. This is discouraged by NUREG-I 021;

,

1

however, it is not prohibited. Licensee does not need to address this

comment if they are satisfied with their applicants receiving this question.

S

Noted. MAB 02/04/2008

Can "B" be eliminated using systems knowledge? Will ABI result in an

auto shutdown of Unit I containment purge when ORA-90-10IA alarms

with Unit I Lower Containment Purge in progress? Discuss with licensee.

This will determine the status of the question.

ABI will not auto SID UI purge. After discussion with licensee, Q is OK.

MAB 02/0412008

93

034A2.02

N

F

2

x

E

"B": Rad Control Manager is not plausible because this is not an irradiated

fuel bundle. Contamination and exposure should not be a concern.

S

Fixed. MAB 02/0412008

Consider the following changes:

. Per AOP-M.04, which one ofthe following correctly describes the

lowest level ofapproval required for approval ofrecovery instructions?

A.

Refueling SRO

B.

Shift Manager

Page 26 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KlA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cnes

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KIA

Only

S

Dist

Dist

B/W

C.

Operations Manager

D.

Plant Manager

Incorporated. OK MAB 02/04/2008

94

G2.1.12

N

H

2

S

Is second bullet worded correctly? Fixed. MAB 02/04/2008

REF

Be consistent with periods after bullets. Fixed. MAB 02/04/2008

95

G2.1.33

N

H

2

x

y

KIA Match: The KIA requires that tech spec entry conditions are tested.

This question skips that part and then tests the actions that are required

S

once the tech spec is entered.

Q revised. OK MAB 02/0412008

TIle stem does not even state that fuel is being moved; therefore, stopping

fuel movement does not appear like a reasonable answer.

Answer choices revised. OK MAB 02/05/2008

Question is disjointed. "A" and "B" are testing knowledge ofmode change

requirements and "C" and "D' are testing knowledge of fuel movement

requirements. This is not the reason the question is unsat, but simply an

observation.

Answer choices revised. OK MAB 02/0512008

96

G2.2.8

B

F

2

.g

Consider wording the Q as follows:

Which one ofthe following correctly describes the MINIMUM required

S

qualifications for the person(s) PREPARING the safety evaluation

I

paperwork in accordance with SPP-9.4, IOCFR50.59 Evaluations of

Changes, Tests, and Experiments?

Incorporated. OK MAB 02/0512008

97

G2.3.l

B

H

2

.g

The topic and construction of the question is satisfactory, There are

concems with the wording ofthe "Why" column choice for "A" and "B".

S

Where is "maintain critical safety function" defined? Would it be wrong

for an applicant to believe that the emergency exposure would be needed to

prevent the conditions from elevating beyond Yellow? Discuss with

licensee.

Q replaced. OK MAB 02/05/2008

98

G2.3.6

M

F

2

x

.g

Tie the question to the procedure, I.E.: Which one ofthe following . ....

in accordance with "procedure name and number"?

S

Incorporated. OK MAB 02/05/2008

Be a little more precise with the first piece of each answer choice. I.E.

Approval not permitted. I Approval is permitted.

The above suggestion is a little more accurate because the SRO could just

choose to not sign it, which is neither disapproving or approving. The

Page 27 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

Psychometric Flaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q=

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

BIW

above wording covers all cases and speaks directly to the procedure

requirement.

Incorporated. OK MAB 02/05/2008

Delete the last piece of"D": ", but dilution flow requirements are raised

due to the higher activity."

This really does not add to plausibility because

it is not needed to make the answer choice unique. If an applicant knows

whether the SM is required to approve, then this extraneous information is

not meaningful.

Incorporated. OK MAB 02/05/2008

"B" is not plausible only because ofthe verbiage. There may be some

improper grammar, which is easily fixed. I.E.:

B.

Approval not permitted. Cannot release monitor tank until 0-

RM-90-122 has been retnmed to OPERABLE status.

Incorporated. OK MAB 02/05/2008

What does "two independent discharge valve lineups" mean? Wording

must be precise and reflect exactly what the procedures require. Do two

lineups need to be performed? Is one lineup performed and then it is

independently verified?

Answer choices modified. OK MAB 02/05/2008

ODCM states that two qualified staffmembers independently verify

release rate calculations. The answer choices in the questions states that 2

release rate calculations are verified. I am not sure that these requirements,

as stated, are exactly the same. Discuss with licensee.

,

Answer choices modified. OK MAB 02/05/2008

99

G2.4.9

B

H

2

x

x

lei

Not SRO-only: Knowing how to recognize pump cavitation and the

actions to take to mitigate the cavitation is RO required knowledge.

S

Knowing that dilution is not permitted is also RO required knowledge.

All I hour and less tech specs are RO knowledge.

Equipment protection actions are also RO knowledge.

Through discussion with licensee, CE allowed Qto remain. OK MAB

0210512008

There are also plausibility concerns with taking suction from VCT with

boron too low. This point is inconsequential due to the question not being

written at the SRO level.

Through discussion with licensee, CE allowed distractors to remain. OK

MAB 02/05/2008

100

G2.4.49

N

H

2

x

lei

"Shutdown Boards Energized" is not an action, it is a statement of fact. -

Similar comment for "Safety Injection Actuated".

S

Qreplaced. OK MAB 02/05/2008

Page 28 of29

ES-401, Rev. 9

Written Exam Review Worksheet

Sequoyah 2008-301

Form ES-401-9

Q#

KiA#

B

L

L

PsychometricFlaws

Content Flaws

U

Comment

M

0

0

Stem

Cues

T/F

1 Non

>1 Non

Partial

Min

Q~

SRO

E

Explanation

N

K

D

Focus

Cred

Cred

KiA

Only

S

Dist

Dist

B/W

Not SRO-only: Knowing whether the status ofthe reactor and turbine is

systems knowledge, which is a required RO knowledge item. Knowing

that upon a reactor trip that E-Ois entered is an RO knowledge item. This

is all that is needed to arrive at the correct answer.

Qrevised/replaced to test SRO-only knowledge. OK MAB 02/05/2008

Page 29 of29

ES-403

Written Examination Grading

Quality Checklist

Form ES-403-1

Facility:

~E('OUD\\(MA

Date of Exam: OJJoO ~B

Exam Level: ROIl SRolro

Initials

Item Description

a

b

c

1.

Clean answer sheets copied before grading

1JK.

NfIJ

Ifff3

2.

Answer key changes and question deletions justified

?Jk.

flJIA

f}$

and documented

3.

Applicants' scores checked for addition errors

sc

~

~

(reviewers spot check> 25% of examinations)

A

4.

Grading for all borderline cases (80 +/-2% overall and 70 or 80,

?1H.

I'k

m>

as applicable, +/-4% on the SRO-only) reviewed in detail

/~

5.

All other failing examinations checked to ensure that grades

~

I~

rrfJ

are iustified

6.

Performance on missed questions checked for training

~

~

n'1O

deficiencies and wording problems; evaluate validity

.~

of Questions missed by half or more of the applicants

Printed Name/Signature

Date

a. Grader

~R.\\AN{) ~~1§.UdtL

z/I er!fJt

b. Facility Reviewer(*)

N)A

.

N;/4

c. NRC Chief Examiner (*)

M"", A,B~I;3,1//2i/}£tp

r:~I.l..ItJ.//J06'el

d. NRC Supervisor (*)

/l.)jJ..UJJLJJ T lVfDj,).AA/A/ /

!1iJjJAfJft~

ozl'l/ItJ?

r

} {

(*)

The facility reviewer's signature is not applicable for ex~ations graded by the NRC;

two independent NRC reviews are required.

ES-403, Page 6 of 6

ES*S01

Post-Examination Check Sheet

Form ES-S01-1

Post-Examination Check Sheet

Facility:

Sf::: (QU 0\\{VtIf

Date of Examination: -:Yt~u.e.,*.'(

0<005

Task Description

Date Complete

1.

Facility written exam comments or graded exams received

();;'/Itt!JDG ~

and verified complete

2.

Facility written exam comments reviewed and incorporated

()J./1'-/J;)C'Cf C;;

and NRC grading completed, if necessary

3.

Operating tests graded by NRC examiners

O?- ) ILl)Jtr/?

4.

NRC chief examiner review of operating test and written exam

OJ!!41;}or/~

grading completed

5.

Responsible supervisor review completed

O;Z I;{d;)C)O C?

6.

Management (licensing official) review completed

o,,:2/;;qIJc;l1} ~

7.

License and denial letters mailed

o2);) JdtJ{)~

8.

Facility notified of results

o;;;./~ J/?CJJ'?,

jJ:i

9.

Examination report issued (refer to NRC MC 0612)

os .' :<oeJg'

10.

Reference material returned after final resolution of any appeals

Aliff

ES-501, Page 23 of 25

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000

Confidential information submitted

under 10 CFR 2.390

February 13, 2008

10 CFR 55.40

Dr. William D. Travers

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission

Sam Nunn Atlanta Federal Center

61 Forsyth Street, SW, Suite 23T85

Atlanta, Georgia 30323-8931

Attention: Mr. M. T. Widmann

In the Matter of

Tennessee Valley Authority (TVA)

Docket Nos.

50-327

50-328

SEQUOYAH NUCLEAR PLANT (SQN) - REACTOR AND SENIOR REACTOR

OPERATOR INITIAL EXAMINATIONS - 05000327/2008301 AND 05000328/2008301

In accordance with Examination Standard (ES) 501, "Initial Post-Examination

Activities," of NUREG-1021, "Operator Licensing Examination Standards for Power

Reactors," SON is providing the following information: written examination, examination

answer key, ES 401-8, examination cover sheets, seating chart, student answer

sheets, and student clarifying questions.

In accordance with 10 CFR 55.49, "Integrity of Examinations and Tests," and

NUREG-1021, appropriate measures have been taken to ensure examination integrity

and security. The Examination Security Agreement Form ES-201-3 will be provided

following the post-examination signatures.

Because of the administratively confidential nature, it is requested that the information

contained in the enclosure be withheld from public disclosure in accordance with

10 CFR 2.390(a)(6). This letter contains no new commitments. If you should have any

questions, please contact me at (423) 843-7170.

S.inc.e.relY,. JI

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J

,~ .. '~ames D. Smith

Manager, Site Licensing and

Industry Affairs

Enclosures

Printed on recycled paper

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000

December 5, 2007

Dr. William D. Travers

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission

Sam Nunn Atlanta Federal Center

61 Forsyth Street, SW, Suite 23T85

Atlanta, Georgia 30323-8931

Attention: Mr. M. T. Widmann

In the Matter of

Tennessee Valley Authority (TVA)

Docket Nos.

50-327

50-328

(

(

SEQUOYAH NUCLEAR PLANT (SQN) - REACTOR AND SENIOR REACTOR

OPERATOR INITIAL EXAMINATIONS - 05000327/2008301 AND 05000328/2008301

This letter transmits the requested information identified in NRC's letter to

William R. Campbell dated August 3,2007, for the examinations to be administrated the

weeks of January 28, 2008, and February 4, 2008.

There are no commitments contained in this submittal. In accordance with 10 CFR 55.49

and NUREG 1021, "Operator Licensing Examination Standards for Power Reactors,"

appropriate measures have been taken to ensure examination integrity and security.

Accordingly, it is requested that this letter and the enclosed documents be withheld from

public disclosure until the examinations are completed.

TVA's principal contact regarding the license examinations is Tom Jones, SON Operations

Training. Should you require additional information regarding this matter, please contact

Mr. Jones at (423) 843-4206 or contact me at (423) 843-7170.

Sincerely,

w.?~

James D. Smith

Manager, Site Licensing and

Industry Affairs

Enclosure

Printed on recycled paper

(

(

U.S. Nuclear Regulatory Commission

Page 2

December 5, 2007

JWP:KTS

cc:

L. E. Nicholson, BR 4X-C

T. D. Wallace, STC 2H-SQN

B. A. Wetzel, BR 4X-C

EDMS, WT CA-K

The information contained within this document is the Property of the Tennessee

Valley Authority and has been determined to be sensitive. Any further distribution of

its contents will be on a need to know basis only as determined by the originator of

the document or the recipient.

SENSITIVE INFORMATION

I:License\\Operator license\\2007\\Requested information IR2008301

(

(

ENCLOSURE

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2

OPERATING EXAMINATIONS FOR REACTOR OPERATOR (RO)

AND SENIOR REACTOR OPERATOR (SRO) CANDIDATES

Written Examination - RO and SRO Portions Including Student Reference Material

Question Development Reference Material for RO and SRO Written Examinations

Job Performance Measures for RO and SRO examinations

Four Simulator examinations

ES-201-3 - Examination Security Agreement

ES-301-2 - Control Room/In-Plant Systems Outline

ES-301-3 - Operating Test Quality Checklist

ES-301-4 - Simulator Scenario Quality Checklist

ES-301-5 - Transient and Event Checklist

ES-301-6 - Competencies Checklist

ES-401-6 - Written Examination Quality Checklist

(

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000

October 23, 2007

Dr. William D. Travers

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission

Sam Nunn Atlanta Federal Center

61 Forsyth Street, SW, Suite 23T85

Atlanta, Georgia 30323-8931

Attention: Mr. M. T. Widmann

In the Matter of

Tennessee Valley Authority

Docket Nos.

50-327

50-328

(

(

SEQUOYAH NUCLEAR PLANT - REACTOR AND SENIOR REACTOR OPERATOR

INITIAL EXAMINATIONS - 05000327/2008301 AND 05000328/2008301

As requested by NRC letter to TVA dated August 3,2007, this letter transmits the

examination outlines identified in NRC's letter to William R. Campbell dated August 3,

2007, for the examinations to be administrated the weeks of January 28, 2008 and

February 4, 2008.

There are no commitments contained in this submittal. In accordance with 10 CFR 55.49

and NUREG 1021, "Operator Licensing Examination Standards for Power Reactors,"

appropriate measures have been taken to ensure examination integrity and security.

Accordingly, it is requested that this letter and the enclosed documents be withheld from

public disclosure until the examinations are completed.

Please direct questions concerning this issue to me at (423) 843-7170.

~rzJ.~

Glenn W. Morris

Manager, Site Licensing and

Industry Affairs

Enclosure

Printed on recycled paper

(

ENCLOSURE

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2

The following are included in this enclosure:

License Examination Outlines:

ES-201-2 Examination Outline Quality Checklist

ES-201-3 Examination Security Agreement

ES-301-1 Administrative Topics JPM Outlines for RO and SRO exams

ES-301-2 Control Room/In-Plant Systems JPM Outlines for RO and SRO exams

ES-301-5 Transient and Event Checklist

ES-D-1 Simulator Scenario Outlines for 4 scenarios

ES-401-2 and 3 Written Exam Outlines for RO and SRO exams

ES-401-4 Record of Rejected KlAs for RO and SRO exams

Written Exam development methodology statement

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000

August 15,2007

Dr. William D. Travers

Regional Administrator, Region II

U.S. Nuclear Regulatory Commission

Sam Nunn Atlanta Federal Center

61 Forsyth Street, SW, Suite 23T85

Atlanta, Georgia 30323-8931

Attention:

Mr. R. C. Haag

In the Matter of

Tennessee Valley Authority

Docket Nos.

50-327

50-328

(

SEQUOYAH NUCLEAR PLANT - REACTOR AND SENIOR REACTOR OPERATOR

INITIAL EXAMINATIONS - 05000327/2008301 AND 05000328/2008301

As requested by Mark Bates of your staff, this letter transmits the written examination

outlines identified in NRC's letter to William R. Campbell dated August 3, 2007, for the

examinations to be administrated the week of January 28, 2008.

Due to the administratively confidential nature of the enclosure, it is requested that the

information contained in the enclosure be withheld from public disclosure until after the

examinations are complete.

Please direct questions concerning this issue to me at (423) 843-7170.

~ZuN.~

Glenn W. Morris

Manager, Site Licensing and

Industry Affairs

Enclosure

Printed on recycled paper

(

u.s. Nuclear Regulatory Commission

Page 2

August 15, 2007

JWP:KTS

cc:

R. H. Bryan, BR 4X-C

T. D. Wallace, STC 2H-SQN

EDMS, WTC A-K

The information contained within this document is the Property of the Tennessee

Valley Authority and has been determined to be sensitive. Any further distribution of

its contents will be on a need to know basis only as determined by the originator of

the document or the recipient.

SENSITIVE INFORMATION

I:License\\Operator license\\2007\\Exam outline IR2008301

ENCLOSURE

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2

LICENSE WRITTEN EXAMINATION OUTLINES