ML14154A377
| ML14154A377 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/02/2014 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML14155A059 | List: |
| References | |
| 50-259/OL-14, 50-260/OL-14, 50-296/OL-14 | |
| Download: ML14154A377 (117) | |
Text
srlO2Or9-sun fin1fnrmQrnc dnr ES-201 Examination Preparation Checklist Form ES-201-1 Facility: RO(A)lbL FIL1I Date of Exam ination:PV 1 2.0 Developed by: i- Facility JRC D IIating - Facility jRC D Target Chief Date* Task Description (Reference) Examiners Initials
-180 1. Examination administration date confirmed (Cia; C.2.a and b) @113/14)
-120 2. NRC examiners and facility contact assigned (C.1 .d; C.2.e) (h1/iq/,.f)
-120 3. Facility contact briefed on security and other requirements (C. .cVlq/
2
-120 4. Corporate notification letter sent (C.2.d)
[-90] [5. Reference material due (C.1 .e; C.3.c; Attachment 3)] (LA 3/+)
{-75} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)
( /4.)
{-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h;_C.3.e)}
{-45} 8. Piposed examinations (including written, walk-through JPMs, an/3/$.
scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (Ole, f, g and h; C3.d)
-30 9. Preliminary license applications (NRC Form 398s) due (C.i.l; C.2.g; ES-202) (3/27/14)
-14 10. Final license applications due and Form ES-201-4 prepared (0.1.1; C.2.i; ES-202) (4/14/4)
-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 i(/ 7A.
-7 13. Written examinations and operating tests ap roved b NRC supervisor (C2.i; C3.h)
(%h4/4c)
-7 14. Final applications reviewed; 1 or 2 (if>10) applications audited to confirm qualifications / eligibility; and examination approval anwaive1 letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204) (4/j / j4)
-7 15. Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) (Ø/7/e4.)
-7 16. Approved scenarios, job performance measures, and que tions distributed to NRC examiners (C.3.i)
(4//+)
Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by case basis in coordination with the facility licensee.
[Applies only] {Does not apply} to examinations prepared by the NRC.
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: çj Date of Examination: April O 14-Initials Item Task Description
- 1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
p/
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T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
- d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. /%
- 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S and major transients.
M b. Assess whether there are enough scenario sets (and spares) to test the projected number u and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.
- c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
- 3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks W 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 form T (3) no tasks are duplicated from the applicants audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations
- c. Determine if there are enough different outlines to test the projected number and mix L/ A// A)/
of applicants and ensure that no items are duplicated on subsequent days. /4 4
/i /4
- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. -
- c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. tfl -
R d. Check for duplication and overlap among exam sections.
L e. Check the entire exam for balance of coverage.
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Supervisor Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines N(. 1) Fy2,n ES-)-2 ,&v?1e34 it; r1t& OA)/
D i/ 3/13 ii -f A O /4 cavt,
ES-201 Examination Outline Quality Checklist Fomi ES-201-2 Facility: Browns Ferry Date of Examination: April 28, 2014 Item Task Description Initials
- 1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
R b. Assesswhethertheoutlinewassystematicallyand randomlyprepared in accordancewith Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.
T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
N
- d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.
- 2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal S evolutions, instrument and component failures, technical specifications, and major transients.
ii U b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of L applicants in accordance with the expected crew composition and rotation schedule without compromising A exam integrity, and ensure that each applicant can be tested using at least one new or significantly T modified scenario, that no scenarios are duplicated from the applicants audit test(s), and that scenarios i{J) 0 will not be repeated on subsequent days.
- c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301 -4 and described in Appendix D.
- 3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
W (1) the outline(s) contain(s) the required number of control room and in-plant tasks I distributed among the safety functions as specified on the form T (2) task repetition from the last two NRC examinations is within the limits specified on the form (3) no tasks are duplicated from the applicants audit test(s)
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
- b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the fonn j j (2) at least one task is new or significantly modified il j1f )%(
(3) no more than one task is repeated from the last two NRC licensing examinations I
- c. Determine if there are enough different outlines to test the projected number and mix of applicants LI1 ,qr and ensure that no items are duplicated on subsequent days. $i
G appropriate exam sections.
- b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
cø N
C. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
A d. Check for duplication and overlap among exam sections.
L
- e. Check the entire exam for balance of coverage.
t
Printed Name/ Signature Date
- a. Author .
/ifItT%,43k , i/9/iy
- b. Facility Reviewer kLA 4, I4i
- c. NRC Chief Examiner RJO 4-Z2 -/-
- d. NRC Supervisor y* CAfLi //1QO\Ak\ L\
9 fi 9 Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
ILT 1404 ES-201 EaminatlonSecurltv Agreement Form ES-201 4
- 1. Pre-Examination I acknowledge that have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 4/28114 and 5/5/14 as of the date of my signatui-e. 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 lam 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 indMdual does not select the training content or provide director indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforoement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 4/28114 and 5/5/14. From The date that 1 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.
PRlrrFED NAME JOB Tm.E I RESPONSIBILII( SIGNATU E(1) DATE SIGNATURE (2) DATE NOTE
- 1. (?AYfrA 3 131ZJ1E5 C:;LAI.1
- 2. /J&- YIIW1_A /-)
- 53. _,, /L_ LAn Ii h 571
- 35 Uc -
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- 8. Ctrt ltrt chii Syc4b4
- 9. k. 1l L
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- 11. . MMc Ad
- 12. 2_. . .-
13.
- 14. /i; i( :
15 jVL.i L NOTES:
ES-201, Page 27 of 28
ILT 1404 ES-201 Examination Security Agreement Form ES-201 -3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC koensing examinations scheduled for the week(s) of 4128114 and 5/5114 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 instnjct 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 indMdual does not select the training content or provide director indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations andlor an enforcement action against me or the facility licensee.
I wP immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
Z Post-Examination To the best of my knowledge. I did not divulge to any unauthorized persons any Information concerning the NRC licensing examinations administered during the week(s) of 4128114 and 615/14. 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.
PR1ED NAME JOB lTfl..EI RESPONSIBILITY SIGNATU E (1) DATE SIGNATURE (2) DATE NOTE iz/% - tq 1 *L
- 1. (<AY,13 Jf,UL$
3 Pe,vw &Mri
- 2. 5i4L41A :
- 3. 1)ii LC) LAD
- 4. &.i 4S 7//> //-
- 5. UC.3
- 6. i5f5 /. tit) <rs
- 7. ?iJF7l/FJ,. IL SH(t Ecr.( 1Nr/lrQc ,!- %j
- 8. Chrs+o her t Syc4.e. 4/qjjA
- 9. V. i3iA- &
- 10. 11 S AL
- 11. 2?%- Z L 1 4 9 /q (/:/
- 12. // -//
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14.
15 4k NOTES:
ES-201, Page 27 of 28
ILT 1404 ES.-201 Examination Security Anreement Form ES-201 4
- 1. PExamlna6on I acknowledge that I have acqubed specialized knowledge about the NRC licensing minations scheduled fec The week(s) of 4128114 aid 518114 as of the date &my signature. agree that I wil n nowingy divulge any information about these eminations to any persons who have not been authorized by the NRC examiner. I understand thati an notto insud ealuate, or provide peixmancefeedbackto those ats scheduled to beadmmlstared these tensing examinations from this date until completion &iiina&n admiilslmtion. ptas spedlk4y noted below and authorized by the NRC (e.g.,
acting as a smiulator booth operr or communicator is acceptable the indMdua does not select the training content or provide director indirect feedback).
Furthermore, I am aware of the physical security measures end requirements (as documented in the facility$censeWs procedures) and understand that voIation of the conditions of this agreement may result in cancellation of the exaninations andIoran et*rcement action against me or the facility licensee.
I wil immedeIy report to facility management or the NRC chief exaniineraiy indications or suggestions that e.ifion security may have been compromised.
- 2. Poet-Exemlnahion To the best of my iciowledge I did not divulge to any unauthorized persons any k*miation concerning the NRC licensing rninations administered during the week(s) of 4128114 aid 5114. From the date that I entered into ttds security agreement until the completion otn*iation administration, 1 did not instnict, eakjate, or provide peilo.ance feedback to those applkta who were administered these licensing asninaticns, eeptas specifically noted below and authorized by the NRC.
PRNTED NAME JOB 1TflEIRESPONSWIUTY SIGNA I1E SI9 MUE çi LTE NOTE
- 1. J,iii.t5 /.
sa iVE& 5i.lwLA 14pf
- 53. LAO _;- - qJIe,4 c&yfrg sa-o ?Y/ /))t /?A -
- 4. fk4AS fka 1 -
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6.
- 7. Ø17,j.j . 4Fjti E1ccAt z-9 #/A
- 8. SVc.ee
- 9. .IiA Ek4 aI
- 10. 17,,A%L 5 Ar 4/
- 11. H(V l AAJA,4fA fr/iy f/
- 12. .L. 15 J / J/ v!(J;I441) JI
- 13. w 471/
- 14. y q K. uJ iThs 15 \7 fi*(i 4f \c S7i-z,kt NOTES:
ES-201, Page 27 of 28
ILT 1404 ES-201 Examination Security Agreement Form ES-201 -3
- 1. Pm-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 412812014 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g.,
acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 412812014. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TIThE I RESPONSIBILITY SIG4OTqfE, DATE SIGNATURE DATE NOTE
- 1. al) lJ i/I/i3 - 1ID
- 2. QL 7////3 ..,
- 3. tot..& c. I P L.i A
1 3 4
7/ZZ, ij
- 4. , . > /,afr/
(kufliel/AL7
- 5. --VL//l
- 6. Fflci.I7-/
7 (jgj Jf3f(.. Coap w64.. /_
- 8. flZr,i ?i)Th1if2iDiJ CLL .d- 1f// 6 /p/i/
fr( SCflic /lLLi- sj fri, 9T37LLQ-L> £)1/4__
- 10. 3 a(v,ce4 2 a4-Z l1
- 11. M.5re ç- Stv c% 4 4 p4.43 3-J
- 12. ;
1 ciç 2i 3 /2 aG9c
- 13. 5. 7 A 4 Q.iiiei sz46 J4 4(Ø. it 4 ci/
- 14. 3jyr 1fi1hj ofizii3 c-,2-2py 15 P4-c 1 I(.. a9 ci NOTES:
Pag ES-201, 27of28
ILT 1404 rftvAweernent -
Foini E8-201 4 xam(nstIon S ES-201
- 1. PrmInatloj1 of the date I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of412812014 asized have not been author by the NRC ation about these examinations to any persons who istered these of my slgnabure. I agree that I will not knowingly divulge any Inform nts schedu led to be admin provide performance feedback to those applica (e.g.,
chief examiner. I understand that I am not to insthict evaluate, or noted below and author ized by the NRC ation admInistration, except as specifically licensing examination8 from this date until completion of examin if the lndMdual does not select the training content or provide director indirect feedback).
acting as a simulator booth operator or communicator Is acceptable tand that Furthermore, I am aware of the physical security measures and requirements (as documented In the facility licensees procedures) and unders facility licensee.
of the examinations andor an enforcement action agains t me or the violation of the conditions &thls agreement may resuft In cancellation er any Indications or suggestions that examination security may have been I will bT,medlately report to facility management or the NRC chief examin compromised.
- 2. Poet-Examlnstloii person s any Information concerning the NRC licensing examinations administered To the best of my knowledge, I did not divulge to any unauthorizedthis security agreement until the completion of examination administration, I did not the date that I entered into specifically noted during the week(s) of 412812014. From nts who were administered these licensing examinations, maept as ktsfruct evaluate, or provide performance feedback to those applica below and authorized by the NRC.
JOB 1TILE1 RSPONSIBILWY DA1, PNTED -
1.
1/1113 7/ifli rr s-94%f
- 2.
- U 1
1 ) P LJJ. 7, W.d AiAi 1wt
- 3. (i,,ffa,e1 (.)(Zk1!
- 4. -.
- 5. ,aJ I i?M iV,AIi&1L.
74$
- 6. l&Li7-/ FA 4nqc. $4 £ *-.-
Rucsaal hp(sv A 31lI 7.
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- 10. Ya-wJ c-szzt
- 11. *I1_ (V1. __e9
- 12. C°iç ;
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- 13. 1PAL#J c. 4ILk c-,2-ffiy
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- 14. 1)4ij1csP,.3idr 0 43yP%_9 15 1 Po.A- 1* 4
. X*yJ SVfr% SFvv.
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NOTES 27i Pag ES-201 of 28
ILT 1404 ES-201 Examteation Security Areemeit Fomi ES-201 -3
- 1. Pro-ExaminatIon I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations sctiedud for the week(s) of 412812014 as of the date of my signature agree that I wit not knowingly divulge any information about these examinations to any persons who have riot been authorized by the NRC chef examiner understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be admkilstered these licensing examinations from this date until complebon of examination administration, except as specifIcally noted below and authorized by the NRC (e.g.
acting as a simulator booth operator or communator is acceptable if the Individual does not select the training content or provide direct or indirect feedback)
Furthermore. I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised
- 2. Post-Examination To the best of my knowledge. I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 412812(j4. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate or provide performance feedback to Those applicants who were administered these licensing examinations, except as specifIcally noted below and authorized by the NRC PRINTED NPME JOB TIThE I RESPONSIRiUW DATE SIGNATURF (2) DATE NOTE 1.
2.
3 . tcpr t. -
)ci P I,
- 4. .
- t. *7e_4& C {g) >/2(jj.i
)
- 5. a.J X///.. f4 - I
- 6. Zh iA3 Mcii-ir/ seA.
7 Coop 4i wib& .... f/l.3 c;=_ / fr4ci .>
i$+/-ail Joft. 4..
8 Hg1i . (Iit?ic
- 9. 2( ,J iL(
4:r 1 1i iJi jLLQ-L
- 10. ec
- 11. 4-l3
- 12. t ,:em ) Cc 5, -., Sr./. cOS -c, ,3
- 13. ç4CI4EiD
- 14. Ir, SfI1If S 15 d C-)
3 r U NOTES:
Pagi ES-201, 27of28
ILT 1404 ES-201 Examination Security Agreement Form ES-201 -3
- 1. Pre-Examination I acknowledge that have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 412812014 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g.,
acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 412812014. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE I RESPONSIBILITY SIG,p4ATURE(1) DATE SIGNATURE (2) DATE NOTE A
. it .
- 1. LT; c:%F-f{A S
- c_*\.*____o\ .:
2.
- 3. tori& ç;* i4 EJ(vv\ T&W
- 7Z43 ç.
- 4. D- Tec 1 a( /
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- 5. /<cJ -cLe//i _4 /
- 6. £J4LP -A-TH Mi1-/7-/ peA. 1
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- 7. .(L _)optv. i2 Ai wf,- 4 W3 S44c4 Il ?
- 8. -tZri (C c- (L w.--- -
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- 9. L( r
£47r
- 10. .)-e. -r.4 çarv /e/ k rvi S3m4L6L 4t44 5-iL-f 11.
- 12. t, / .c ,*i C -.)ç -, .c i. c 1-, 3
- 13. 79nJ 5. 4 g 4 Sjrn / c1cfitb3
- 14. Q4JftcP,JLJr)
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15 1 C-f A 11-4 fLdLky( 0 (%. 9 d U NOTES:
ES2O1, 27of28
lIT 1404 ES-201 Examination Security Agreement Form ES-201 4
- 1. P*Exarntnatlon I acknowledge that I have acquired specialized knowledge about the NRC licensing exéminations scheduled for the week(s) 01412812014 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 Ilcenslqg examinations from this date until corn pletion 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 indMdual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented In the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and!or an enfoitement action against me or the facitity licensee.
I will immediately report to facility management or the NRC chief examiner any Indications or suggestions that examination security may have been corn promised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any infomiafion concerning the NRC licensing examinations administered during the week(s) of 412812014. From the date That I entered into this security agreement until the completion of examination administration, I did not instrUct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC:
PRINTED NAME JOB TITLE! RESPONSIBILITY nm SIGNATURE (2) DATE NOTE
- 1. niRAWLDA4&IPJ E ATt4c4ac a ,tdt.tEwpOIc1 .- r9ic/
O-YL%Z-.
- 3. Du4 t)CAA% 1SN1..__ till
- 4. .ac,unuta r/fl 5 1,L1 //ejrer goc -nhr 3,
- 6. Csse
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- 11. &AOr Ck\k c.o .4fJJ. frioi( SJ9-$j -
- 12. q kv4 ..sCo
- 13. 1 9 Jt
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- 14. T)-e4 Mhthc1 5e0*
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NOTES:
ES-201, Page 27 of 28
1 ILT 1404 ES-20i lnat1on Security Agreement Form ES-WI -3
- 1. Pre-Examinahog I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 412812014 as of the date of my signature. I agree that I wilt not knowmgty 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 prcniide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancetiation of the examinations andlor an enfoitement action against me or the facility licensee.
I will Immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-ExamInation To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing during the week(s) of 412812014. From the date that I entered into this security agreement until the completion of examinations administered examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE (RESPONSIBILIW SIGNATURE Cl) DATE NOTE
- 1.
- 2. _1irL
- 3. 6 A c 4.
5.
6.
7.
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- 14. r *-) .1 I L_. L- I 15 NOTES:
ES-201, Page f 28
ILT 1404 ES-201 Examination Security Agreement Form ES-201 -3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 412812014 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g.,
acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been corn promised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 412812014. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE / RESPONSIBILITY DATE SIGNATURE (2) DATE NOTE
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ES-201, Page 27 of 28
ILT 1404 ES-201 Examination Security Agreement Form ES-201 -3
- 1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 412812014 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g.,
acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
- 2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of 412812014. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE I RESPONSIBILITY SIqNTI,JRE (1) DATE SIG7E (2) DATE NOTE
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ES-201, Page 27 of 28
ILT 1306 Administrative Topics Outline FINAL Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 4/28/20 14 Examination Level: RO / SRO Operating Test Number: 1404 Administrative Topic Type Describe activity to be performed Code Conduct of Operations 2. 1.26 Determine Electrical Safety requirements and the correct N procedural requirements to Rack Out 480V SD BD 2A compartment SRO/RO Al a 7A supply for Control Bay Chiller 3A Conduct of Operations M 2.1.7 2-SR-2 Drywell Floor and Equipment Drain Log Calculation SRO/RO Aib N 2.1.5 NFR ESOMs Shift Staffing Equipment Control SRO/RO A2 M 2.2.44 Evaluate Recombiner Performance Radiation Control D 2.3.4 Determine Stay Time under Emergency Conditions and authorize SRO A3 Emergency Plan D 2.4.43 EPTP-5 Appendix B and C Notifications RO/SRO A4 D 2.4.41 Emergency Action Level Classification NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
Type Codes & Criteria: (C)ontrol Room (D)irect from bank (<3 for ROs; <4 for SROs and RO retakes)
(N)ew or (M)odified from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator
ILT 1306 Administrative Topics Outline FINAL Form ES-301-1 Reactor Operator
- 1. Determine Electrical Safety requirements and the correct procedural requirements to Rack Out 480V SD BD 2A compartment 7A supply for Control Bay Chiller 3A.
- New
- O-GO1-300-2, Electrical and TI-300, Electrical Safe Work Practices
- Determine correct section of O-GOI-300-2 that is required to Rack Out the breaker, the verification requirement and the Electrical Safety PPE and Protective Boundary requirement.
- Modified from Bank
- 2-SR-2 Instrument Checks and Observations) (Applicant Handout)
- 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance RO 4.4
- 3. Evaluate Recombiner Performance
- Modified from Bank
- 2/3 3-01-66, Offgas System
- Determines that Recombiner performance meets the acceptance criteria and standby Recombiner is not required to be placed in service.
- 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions RO 4.2
- 4. EPIP-5, Appendix B and C Activation of ERO and State Notifications
- Direct from Bank
- EPIP-5, General Emergency
- Completion of ERO Activation and State Notification in accordance with Appendix B and Appendix C of EPIP-5.
- 2.4.43 Knowledge of emergency communications systems and techniques. Importance RO 3.2
ILT 1306 Administrative Topics Outline FINAL Form ES-301-1 Senior Reactor Operator
- 1. Determine Electrical Safety requirements and the correct procedural requirements to Rack Out 480V SD BD 2A compartment 7A supply for Control Bay Chiller 3A.
- New
- O-GOI-300-2, Electrical and TT-300, Electrical Safe Work Practices
- Determine correct section of O-GOI-300-2 that is required to Rack Out the breaker, the verification requirement, the LCO condition, and the Electrical Safety PPE and Protective Boundary requirement.
- 2. NFR ESOMs Shift Staffing
- New
- Using ESOMs the SRO determines who is available and who would be in violation of the Fatigue Rule JAW NPG-SPP-3.21.
- 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. Importance SRO 3.9
- 3. Evaluate Recombiner Performance
- Modified from Bank
- 2/3-01-66, Offgas System
- Determines that Recombiner performance meets the acceptance criteria and standby Recombiner is not required to be placed in service.
- 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions SRO 4.4
- 4. Determination of Stay Time and Approving Authority to perform an emergency evolution to save equipment.
- Direct from Bank
- EPIP 15, Emergency Exposure
- Determine amount of time an operator has to perform an emergency evolution due to radiation levels and authorize on the correct form.
- 2.3.4 Knowledge of radiation exposure limits under normal and emergency conditions.
Importance SRO 3.7
ILT 1306 Administrative Topics Outline FINAL Form ES-301-1
- 5. Emergency Action Level Classification
- Direct from Bank
- EPIP- 1 and 5 Emergency Classification Procedure and General Emergency
- Complete Notification Handouts Appendix A
- 2.4.41 Knowledge of emergency action level thresholds and classifications. Importance SRO 4.6
ES-301 Control Roomlln-Plant Systems Outline FINAL Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 4/28/20 14 Exam Level: RO I SRO-I I SRO-U Operating Test No.: 1404 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including I ESF)
Safety System I JPM Title Type Code*
Function
- a. Dual Recirc Pump Quick Restart N, L, S 1
- b. RFPT Trip Recovery Unit 3 only N, L, S 2
- c. Respond to a Stuck Open SRV Unit 2 only A, M, 5 3
- d. 2/3-SR-3.3.1.1.8(11) RPS Channel Functional A, P, S 7
- e. Placing Primary Containment Ventilation in service L, N, EN, 5 5
- g. Cross-Tie CAD to Drywell Control Air A, D, S 8
- j. Shutdown Cooling in Service JAW CR Abandonment N, R, E 7
- k. Align 480V RMOV BD 3B and Start RIIR Pump 3A A, D, E 8
@ Au RO and SRO-l controi room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
Type Codes Criteria for RO I SRO-l I SRO-U (A)lternate path 4-6/2-3 (C)ontrol room (D)irect from bank <91<81<4 (E)mergency or abnormal in-plant > 1/> 11>1 (EN)gineered safety feature - / 1>1 (control room system)
(L)ow-Power / Shutdown >11>11>1 (N)ew or (M)odified from bank including 1 (A) > 2/> 21>1 (P)revious 2 exams < 31< 31< 2 (randomly selected)
(R)CA >11>11>1 (S)imulator
ILT 1306 Control Roomlln-Plant Systems JPM Narrative Control Room Systems:
- a. Dual Recirc Pump Quick Restart (Unit 2 or 3)
- New / Simulator / Low Power
- 2/3-01-68, Reactor Recirculation System
- Operator directed to perform dual Recirculation Pump quick restart lAW 2/3-01-68, the operator will start the A Recirculation Pump.
- b. RFPT Trip Recovery (Unit 3)
- New / Simulator / Low Power
- 3-01-3, Reactor Feedwater System
Pump trip. IMPORTANCE: RO 3.7 SRO 3.7
- The operator places an Alternate RFPT in service JAW 3-01-3 section 8.1 and restores Reactor Level.
- c. Responds to a stuck Open SRV (Unit 2 Only)
- Alternate path / Modified from Bank / Simulator
- 2-AOl-i-i, Relief Valve Stuck Open
- 239002 Relief! Safety Valves A2.03 Ability to (a) predict the impacts of the following on the Relief! Safety Valves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV IMPORTANCE: RO 4.1 SRO 4.2
ILT 1306 Control Roomlln-Plant Systems JPM Narrative
- d. 2/3-SR-3.3.1.1.8(11) RPS Channel Functional with Rod Drifts (Unit 2 or 3)
- Previous Exam / Alternate Path / Simulator
- 2/3- SR-3.3.1 .1.8(11) Reactor Protection System Manual Scram Functional
- 2/3-AOI-85-5, Rod Drift In
- 212000 Reactor Protection System A4.0l Ability to manually operate and/or monitor in the control room: Provide manual SCRAM signals IMPORTANCE: RO 4.6 SRO 4.6
- Operator directed to perform RPS channel functional. The A RPS channel will test correctly, when the B channel is tested two control rods will scram. The operator will respond to the rod drift alarm and with more than one control rod inserting the operator will be required to insert a manual reactor scram.
- e. Placing Primary Containment Ventilation in service (Unit 2 or 3)
- New / Simulator / Low Power I ENgineered Safety Feature
- 2/3-01-64 Primary Containment System
- 223001 Primary Containment System and Auxiliaries A4.03 Ability to manually operate and/or monitor in the control room: Air dilution valves drywell and suppression pool:
Plant-Specific IMPORTANCE: RO 3.4 SRO 3.4
- The operator places Primary Containment Ventilation in service lAW 2/3-01-64.
- New / Simulator / Low Power / Alternate path
- 0-A0I-57-1A, Loss of Offsite Power / Station Blackout
Loss of off-site power IMPORTANCE: RO 3.9 SRO 4.3
ILT 1306 Control Roomlln-Plant Systems JPM Narrative
- g. Cross-Tie CAD to Drywell Control Air (Unit 2 and 3)
- Direct from Bank / Simulator / Alternate Path
- 2/3-EOI Appendix-8G Crosstie CAD to Drywell Control Air
- h. Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only) (Unit 2 or 3)
- Previous / Simulator
- 2/3-ARP-9-4C, Window 35
- 2/3-AOI-66-2, Offgas Post-Treatment Radiation HI-HI-HI
- 271000 Offgas System A2.04 Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Offgas system high radiation IMPORTANCE: RO 3.7 SRO 4.1
- Operator is directed to respond to Offgas Post-Treatment Radiation HI-HI-HI alarm in accordance with 2/3-ARP-9-4C Window 35. Then the operator refers to 2/3-AOI-66-2, Offgas Post-Treatment Radiation HI-HI-HI, and perform the actions of 2/3-AOI-66-2 insert a core flow runback and reactor scram. Operator will then shut the MSIVs.
In-Plant Systems:
- Direct from Bank I Emergency or Abnormal In-Plant! RCA Entry
- 1 -EOI Appendix-7G, Alternate RPV Injection System Lineup Pressure Suppression Chamber Head Tank Pumps
ILT 1306 Control Room!ln-Plant Systems JPM Narrative
- j. Shutdown Cooling in Service JAW CR Abandonment
- New / Emergency in Plant / RCA Entry
- 1-AOI-100-2, Control Room Abandonment
- Simulates placing Shutdown Cooling in service from outside the control room JAW I -AOl- 100-2.
- k. Align 480V RMOV Board 3B and Start RHR Pump 3A
- Direct from Bank / Emergency in Plant / Alternate Path
- 0-SSJ-16, Control Building Fire EL 593 through EL 617
ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Date of Examination: Operating Test Number:
Initials
- 1. General Criteria 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 distribution). t. .
- b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.
- c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1.a.) Ot-
,( 7L
- d. Overlap with the written examination and between different parts of the operating test is within acceptable limits.
- e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. Ot..
- 2. Walk-Through Criteria --
- a. Each 1PM includes the following, as applicable:
- initial conditions
- initiating cues
- references and tools, including associated procedures
- reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee
- operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable
- b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g.. item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.
oi
- 3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.
Printed Name / Signature Date
- a. Author 7 i LJSL iZ_--- -
b.
c.
Facility Reviewer() JkZ)/$Jl 4. /4JTW NRC Chief Examiner (#) 3 tAt4 0 C-A A LLZ.O 4 4
/-j/a
- 22 ii
- d. NRC Supervisor fl ? 1 r L( 5 Lj
\j NOTE:
- The facility signature is not applicable for NRC-developed tests.
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
ES-301, Page 24 of 27
ES-301 Simulator Scenailo Quality Checklist Form ES-301-4 Facility: Browns Ferry Date of Exam: April 2014 Scenario Numbers: 4151617 OperatIng st No.: 1404 Initials QUALITATIVE ATTRIBUTES a
b*
- 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
- 2. The scenarios consist mostly of related events. Ot. 13Z.
- 3. Each event description consists of
- the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event
- the symptoms/cues that will be visible to the crew the expected operator actions (by shift position)
- the event termination point (if applicable) 0Z.
- 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event
- 5. The events are valid with regard to physics and thermodynamics. OL
- 6. Sequencing and timing of events is reasonable, and aiiows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
- 7. If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints. Cues
/ ,,) /
are given.
- 8. The simulator modeling is not altered. ØL
- 9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios. DZ.-
- 10. Every operator will be evaluated using at least one new or significantly modified scenario. All other scenarios have been altered in accordance with Section D.5 of ES-301.
- 11. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 oZ.
(submit the form along with the simulator scenarios).
- 12. Each applicant wifl be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
- 13. The level of difficulty is appropnate to support licensin9 decisions for each crew position. -
/
V.
Ta t Quantitative Atbibutes (Per Scenario; See Section D.5.d) Actual Attributes
- 1. Total malfunchons (5-8) 911019110 ot-Pt-
?K
- 2. Malfunctions after EOP entry (1-2) 1131312 j
- 3. Abnomial events (2-4) 4141414 )t.
- 4. Major transients (1 -2) 2111112 OZ..
4 ?)ZL
- 5. EOP5 enteredlreguirlng substantive actions (1-2) 2121212 oz.
- 6. EOP contingencies requiring substantive actions (0-2) 2121011 ..
- 7. Critical tasks (2.3) 6/3/313 L ES-301, Page 25 of 27 L
ES3O1 Transient and Event Checklist Form ES-301-5 Facility: Browns Ferry NPP Date of Exam: April 28 - May 2, 2014 Operating Test No: ILT 1404 Scenarios 4 5 6 7 T M P E L N CREW CREW CREW CREW 0 POSITiON POSITION PosmoN POTION T A T S A 8 S A B S A B S A B A M N R IT 0 R T 0 R T 0 R T 0 L U r C P 0 C P 0 C P 0 C P R I U 0 RX 1 1 2 1 NOR RO- -
3,45,6 345.6 8 2 IIC SRO-U 3 1
- i MAJ 7,8 7 13 346 5 2 1
T S 2 2 2 2 1 RX 1 2 I NOR I -
R0
- 1 45,6 34,5,6 11 4 IC 34,5,6 itt SRO-U 7 7 42 MAJ 7,8 TS 1,3 3,5,6 . *.
5 2 1
2 2 2 RX 1 1 2 1 NOR RO-I .
- 2 3,4 34,5,6 3,6 8 4 I/C
- SRO-U .... .
7 5 2
- MAJ 7,8 7 TS .
3,4,6 . . . 3 2 RX NO 1 1 2 1 R0-I/C 3,4,5,6 3456 5 2 SROU MAJ 78 7 31 TS 1,3 34.6 .
5 1 1 I
2 .-
NOR -
1 -
- 1 1 R0- - ..._
I/C 35,6 3,4 ,-
5 4 MM 7,8 7 3 2
.,R0-U TS P.. 2
Transient and Event Checklist Form ES-301-5 ES-301 Date of Exam: April 28 - May 2, 2014 Operating Test No: LT 1404 Facility: Browns Ferry NPP Scenarios 6 7 T M P C 4 5 CREW CREW CREW CREW 0 posmoN POSITION POS1TION POSITION T c AS A M A T S A B S A B S A B S T 0 R T 0 R T 0 R T 0 L U R M()
0 C P 0 C P 0 C p o CP C R I U
°° RX 2 1 1 1 NOR RO-I
/C 35,6 3,4 5 4 MAJ 78 7 3 2 ROU TS o RX 2 __
NOR 1 1 1 cR0.1
- I/C 35,6 3,4 4 78 7 3 2
.ROU MM TS RX 1
2 Z_EE_ 1 2 1 NOR R0I 7 4 IC 34 456 45 78 7 7 4 2 ou MAJ TS O
EE 2
£ LE 1 1 NOR 1 6R04 5 4 I/C 34 456 78 7 3 2 ROU MAJ TS
.fl.V!G41$
event numbers for each event type; TS are I Check the apphcant tevel and enter the operating test number anc Form ES-ID-i (ATC) and balance-ct-plant (SOP) not applicable for RO applicants. ROe must serve in both the at-the-controls positions; Instant SROs must serve in both the SRO and the ATC positions. including at least two instrument or component Instant SRO additionally serves in the SOP position.
(lIC) malfunctions and one mor transient, in the ATC position. If an malfunction can be credited toward the two IC malfunctions required for the ATC position.
one I/C abnormal conditions (refer to Section D5d) but
- 2. Reactivity manipulations may be conducted under normal or controlled and normal evolutions may be replaced with additional must be significant per Secticn C2.a of Appendix ID. () Reactivity instrument or component malfunctions on a i-for-i basis.
should be included; only those that require ventlable 3, Whenever practical, both instrument and component malfunctions competence count toward the minimum requirements specified for the actions that provide insight to the applicants applicants license level in the right-hand columns.
ES-301, Rev. 9 Competencies Checklist Form ES-301-6 Facility: Browns Ferry Date of Examination: April 2014 Operating Test No.: 1404 APPLICANTS RO SRO-I SRO-U Competencies SCENARIO SCENARIO SCENARIO 4567 4 567 4567 Interpret/Diagnose Events 3,4,5, 3,4,5, 3,4,5, 3,4,5, ,4,5, 3,4,5, 3,4,5, 3,4,5, ,4,5, 3,4,5, 3,4,5, 3,4,5, and Conditions 6, 6,7 6,7,8 6,7,9 6, 6,7 6,7,8 6,7,9 6, 6,7 6,7,8 6,7,9 Comply \Nith and 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3, 1,2,3, ,2,3, 1,2,3, 1,2,3, 1,2,3, 4,5,6 4,5,6 5,6,7, 5,6,7, 4,5,6 4,5,6 5,6,7, 5,6,7, 4,5,6 4,5,6 5,6,7, 5,6,7, Use Procedures (1) 7 8 9 7 8 9 7 8 9 Operate Control 1,2,3, 1,2,3, 1,2,3 1,2,3 ,2,3, 1,2,3, 1,2,3 1,2,3 ,2,3, 1,2,3, 1,2,3 1,2,3 Boards (2) 4,5,7, 4,5,6, 4,5,6 4,5,6 ,5,7, 4,5,6, 4,5,6 4,5,6 ,5,7, 4,5,6, 4,5,6 4,5,6 8 7 7,8 7,9 8 7 7,8 7,9 8 7 7,8 7,9 Communicate 7,8 3,4,6, 3,4,5, 7,9 7,8 3,4,6, 3,4,5, 7,9 7,8 3,4,6, 3,4,5, 7,9 and Interact 7 6,7,8 7 6,7,8 7 6,7,8 Demonstrate Supervisory ,4,5, 3,4,5, 3,,5, 3,,5, 45 3,4,5, 3,4,5, 3,4,5,
\bility (3) 6,7,8 6,7,8 6,7,8 6,7,9 6,7,8 6,7,8 6,7,8 6,7,9 Comply With and 1,3 3,4,6 3,5,6 4,5 1,3 3,4,6 3,5,6 4,5 Use Tech. Specs. (3)
Notes:
(1) Includes Technical Specification compliance for an RO.
(2) Optional for an SRO-U.
(3) Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-4O1Rev. 9 BWR Examination Outline Form ES-401-1 Facility Browns Ferry Date of Exam: -20i0- Afr( 2Dr-RO KIA Category Points SRO-Only Points Tier Group KKIKKKKAAAAG A2 G* Total 1 213 4 5 6 1 2 3 4
- Total
- 1. 43 3433 20 4 3 7 Emergency &
2 i T i 2 1 T 2 1 3 Abnormal Plant NIA NIA Evolutions Tier Totals
= 6
27 6 4 10 1 23322222332 26 3 2 5
- 2. 1 1 1 11 2 11 1 1 1 12 2 02 1 3 Plant Systems Tier Totals 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 3 2 1 2 2 2 jff 1. Ensure that at least two topics from every applicable KJA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tler Totals in each K!A category shall not be less than two).
- 2. The point total for each group and tier in the proposed outiine must match that specified in the table.
1 The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
1,,4 3. Systemslevolutlons within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
ØZL 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.
- 7. The generic (C) K1As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 8. On the following pages enter the KIA numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category In the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column AZ for Tier 2, Group 2 (Note
- 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group EIAPE #1 Name I Safety Function K K K A A G K/A Topic(s) IR #
i2i1 295001 Partial or Complete Loss of Forced ( AI.O3 Core Flow Circulation / 1 & 4 (1k) A2 .04 295003 Partial or Complete Loss of AC / 6 295004 Partial or Total Loss of DC Pwr 16 S cR)API.° cs) z.t.7 295005 )AAI.0l Main Turbine Generator Trip /3 295006 SCRAM/i
$ () AjL) .03 (..S) 2. 1. 2o R (2.) 2.4.49 295016 Control RoomAbandonment/7 295018 Partial or Total Loss of CCWI 8 R g) A, l O_
295019 Partial or Total Loss of Inst. Air! 8 R R) a. 4-. I () AP 2. D2 295021 Loss of Shutdown Cooling /4 ka.o 295023 Refueling Acc 18 g) A 3<3 .03 295024 High Drywell Pressure! 5 R )
C ,4.3 (5) EAZ.D3 295025 High Reactor Pressure/3 295026 Suppression Pool High Water () -A 1. 0 3 Temp. /5 295027 High Containment Temperature /5 :: : ::
E 3<3 .%
295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl /5
. 0 I 295031 Reactor Low Water Level /2 R
() I3. v2.
295037 SCRAM Condition Present R () E- . 04- (5) AZ.
and Reactor Power Above APRM Downscale or Unknown /1 295038 High Off-site Release Rate /9
( 2. o 600000 Plant Fire On Site /8 R (!) P 1<. o 4 ) AAZ. 35 700000 Generator Voltage and ElectncGnd R S (g) A14jD3 L5)
Disturbances 16 K/A Category Totals: (ZV 3 14 [!, 13 Group Point Total: 20/7 H
ES-401,REV9 -_______________
T1G1 BWR EXAMINATION OUTLINE ____________________
FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 1(3 K4 KS 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 295001AX1.03 Partial or Complete Loss of Forced 3.6 4.1 1LJLIEiELIEJL1 Thermal limits.
Core Flow Circulation/i & 4 295OO3A204 Partial or Complete Loss of AC! 6 35 3 LI LI LI LI LI [3 LI I) El U LI System Iups.
295004M1.03 Partial or Total Loss of DC Pwr / 6 3.43.6 [] LI [1 CI[1 [1 l Cl [3 [1 LI A.C. electrical distribution 295005AA1.01 Main Turbine Generator Trip! 3 3.1 3.3 [3 [3 El LI LI LI i LI LI [1 LI Recirculation system: Plant-Specific 295018G24.49 Control Room Abandonment/7 4.6 4.4 Cl LI LI LI LI LI LI LI LI[I Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
295018M1.02 Partial or Total Loss of CCW /8 3.3 3.4 U LI [1 El El U [I LI [I U LI System loads 29501 9G2.4.1 Partial or Total Loss of Inst. Air / 8 4.6 4.8 [] U LI C] [I C] LI LI C] C] Knowledge of EOP entry conditions and immediate action steps.
295021AA2.02 Loss of Shutdown Cooling / 4 3.4 3.4 LI LI Li LI LI LI LI ll LI LI LI RHfllshutdown cooling system flow 295023AK3.03 Refueling Acc Cooling Mode /8 3.3 3.6 LI LI ti LI [1 LI LI LI [1 C] U Ventilation Isolation 295024G2.4.3 High Drywall Pressure! 5 3.7 3.9 LI LI LI Li LI LI LI [I LILIl Atslity to identity post-accident instrumentation.
295025EA2.05 High Reactor Pressure/3 3.4 3.6 LI LI LI LI Li [I LI [l LI LIE] Decay heat generation Page 1 of 2 071/2013 2:00PM
ES-401,REV9 T1G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION: FORM ES-401-1 IR K1K2K3K4K5K6A1A2A3A4G TOPIC:
RO SRO 295026EA1.O1 Suppression Pool High Water Temp.! 4.1 4.1 5 Suppression pool cooling 295028EK3.06 High Olywell Tempeyature / 5 3.4 3.7 ADS 295030EK2.O1 Low Suppression Pool Wtr Lvi! 5 3.8 3.9 HPCI: Plant-Specific 295031 EK3.02 Reactor Low Water Level /2 4.4 4.7 Core coverage 295037EK 1.04 SCRAM Condition Present and Power 3A 3.6 JOEFJ Above APRM Downscale or Unknown Hot shutdown boron weight: Plant-Specific
/1 295038EK2.06 High Off-site Release Rate/9 a43.7 Process liquid radiation monitoring system 600000AK2.04 Plant Fire On Site / 8 2.5 2.6 DEEJLJ Breakers I relays / and disconnects 295006AK1 .03 SCRAM/I 3.7 4.0 Reactivity control 70000041(1.03 Generator Voltage and Electric Grid 3*3 Oistrurbancecs E1E1L1ELiL1E1L1 Under-excitation Page 2 of 2 07/01/2013 2:00PM
ES-401, REV 9 ()T1G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1< 1<2 1<3 1<4 1<5 1<6 Al A2 A3 A4 G TOPIC:
nO SRO 295004G21.7 Partial or Total Loss ot DC Pwr / 6 4.4 47 [] [] El El El [1 El LI Ci Cl l Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and Instrument interpretation.
29500602.1.20 SCRAM! 1 4.6 4.6 [] [] C] C] El CI El Li CI L] Iil Ability to execute procedure steps.
29501 9AA2.02 Partial or Total Loss of Inst. Air! 8 3.6 3.7 [] E][1 El U U U (l Li C] C] Status of safety-related instrument air system loads (see AK2.l -AK2.19) 296025EA2.03 High Reactor Pressure/3 3.9 4.1 CI [1 CI [1 [1 U E]i [1 LI U Suppression pool temperature 295037EA2.06 SCRAM Condition Present and Power 42 4.3 C] [] U U El U LI Sl LI [1 LI Control rod position Above APRM Downscate or Unknown
/1 600000AA2.15 Plant Fire On Site /8 2.3 3.5 [1 U Li El C] El U l] U U U Requirements for establishing a fire watch 70000002.4.9 Generator Voltage and Electric Grid 3.8 4.2 [] LI LI LI U U C] U LI U (l Knowledge of low power I shutdown implications in Distrurbancecs accident (e.g. LOCA or loss of RHR) mitigation strategies.
Page 1 of 1 07/01/2013 2:00PM
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 RO SRO)
E/APE # / Name/ Safety Function K K K A A G K/A Topic(s) IR #
12312 295002 Loss of Main Condenser Vac /3 c A2. I 295007 High Reactor Pressure / 3 295008 high Reactor Water Level! 2 R () IZ .02 p3,,
295009 Low Reactor Water Level /2 295010 High Drywell Pressure / 5
( T..4.2..D 295011 High Containment Temp / 5 295012 High Drywell Temperature /5 295013 High Suppression Pool Temp. /5 295014 Inadvertent Reactivity Addition / 1 (t)AA2.Dl 295015 Incomplete SCRAM I 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation! 5&7 R ç) A 3.
295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5
(\ E..03 295032 High Secondary Containment Area Temperature /5 295033 High Secondary Containment R S (R) Al. 0 Area Radiation Levels /9 (5) .A2.. P3 295034 Secondary Containment Ventilation High Radiation /9 295035 Secondary Containment High ) 1.0 I Differential Pressure /5 295036 Secondary Containment High Sump/Area Water Level /5 500000 High CTMT Hydrogen Conc. /5 K/A Category Point Totals: Ro I I I Group Point Total: 7/3 21
ES-401, REV9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki 1<2 1(3 1(4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 295QOAK2.02 High Reactor Water Level /2 3.6 3.8 [1 l Reactor feedwater system H H [1 H [1 [1 El El 0 296014G2.4.9 Inadvertent Reactivity Addition/i 3.8 4.2 [] El H El El fl [] [] J {) Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation Strategies.
295015M2O1 Incomplete SCRAM/i 4.1 4.3 flQ[]Q Reactorpower 295020AK3.03 Inadvertent Cont. Isolation / 5 & 7 3.2 3.2 fl [] [J [J [] [3 [] [] [] [] Diywelt/containment temperature response
(-re..yi.m e
1 ,
295032EK1.03 High Secondary Containment Area 3.5 3.9 (] [J[][] [3 [3 [] [J [][][] Secondary containment leakage detection: Plant-Temperature /5 Specific 295G33A1.02 High Secondary Containment Area 3.7 3.8 [3 [3 [3 []Q [3 J [3 [3 [J[] Process radiation monitoring system Radiation Levels /9 295035EA1.O1 SecondaryContalnment High 3.6 3.6 Secondary containment ventilation system Differential Pressure /5 fl [3 []Q [] Q] [] [3 Q[]
Page 1 of 1 07/01/2013 2:00PM
ES-401, REV 9 (T1G2 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: JR KIK2K3K4K5K6A1A2A3A4G TOPIC:
no sno 295002A.A2.01 Loss of Main Condenser Vac /3 2.9 3.1 Condenser vacuum/absolute pressure 295010GZ4.20 Hi Dryweil Pressure/5 3.8 4.3 Knowledge of operational implications of EOP warnings.
cautions and notes.
295O33EA2.O High Secondary Containment Area 3.742 Cause of high area radiation Radiation Levels / 9 Page 1 of 1 07/01/2013 2:00 PM
ES-401 4 Form ES-401 -1 ES-401 BWR Examination Olt1iQe.... Form ES-401-1 Plant ysterns Tr 2IGroupl ((Roy(sRo)
=
System #1 Name K K K K K K A A A A G K/A Topic(s) IR #
1234561234 203000 RHRJLPCI: Injection R S 0) A4-D3 (5) 3g Mode 205000 Shutdown Cooling U) V.o2.
206000 HPCI R
207000 Isolation (Emergency) p.) /
Condenser 209001 LPCS R
() 1(1.1+
2O9002HPCS 211000 SLC CR) M-.P4-212000RPS 2150031RM R 1) R303 215004 Source Range Monitor IR) A3. 0 215005 APRM / LPRM 5 (g) 3,07 c) A 2.
217000 RCIC .
() A4-.DS ?.)i<.O.2 218000ADS iI.o3 223002 PCIS!Nuclear Steam cA .0 I SupplyShutoff 239002 SRVs R R)2.4.4t 259002 Reactor Water Level (a.) 144,01 Control 261000SGTS 5 1R)i.0l ($)CZ2.4-262001 AC Electrical R. () (4.D3 Distribution 262002UPS(AC/DC) R )tv4 cj)1(,03 263000 DC Electrical j. EI A 1.01 (5) AZ .02.
Distribution cs.) K .01 264000 EDGs (f 03 300000 InstrumentAir i A3.v..
400000 Component Cooling p5 c 1) 0c1 (S) A2. 0 Water K/A Category Point Totals: (ZO ]J. 3i3T- ,2 12 2 2 3 3j Group Point Total: j2615 3 2.
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES4O1-1 KA NAME / SAFETY FUNCTION: IR Xl K2 1(3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 203000A4.03 RIIR/LPCI: Injection Mode DDOOüDU1ThE1 Keep fill system 205000K5.02 Shutdown Cooling 2.8 2.9 UflO1JE1 Valve operation 206000K3.02 HPCI 3.8 3.8 DWJOLi Reactor pressure control: BWR-2,34 206000K5.07 HPCI 2.8 2.8 EUflüLJ System venting: BWR-23,4 209001K1.14 LPCS 3.7 3.8 1E1E1E1E1E1 Reactor vessel 211000A4.04 SLC 4.5 4.6 Reactor power 21 2000A2 03 RPS flEJüLDLLE1L Surveillance testing 215003K3.03 IRM OOLJLJÜLJLJ Rod control and information system: Plant-Specific 21 5004A3.02 Source Range Monitor DflflOE111O Annunciator and alarm signals 215005K307 APRM / LPRM 3.2 3.3 DDJEID Rod block monitor: Plant-Specific 217000A4.08 RCIC 3.7 3.6 DFLJUIIJEJ System flow Page 1 of 3 07/01/2013 2:00PM
ES-401, REV 9 c)
T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:
RO SRO 217000K2.02 RCIC 2.8 2.9 RCIC initiation signals (logic) 218000K1 .03 ADS 373.8 Nuclear boiler instrument system 223002A3.O1 PCISFNuclear Steam Supply Shutoff L1LEtJULHJE1Ü System indicating lights and alarms 22300202.4.31 PCIS/Nuclear Steam Supply Shutoff 4.2 4.1 Knowledge of annunciators alarms, indications or flj response procedures 239002G2.4.46 SRVs -____________
4.2 4.2 fljOFJ Ability to verify that the alarms are consistent with the plant conditions.
259002K4.O1 Reactor Water Level Control 3.0 3.1 EflE1flEE1 Ensuring adequate NPSH for recirculation pumps: Plant-Specific 261000A1.01 SGTS 2.9 3.1 System flow 262001K4.03 AC Electrical Distribution 3.1 3.4 1[1OL Interlocks between automatic bus transfer and breakers 262002A2.04 UPS (ACIDC) - 3.4 Abnormal battery operation: 8WR-1 262002K6.03 UPS (AC/DC) 2.7 2.9 flE1JOEIL Static inverter 263000A1.01 DC Electrical Distribution 2.5 2.8 Dfl1jFJ Battery charging/discharging rate Page 2 of 3 07/01/2013 2:00PM
()
ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR KI 1(2 1<3 K4 1<5 1<6 Al A2 A3 A4 G TOPIC:
FlO SRO 2830001(2.01 DC Electrical DistributIon 3.1 3.4
[] [] [J J [] [] U El Major D.C. loads 264000K6.03 EDGs 3.5 3.7 [] [] [] Lube oil pumps
[J J [] [] [] U []
300000A3.02 Instrument Mr 2.9 2.7 {) [J [][] fl Air temperature
[] U []
4000001(2.02 Component Coohng Water 2.9 2.9 CCW valves
[] [] L] [] [] [J [] [] [] [j [J Page 3 of 3 07/01/2013 2:00 PM
ES-401, REV 9 JT2G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 1(2 1(3 1(4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 2030000aa38 RHRILPCI: Injection Mode 3.6 4.5 Knowledge of conditions and limitations in the facility 0 El [1 0 [] [] [1 H [1 H J license.
215005A2.05 APRM I LPRM 3.5 3.6 Loss of recirculation How signal
[1 El El El LI H LI F] LI LI LI 261000G2.2.4 SGTS 3.6 3.6 (multi-unit) Ability to explain the variations in control LI H El El LI El H El El El board layouts, systems, instrumentation and procedural actions between units at a facility.
263000A2.02 DC Electrical Distribution 2.6 2.9 Loss of ventilation during charging El LI El El El El El [) El El El 400000A2.O1 Component Cooling Water 3.3 3.4 Loss of CCW pump El El El El LI El El Fl LI [I H Page 1 of 1 07/01/2013 2:00 PM
ES-401 5 Form ES-401-1 ES-401 BWR Examination Outi Form ES-401-1 Tier System #1 Name K K K K K K A A A A G KIA Topic(s) IR #
1 23456 1 2 34 201001 CRD Hydraulic R (j) 2O1002RMCS W!S)A2.04 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 2OIOO6RWM P.. )j.D4 202001 Recirculation 202002 Recirculation Flow CotroI 204000 RWCU 4
l.R)2.4 214000RPIS 215001 Traversing In-core Probe 215002RBM tS)A2.02.
216000 Nuclear Boiler Inst. R U..) A 3,01 219000 RHRILPCI. Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
226001 RHRILPCI: CTMT Spray Mode 230000 RHR1LPCI: Torus/Pool Spray (ii) 08 Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment R (P.) Af. 02 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure 5 (5) t 2.4. D Regulator 245000 Mait, Turbine Gen. I Aux.
256000 Reactor Condensate 259001 Reactor Feedwater k R ) v.4-. D2 268000 Radwaste 27l0000ffgas S (5)A2Q9 272000 Radiation Monitoring () O3 286000 Fire Protection 288000 Plant Ventilation 12. R(,. 03 290001 Secondary CTMT 290003 Control Room HVAC RI 1. 3,93 290002 Reactor Vessel Internals (R) )< OS K/A Category Point Totals Ro II J. L1 FFT II I -
I I Group Point Total
çgQ 2.
ES4O1, REV 9 T2 2 GWR EXAMINATION OUTLINE FORM ES401-1 KA NAME! SAFETY FUNCTION: IR 1(1 K2 K3 1(4 KS K6 Al A2 A3 A4 G TOPIC:
RO SRO 201001 1(6.06 CRC) l-iydrauiic 2.8 2.8 LI [] [] El U fl fl ) [] Component cooling water systems: Plant-Specific 2olooaA2.o4 RMCS 3.2 3.1 [3 [3 [3 [][] [3 ] [3 [3 [] Control rod block 201006K1.04 RWM 3.1 3.2 j [3 [3 [3 [3 [3 [3 [3 [3 [3 [3 Steam flow/reactor power. P-Spec(Not-8WR6) 214000624.34 RPIS 4.2 4.1 [] [3 [3 [3 [3 [] [3 [3 [3 [3 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 216000A3.01 Nuclear Boiler Inst. 3.4 3.4 [3 [3 [3 [3 [3 [3 [3 [3 -
[3 [3 Relationship belween meter/recorder readings and actual parameter values: Plant-Specific 230000A4.0B RHPJl..PCl: Torus/Pool Spray Mode 3.0 2.9 [3 [] [3 [3 [] [3 [3 [] [3 jj [] Pump/system discharge pressure 234000A1.02 Fuel Handling EquIpment 3.3 3.8 [] [3 [3 [3 [] [3 [] [] [3 [3 Refuel floor radiation levels? airborne levels 2590011(4.02 Reactor Feedwater 2.8 2.9 Ci LI C II LI El [1 El 0 El El Feedwater heating 2720001(2.03 Radiation Monitoring 2.5 2.8 El [l El El El LI El [3 El El El Stack gas radiation monitoring system 2880001(6.03 Plant Ventilation 2.7 2.7 [] [3 [] [3 El L] El El El El [] Plant air systems 2900O2K.O5 Reactor Vessel Internals 3.1 3.3 Brittle fracture Page 1 of 2 07/01/2013 2:00 PM
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 0 TOPIC:
RO SRO 290000K3.03 Control Room HVAC 2.9 31 Control room temperature
[] fl [] fl [] [] [3 [3 [3 [3 Page 2 of 2 07l!2013 2:00 PM
ES-Wi, REV 9 ( T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:
RO SRO 215002A2.02 RBM Loss or reduction in reclrculatlon system flow (flow EUUUU)[1[1U comparator): BWR-3,4,5 241000G2.4.30 Reactor/Turbine Pressure Regulator 2.7 4.1 Knowledge of events related to system operations/status U U UU [1 U U U U U I]
that must be reported to internal orginizations or outside agencies.
271O002.09 offgas 2.6 2.8 Valve closures U U U U LI U LI U [1 U Page 1 of 1 07/01/2013 2:00 PM
m B 3 Co ID 0 (DO G) m m
C,
ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR KI 1(2 K3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:
80 SR0 62.1.31 Conduct of operations 4.6 4.3 AbilIty to locate control room switches, controls and
[ El [3 [3 [1 [3 L] LI [] [3 indications and to determine that they are correctly reflecting the desired plant lineup.
62.1.39 Conduct of operations 3.6 4.3 Knowledge of conservative decision making practices Ci [] [] [] [3 [] [1 El [3 [3 62.2.15 Equipment Control 3.9 4.3 Ability to determIne the expected plant configuration
[] [3 [] [3 [1 [3 [3 [] [3 [] j using design and configuration control documentaion 62.2.22 Equipment Contro 4.0 4.7 Knowledge of limiting conditions for operations and
[3 LI [3 El U Li El LI [3 El l safety limits.
62.2.38 EquIpment Control 3.6 4.5 Knowledge of conditions and limitations in the facility LI LI LI [I [3 [3 [3 El LI LI license.
62.3.13 Radiation Control 3.4 3.8 Knowledge of radiological safety procedures pertaining to LI LI LI [3 [1 C] [3 LI [I El ))
licensed operator duties 62.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that El LI El El LI Li El El [3 El (]
may arise during normal, abnormal, or emergency conditions or activities 62.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements El LI El El LI LI LI Li LI El during normal or abnormal conditions 62.4.1 Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate
[J LI [I C] LI El El [3 LI Li J action steps.
G2.4.45 Emergency Procedures/Plans 4.1 4.3 Ability to prioritize and Interpret the significance of each LI LI LI El LI LI LI LI LI LI annunciator or alarm.
Page 1 of 1 07/01/2013 2:00PM
ES-401, REV 9 ()T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:
RO SRO G2.1.23 Conduct of operations OOEiOL1EJ Ability to perform specific system and integrated plant procedures during all modes of plant operation.
G2.2.22 Equipment Control 04.7 Knowledge of limiting conditions for operations and safety limits.
G2.2.38 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.
G2313 Radiation Control 3.4 3.8 L1EJLiDflEL1E1Eü Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.6 Radiation Control 2.0 3.8 ))j Ability to aprove release permits G2.4A0 Emergency Procedures/Pls LLJE1LJ Knowledge of the SROs responsibilities in emergency plan implementation.
G2A.42 Emergency Procedures!Plans 2.6 3.8 Li11J Knowledge of emergency response facilities.
Page 1 of 1 0710112013 2:00 PM
ES-401 Record of Rejected KIAs Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA Unabletowritean SRO-Only level question to this KA. Replaced with SRO 295002 T1IG2 SRO 295022 AA2.01 Overlap with RO Question #74.. Replaced with KA 500000 EA2.01 T1/G2 SRO 215005 A2.05 Overlap with SRO Question 91. Replace with KAA2.04 T2/G1 RO 295028 EK3.06 A discrinating question could not be written at the RO license level.
TI/Gi Question would have required extensive EOP Bases Knowledge. Replaced with KA EK3.01 ES-401, Page 27 of 33
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: ,. Date of Exam: Exam Level: RD SRD SZ Initial Item Description a b* #
1 Questions and answers are technically accurate and applicable to the facility. DL. j( 1L
- 2. a. NRC K/As are referenced for all questions. -
- b. Facility learning objectives are referenced as available.
- 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or
>< the licensee certifies that there is no duplication; or OZ_
other (explain)
- 6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RD / SRD-only question_distribution(s)_at_right. 1 i / a L] /
B
- 7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; (
the SRD exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RD / SRD question distribution(s) at right.
qq / ()
5! -L
/ , -
4.7 iL.
- 8. References/handouts provided do not give away answers or aid in the elimination of distractors. IDZ
- 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; J1 deviations are justified. OC
- 10. Question psychometric quality and format meet the guidelines in ES Appendix B.
- 11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note: The facility reviewers initials/signature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column c: chief examiner concurrence required.
ES-401, Page 29 of 33
ES-401 Written Examination Review Worksheet Form ES-401-9
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 10-25-13: Received 10 sample questions (5 RO + 5 SRO) from licensee.
1 1-14-13: Provided feedback to the licensee. Sample assessment indicated that the RO question comments were all enhancement comments. Three of the SRO questions were unacceptable and two SRO questions were enhancements.
RO Exam: Meets acceptability requirements, 18.6% unsat items:
- QKIA: 5, 19, 26, 46, 47, 64
- Cred Dist: 12, 31, 42, 43, 45, 55, 73, 75 SRO Exam: Preliminary assessment does NOT meet acceptability requirements, 30% unsat items:
- Q=K/A: 77
- SRO-only: 78, 83, 96, 100
- Cred Dist: 98, 99
- Multiple flaws above: 82
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only There are 7 RO (9%) + 6 SRO (24%) questions repeated from the (single) June 2010 NRC Exam. (These items are flagged with nd 2
underlines throughout the ES-401-9.) Per ES-401 Section D.2.f (
bullet), if the bank contains more than one question that fits a specific K/A statement, randomly select from among the available questions. How did the bank random selection process allow 13 questions off of the June 2010 exam? Just because a bank question isnt electronically linked to a specific K/A doesnt necessarily mean that it doesnt work for the K/A.
On the June 2013 (last) exam, there were five repeat questions from the June 2010 exam. NUREG 1021, Appendix A, Section C.3.e (page 10 of 11) explains that when the bank of items from which the exam is drawn is known to the examinees prior to the exam, the exam is said to be highly predictable. Because the last exam also contained several test items from the June 2010 exam, this makes our April 2014 exam somewhat predictable; especially the SRO exam portion.
After the enhancement comments for these 13 questions are addressed, this may not be an issue anymore.
Note: To be considered a significantly modified question, at least one pertinent condition in the stem and at least one distractor must be changed from the original bank question. Changing the conditions in the stem such that one of the three distractors in the original question becomes the correct answer would also be considered a significant modification.
RO questions #50, #53, and #59 have a borderline level of difficulty; we may have to raise the level of difficulty of one or two of the questions.
Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
Enter the level of difficulty (LCD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).
2.
- 3. Check the appropriate box if a psychometric flaw is identified:
- The stem lacks sufficient focus to elicit the correct answer (e.g. unclear intent, more information is needed, or too much needless information).
- The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
- The answer choices are a collection of unrelated true/false statements.
- The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
- One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
- 4. Check the appropriate box if a job content error is identified:
- The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
- The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
- The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
- The question requires reverse logic or application compared to the job requirements.
- 5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).
- 6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.
- 7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
- 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/MIN U/E/S Explanation Focus Dist. Link units ward K/A Only F 1.99 x x B E T1G1, 295001 AK1.03, Brunswick 2010, Q#37
- 1. Stem Focus: To ensure the l fill-in-the-blank statement tests plant specific knowledge, re-word it to refer to the critical power RATIO. The correct terminology for the 3D Monicore (or PowerPlex) thermal limit value (see below) is critical power RATIO (CPR).
Critical P0werGEXL CPR Bundle Power
- 7kir [L[k.
- IT 2 _ . . , .
7: _.7_
I. . 1. 71 l_-x [.47 .747 1- j 22-3. 1SR I.. . . . 7.61 .23 232] I . .7O 7.]- 31.31 13.6
- 7 1 .. 4 7 4 1 13 712-l l.7. 12.
- 2. Cred Dist: The plausiblity of the second part of choices B/D (thermal limits are NOT required to be adjusted) is weak. Suggest changing the second fill-in-the-blank statement to test the applicants knowledge of how the thermal limit values are changed (1 is selected as the number of operating recirc loops on Powerplex) or some aspect of the 10 % Aw value inserted at each APRM chassis. This is related to the RO job based on the following P&L:
C. This surveillance is intended to be performed by Reactor Engineenng (RXE) personnel However, on occasions where a RE from RXE is NOT immediately available, other Operations (e.g., UO) personnel may commence surveillance performance provided the Lead Performer is cognizant of this condition
- 4. Note: The proposed question is very similar to the June 2013 Browns Ferry NRC Exam, Q#1. Not an issue; just an observation.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 2 H 3 x B E T1G1, 295003 AA2.04, BFN 2007 NRC Exam, Q#24
- 1. Stem Focus: Clarify whether the LOOP affects all 3 units or just Unit 3. Also clarify the fill-in-the-blank statement to specify which EDG5 (Unit 1 / 2 or Unit 3).
- 3. Stem Focus: Consider using a timeline of events, including the time that the EDG output breakers closed, then key all the choices from that time.
Question is SAT 3 H 2 x x x B E/U T1G1, 295004 AA1 .03, BFN June 2010 NRC Exam, Q#3 Job Link: Not operationally valid because a loss of control power to Breaker 1616 wont cause it trip open (see ARP-9-23B, W27, 4160V SD BD 250V CONT PWR UV). A loss of control power to Breaker 1616 will cause it to always remain closed.
Instead, suggest testing the applicants knowledge of how a 480 or 4KV Shutdown Board will respond to a LOOP when annunciator 9-23B, W27 was already in alarm (or DC control power to a BOP bus was lost) before the LOOP occurred.
- 3. Stem Focus: Also add the breaker number 1616 to the stem bullet to be precise.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 4 H 2 x x M E T1G1, 295005 AA1.01, Modified from Perry 2010 NRC Exam, Q#14 1 Cue: The word enabled is not necessary to elicit the correct response. Instead, reword the 2 bullet to say:
RPT LOGIC A(B) TEST SWITCHES, located at Panels 1-PNLA-009-0015 (0017,) are in the NORMAL position.
- 2. Stem Focus: If necessary, add another bullet as:
Alarm windows 9-4A (9-48), W19, RPT SYS A(B) OUT OF SERVICE are extinguished.
- 3. Cue: re-word the stem question and choices as follows to streamline and eliminate potential cues to other questions as to what constitutes high or low:
WOOTF subsequent conditions will cause an automatic trip of the Reactor Recirculation Pumps?
A. turbine trip B. reactor water level (4-) 2 inches C. reactor pressure 1073 psig B. reactor feed pump trip coincident with reactor water level
(+) 27 inches 3-26-14 telecon: Licensee was concerned with using the word normal; we compromised to use Section of procedure title for 2 bullet; verify in Atlanta.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/E Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 5 F 2 x N U T1G1,295006AK1.03 Q=KA: The proposed question:
Suggest testing how a scram can be determined to be successful, e.g., some aspect of this EOP note:
NOTE The reactr will -ena subcI,cal LJt borc under aU conclions when.
- Ay tO control Cons are at poslion 02 wch ct er control c: f, ins.eled OR
- A co-o rois excepL one are -seled to or Lteycnd posbcOO OR
- Oeten,nen by Reacto Eng e.erng Alternatively, test some aspect of a startup when an excessively short period requires a shutdown or scram.
6 F 2 x B S T1G1 295016 G2.4.49 Stem Focus: AOl-i 00-2 doesnt use the phrase pressure control. Consider the following re-word of the fill-in-the-blank statement to ensure no post exam appeals:
When the immediate operator actions listed in 3-A 01-100-2, Control Room Abandonment, are performed, reactor pressure will initially be controlled by PRIOR to proceeding to Backup Control Panel 3-25-32.
3-26-14 telecon: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 7 F 2 x x x B E T1G1 295018 AA1.02, BFN 2008 NRC Exam, Q#7
- 1. Partial: The lesson plan and AOl conflict with one another on the supply (discharge?) header pressure set point. Because the lesson plan and AOl conflict, this question has the possibility of being contested during the post-exam review process, and may not be fair to the applicants.
OPL171 .047 states:
(b) All three units FCV-70-48 close on low RBCCW supply header pressure of 51 psig, (corresponds to an actual header pressure of 50 psig)
AOl-70 states:
RBCCW SECTIONALIZING VLV. 1 -FCV-70-48, closes automatically on RBCCW Pump discharge header pressure at or below 57 psig.
Please provide set point documentation with transmitter number.
Just because the discharge pressure is provided, this question may still not be fair to the applicants.
- 2. Stem Focus: The word reactor in the first sentence is not necessary.
- 3. Cue: The only component that is located in the drywell is the correct answer. Suggest changing Choice D to:
B. Reactor Recirculation Pump discharge sample cooler.
3-26-14 telecon: Supply and Discharge are the same pipe. Added the local pump indicator values. Verify in ATL.
Question is SAT 8 F 2 x N S T1G1 295019 G2.4.1
- 1. Stem Focus: The less than symbol (<) makes the stem question confusing. Suggest changing the choices to:
- a. 84psig
- b. 72psig
- c. 54psig
- d. 44psig 3-26-14 telecon: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 9 F 2 x x N E T1G1 295021 M2.02
- 1. Cred Dist: Choice D (14k20k gpm) is not plausible fora single RHR pump. Suggest changing Choices A thru D to 1500 gpm, 3500 gpm, 6250 gpm, and 8000 gpm, respectively.
- 2. Cue: RO Q#13 provides a cue to the flow rate knowledge for this question.
- 3. Stem Focus: Add a bullet to the Subsequently section that states No Group 2 PCIS signal exists in order to comply with AOl-74-1, Step [14].
- 4. Level of Knowledge (LOK) was listed as Comprehension or Analysis; however, it may be better suited as Memory or Fundamental Knowledge.
3-26-14 telecon: Re-worked to remove fill-in-the-blank statement. Verify in ATL.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
LOK LOD Q# r (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link unitsj ward K/A Only 10 H 2 x N E T1G1 295023 AK3.03
- 1. Partial: Choice B is also correct because the release is actually contained within the secondary containment (and then released via the SGT).
5t
- 2. The 1 part of the question is same as the May 2012 NRC Exam, Q#10. Not an issue; just an observation.
Suggest modifying the fill-in-the-blank statements and the choices as follows.
This condition will cause an automatic isolation of the One reason for the other automatic actuation that occurs as a result of this high radiation condition on the refuel floor is to ensure that________
A. (1) RF Zone ONLY (1) any air discharged to the environment is at an elevated release point B. (1) RF Zone ONLY (2) the main steam vault temperature does not reach the group I isolation set point 3-26-14: Removed environment and added SGT to the 2 fill-in the-blank statement (to be clear). Verify in ATL.
d 2
Changed part to the SC rad levels remain below EOl-3 entry conditions.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/h) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 11 F 2 x x N E T1G1 295024 G2.4.3
- 1. Partial: There is no correct answer because of the wording of the 2 fill-in-the-blank statement, that is, it refers to Drywell Pressure whereas 3-EOl-2 refers to primary containment / suppression chamber pressure (not drywell pressure).
- 2. Cue: The underline is not necessary to elicit the correct response.
Suggest rework of the 2 fill-in-the-blank statement:
This recorder is used to trigger the annunciator.
A. DRYWELL PRESS APPROACHING SCRAM (9-3B, W30)
B. DRYWELL PRESSURE HIGH (9-3B, W23)
Question_is_SAT.
12 H 2 x M U T1G1 295025 EA2.05, Fitzpatrick 2010 NRC Exam, Q#81
- 1. Cred Dist: Because the 2nd fill-in-the-blank statement tells the st 1
applicant that SRV operation(s) occur(s) over the next hour, the part of Choices C/D (SRV5 only open once) is not plausible.
- 3. Cue: The first bullet is not necessary to elicit the correct response.
There are options. Rework the 1St part of the question to test whether or not RCIC steam demand is / is NOT sufficient to preclude SRV operation. (and some other piece of knowledge).
Alternatively, write a question dealing with a situation where the crew is removing the turbine from service due to a condenser vacuum leak (in accordance with 01-47, Section 7.1 and/or AOl-47-1). When the operator trips the turbine, the Reactor High Press annunciator (9-5A, Wi) alarms with all bypass valves fully open. (because turbine load was too high when she tripped the turbine).
Another possibility is to write a question to test the minimum number of SRV5 required for decay heat removal.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only
= = = = = = = = = =
13 N E T1G1: 295026 EA1.01; Samplequestion recd 10-25-13 he word MA 13 H 2 N S Comments on Licensees changes to sample Q#13
- 1. 2-3-14: Previous sample question comments have been incorporated.
- 2. Cue: This question may provide a cue to the flow rate knowledge for RO Q#9.
3-26-14 telecon: Question is SAT.
14 F 5 x x B E T1G1 295028 EK3.06, 2008 Nine Mile NRC Exam, Q#47 Partial: There is no correct answer because (according to EOIPM Section 0-lll-D, EOl-2 PCCP Cross Reference, page 37 of 114) at BFN the drywell design temperature <**A.34**> is LOWER than the max temperature at which ADS is qualified
<**A.35**>.
- 3. Cred Dist: Choice B (Recirc Pump damage) is not plausible because the recirc pumps are not needed for post accident events.
See if you can find a lesson plan learning RO learning objective that deals with the ADS solenoid operability. If not, then we should probably replace this K/A.
New Question is SAT
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIE/S Explanation Focus Dist. Link units ward K/A Only 15 F 5 x N E 295030 EK2.01
- 1. Minutia: Draft submittal indicated learning objective in OPL171.065, Obj#19. This lesson plan was not provided in the references disc. Is this an RO learning objective? Im concerned that testing the time when the DECISION should be made is a bit over the line for the RO. Please provide RO learning objective for BEN-ODM-4.20 strategies knowledge.
There are other ways to test the following knowledge:
540 6 j55 1
/
ottom of Vacro Bre_.
ottor of Rog Heode, E
RCIC and HPCI both discharge at the same / different elevations, or, what elevation does HPCI discharge to and when does EOl-2 require locking it out?
- 2. Note: The EOI-2 set point for securing HPCI was tested in June 2013 BEN NRC Exam Q#15. Not an issue; just an observation.
3-26-14 telecon: Question is SAT.
16 B E T1G1: 295031 EK3,02; Sample question recd 10-25-13 Cooper 2008 NRC Q#17
- 1. Partial: The term adequate core cooling (unless tied to a specific EOP Basis document) can be loosely interpreted to make Choice A also correct.
Suggest testing:
The reaso ction curves are required to be used for 2-Ll-3-52 and 2-Ll-3-62 is beca (real reason vs. plausible one)
The top of active fuel (is us bmerged at this time.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EIS Explanation Focus Dist. Link units ward K/A Only 16 H 2 x M E Comments on Licensees changes to sample Q#16 2-3-14: Previous sample question comments incorporated.
- 1. Cue: Instead, format the 2 and 3 bullets as:
- Fl #, name: 400 psig
- 2-Ll-3-52 & -62, name: (-) 190 1d 3
Including the words as indicated and is in the bullet is not necessary to elicit the correct response.
3-26-14 telecon: Question is SAT.
17 H 2 x B E T1G1295037EK1.04
- 1. Cred Dist: The plausibility of Choice C (HSD [B] has been injected which allows a cool down) is borderline because the l and 2 portions conflict with the word hot shutdown boron weight.
Suggest using the following for this question or for Q#33 (ensure no overlap)
ATWS on Unit 2.
Reactor Water Level (RWL): (-) 55 SLC Injecting, Tank level lowering WOOTF completes the statements?
When the SLC tank level FIRST reaches , then the Hot Shutdown Boron Weight has been injected.
It will take to achieve this tank level.
A. 67%; more than one hour B. 43%; more than one hour C. 67%; less than one hour
- 0. 43%; less than one hour 3-26-14 Telecon: Question is SAT 18 H 2 N S T1G1 295038 EK2.06
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 19 H 2 x N U T1G1 600000 AK2.04
- 1. Q=K/A: The proposed question does not test Tier 1 knowledge of the relationship of 0-AOl-26-1 (or SSIs) to breakers/relays/disconnects. The Tier 1, Group 1 aspect
[PLANT FIRE ON SITE PROCEDURE] is not being tested.
Instead, the proposed questions solely tests the Tier 2 (systems) knowledge associated with 286000 (Fire Protection),
K4.02k, Automatic Initiation.
4-18-14: Licensees proposed fix had issues with plausibility and had two correct answers.
20 H 2 x x x M E T1G1 700000 AK1.03, 2013 BFN NRC Exam, Q#20 5t 1
- 1. Cue: The wording of the fill-in-the-blank statement, in combination with the noun name of URAL, make the i part of Choices C/D not plausible.
- 2. Partial: Choice D can also be successfully argued as correct because the URAL limits incoming reactive load, which, in turn, does help prevent the possibility of exceeding heating limits on the rotor.
St
- 3. Stem Focus: The word helps in the 1 fill-in-the-blank is vague.
Suggest reworking the stem information to test the following:
The Under-excited Reactive Ampere Limit (URAL) circuit is/is NOT in automatic at this time.
IA W 0-A 01 IE, Grid Instability, the operator is required to
. (raise reactive load until MVARS reach +300 outgoing OR lower reactor power by 10 MW(e)/min)
Question is SAT 21 H 2 N S T1G2 295008AK2.02 Note: The Tier 1 aspect is being tested (indirectly) because 3-AOl-100-1 is required when the RFPTs trip at 26% power.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 22 H 2 x N E T1G2 295014 G2.4.9
- 1. Cue: RO Q#32 provides a cue to this question and/or is double jeopardy for shroud knowledge.
- 2. Stem Focus: To streamline, modify the l fill-in-the-blank statement as:
Prior to perfoiming the emergency depressurization, HPCI required to be secured. (is / is NOT)
- 3. Stem Focus: Modify the part of each choice as follows:
(2) Any available injection source (2) Only injection sources which inject outside the shroud 3-26-14 Telecon: Question is SAT.
23 H 2 N E T1G2 295015 AA2.O1
- 1. This question overlaps with SRO Q#77.
- 2. Suggest rewording the fill-in-the-blank statements (to raise discriminatory value) as:
Reactorpoweris_(1) than 10%.
In accordance with 2-EQ/-i, RPV Control, the recirc pumps are required to (2).
3-26-14 Telecon: SRO Q#77 different. Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 24 H 5 x x x M E T1G2 295020 AK3.03 Minutia and/or LOD=5: The proposed question tests the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> containment response (per FSAR) following a Group 1 isolation.
This appears to be minutia for the RO applicant. Please provide RO learning objective.
- 2. Cred Dist: Choice D (rising torus pressure opens rx bldg. to torus vacuum breakers) physics are not correct.
- 3. Partial: Choice B (SRV heat to torus raises drywell temperature) may also be correct; this seems to be testing simulator minutia.
The 295020 Inadvertent Containment Isolation Topic can be tested with an RPS MG set trip; this is not required, but typically a good way to hit the K/A. One alternative is to test how the main steam vault temperature responds following an RPS MG set trip, especially if there are unit differences.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 25 H 4 x x M E T1G2 295032 EK1.03, 2011 BFN NRC Exam, Q#85 The draft submittal incorrectly listed this question as a Tier 1 Group 1 (should be Tier 1 Group 2) test item.
- 2. Partial: There is no correct answer if the applicant assumes TS 839A/B/CD instruments reach their isolation set point (166°F).
The stem statement should say When RWCU reaches the lowest isolation set point..
- 3. Partial: There is technically no correct answer to the first part of nd 2
the question since the answer to the part is any on scale reading. In other words, even as temperature continued to rise to the isolation set point, the level instrument WAS NOT affected to a substantial degree because any on scale reading was still allowed. The l fill-in-the-blank statement is confusing because it uses the words will affect even though the 2 part of the question has no effect.
- 4. #/units: The noun name for the level instruments should be provided in the choices.
Suggest the following re-word:
WOOTF completes both statements?
Based on the location of this leak, a level indicator, which is also located on Panel 2-9-5, that could potentially be affected is If the leak continues, and the RWCU Heat Exchanger Room temperature rises to its lowest isolation temperature set point, then the MINIMUM allowed valid level indication for this level indicator will be 3-26-14 telecon: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 26 F 2 x M U T1G2 2950033 EA1.02
- 1. The Bank question (used for this modified question) was not included in the Draft Submittal.
- 2. Q=K/A: The proposed question solely tests the systems (Tier 2) aspects; no Tier 1 knowledge is being tested. [See Tier 2 K/As for 272000 Rad Monitoring System, K/A 1.09 & K4.02; also 288000 Plant HVAC, Ki .05.]
Suggest testing some aspect of AOI-64-2D (Gp 6 HVAC Isolation) or EOI-3, SC/R.
Question is SAT.
27 H 2 x N E T1G2 295035 EA1.01
- 1. The draft submittal incorrectly listed this question as a Tier 1 Group 1 (should be Tier 1 Group 2) test item.
- 2. Stem Focus: The 4 bullets can be streamlined into two bullets 1d 3
( th as follows and 4 bullets not necessary):
- Reactor Power is 100%
- REACTOR ZONE DIFFERENTIAL PRESSURE LOW (2 3d, window 32) is intermittently alarming due to high winds outside.
- 3. Stem Focus: After the WOOTF stem question, consider adding (Consider each statement separately.) to ensure the applicant doesnt think that entering EOI-3 is required after a Rx Zone isolation.
- 4. Stem Focus: There should be a comma after the title in the l fill-in-the-blanks statement.
- 5. Stem Focus: The word inch should be inches.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-I Q= SRO B/M/N U/E/S Explanation Focus Dist. Link j units ward K/A Only 28 F 2 x x N E T2G1 203000 A4.03
- 1. Cred Dist: One of the Choices (either B or C) is not plausible because an applicant can successfully eliminate both of these choices based on psychometrics.
nd 1d 3
- 2. Stem Focus: The 2 and bullets are not necessary to elicit the correct response.
- 3. Stem Focus: The fill-in-the-blank statement can be streamlined by eliminating the name of the alarm (since its already provided th in the 4 bullet.
Suggest testing different knowledge (to address comment #1 above) as:
The PSC Head Tank inventory is normally maintained with water from the (CST or Torus)
IAWARP 3-9-3A, W26, . (both pumps should be running or only one pump should be running).
Question is SAT
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 29 H 2 x x x x N E/U T2G1 205000 K5.02
- 1. Q=K/A: Its questionable whether the operational implication (draining the vessel to the torus?) of mm flow valve operation is being tested. Will vessel level lower while the valve is stroking?
- 2. Cue: The 3 bullet is not necessary to elicit the correct response because when SDCg is placed in service, the procedure requires placing the INHIBIT switch to the INHIBIT 1d position. If you keep the 3 bullet, then you should test the applicants knowledge of whether the valve will or will not initially open.
th
- 3. Job-Link: Because the 4 bullet is not allowed by procedure, add the word inadvertently to this bullet.
- 4. Stem Focus: Clarify the fill-in-the-blank statement as:
RHR SYSTEM II MIN FLOW BYPASS VALVE (3-FCV-74-30) will begin opening (1) and, once fully open, will (2).
- 5. Stem Focus: The stem should include the shutdown cooling flow rate value in order to make it plausible for the valve to remain open.
Question is SAT.
30 H 3 x x x B E T2G1 206000 K3.02, BFN June 2010 NRC Exam, Q#3
- 1. Partial: An applicant could argue that there is no correct answer since the stem states that EOI-2 was entered (which could mean a valid high drywell condition still persists).
1d
- 2. Stem Focus: The 3 bullet should be modified (to cause no confusion as to whether the operator complied with procedures) to state:
After HPCI had restored level, and while it was still operating, the operator transitioned to pressure control in accordance with 2-EOl-Appendix-IIC, Alternate RPV Pressure Control Systems HPCI Test Mode.
- 3. Cred Dist: Choice D should eliminate the over speed trip and just say HPCI is tripped.
Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 31 F 2 x N U T2G1 206000 K5.07 nd 2
- 1. Cred Dist: The part of Choices B & D (pressure locking of the injection valve) is not plausible because 1) the stem doesnt include any information pertaining to FW line pressure/temperatures and 2) the 2 fill-in-the-blank statement restricts the choices to discharge piping not full of WATER.
st Suggest keeping the 1 fill-in-the-blank statement and reworking the 2 part of the question to test the applicants knowledge of the location of the vent valve used in 1-SR-3.5.1.1 to verify piping is full of water. Alternatively, test some aspect of 1-01-73, P&L MM.
Question is SAT.
32 F 1 B E/U T2G1 209001 K1.14, BFN June 2010 NRC Exam, Q#4
- 1. RO Q#22 provides a cue to this question and/or is double jeopardy for shroud knowledge.
- 2. Cred Dist: The plausibility of Choices B,C, & D is borderline.
- 3. LOD=1 Suggest testing the applicants knowledge of some aspect of the sparger break detection.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/EIS Explanation Focus Dist. Link units ward K/A Only 33 N EIU T2G1 211000A4.04 Q=KIA: In the proposed question, the decision of whether to initiate SLC is solely based on torus temperature even though the K/A requires testing some aspect of SLC that deals with reactor power (such as expected power response as the SLC tank contents are first injected and then as water level is restored). Therefore, the K/A is not being met.
d 2
- 2. Stem Focus: The bullet is not necessary to elicit the correct response.
- 3. Stem Focus: The torus temperature trend is not provided.
Suggest using the following question as a replacement or for Q#17 (ensure no overlap):
ATWS on Unit 2.
Reactor Water Level (RWL): (-) 55 SLC Injecting, Tank level lowering WOOTF completes the statements?
When the SLC tank level FIRST reaches , then the Hot Shutdown Boron Weight has been injected.
It will take to achieve this tank level.
A. 67%; more than one hour B. 43%; more than one hour C. 67%; less than one hour D. 43%; less than one hour Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIE Cred. Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward K/A Only 34 H 2 x N E T2G1 212000 A2.03
- 1. Stem Focus: The phrase in order to measure stroke time is not needed, and could cause someone to pick the wrong answer.
- 2. Suggest modifying the stem and fill-in-the-blank statements:
When directed by 1-SR-3. 3.1. 1. 8(5), the operator depresses 1-HS-27B, MSIV LINE B OUTBOARD TEST pushbutton.
The MSIV LINE B OUTBOARD RPS Closure Relay will de energize at_(1)_ percent CLOSED.
An RPS half-scram reset (2) be required after the pushbutton is released.
Question is SAT.
35 H 2 x x B E T2GI 215003 K3.03, BEN 2008 NRC Exam, Q#35
- 1. Cred Dist: Choice A (full scram) is not plausible because plant design always allows for one instrument failure, surveillance testing, etc.
- 2. Stem Focus: Choice B should be worded as half scram (instead of Half Reactor Scram) because this is consistent with the way the operators talk.
- 3. Stem Focus: The last part of Choice D (NOR a Scram occurs) should be worded as NOR a HALF scram occurs.
- 4. The draft submittal listed this questions level of knowledge as fundamental/memory; however, it may (?) be better as Comprehension or Analysis since the applicants must 1) know the set point and 2) calculate where the IRM will be reading on Range 6. Lets discuss.
Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 36 H 2 x x B E T2G1 215004 A3.02 Cred Dist: Choice B (Retract Not Permitted annunciator alarming and no rod block if operator attempts withdraw) is not plausible because the two fill-in-the-blank statements conflict with each other. In other words.. IF the retract-not-permitted alarm is ON, then youd expect SOMETHING to happen if the operator tried to retract the detector.
Question is SAT 37 E T2G1: 215005 K3.07; Sample question recd 10-25-13 Stem Focus: The wording of Choice C is not parallel with Choice B.
- 2. Stem Focus: The wording of Choice A doesnt flow well with the fill-in-the-blank statement.
- 3. Stem Focus: The 2 bullet doesnt need to have APRM spelled out.
Suggest the following changes:
Unit I is operating at 100% power.
After the operator selected control rod 26-27, she observed the following indications:
APRMI: 75%
.. APRMs2,3,&4: 100%
WOeetes the statement below?
Rod Block Monito A. Channel A will auto-tra to another APRM reference B. will cause RBM DOWNSCALE ( - 31) to alarm C. will cause RBM HIGH/INOP (9-5, W24) to D. Channel B will auto-transfer to another APRM refere
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 37 H 2 x x B E Comments on Licensees changes to sample Q#37 2-3-14: Previous sample question comments NOT incorporated.
- 1. Cue: The word non-conservative is a cue since APRM 1 is the only instrument reading (non-conservatively) 75%. Reword Choice D as:
enforce the 117% RBM Upscale rod block set point instead of the 112% set point.
- 2. Stem Focus: Choice A should be worded as automatically bypass to flow better with the fill-in-the-blank statement wording.
- 3. Stem Focus: Choice B should be worded as immediately cause RBM DOWNSCALE (9-5, W31) to alarm. This is more precise.
Question is SAT.
38 H 2 N S T2G1 217000A4.08 39 H 2 B S T2G1 217000 K2.02
- 1. Level of knowledge is Fundamental/Memory or Comprehension/Analysis?
Question is SAT.
40 F 2 N S T2G1 218000 K1.03
- 1. The plural versions of words in the fill-in-the-blank statement arent necessary, that is, the (s).
Question is SAT.
41 H 2 N S T2G1 223002 A3.01
,d 3
- 1. Stem Focus: The bullet is not necessary.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/h) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 42 H 2 x x B U T2G1 223002 G2.4.31, Peach Bottom 2007 NRC Exam, Q#43
- 1. Cred Dist: Choices C/D (Full Group 1 isolation occurs) are not plausible because plant design always allows for one instrument failure, surveillance testing, etc.
- 2. Cue: The last part of Choice A (.. since the Mode Switch is NOT in RUN.) is not necessary to elicit the correct response.
- 3. Stem Focus: The stem question is awkward. Suggest:
WOOTF describes the effect, if any, on the plant?
Need to add pictures of Group 1 lights instead of referring to as half group 1 4-18-14: Question is SAT.
43 H 2 x N U T2G1 239002 G2.4.46
- 1. Cred Dist: The part of Choices A/C (MWe remains the same after the SRV is closed) is not plausible because the steam that was diverted to the torus is now going to the turbine; more steam = more electricity.
4-18-14: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only x B E T2G1: 259002 K4.01; Sample question recd 10-25-13 2007 Vermont Yankee, Q#1 8
- 1. Partial: There may be no correct answer. The 28% limiter initiates only if total FW flow is < 19%. The stem doesnt indicate that total FW flow was ever less than 19%. The sentence in the stem that says ..the feed water flow summer fails to zero may not necessarily mean that total feed water flow was < 19% for at least 15 seconds. The stem says the operator got on the manual mode quickly; therefore, total feed water flow never got <19%.
You can test the same thing this way:
Unit 2 is operating at 100% power.
OOTF completes the following statement?
IF , THEN recirculation pump speed will automatically ck to A. a reactor scram oc 345 rpm B. total FW flow is < 19% for econds; 480 rpm C. one feed pumps flow lowers to < O and RPV level lowers to Level 4; 480 rpm D. total FW flow is < 19% for 15 seconds; 1130 p 44 H 2 M S Comments on Licensees changes to sample Q#44 2-3-14: Previous sample question comments incorporated.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 45 H 2 x x N U T2G1 261000A1.01
- 1. Cred Dist: Choices A/C (the only place the operating train differential pressure can be read at this time is on Unit 1) is not plausible because the reactor scram occurred on Unit 2.
Common sense can be (correctly) used to deduce that there should be some indication available on Unit 2 since the scram occurred on Unit 2.
- 2. Cue: The fill-in-the-blank statement provides a cue that two trains are running because the word Trains is plural. The fill-in-the-blank statement should be worded as:
The SGT Filter Bank differential pressure for the train(s) that is/are operating at this time can be read on Question is SAT.
46 F 2 x x x N U T2G1 262001 K4.03
- 1. Q=K/A: The K/A requires testing the applicants knowledge of the AUTOMATIC bus transfer and breaker interlock logic but the proposed question tests the applicants knowledge of the MANUAL transfer interlock logic.
- 2. Cred Dist: The l part of Choices A/B (manual transfer is slow) is not plausible because there is no such thing as a slow (delayed) MANUAL transfer; this would cause a voltage perturbation on the plant. The slow (delayed) transfer is only associated with AUTOMATIC transfers. For example, in 0 57A, Section 8.1, the transfer of SD Bd A is done the same way as the common board: manually executed FAST bus transfer.
- 3. #/units: The procedures and lesson plan utilize the word delayed instead of slow.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LODF (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN UIEIS Explanation Focus Dist. Link units ward K/A Only 47 F 2 x x x N U T2G1 262002 A2.04 Q=K/A: The K/A requires testing the RO applicants ability to implement procedure steps to remedy an abnormal battery situation on the UPS. The proposed question only tests the applicants knowledge of the normal and alternate DC sources to the inverter. No procedure actions are being tested. As written, the proposed question fits the K/A for Q#48.
- 2. Double Jeopardy with Q#48. If an applicant doesnt understand the Unit 1 Unit Preferred lnverter transfer scheme, he/she could potentially miss this question and Q#48 because both questions test the transfer to the regulating transformer.
- 3. Partial: Neitherthe lesson plan (OPL171.102, pg 23 of67) nor the procedure (0-OI-57C, pg 94 of 95) are clear as to what happens when only the DC input to the inverter is lost. The automatic action listed in ARP 9-8B, W35 occurs when the INVERTER fails. In this situation, the inverter has not failed; the rectifier is still working fine. I think that the inverter would transfer to the regulating transformer. The word loads in the 2 fill-in-the-blank is vague and confusing; are we talking about BB1, Panel 11 as the loads?
- 4. Stem Focus: The i fill-in-the-blank statement should be worded as:
The Unit Preferred Inverters normal DC source, which is Battery Board _(1)_, is no longer aligned to the inverter.
- 5. Stem Focus: The 2 part of Choices B/D should include the alternate AC sources noun name, which is the regulating transformer.
Suggest using this question for Q#48 and use another question to test the required actions for a different BFN uninterruptible power supply arrangement (several to choose from).
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward K/A Only 48 F 2 x x M E T2G1 262000 K6.03, BFN 2008 NRC Exam, Q#49
[Note: The proposed Q#47 fits the K/A for this questionj
- 1. Double Jeopardy with Q#47. If an applicant doesnt understand the Unit 1 Unit Preferred lnverter transfer scheme, he/she could potentially miss this question and Q#47 because both questions test the transfer to the regulating transformer.
- 2. Cred Dist: The plausibility of the 2 part of Choices B/D (static switch automatically goes back to the inverter) is borderline because of the way the first sentence in the stem is worded, that is, inverter output FAILS.
- 3. Stem Focus: Why is the word ONLY needed?
- 4. Stem Focus: Why are the words and rectifier needed in the first sentence?
Suggest re-wording as follows:
The Unit 1 Unit Preferred System Inverter, 1-IN V-252-OO1, output temporarily falls to zero.
WOOTF completes both statements?
Battery Board 1, Cabinet 11 will automatically be powered from the (1).
IF the Unit Preferred Inverter output returns, the static switch will (2) to the inverter.
Question is SAT.
49 6-_ x x B E T2G1: 263000 A1.01; Sample question recd 10-25-13 2009 Duane Arnold, Q#14 nd
- 2. Stem Focus: The -blank statement is confusing because of the number (2) in the b a . akes it very difficult for the applicants to pick out the correct choi
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= ISRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A jOnly 49 F 5 x x B E Comments on Licensees changes to sample Q#49 2-3-14: Previous sample question comments NOT incorporated.
- 1. Minutia and/or LOD=5: Provide learning objective that requires knowledge of the 24 VDC battery capabilities. The original question (from Duane Arnold) dealt with the safety related Division 1 battery. This question may be contested as minutia.
- 2. Stem Focus: Add the phrase In accordance with O-Ol-57D, DC Electrical System.. to the beginning of the 2 fill-in-the-blank statement.
- 3. Stem Focus: Spell out the numerals in the 2 part of each choice to minimize the potential for the applicants selecting the wrong choice by accident.
Licensee proposes to use 2013 NRC Exam Question #49.
Need to verify limits on previous two exams not exceeded.
4-18-14: Question significantly modified by changing the picture. Question is SAT.
50 F 1.99 x x N E T2G1 263000 K2.01
- 1. Q=K/A and/or minutia: What classifies this as a major load?
Please provide basis. The written basis is needed for any post exam appeals that this is testing minutia.
OpS Mgmt indicated this is insurer concern and prevalent in procedures.
Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 51 F 2 x x E T2G1 264000 K6.03, BFN 2011 NRC Exam, Q#51 M 1. Q=KIA: The effect of losing the soak back pump is none. The K/A requires us to test the applicants knowledge of the effect that a loss or malfunction of the lube oil pumps will have on the EDG. Can we write a question where the answer becomes like Choice B, that is, will NOT be able to auto-start? As proposed, the K/A match is questionable.
- 2. Stem Focus: The word provides in the 1stfillintheblank statement doesnt grammatically correct with any of the choices.
St 1
- 3. Stem Focus: The word area at the end of the fill-in-the-blank statement is not necessary.
- 4. Stem Focus: The 2 fill-in-the-blank statement should include the word auto right before the word start.
- 5. The Draft submittal Question History selected Previous NRC as none even though a copy of the question, as administered on the 2011 NRC Exam (Q#51), was provided in the Draft submittal package. Correct the question history sheet if it is incorrect.
Replaced 2 portion of question; Question is SAT.
52 F 2 x B E T2G1 300000 A3.02, BFN 2011 NRC Exam, Q#52
- 1. Stem Focus: None of the information before the WOOTF stem question is needed.
- 2. Stem Focus: To ensure no subset issues, re-word the fill-in-the-blank statement as:
In accordance with 0-01-32, Control Air System, the G Air Compressor will trip when (1)_ first reaches _(2)_.
Licensee had concerns with the proposed change was testing minutia between two parameters setpoints.
4-18-14: Proposed change had a direct lookup in the first part of the two part question.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back-I Q= SRO B/M/N U/E/S Explanation Focus Dist. Link unitsj ward K/A Only 53 F 1.99 x x B E T2G1 400000 K2.02, Oyster Creek 2008 NRC Exam, Q#52
- 1. Cue: The only choice that lists a component located in the reactor building, or that has the word reactor in the choice, is also the correct answer. The stem asks for load off of the 480 V REACTOR MOV Bd.
- 2. Partial: The word directly is subjective based on past exam appeals. Do not use this word, instead, re-phrase the stem question to specify more detail.
Question is SAT.
54 F 1 x M E/U T2G2 201001 K6.06, Quad Cities 2009 NRC Exam, Q#54
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Partial: The word directly is subjective based on past exam appeals. Do not use this word, instead, re-phrase the stem question to specify more detail. Choice A is also correct for this reason because RCW cools RBCCW.
Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN U/E/S Explanation Focus Dist. Link units ward K/A Only 55 H 2 x B U T2G2 201002 A2.04, BFN June 2010 NRC Exam, Q#54
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Cred Dist: The 2 part of Choices BID (in order to continue the surveillance must place APRM chassis in INOP position) is not plausible because this is the same thing as being at 0%, that is, a control rod block will still be present.
- 3. Cred Dist: The l part of Choices C/D (insert block also generated) is not plausible because there are no other RMCS signals that cause an insert block; only Rod Worth Minimizer.
Suggest testing the required procedural actions when RBM imposes a rod block, in accordance with the annunciator procedure(s).
Question is SAT.
56 F 2 x x B E T2G2 201006 K1.04, Columbia 2009 NRC Exam, Q#63
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Cue: The only answer with no capitalized words is also the correct answer.
- 3. Stem Focus: Suggest streamlining fill-in-the-blank statement (to be more precise) and choices as:
The Rod Worth Minimizer (RWM) utilizes a signal to determine the Low Power ALARM Point (LPAP).
A. totalsteam flow B. turbine first stage pressure C. APRM D. Powerplex heat balance Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 57 F 1 N E/U T2G2 214000 G2.4.34 The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
Suggest testing some aspect of the following AOI-85-4 activity, which is performed outside the main control room:
4.2 Subsequent Actions (continued)
[7] IF half or all control rod position indications on Full Core Display are off. THEN PERFORM the followin NOTES
- 1) A tailed power supply oiay be indicated by the power supply alarming.
- 2) 3-inch to 6-inch standard screwdriver and voltage tester are required to complete this step
[7.1] CHECK the foilowing fuses located in Auniliarv Instrument Rooni. Panel 3-9-27. Say X.Rear Lower Right Sidel and REPLACE if CLEARED C J.BOX NUMBER FUSE ID TB2 ONE (1) 3-FUt-OBS-000SXA TB2 ONE (1) 3-FUI-OB5-0005YA
[7.2] IF breaker 612 on Panel 3-9-9 OR any of the four Lambda power supplies internal breakers located in Panel 3-11-27 urn tnpped THEN DIRECT Ms to petfomi Power Restoration sequence of RPIS power supplies per SlI-3-PX-85-OOt. C Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LODf (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 58 H 5 x x x B E T2G2 216000 A3.01 The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Minutia and/or LOD5: Its not fair to put the applicants in a situation where two (of four) level transmitters are failing. Level transmitters 3-53 and 3-206 both failing low may not be operationally valid since these transmitters come off of two entirely different condensing chambers. What were the validation comments?
- 3. Partial: Choice A may also be correct if current plant trends continue.
- 4. Stem Focus: With two level transmitters slowly failing low, actual RPV level will rise. [Avg of 4 = 29, none of transmitters st 1 nd outside 8 inches yet.] This contradicts the and 2 bullets in the stem, as well as bullets 4 and 6 (stable level). IF the simulator doesnt move level, then we need to understand why.
5t 1
Suggest eliminating the two bullets and testing the applicants knowledge of whether, at this exact point in time, the DFWCS remains in 3-element control. Lets discuss this question.
When two level transmitters failing at the same time, second validation algorithm looks at the median difference of 4 inches.
Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD ---
(F/h) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SROIB/M/N U/EIS Explanation Focus Dist. Link units ward K/A Onlyj 59 F 1.99 x x N E T2G2 230000A4.08
- 1. Partial: There is no correct answer because 2-EOl-Appendix 17C does not specify unid# 2-Pl-74-51 anywhere in the procedure.
- 2. Partial: Choice A is correct because the term chugging can be interpreted to also mean fluctuating discharge pressure.
Suggest using intermittent condensation in the downcomers instead of chugging.
- 3. LCD = 1.99; borderline level of difficulty, based on GFES knowledge in the second part of the question.
Suggest testing the applicants ability to monitor torus pressure during suppression pool sprays since this is also system pressure as referred to in the K/A statement.
Suggest using NPSH graph and when to secure sprays.
60 F 3 N S T2G2 234000A1.02
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. The draft submittal listed this question as comprehension/analysis although both fill-in-the-blank statements are testing memory/fundamental knowledge.
61 H 3 x N S T2G2 259001 K4.02
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
st 1
- 3. The draft submittal listed this question as memory/fundamental knowledge even though the applicants must assess analyze the stem conditions to obtain the correct answer.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- 0= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 62 F 2 M S T2G2 272000 K2.03, BFN 2013 NRC Exam, Q#62 B Note: This question is NOT modified; revise question history sheet.
63 F 2 x N E T2G2 288000 K6.03
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Partial: Choice A is also correct; at 73 psig, the service air x-tie valve would already be open (same as opens) and train A continues to run.
Question is SAT.
64 F 3 x N U T2G2 290003 K3.03
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
- 2. Q=K/A: The proposed question does not test the applicants knowledge of how a HVAC malfunction affects control room temperature.
- 3. Need the following FSAR diagrams to study this question:
The control bay HVAC to. diagrams are sho,n in Figures 10.12-2a, 10.12-2b, and 10.1 2-2c. Cooling of the atmosphere in the Main Control Room is provided by a Suggest keeping the first part of the question (scenario where 1 B CB Supply Fan trips) and write the second part to test normal vs. abnormal control room temperatures and/or the actions in Section 8.15 of 0-01-31, when temperatures are high.
Does SR-2 have any control room temperature logging criteria or limitations?
Changed to test the alternate method of cooling control rooms.
Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
LOK LOD Q#
(F/H) (1-5) Cred. Partial Job- Minutia #1 Q= SRO BIM/N UIEIS Explanation Stem Cues T/F I Back-Focus Dist. Link unitsi ward K/A Only 65 F 2 x x st N E T2G2 290002 K5.05 1 The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
nd 2
- 2. Cue: The fill-in-the-blank statement (starting a Recirc Pump) cues the applicant that the LCO applicability is more than just Mode 4 or Mode 5. (Choices A/B plausibility is borderline.)
- 3. Stem Focus: The first portion of the l fill-in-the-blank statement is not necessary.
- 4. The draft submittal indicated that the proposed questions level of knowledge was comprehension/analysis even though it is a memory/fundamental knowledge question.
Suggest the following:
One operational implication of Tech Spec 3.4.9, RCS Pressure and Temperature (PIT) Limits, is that during a Recirc Pump Startup, the difference between the bottom head coolant temperature and the RPV coolant temperature must be and this must be verified once within minutes prior to each startup of a recirc pump.
Question is SAT.
66 H 2 x N E T3 G2.1.31
- 1. Suggest changing the l part of the question to test whether or not SLC INJECTION FLOW TO REACTOR (9-SB, W14) is lit or extinguished.
- 2. Stem Focus: Separate each of the two fill-in-the-blank statements by a separate line.
- 3. Stem Focus: The pictures provided with the draft submittal are too blurry for me to read; the versions that the applicants receive should be clearer.
Need to eliminate switch pic and take new pics.
4-18-14: Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 67 F 2 x B E T3 G2.1.39, BFN 2008 NRC Exam, Q#66
- 1. Cred Dist: Choice D (do nothing) is not plausible because the stem question asks for a required action. Even if the words if any are added to the stem question, the Choice is still not plausible because the stem says this is an approach to criticality, therefore the next time the power will decay to greater than 100 seconds will be at the POAH (IRM Range 7), which is a long way away. Choice D says to do nothing until IRM Range 7, which is not plausible.
- 2. Stem Focus: Add in accordance with 3-GOl-iQO-IA to the stem question.
- 3. Stem Focus: In the stem sentence (after the two bullets), add the word stable before Reactor.
- 4. Stem Focus: The first three choices can be streamlined as:
A. Insert ALL control rods.
B. Re-insert control rod 30-31 to obtain a stable period greater than 60 seconds.
C. Insert control rods until the reactor is subcritical. All rods are NOT required to be inserted.
Question is SAT.
68 H 2 x M E T3 G2.2.15, BFN 2013 NRC Exam, Q#69
- 1. Cue: The drawing provided in the stem should not indicate the valve/hand switch/panel numbers, because this is not necessary to elicit the correct response.
- 2. The draft submittal listed this as a memory item; however, this test item requires recalling (from memory) the rules for prints and then analyzing the drawing. Lets discuss.
4-18-14: Question is SAT.
69 F 2 B S T3 G2.2.22, BFN June 2010 NRC Exam, Q#70
- 1. In order to become a modified bank question, suggest changing the 2 column to core flow values (instead of reactor pressure values).
Question is SAT
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD T (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q B/M/N U/E/S Explanation K/A I SRO Focus Dist. Link units ward j0r1y 70 F 5 B E T3 G2.2.38, BFN June 2010 NRC Exam, Q#24
- 1. LOD=5: The decision of whether to declare a control rod inoperable (or slow) is SRO knowledge.
- 2. This test item is very likely to overlap our scenario event with the tripped CRD pump.
Suggest the following:
WOOTF completes both statements in accordance with the BFN Operating License and 2-SR-2?
The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of_______ MW thermal.
In accordance with SR-2, Attachment 2, Suiveillance Procedure Data Package Modes 1, 2, &3, core thermal power is normally recorded evety_______
A. 3458; hour B. 3458; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> C. 3463; hour D. 3463; 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Question_is_SAT.
71 F 2 x B E T3 G2.3.7, BFN 2011 NRC Exam, Q#71
- 1. Stem Focus: Add the phrase for this situation after the word required in the 2 fill-in-the-blank statement.
Question is SAT.
72 F 2 x B E T3 G2.3.13, BFN 2013 NRC Exam, Q#72
- 1. Stem Focus: After the word pressure add the phrase during a startup to perform leak inspections.
Question is SAT
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 73 H 2 x U T3 G2.3.14, BFN June 2010 NRC Exam, Q#72 M 1. Cred Dist: Choices B/C (rad levels will stabilize at a point not consistent with the normal hydrogen injection rate) are not plausible because the normal expected full power rad levels dependent on the normal 100% reactor power hydrogen flow rate. In other words, the two parts, when joined together as a single distracter, dont make sense.
- 2. Stem Focus: add the just before the word Automatic in the first sentence.
- 3. Stem Focus: add the current just after 1-01-4 in the first fill-in-the-blank statement.
- 4. The proposed question is very close to the BFN 2013 NRC Exam, Q#73, but it is MODIFIED (not bank). Not an issue; just an observation.
Question is SAT.
74 H 2 x B S T3 G2.4.1, BFN 2012 NRC Exam, Q#23
- 1. Stem Focus: Streamline the choices as follows:
A. Immediately insert a manual scram B. Place lB CRD Pump in service.
C. If any withdrawn rod(s) have accumulator alarms, immediately insert the rod(s).
D. After 20 minutes, if charging water is not greater than 940 psig, and two or more accumulator alarms exist for withdrawn rods, then manually scram.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q B/M/N U/E/S Explanation I SRO Focus Dist. Link units ward K/A 10n1y 75 H 2 x x B U T3 G2.4.45, BFN 2008 NRC Exam, Q#44 st 1
- 1. Cred Dist: The part of Choices C/D (manually scram after losing one feed pump at 100% power) is not plausible because all three plant designs accommodate one feed pump tripping at 100% power.
th
- 2. Cue: The phrase due to Low Level in the 4 bullet is not necessary to elicit the correct response.
- 3. #/units: The 2 bullet engraving should be RPFT TRIPPED (instead of TRIP).
Suggest the following:
WOOTF completes both statements?
Based on these conditions, the RECIRC LOOP A(B) FLOW LIMITER ENFORCING annunciator (9-4B(A), W35) alarming. (is / is NOT) 7K1 (Keep the fill-in-the-blank statement the same as it is.)
Question is SAT 76 H 2 x x B E T1G1 G2.1.7, BFN June 2010 NRC Exam, Q#76 d
2
- 1. Stem Focus: Re-word the fill-in-the-blank statement (to ensure plausibility to the OPERABLE choices) as follows:
In accordance with Tech Spec Bases 3.8.7, Distribution Systems Operating, if this RMOV Board is transferred to its alternate source, it (remains operable; must be declared inoperable)
- 2. Stem Focus: Include RHR and Core Spray alarms in the stem, (like this see below) or list individually:
CORE SPRAY SYS 1(11) LOGIC PWR FAILURE (9-3C, W27 &
9-3F, W23)
- 3. Cue: Delete the word significant in the stem because this is not necessary to elicit the correct response.
- 4. Stem Focus: The information in the first sentence about normal supply breaker tripping open and the arcing damage is not necessary.
- 5. 3-24-14 telecon: All comments incorporated, question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 77 H 2 x x N U T1G1 G2.1.20 Q=KIA: The proposed question tests the 295037 ATWS topic; even though the sample plan requires testing the 295006 T1G1 SCRAM topic.
- 2. This question overlaps with RO Q#23.
- 3. Cue: The phrase assuming AR! caused NO rod motion is d
located in the 2 fill-in-the-blank statement, which is not necessary.
Suggest re-arranging stem as follows:
A reactor scram occurred on Unit I and the RO A TC completed ATWS actions in accordance with 1-AOl-IOO-I, Reactor Scram.
Current plant conditions are:
- Mode Switch: SHUTDOWN
- 12 rods are at position 24
- RPV level: (-) 9 inches, slowly ,ising
- Reactor Pressure: 955 psig, steady
- MSlVs: Open WOOTF completes both statements in accordance with the EOP5?
The Reactor Recirc Pumps (are allowed to remain running at minimum speed vs. are required to be tripped) is required for RPV level control.
(EOl-1, RC/L vs C-5, Level/Power Control) 2008 NRC Exam-Modified; Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIMIN UIEIS Explanation Focus Dist. Link units ward KIA Only 78 H 2 x N U T1G1 295019 2.02 nd SRO-only: The 2 portion of the question (the SRO portion) can be deduced using psychometrics and RO knowledge as follows:
nd
- Psychometric: Since the 2 part of each choice contains AOl-32-2, the question boils down to whether the EOl Appendix is (or is not) required.
- RD Knowledge: The EOI network prescribes actions using EOl APPENDICES.
The RD applicant can deduce that the answer to the 2 portion of the question contain both procedures. No real SRO knowledge of procedures is being tested.
th 5
- 2. Stem Focus: The 3 bullet is not necessary if the bullet is modified to say RPV water level was deliberately lowered to (-)
55 inches.
th
- 3. Cue: The 4 bullet contains a trend, which is not necessary to elicit the correct response.
nd 2
Suggest re-working the part of the question as:
EQ/-Appendix 8B, Reopening MSI Vs/Bypass Valve Operations, the steps for aligning diywell control air to the MS/Vs. (contains vs does NOT contain)
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 79 H 2 x B E T1G1 295025 EA2.03, Perry 2009 NRC Exam, Q#3 Partial: In order to avoid exam appeals, write all exam questions to use the words is required to instead of using subjective words like should, could, may, etc. For this question, the fill-in-the-blank format is not necessary. Instead, use WOOTF identifies the required actions in accordance with 1-EOI-2, PCCP?
- 2. Partial: The HCTL curve point is below the 900 psig line, which is SAFE. 1-EOl-1, Step RC/P-7, only applies in the UNSAFE region. An applicant can successfully argue that the fill-in-the-blank word should, in combination with the HCTL curve point, and the torus temperature trend, means that Choice A is correct.
Suggest changing the 3 bullet so that torus temperature is 190°F.
- 3. 3-24-14 telecon: Further refined choices to proposed fix to make choices parallel. (changed to C-2 from C-i) Verify in Atlanta.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/EIS Explanation Focus Dist. Link units ward K/A Only 80 H 2 x x x M E/U T1G1 295037 EA2.05, BFN 2006 NRC Exam, Q#80 Ensure no overlap with RO Q#5.
- 2. SRO-only: The question explanation sheet provided with this question indicated that the 10CFR55.43(b)(5) procedure selection topic was being tested in this question.
The SRO clarification guidance document (Figure 2) provided with this question indicated that knowledge of decision points in the EOPs that involve transitions to emergency contingency procedures was being tested.
This is a borderline SRO question. On one hand, the knowledge of the EOP contingency is being tested; however, the knowledge of transitioning to the procedure (the procedure selection piece) is not being tested.
In order to make this a clean procedure selection question, 9t 1
suggest keeping the fill-in-the-blank and change the 2 fill-in-the-blank as:
The procedure required to be implemented for reactor power control at this time is . (RCIQ vs C-5)
- 3. Job-Link: The 6th bullet may not be operationally valid (torus temp stable while RCIC running due to a Gp 1 Isolation).
Suggest eliminating the words and steady.
- 4. Cue: The bold in the 2 fill-in-the-blank statement is not necessary to elicit the correct response.
Question is SAT; procedure selection is based on level strategy within a contingency.
81 H 2 x M E T1G1 600000 AA2.15, Perry 2009 NRC Exam, Q#4 Stem Focus: Re-word the stem question (to be more precise and to eliminate the word would) as:
WOOTF identifies a subsequent inoperability that, in combination with the conditions listed above, requires an hourly fire watch?
3-24-14 Telecon: Question is SAT
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 82 H 2 x x x N U T1G1 700000 G2.4.9 Cred Dist: The l part of Choices CID (turn off the only injection source) is not plausible because core cooling is always more important than equipment protection. Turning off the RHR Pump is not plausible because the stem contains no information related to the electrical plant status that could be misconstrued as an urgent enough reason to neglect core cooling (to protect the containment).
- 2. Q=K/A: The Generator Voltage & Electric Grid Disturbance topic is not being tested for the reason listed above.
- 3. SRO-only: The 10CFR55.43(b)(5) [procedure selection] topic is not being tested because there is no procedure selection in any of the choices.
Suggest writing a question that solely tests the grid disturbance topic AND hits one of the 1 OCFR55.43(b) topics. For example, test something related to the grid mitigation strategy in TRO-TO SOP-i 0.128, BFN Grid Operating Guide that involved shutting down the units.
CAUTION rET 16T4\ ,our,er (I$J00L1E100 TIne BFN COP,CTTTAO,& I, O,nJaOTed NOTE The BEN C.eTratorIeTaIo nAil TAO,,, the T,a,,T,,00,, S,sIe.n OceloT,,, of the slabs Belie BEN UI-TV caBstilo, bas CrueT avodtAe ETegraoed or csecwaseedr TOO Su00r0 0,001,1 nub stoles, Plo,,) BAN) GOd TRO.TO.SOP.TO.121 OlpIflhTTefli OT,e,el,,,000N 000.0003 P500.0000 Pese$olTOO 5.3 Br000, Pe,ry ¶61-TO Cspuci,0T BaTE I,TTI,,,UqdI
- EUll 0,006,. no,,,, IN)) boll, C.I001IIOI Lone, love a tree, 005I00 ret boOr 0,000 700000,s ne (PEN 0Gm OUTOI.IbTIC Use 0000.,th B
- 000G000,,u.orr005?0.TrIE0000000,,tCJlUeIaruen00050labxO Is, doll T,edtI)OFNE,)3teefeqI,,)3Ub4e eTUihetmboBsw4hllSIOPENotdm AUTCMUT-D doe OpOATO. C athrnolorniroletosthontGnqndenl&theurs.,c003cT.abxtIas Cello,, nod V) 0(1) E,,nne,enI :, a,., tall, 00, tEe TOdoe) re,boEerI,I CLOSED0,
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/h) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 83 . x x B* U T1G2: 295002 AA2.01; Sample question recd 10-25-13 nd
- 1. Cred Dist: The 2 part of Choices A & D (Re-open MSIV5 when you dont have vacuum) is not plausible.
nd 2
- 2. SRO-only: The part of the question is the only part that is at the SRO level; however, because of comment #1 (above), the correct procedures can be deduced by the process of elimination.
- 3. Cred Dist: The 1 St part of Choices A & C (vacuum is going away because hotwell level is diminishing even though 80 klbm/hr makeup). Is the stem of the question intent for the applicants to assume that hotwell level lowered to ZERO before the condensate 5t 1
pumps were stopped? As written the part of Choices A&C isnt plausible because the stem doesnt include any hotwell level parameters.
--cte ES-401-5 Form provided with the question indicated that this etjn was previously used on another BFN NRC Exam; however, I 4&Qot locate the question on any of the exams.
Please provide a cpyQhe question to the Chief Examiner, from the previous NRC exam. .N0610, Q#83]
The K/A may be difficult to hit at the R.aeyel (deals with main condenser vacuum, etc.); contact Chief Exam asap for replacement K/A if a discriminating SRO question ca be developed without an extraordinary amount of effort.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 83 H 3 x x B U Comments on Licensees changes to sample Q#83 2-3-14: License replaced K/A (condenser vacuum related) with a new randomly selected K/A (related to CRD).
T1G2 295022 AA2.01, Perry 2004 NRC Exam, Q#84
- 1. SRO-only: The question explanation provided with the proposed question indicated that knowledge of Tech Spec Bases was required to obtain the correct answer even though RO knowledge can be used to obtain the correct answer as illustrated below:
- All TS 3.1.5 Immediate & 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action statements (B.2.1, B.2.2, Cl, C.2, and Dl) are RO knowledge (See SRO Clarification Guidance Document, Figure 2); the applicants can use the reference provided and RO knowledge to obtain the correct answer.
- ROs routinely perform 2-SR-2, Attachment 2 to verify HCU Scram Accumulator (operability) pressures are greater than 940 psig using amber accumulator status lights on the full core display or by observation of local HCU Accumulator Pressure Indicators.
The proposed reference to be provided to the applicants (why doesnt the stem say reference provided?) allows the applicants to get the correct answer solely using the two knowledge items listed above.
- 2. Ensure no overlap with RO Q#74.
K/A replaced twice. Question is SAT.
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only
84 _ x N U T1G2: 295010 G2.4.20; Sample question recd 10-25-13 SS
- 1. Cred Dist: Choices B & D are not plausible because the nd 2
-- combinations of the Caution #6 title and the portions of each S
choice are mutually exclusive. The title of Caution #6 is HPCI or RCIC Turbine with elevated suction temperatures and the 2
.-. part of Choices B & D doesnt include both systems. Therefore,
-__ an applicant can eliminate these choices because the title has
... both HPCI and RCIC affected with elevated suction temperatures.
--- 2. SRO-only: Borderline SRO question because an applicant can S
answer the 2 part of the question solely by knowing the RCIC gh Exhaust pressure turbine trip set point value.
Oesibe solution is to test the SRO applicants knowledge of a situatioiflig a sustained SBO where suppression chamber pressure ca beniaintained in the safe area of Curve 6. You could test their iIitw1e of whether release rates are/ are NOT allowed to be exce?teii1Lle venting and which space is required to be vented (drywell or . This is in essence hitting the K/A statement.
84 H 2 x x x B E Comments on Licensees changes to sample Q#84 2-3-14: Licensee replaced question.
T1G2 295010 G2.4.20, BFN June 2010 NRC Exam, Q#97
- 1. Cue: The phrase to vent primary containment in the 1stfillin the-blank statement is not necessary to elicit the correct response.
- 2. Cue: The 7 bullet (emergency depressurization in progress) is not necessary to elicit the correct response.
th 8
- 3. Stem Focus: The 1st, 2, and bullets are not required.
- 4. Job-Link: Why is torus pressure lowering when drywell pressure is rising? Suggest deleting the trends.
th 8
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 85 H 2 x x x B E/U T1G2 295033 EA2.03, BFN 2008 NRC Exam, Q#85 st
- 1. Cred Dist: The 1 part of Choices C/D (EOl-4 entry required) is not plausible because the stem doesnt include anything that could be misconstrued as an EOl-4 entry condition such as An Unusual Event has been declared based on Stack Noble Gas (WRGERMS) exceeding 2.88 X 10 7 pCi/sec for more than an hour.
- 2. Stem Focus: Split out the fill-in-the-blank statement into two separate pieces. In the second fill-in-the-blank statement, refer to in accordance with Table 4, Seconda,y Cntmt Area Radiation.
- 3. Cue: In the second sentence, the phrase primary system discharging is not necessary to elicit the correct response.
- 4. Stem Focus: The first sentence is not necessary.
- 5. 3-24-14 telecon: Split out fill-in-the-blank statements; verify in Atlanta.
Question is SAT.
86 T2G1: 203000 G2.2.38; Sample question recd 10-25-13 Cred Dist: The 2 part of Choices A & D (RHR Loop 1 cant be considered an operable ECCS subsystem) is not plausible because the 1stfillintheblank already says that RHR Loop 1 CAN be considered an operable ECCS subsystem.
It appears the correct answer should be B (not C) since the plant is I . not 3.5.1). The stem does not provide the current plant mode; the - lank statement implies
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/MIN U/E/S Explanation Focus Dist. Link units ward K/A Only 86 F 2 x B E Comments on Licensees changes to sample Q#86 2-3-14: Comments incorporated by changing question.
T2G1 203000 G2.2.38
- 2. Stem Focus: In the fill-in-the-blank statement, replace the word in with aligned for.
- 3. LOK: The explanation sheet for this question indicated this question was a comprehension/analysis level; however, it is memory/fundamental.
3-24-14 telecon: Question is SAT.
87 B E/U T2G1: 215005 A2.05; Sample question recd 10-25-13 Nine Mile 2010 Q#88
- 1. Cred Dist: Borderline plausibility for Choices AID (half scram due to one or more APRM failures) because there is no such thing as an APRM causing a half scram.
- 2. Direct Lookup: Choice D (LCO 3.3.1.1 Condition B) is a direct lookup because the reference states that this condition is not applicable to Function 2.b (Flow Biased Simulated Thermal Power High)
Stem Focus: The 2 part of each choice contains an essary sentence. Only list the LCO 3.3.1.1 Condition A or C.
- 4. Stem Focus: The stem indicate that FT-68-5A flow signal input to APRM #1 fails ups
- 5. Stem Focus: The 1 part of each choice shou iled down to Rod Block does (or does not) occur.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 87 H 2 B E Comments on Licensees changes to sample Q#87 2-3-14: Comments incorporated.
T2G1 215005 A2.05, Nine Mile 2010 NRC Exam, Q#88 nd
- 1. Cred Dist: Change the 2 bullet to affect APRM #4 instead of
- 3, to make action statement B more plausible.
- 2. Stem Focus: Add the phrase in accordance with Tech Spec LCO 3.3.1.1, RPS Instrumentation to the end of the stem question; the LCO # can be deleted from each of the four choices.
- 3. Ensure no overlap with SRO Q# 91 references and content.
Replaced the K/A. Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 88 H 3 x x M E T2G1 261000 G2.2.4, BFN June 2010 NRC Exam, Q#88 Cues: Do not include 3 items in each choice; only include 2 items in multiple choice questions with four choices. For this question, each of the choices contains 1) whether U3 refueling can continue, 2) Unit ls requirements, and 3) Unit 2s requirements. An applicant only has to know Unit 2s requirements in order to get the correct answer. In other words, the requirements for Unit 3 and Unit 1 are not being tested.
Instead, streamline the question to test 1) whether Unit 3 fuel moves may or may NOT continue and 2) the EARLIEST time/date that Units 1 & 2 must be placed in Mode 3.
- 2. Stem Focus: The stem does not provide a timeline which makes the correct Choice B (Enter 3.0.3 in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) somewhat confusing; given the way Choice C (Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) is worded. Its better to provide a time/date in the choices when the unit must be in Mode 3. In other words, for Choice B, provide the time/date when the unit must be in Mode 3 instead of saying Enter 3.0.3 in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
For example:
Given the following plant conditions on May 5, 2014 at 08:00:
Unit 1 is starting up, currently in Mode 2 Unit 2 is in Mode 1, 100% power Unit 3 is in Mode 5 with core unloading in progress Diesel Generator 3ED is inoperable At 09:00, SGT Train B is declared inoperable.
Which one of the following identifies whether further fuel movement is allowed and the EARLIEST time Unit I and 2 must be placed in Mode 3?
[REFERENCE PROVIDED]
A. Fuel moves may continue; May Sat 23:00 B. Fuel moves may continue; May 6 at 03:00 C. Fuel moves may NOT continue; May Sat 23:00 D. Fuel moves may NOT continue; May 6 at 03:00 3-24-14 telecon: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus Dist. Link units ward K/A Only 89 F 2 x x x x B E/U T2G1 263000 A2.02 Cred Dist: The 151 part of Choices C/D (loss of HVAC requires LCO entry) is not plausible because the temperature is only 79°F. Additionally, the words but available make these choices not plausible.
- 2. Cues: The l stem bullet tells the location of Unit Battery #3 (Battery Room 3), which tells the applicant that the location is on the 1 C elevation of the Control Bay.
- 3. Stem Focus: The word associated in the 1° fill-in-the-blank statement is not necessary.
- 4. Partial: Avoid using the word should.
- 5. Job-Link: Please provide BFN documentation (if any) that tells when the Operations is required to declare the battery inoperable solely based on ambient temperatures. I was only able to find the following P&L from 0-Ol-57D; does this require declaring the battery inoperable?
V. Environmental calculations assume battery ambient temperatures at BO to 1 10F for all battenes except Shutdown Board 3EB and DO batteries which are 40F- l1OF.
- 6. LOK: The draft submittal indicated that the proposed question was comprehension/analysis; however, it may be recall of two memory/fundamental items.
Suggest the following:
Unit 3 is at 100% power and the following conditions exist:
- Battery is on charge ventilation for Unit #3 float and this area has been lost.
- Ambient temperature at Unit Battery #3 is 105°F.
- All other battery cell parameters are normal.
WOOTF completes both statements?
Unit Battery #3 is The procedure which provides guidance for setting up temporary ventilation to the area where this battery is located is Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 90 H 2 x B E/U T2G1 400000 A2.01, BFN June 2010 NRC Exam, Q#90 SRO-only: The l part of the question, TRM LCO temperature limit is RO knowledge because it is above-the-line LCO information. The 2 part of the question can be answered without any procedure [selection] ability; the fuel pool gates are installed and RHR supplemental fuel pool cooling cannot be used.
This question not graded as unacceptable because the licensee may have (incorrectly) thought that the T2G1 4000000 topic could only test RBCCW topics.
The component cooling water topic should not be restricted to only testing RBCCW. Although the SERVICE WATER System is not included among the systems in the BWR Catalog, K/As related to that system may still be selected for testing. The BWR K/A Catalog does not include SERVICE WATER (See DL Feedback Item #401.51)
If a discriminating question at the SRO level cannot be written for the RBCCW topic, then suggest writing a SRO question to test EECW.
Question 90 is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 91 H 2 x x N E T2G2 215002 A2.02
- 1. The draft submittal incorrectly listed this question as a Tier 2 Group 1 (should be Tier 2 Group 2) test item.
nd 2
- 2. Cue: The phrase if any is used twice in the fill-in-the-blank statement.
- 3. Stem Focus: The l part of each choice can be streamlined to control rod block will (will not) occur.
- 4. Ensure no overlap with SRO Q#87 references and content.
Suggest the following:
WOOTF completes both statements?
CONTROL ROD WITHDRAWAL BLOCK (9-5A, W7) be alarming for this plant condition. (will vs will not)
In accordance with Tech Spec 3.3.2.1, Control Rod Block Instrumentation, Action Condition A . (is not required at this time vs is NOT required at this time)
- 5. 3-24-14 telecon: Added recirc flow value at 75% power per validator comment; verify in Atlanta.
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 92 H 2 x N E T2G2 241000 G2.4.30
- 1. The draft submittal incorrectly listed this question as a Tier 1 Group 1 (should be Tier 2 Group 2) test item
- 2. Stem Focus: The 3 bullets listed under the word Subsequently should all be past tense.
- 3. Stem Focus: Modify the 3 bullet to say The reactor was MANUALLY scrammed when pressure was 1060 psig and rising.
st
- 4. Stem Focus: Modify the 1 fill-in-the-blank statement to test the applicants knowledge of whether the TS 3.4.10 LCD was (vs.
was not exceeded).
- 5. Stem Focus: For the 2 fill-in-the-blank statement, add the phrase in accordance with NPG-SPP-035, Regulato,y Reporting.
3-26-14 telecon: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 93 H 2 x x x N E/U T2G2 271000A2.09 Q=K/A: The proposed question does not test the applicants ability to predict the impact of an offgas valve closure.
- 2. Cues: The proposed reference [EPIP-1, Section 4, Radioactivity nd 2
Release] makes the part of the question a direct lookup. Do not provide the EPIP-Section 4 to the applicants.
- 3. Stem Focus: The ls part of the question should be streamlined to test whether EOI-4 is (or is NOT) required to be entered for these plant conditions.
5t
- 4. Stem Focus: The word correct in the 1 fill-in-the-blank statement is not necessary; replace with required.
Suggest something to target valve closures as follows:
WOOTF completes both statements regarding the off gas system?
Charcoal bed alignment during power operation is NOT to be changed because any major change in off-gas flow will disturb bed equilibrium and result in a temporaty_______ rise in stack discharge activity. (8 to 12 days vs. 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
The LOWEST stack activity gaseous release rate that requires an Unusual Event classification is a release fraction of.
(2 vs 20)
Or Unit 2 is operating at 100% with hydrogen water chemistty in sen/ice.
Subsequently, 2-FCV 66-14 and 66-18 (Off-Gas Outlet Valve from SJAE A and B) automatically close.
WOOTF following identifies: 1) the reason why hydrogen concentration is expected to RISE and 2) the required actions if hydrogen concentration subsequently reaches 4.1%?
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIE/S Explanation Focus Dist. Link units ward K/A Only 94 H 2 x B E T3 G2.1.23, BFN 2011 NRC Exam, Q#92 5t
- 1. Stem Focus: In the 1 part of Choices A/B, use the word constitute instead of represent.
st
- 2. Stem Focus: In the 1 part of Choices C/D, use the phrase do NOT indicate instead of do NOT represent.
- 3. Stem Focus: Re-word the 2 fill-in-the-blank statement as:
Mode I be entered if the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period average for TOTAL operational leakage is 31 gpm.
3-26-14 telecon: Question is SAT.
95 H 2 N S T3 G2.2.22
- 1. The proposed question is very similar to BFN May 2012 NRC Exam, Q#87. Not an issue; just an observation.
3-26-14 telecon: Question is SAT.
96 H 2 x M U T3 G2.2.38, BFN 2011 NRC Exam, Q#84 st SRO-only: The 1 part of the question is RO knowledge. The 2 part of the question can be deduced using RO knowledge of conduct of operations procedure content and RO knowledge of reactivity management, per the following RO task:
!.I-QOOAjj- 18 Observe Peaclivily lIanaement Train RI) OPL 17985 NER Proqrarn Guidelines During Plant REACTIVITY Operation EVENTS This K/A is amenable to MANY different question possibilities; suggest using another bank question related to any systems LCO action statement.
4-18-14: Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LCD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 5 x B E T3: G2.3.6; Sample question recd 10-25-13 2008 River Bend Q#97
- 1. LOD=5: Without a reference, this makes the question vulnerable to post-exam appeals based on level of difficulty.
- 2. Cred Dist: Choice D is not plausible because the second part says that liquid radioactive material releases are not permitted.
This Choice is also not parallel with any of the other three choices.
Suggest the following to test the 0-Sl-4.8.A.1-1 content (instead of ODCM action statement):
After a radwaste tank was propeily recirculated and sampled, the SRO authorized the release in accordance with O-Sl-4. 8.A. 1-1, Liquid Effluent Permit.
During this tank batch release, the O-RM-90130, Radwaste Efffluent Radiation Monitor is determined to be inoperable.
WOOTF identifies the MINIMUM required actions in accordance with O-SI-4.8.A. 1-1?
II6rec,.,ttachment 2 of O-SI-4. 8.A. 1-1 is titled Valve Checklist.
A. nQjreIease must be terminated; Attachment 2 is required to be perforcithe release is re-commenced.
B. The releaset7s&.pe terminated; Attachment 2 is NOT required to be perfom7editeelease is re-commenced.
C. The in-progress release mQntinue; Attachment 2 is required to be performed.
B. The in-progress release may continue; tttjment 2 is NOT required to be performed.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIEIS Explanation Focus Dist. Link units ward K/A Only 97 F 2 x M E Comments on Licensees changes to sample Q#97 2-13-14: Licensee replaced question with the suggestion; however, choices worded differently.
T3 G2.3.6, River Bend 2008 NRC Exam, Q#97 Partial: The choices are all subsets of one another for several reasons:
The stem question does not include the phrase MINIMUM required actions.
The Choices dont include the words ONLY.
The Choices arent symmetric.
Suggest the following:
WOOTF completes both statements in accordance with 0-SI-4.8.A. 1-1, Liquid Effluent Permit?
If the 0-RM 130 monitor is declared inoperable during a release, then the release (must be terminated and a new release permit initiated vs.
may continue if an independent verification of the valve lineup and release calculation is immediately performed.)
Ifajumper is used to bypass 0-RM-90-130 monitor, (it must be removed after the release is terminated vs it may remain in place until the rad monitor is declared operable.)
Question is SAT.
- 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues TIF Cred. Partial Job- Minutia #1 Back- Q= SRO B/M/N UIE/S Explanation Focus Dist. Link units ward K/A Only 98 F 2 x x B U T3 G2.3.13, BFN June 2010 NRC Exam, Q#85 d
2 Cred Dist: The part of Choices AID (Chattanooga Central Emergency Command Center procedure) is not plausible rd 3
because the bullet states that NO TVA emergency response facilities are activated.
- 2. Partial: Choice A is also correct when if the CECC is subsequently staffed, as it is expected to be; the wording of the nd 2
fill-in-the-blank statement does not preclude Choice A from also being correct.
- 3. Direct Lookup: The way the question is constructed in combination with the proposed reference to the applicants makes this a direct lookup.
- 4. LOK: This seems to be a fundamental/memory level of knowledge question when the reference is provided (because of the way the question is constructed).
- 5. The proposed question is very similar to Q# 78 on June 2013 NRC Exam), same event classification (Alert due to Fuel Pool ARM at 1000 mr/hr); may not be discriminating anymore; lets see if we can make this a different classification.
Suggest writing a question to test some aspect of Fuel Handling Supervisor, such as SPP-8.1, Nuclear Fuel Management or, alternatively, the Tech Spec 3.9.1 Bases requirements for continuing with core alterations when all refuel interlocks are inoperable.
Question is SAT
- 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.
Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #1 Back- Q= ISRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A 101y 99 F 2 x B U T3 G2.4.40, BFN June 2010 NRC Exam, Q#99
- 1. Cred Dist: Choice B (shift manager cant delegate shutdown of the plant to another SRO) is not plausible because a Unit Supervisor normally directs the plant shutdown.
- 2. Cred Dist: Choice C (the shift manager must do the whole plant site accountability himself) is not plausible because security has computers that tell who is onsite.
Suggest the following new question:
A LOCA event has just been upgraded to a General Emergency Classification.
All Emergency response organizations were already staffed when the General Emergency declaration was made.
WOOTF completes both statements in accordance with EPIP-5, General Emergency?
Notification of the NRC is required to be completed as soon as possible not to exceed minutes from declaration. (15 vs 60)
The determination of protective action recommendations will come from the (CECC vs TSC)
Question is SAT.
100 F 2 x M U T3 02.4.42, BFN 2011 NRC Exam, Q#75
The 2 part of the question (where the AUOs gather and report out of during an emergency) is AUO/RO knowledge of overall emergency plan strategy.
- 2. 3-26-14 Telecon: Re-worded 2 fill-in-the-blank statement to refer to BFN-ODM-4.2 chart. Verify in Atlanta. This question should have been marked as enhancement.
Question is SAT.
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Date of Exam: 5- / ) zo r-f Exam Level: ROf7I SROEI Initials Item Description a b c
- 1. Clean answer sheets copied before grading 13
- 2. Answer key changes and question deletions justified and documented 7
- 3. Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) d t
,4J/
/A
- 4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail
- 5. All other failing examinations checked to ensure that grades are justified 64
- 6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed NameJignature Date
- a. Grader c/is )u
- b. Facility Reviewer(*) -/A
- c. NRC Chief Examiner (*) 5I /
- d. NRC Supervisor (*)
(*) The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6