ML111540522

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Initial Exam 2010-301 Final Administrative Documents
ML111540522
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/02/2011
From:
Duke Energy Corp
To:
NRC/RGN-II
References
Download: ML111540522 (50)
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Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Catawba Date of Examination: 12/13/2010 li Examinations Developed by:

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

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

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

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

-120 4. Corporate_notification_letter_sent_(C.2.d)

[-90] [5. Reference material due (C.l.e; C.3.c; Attachment 2)]

..4

{-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-l/2, ES-401-3, and ES-401-4, as 9/24/2010 applicable (C.1.e and f; C.3.d)

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

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

-30 9. Preliminary license applications (NRC Form 398s) due (C.1.1; C.2.g; ES-202) 4

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

-14 1 1. Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

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

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

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

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

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

  • Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

8037013204 7710 TRAINING CENTER 08:59:31 am. 05052011 111 ES-201 Examination Outline Quality Checklist Form ES-201 -2 F1,JAL vrrlr1-r, Facility: Catawba Nuclear Station Date of Examination: 1211312010 Item Task Description Initials a b*

1. a. Venfy that the outline(s) fit(s) the appropriate model, in accord w ance with ES-401.

R b. Assess whether the outline was systematically and random ly prepared in accordance with I Section 0.1 of ES-401 and whether all KIA categories are T appropriately sampled.

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

d. Assess whether the justifications for desetected 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, technic S al specifications, and major transients. ç j b. Assess whether there are enough scenario sets (and spares) to test the projected number and u mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant cart be tested using at A least one new or significantly modified scenario, that no scenar ios are duplicated from the $4.

r applicants audit test(s), and that scenarios will not be repeate d on subsequent days.

c. To the extent possible, assess whether the outline conlbr (s) rn(s) with the qualitative and quantitative criteria specified on orm 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 W control room and in-plant tasks distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within T 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 mit*nums 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 specifi ed on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subseq uent days.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

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

c. Ensure that K/A importance ratings (except for plant-specific R d. Check for duplication and overlap among exam section priorities) are at least 2.5. (9i1 s,

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

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

PrinØ NmeISature

a. Author Darrell Henslev / FiM,iW 4.QAA -
b. Facility Reviewer(*)

jL.V-.. lif.Jj 10 Chad Kidd I ,

c. NRC Chief Examiner (#)
d. NRC Supervisor

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g Note: # Independent NRC reviewer initial items in Column c;

  • Not applicable for NRC-prepared examination outlines chief examiner concurrence required.

e JAMES R MORRIS Vice President iøEnergy Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax February 14, 2011 Mr. Edwin Lea, Senior Operations Engineer U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257

SUBJECT:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Post Examination Documentation The Examination Security Agreement (form ES-201-3), for the Catawba Nuclear Station Initial License Examination completed December 21, 2010, in accordance with NUREG 1021, ES 501 C.1.a, is enclosed.

If you have any questions or need additional information, please contact Steven Tripi, Initial Training Supervisor, at (803) 701-3770 or Alan Orton, Operations Training Manager at (803) 701-3977.

James R. Morris Attachment FE www. duke-energy, corn

U. S. Nuclear Regulatory Commission, Region II February 14, 2011 Page 2 xc: without attachment Malcolm T. Widmann, Chief U.S. Nuclear Regulatory Commission, Region Il Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 G. A. Hutto, Ill, Senior NRC Resident Catawba CNO1NC

ES-201 Examination Security Agreement Form ES-2O1-

1. P re-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 2.o iD 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 examinatiom 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) ofThQ1O. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 2045 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 hoted 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 wiTI 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) o?t Pib From the date that I entered into this security agreement until the completion of examination admihistratio n, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically below and authorized by the NRC. noted PRINTED NAME JOB TITLE I RESPONSIBILITY SIGNATURE 1) DATE SIGNATURE (2) DATE NOTE 1.

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ES-201 Examination Security Agreement Form ES-2O1-

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) ofbe.C 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, 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) ofl t.1° From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of kL 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) ofl .aQlO. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201 Examination Security Agreement Form ES-2Oj.

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

2 Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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

1. Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of tC 2045 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 hoted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2 Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered dUring the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE I RESPONSIBILITY URE1 DATE SIGNATURE (2) DATE NOTE

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S-2O1 Examination Security Agreement Form ES-201-3 t Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 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 Tb the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-201 Examination Security Agreement Form ES-201-3 t Pre-Examination 1 acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 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 arid/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2 Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of From the date that I entered into this security agreement until the completion of examination administration, I did not intruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

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ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Examination Level: RO SRO LJ Operating Test Number: 1 Administrative Topic Type Code* Describe activity to be performed (See Note)

Conduct of Operations Perform a shutdown margin calculation with Xenon credit R,D in Mode 3.

Conduct of Operations R,N Determine active/inactive license for RO.

Equipment Control Perform a manual NC leakage detection calculation per R,D PT/I /A/4600/009.

Radiation Control Emergency Procedures/Plan Perform emergency plan requirements for a site fire S,D emergency.

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

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

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

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

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Examination Level: RO LI SRO Operating Test Number: 1*

Administrative Topic Type Code* Describe activity to be performed (See Note)

Perform a shutdown margin calculation with Xenon credit Conduct of Operations R,D in Mode 3.

Conduct of Operations R,N Determine active/inactive license for SRO.

Perform a manual NC leakage detection calculation per Equipment Control R,D PT/1/N4600/009.

Radiation Control Calculate Low Pressure Service Water discharge flow for R,D Liquid Radioactive Release.

Emergency Procedures/Plan Determine guidance for protective action R,D recommendations.

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

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

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

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

ES 301, Page 22 of 27

ES4O1 Control Roomllri-Plant Systems Outline Form ES3O1-2 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO El SRO-l SRO-U El Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

a. NV pump 1A controlled restart per AP/1/A15500/021 (Loss of N,S I Component Cooling Water) End. 6
b. Transfer ECCS to Cold Leg Recirc A,D,EN,S 2
c. Depressurize the NC system during natural circulation D,L,S 3
d. Establish NC system Feed and Bleed A,M,L,S 4P
e. Restore power to 1ETA from offsite power A,M,L,S 6
f. Ensure proper feedwater isolation on a reactor trip A,D,L,S 4S
g. N/A N/A N/A
h. Increase level in the PRT using OP/1/A/6150/004 End. 4.2 N,S 5 In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
i. Start MG set 1A D,L 1
j. Place lB Hydrogen recombiner in service D,R 5
k. 2B D/G start using AP/2/A/5500/007 A,D,E 6

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

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irectfrom bank 9/ <8 / <4 (E)mergency or abnormal in-plant 1 / 1 / I (EN)gineered safety feature - I - / 1 (L)ow-Power / Shutdown > 1 I > 1 / > 1 (N)ew or (M)odified from bank including I (A) 2 I 2 / 1 (P)revious 2 exams < 3 < 3 I < 2 (randomly selected)

(R)CA >1/ >1 1>1 (S)imulator ES-301, Page 23 of 27

ES-31 Control Roomlln-Plant Systems Outline Form ES-301 2 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO SRO-I LI SRO-U LI Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

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a. NV pump 1A controlled restart per AP111A155001021 (Loss of N,S 1 Component Cooling Water) End. 6
b. Transfer ECCS to Cold Leg Recirc A,D,EN,S 2
c. Depressurize the NC system during natural circulation D,L,S 3
d. Establish NC system Feed and Bleed A,M,L,S 4P
e. Restore power to 1 ETA from offsite power A,M,L,S 6
f. Ensure proper feedwater isolation on a reactor trip A,D,L,S 4S
g. Place KC in parallel operation per 0P111AJ64001005 N,S 8
h. Increase level in the PRT using OP/1/A/6150/004 End. 4.2 N,S 5 In-Plant Systems@ (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
i. StartMGsetlA D,L 1
j. Place 1 B Hydrogen recombiner in service D,R 5
k. 2B D/G start using API2/A15500/007 A,D,E 6

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

  • Type Codes Criteria for RO / SRO-I I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank < 9 I < 8 / < 4 (E)mergency or abnormal in-plant 1 I 1 I 1 (EN)gineered safety feature - / - / 1 (L)ow-Power / Shutdown > I / > I / > 1 (N)ew or (M)odified from bank including 1 (A) > 2 I 2 I 1 (P)revious 2 exams < 3 < 3 I < 2 (randomly selected)

(R)CA >1/ >1 /1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Exam Level: RO J SRO-I fl SRO-U Operating Test Number: I Control Room Systems (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System I JPM Title Type Code*

Funclion a.

b. Transfer ECCS to Cold Leg Recirc A,D,EN,S 2 c.
d. Establish NC system Feed and Bleed A,M,L,S 4P e.

f.

g.

h.

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

i. StartMGsetlA D,L 1
j. Place lB hydrogen recombiner in service D,R 5
k. 2B D/G start using AP121A155001007 A,D,E 6

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

  • Type Codes Criteria for RO I SRO-l / SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrombank <9/ <8 / <4 (E)mergency or abnormal in-plant I / 1 I 1 (EN)gineered safety feature - / - I 1 (L)ow-PowerlShutdown >1 / >1 I >1 (N)ew or (M)odified from bank including 1(A) 2 / 2 I 1 (P)revious 2 exams < 3 < 3 I < 2 (randomly selected)

(R)CA >1/ 1 />1 (S)imulator ES-301, Page 23 of 27

ES-301 Operating Test Quality Checklist Form ES-301-3 F421 Facility: Catawba Nuclear Station Date of Examination: Dec. 2010 Operating Test Number: 1 FINAL SUBMITTAL Initials

1. General Criteria a b*
a. The operating test conforms with the previously approved outline; changes are consistent with /72 sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution). LY
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.) 1GJ- R 4
d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. WJ
e. It appears that the operating test will differentiate between competent and less-than-competent (J4 1 ,2 - /

applicants at the designated license level.

2. Walk-Through Criteria -- --
a. Each JPM includes the following, as applicable:

initial conditions

  • initiating cues
  • references and tools, including associated procedures
  • reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee
  • operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task j identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.
3. Simulator Criteria -- --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with JI Form ES-301-4 and a copy is attached. IC?

Printed Name / Signature Date

a. Author Darrell D. Hensley / l&MLtQ 12/02/10
b. Facility Reviewer(*) Chad Kidd / -f J 12/02/10
c. NRC Chief Examiner(#) Lcf2 /Y2 //
d. NRC Supervisor L.--

( L I NOTE:

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

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Catawba Nuclear Station Date of Exam: 12/10 Scenario Numbers: 1 121 S Operating Test No.: I FINAL SUBMITTAL 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.

IL. /7 Pd-iW 1;-

2. The scenarios consist mostly of related events. 4j
3. Each event description consists of
  • the point in the scenario when it is to be initiated
  • the malfunction(s) that are entered to initiate the event

. the symptoms/cues that will be visible to the crew

. the expected operator actions (by shift position)

. the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario F without a credible preceding incident such as a seismic event. I1F
5. The events are valid with regard to physics and thermodynamics.

Jj - j

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain A

complete evaluation results commensurate with the scenario objectives. L.&

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. )A j/

Cues are given. WI

8. The simulator modeling is not altered.
9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
10. Every operator will be evaluated using at least one new or significantly modified scenario. //

All other scenarios have been altered in accordance with Section D.5 of ES-301. ILI 1-

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

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

1. Total malfunctions (58) 7 I 8/7 Z jj
2. MalfunctionsafterEOPentry(12) 2/2/2 ii
3. Abnormal events (24) 4 /314 1/
4. Major transients (12) 1 II II
5. EOP5 entered/requiring substantive actions (12) 1 I 2! 1
6. EOP contingencies requiring substantive actions (02) 0/0II E7
7. Critical tasks (23) 2 /2/2 .2_

ES301 - Transientand Event Checklist Form ES-301-5 FINAL SUBMITTAL Facility: Catawba Date of Exam: Dec. 2010 Operating Test No.: I A E Scenarios for U-I, I-I, R-I P V T

Scenario 1 Scenario 2 M E

I L N CREW CREW CREW CREW T N I T C POSITION POSITION POSITION POSITION A T i E i T u N R T 0 R T 0 R T 0 R T 0 M*)

0 C P 0 C P 0 C P 0 C D R IU E

RO RX ..

0110 SRO-I NOR i 2111 I/C 23458 25 7 4 4 2 SRO-U1 MAJ 6 6 2221 TS 234 --

022 RO RX i - 1110 NOR -. 1 111 SRO-II I/C 2578 458 7 4 4 2 SRO-U MAJ 6 6 2221 TS 23 2022 Rd RX -. 1 1 110 NOR 1 --

1 111 SRO-I I/C 34 3478 6 4 4 2 SRO-U MAJ 6 6 2221 TS -- .. 0022 RO RX 110 NOR 111 SRO-l I/C 442 SRO-U MAJ 2 2 1 TS 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-i event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-304 Transient and Event Checklist Form ES-301-5 rFacility: Catawba Date of Exam:

FINAL SUBMITTAL Dec. 2010 Operating Test No.: I A E Scenarios for U-2, 1-2, R-2, 1-4 Scenario 1 Scenario 2 T M P E L N o I I T CREW CREW CREW CREW A I C POSITION POSITION POSITION POSITION L M A T S A B S A B S A B S A B U N Y R T 0 R T 0 M(*

R T 0 R T 0 ROT RX 0110 SRO-I NOR 1 1 2 1 1 1 I/C 23458 25 7 4 4 2 SRO-U2 MAJ 6 6 TT TS 234 3 022 RO RX 1 --

1110 NOR .. i 1 111 SRO-12 I/C 2578 458 7 4 4 2 SRO-U MAJ 6 6 2 221 TS -- 23 2022 RX -- 1 1 110 NOR i --

1 111 SRO-I I/C 34 3478 6 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS -- -- 0 022 RO RX 1 -- 1110 NOR . 1 i iii R04 I/C 2578 25 6 442 SRO-U MAJ 6 6 2221 TS -. -- 0 022 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301 Transient and EventChecklist Form ES-301-5 FINAL SUBMITTAL Facility: Catawba Date of Exam: Dec. 2010 Operating Test No.: I A E Scenarios for U-3, 1-3, R-3, U4 Scenario I Scenario 2 T M E

0 I L N CREW CREW CREW CREW T N I T C POSITION POSITION POSITION POSITION A T S A B S A B S A B S A B U N Y R T 0 R T 0 R T 0 R T 0 Mi 0 C P 0 C P 0 C P 0 C RIU E

RO RX -- -- 0 110 SRO-I NOR i 1 2111 I/C 23458 25 7 4 4 2 SRO-U3 MAJ 6 6 2221 TS 234 -- 3 022 RO RX -- 1 1 1 0 NOR -- i I lii SRO-13 I/C 2578 458 7 4 4 2 SRO-U MAJ 6 6 2221 TS -- 23 2 022 R03 RX -- 1 1110 NOR i -- I lii SRO-I I/C 34 3478 6 4 4 2 SRO-U MAJ 6 6 2 2 2 1 TS -- -- 0022 RO RX -- -- 0 110 NOR 1 1 2111 SRO-I I/C 23458 458 8 4 4 2 SRO-U4 MAJ 6 6 2 2 2 1 TS 234 5 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-l event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-i basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

ES-301, Rev. 9 Competencies Checklist Form ES-301-6 FINAL SUBMITTAL Facility: Catawba Date of Examination: Dec. 2010 Operating Test No.: I APPLICANTS RO X RD RD SRO-I SRO-l X SRO-I SRO.-U SRO-U SRO-U X Competencies SCENARIO SCENARIO SCENARIO 12 1 2 12 Interpret/Diagnose Events 245 2345 4567 2345 137 2345 and Conditions 67 67 67 Comply VVith and 123 1235 ALL ALL 147 ALL Use Procedures (1)

Operate Control 135 1235 135 1235 Boards (2) 6 6 Communicate ALL ALL ALL ALL ALL ALL and Interact Demonstrate Supervisory ALL ALL ALL ALL Ability (3)

Corn ply With and 34 24 34 24 Use Tech. Specs. (3)

Notes:

(1)lncludes 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-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Catawba Dateof Exam: 2010 RO K/A Category Points SRO-Only Points Tier Group K K K KK KAAAAG A2 G Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant 2

T T N/A 2 1 N/A 2

9 2 2 4 Evolutions Tier Totals 5 4 4 5 4 5 27 5 5 10 1 32332323232 28 3 2 5 2.

2 1 1 1 11 1 011 1 1 10 2 1 3 Plant Systems Tier Totals 4 3 4 4 3 4 2 4 3 4 3 38 3 8

3. GenericKnowledgeandAbilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 2 1
1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

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

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

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

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

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KAs.
8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401 -3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 007EK2.02 Reactor Trip Stabilization

- - Recovery 2.6 2.8 Breakers, relays and disconnects OO8AK1 .01 Pressurizer Vapor Space Accident / 3 3.2 3.7 Thermodynamics and flow characteristics of open or leak- ing valves 009EK2.03 Small Break LOCA /3 3 3.3 S/Gs O11EG2.l.7 Large Break LOCA/3 4.4 4.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

015AA2.08 RCP Malfunctions / 4 3.4 3.5 When to secure RCPs on high bearing temperature 022AG2.4.34 Loss of Rx Coolant Makeup / 2 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 025AK3.03 Loss of RHR System / 4 3.9 4.1 Immediate actions contained in EOP for Loss of RHRS 029EA2.06 ATWS / 1 3.8 3.9 ri Main turbine trip switch position indication 038EA1.15 Steam Gen. Tube Rupture / 3 3.9 3.9 AFW source level and capacity (chart) 040AK2.0l Steam Line Rupture Excessive Heat

- 2.6 2.5 Valves Transfer / 4 054AK1 .02 Loss of Main Feedwater / 4 3.6 4.2 Effects of feedwater introduction on dry S/C Page 1 of 2 03/17/2010 6:40 AM

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 056AA2.83 Loss of Off-site Power / 6 2.7 3 Instrument air pressure gauge 062AG2.4.6 Loss of Nuclear Svc Water /4 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

065AK3.03 Loss of Instrument Air / 8 2.9 3.4 LI LI Knowing effects on plant operation of isolating certain equipment from instrument air 077AA1 .03 Generator Voltage and Electric Grid 3.8 3.7 Voltatge regulator controls Disturbances / 6 WE04EK1 .1 LOCA Outside Containment / 3 3.5 3.9 LI Components, capacity, and function of emergency systems.

WEO5EAI .1 Inadequate Heat Transfer Loss of

- 4.1 4.0 Components and functions of control and safety systems, Secondary Heat Sink / 4 including instrumentation, signals, interlocks, failure modes and automatic and manual features.

WE11EK3.4 LossofEmergencyCoolantRecirc./4 3.6 3.8 [] LI LI LI LI LI LI LI RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

Page 2 of 2 03/17/2010 6:40AM

ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401 -2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO O01AA1 .05 Continuous Rod Withdrawal / 1 4.3 4.2 Reactor trip switches 028AA2.12 Pressurizer Level Malfunction! 2 3.1 3.5 Cause for PZR level deviation alarm: controller mal function or other instrumentation malfunction 036AK3.01 Fuel Handling Accident / 8 3.1 3.7 Different inputs that will cause a reactor building evacuation 060AK3.03 Accidental Gaseous Radwaste Rel. / 9 3.8 4.2 Actions contained in EOP for accidental gaseous-waste release 067AK1 .01 Plant Fire On-site / 9 8 2.9 3.9 J Fire classifications by type 068AG2.4.45 Control Room Evac. / 8 4.1 4.3 Ability to priotize and interpret the significance of each annunciator or alarm.

076AK2.01 High Reactor Coolant Activity /9 2.6 3 fl Process radiation monitors WEO8EK1 .2 RCS Overcooling - PTS / 4 3.4 4.0 Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

WEO9EA2.l Natural Circ./4 3.1 3.8 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Page 1 of 1 03/17/2010 6:41 AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003K1.13 ReactorCoolant Pump 2.5 2.5 RCP Bearing Lift Oil Pump 0031(3.01 Reactor Coolant Pump 3.7 4.0 j j RCS 004K3.08 Chemical and Volume Control 3.6 3.8 RCP seal injection 005K1.l0 Residual Heat Removal 3.2 3.4 [] [] [] [] CSS 005K4.05 Residual Heat Removal 2.5 2.9 Li [] [] [] Relation between RHR flowpath and refueling cavity 006K2.02 Emergency Core Cooling 2.5 2.9 Li Valve operators for accumulators 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 Li Li Li Li Li Li Li Li Li Li Method of forming a steam bubble in the PZR 010K6.02 Pressurizer Pressure Control 3.2 3.5 Li Li Li Li Li Li Li Li Li Li PZR 012K5.0l Reactor Protection 3.3 3.8 Li Li Li Li Li Li Li Li Li Li DNB 012K6.04 Reactor Protection 3.3 3.6 Li Li Li Li Li Li Li Li Li Li Bpass-block circuits 013K2.0l Engineered Safety Features Actuation 3.6 3.8 Li Li Li Li Li Li Li Li Li Li ESFAS/safeguards equipment control Pagelof3 03/17/2010 6:41AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 013K5.02 Engineered Safety Features Actuation 2.9 []

3.3 [] [] [] Safety system logic and reliability 022A2.0l Containment Cooling 2.5 2.7 El El El El El El El El El El Fan motor over-current 025G2.2.22 Ice Condenser 4.0 4.7 El [] El El El El El El El El Knowledge of limiting conditions for operations and safety limits.

025G2.4.46 Ice Condenser 4.2 4.2 El El El El El El El El El El Ability to verify that the alarms are consistent with the plant conditions.

026A2.02 Containment Spray 4.2 4.4 El El El El El El El El El El Failure of automatic recirculation transfer 026A3.0l Containment Spray 4.3 4.5 El El El El El El El El El El Pump starts and correct MOV positioning 039A1.l0 Main and Reheat Steam 2.9 3.0 El El El El El El l] El El El El Air ejector PRM 039A2.03 Main and Reheat Steam 3.4 3.7 El El El El El El El El El El Indications and alarms for main steam and area radiation monitors (during SGTR) 059A1 .07 Main Feedwater 2.5 2.6 El El El El El El [] El El El El Feed Pump speed, including normal control speed for ICS 061 K4.02 Auxiliary/Emergency Feedwater 4.5 4.6 El El El El El El El El El El AFW automatic start upon loss of MFW pump, S/G level, blackout or safety injection 062A3.05 AC Electrical Distribution 3.5 3.6 El El El El El El El El El El Safety-related indicators and controls Page 2 of 3 03/17/20 10 6:41 AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1K2K3k4K5K6A1A2A3A4G TOPIC:

RO SRO 063K3.02 DC Electrical Distribution Components using DC control power 063K4.02 DC Electrical Distribution 2.9 3.2 Breaker interlocks, permissives, bypasses and cross-ties.

064K1 .02 Emergency Diesel Generator 3.1 3.6 D/G cootng water system 073G2.2.40 Process Radiation Monitoring 3.4 4.7 Ability to apply technical specifications for a system.

076A4.02 Service Water 2.6 2.6 SWS valves 103A4.04 Containment 3.5 3.5 Phase A and phase B resets Page 3 of 3 03117/2010 6:41 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 00102.2.44 Control Rod Drive 4.2 4.4 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 011K3.02 Pressurizer Level Control 3.5 3.7 RCS 015A1.05 Nuclear Instrumentation 3.7 3.9 Imbalance (axial shape) ______

017A2.02 In-core Temperature Monitor 3.6 4.1 Core damage 027K2.0l Containment Iodine Removal 3.1 3.4 Fans 029A3.01 Containment Purge 3.8 4.0 CPS isolation 035K5.01 Steam Generator 3.4 3.9 El El El El El El El El Effect of secondary parameters, pressure and temperature on reactivity 045A4.02 Main Turbine Generator 2.7 2.6 El El El El El El El El El [] El T/G controls, including breakers 068K1 .07 Liquid Radwaste 2.7 2.9 El El El El El El El El El El Sources of liquid wastes for LRS 079K4.01 Station Air 2.9 3.2 El El El [j El El El El fl El El Cross-connect with AS Page 1 of 1 03117/2010 6:41 AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.44 Conduct of operations 3.9 3.8 El El El El Knowledge of RO duties in the control room during fuel handling.

G2.l.5 Conduct of operations 2.9 3.9 El El El El El El El El El El Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.20 Equipment Control 2.6 3.8 El El El El El El El El El El Knowledge of the process for managing troubleshooting activities.

G2.2.6 Equipment Control 3.0 3.6 El El El El El El El El El El Knowledge of the process for making changes to procedures G2.3.15 Radiation Control 2.9 3.1 El El El El El El El El El El Knowledge of radiation monitoring systems G2.3.4 Radiation Control 3.2 El El El El El El El El El El Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 El El El El El El El El El El Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.3 Emergency Procedures/Plans 3.7 3.9 El El El El El El El El El El j] Ability to identify post-accident instrumentation.

G2.4.31 Emergency Procedures/Plans 4.2 4.1 El El El El El El El El El El Knowledge of annunciators alarms, indications or response procedures G2.4.47 Emergency Procedures/Plans 4.2 4.2 El El El El El El El El El El Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Page 1 of 1 03/17/2010 6:42 AM

ES-401, REV9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 011 EG2.2.37 Large Break LOCA /3 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 025AG2.l.7 Loss ofRHRSystem/4 Ability to evuate plant performance and make operational judgments bed on operating characteristics, reactor behavior and instrument interpretation.

026AA2.05 Loss of Component Cooling Water / 8 2.4 2.5 The normal vues for CCW-header flow rate and the flow rates to the components cooled by the CCWS 056AA2.46 Loss of Off-site Power / 6 4.2 4.4 That the ED/Gs have started automatically and that the bus tie breakers are closed 077AG2.1 .28 Generator Voltage and Electric Grid 4.1 4.1 Knowledge of the purpose and function of major system Disturbances / 6 components and controls.

WEO5EA2.2 Inadequate Heat Transfer - Loss of *. Adherence to appropriate procedures and operation within Secondary Heat Sink / 4 the limitations in the facilit/s license and amendments.

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ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 032AA2.09 Loss of Source Range NI /7 2.5 2.9 Effect of improper HV setting 060AA2.04 Accidental Gaseous Radwaste Rel. / 9 2.6 3.4 The effects on the power plant of isolating a given radioactive-gas leak 061AG2.4.46 ARM System Alarms / 7 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

wel 3EG2. 1.27 Steam Generator Over-pressure! 4 3.94 Knowledge of system purpose and or function.

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ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004A2.21 Chemical and Volume Control 2.7 2.7 Excessive letdown flow, pressure and temperatures on ion exchange resins (also causes) 013G2.2.38 Engineered Safety Features Actuation 3.6 4.5 Knowledge of conditions and limitations in the facility license.

022G2.4.l Containment Cooling 4.6 4.8 Knowledge of EOP entry conditions and immediate action Ej steps.

064G2.4.l Emergency Diesel Generator 4.6 4.8 Knowledge of EOP entry conditions and immediate action steps.

073A2.Ol Process Radiation Monitoring 2.5 2.9 Erratic or failed power supply Page 1 of 1 03/17/2010 6:46AM

ES-401, REV9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028G2.2.25 Hydrogen Recombiner and Purge 3.2 4.2 Knowledge of the bases in Technical Specifications for Control LI limiting conditions for operations and safety limits.

068A2.04 Liquid Radwaste 3.3 3.3 Failure of automatic isolation 071G2.4.4 Waste Gas Disposal 4.5 4.7 LI LI LI LI LI LI LI LI LI LI Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

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ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.17 Conduct of operations 3.9 4.0 Ability to make accurate, clear and concise verbal reports.

G2.1 .7 Conduct of operations 4.4 4.7 AbUity to evaluate plant performance and make -______

operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

G2.2.20 Equipment Control 2.6 3.8 Knowledge of the process for managing troubleshooting activities.

G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.29 Emergency Procedures/Plans 3.1 4.4 Knowledge of the emergency plan.

G2.4.44 Emergency Procedures/Plans 2.4 4.4 Knowledge of emergency plan protective action recommendations.

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E,-401 Record or Rejected KIAs Form E-401-4 Catawba Nuclear Station NRC Initial License Exam Dec. 2010 FINAL SUBMITTAL Tier? Group Randomly Selected KJA Reason for Rejection 1 /2 APEO68 G2.4.45 This K/A not conducive to an operationally valid RO question. At direction of Chief Examiner, a randomly selected K/A was used: G 2.4.35. RO I / 1 000056 M2.46 This K/A is not conducive to an operationally valid SRO only question. Permission was obtained from Chief Examiner to randomly select an alternate K/A. Resampled and obtained AA2.72 SRO 2/1 022 G2.4.1 This K/A is not conducive to an operationally valid SRO only question, since it involves immediate action steps, and since there are no EOP_entry_conditions_associated_with_CCS._Per_alignment with_Chief_Examiner,_resampled_and_obtained_G2.4. 11. SRO

ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Catawba Nuclear Station Date of Exam: Dec. 2010 Exam Level: RO X SRO X FINAL SUBMITTAL Initial Item Description a b* c#

1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC K/As are referenced for all questions.
b. Facility learning objectives are referenced as available..
3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 i1
4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from thelast 2 NRC licensing exams, consult the NRR OL program office).
5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly 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 wv , 4 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 J\IL.

fNT

/7 L.4 rest new or modified); enter the actual RO / SRO- 35%! 16% 9%! 4% 56% I 80% 7 only_question_distribution(s)_at_righL

7. Between 50 and 60 percent of the questions on Memory C/A the RO exam are written at the comprehension/

analysis level; the SRO exam may exceed 60 44% I 24% 56% 1 76%

percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question_distribution(s)_at_right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors. QM â /
9. Question content conforms with specific K/A statements in the previously approved examination ,.,

outline and is appropriate for the tier to which they are assigned; deviations are justified. 1ILJ t .4

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.

Printed Name / Signature Date

a. Author Darrell D. Hensley / ,&11&ALIJ iQ&L4 i

4 6 12/02/10 b.

c.

Facility Reviewer (*)

NRC Chief Examiner (#)

Chad Kidd /

J;], /

cj 12/02/10

d. NRC Regional Supervisor rbj._

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

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

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

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 I H 2 X X B Distractor D is not plausible. Did BYB not open on a reactor trip (1020)? If the trip occurred as designed, why would the action described at 1025 take place? Are both units design/procedures the same? It appears that you are asking which of the following will result in a reactor trip. Licensee provided insight into why the question was sat. Applicant needed to realize the combination of things that would cause a reactor trip. OK. Should not have been an E. (S) 2 H 3 B S (OK) 3 H 2 B S (OK) 4 H 2 N U/E? As written distractors A and C are implausible. Per procedure ES-1.4 hot leg recirculation flow is determined in Step 2, by Verify flow from at least one train of NI. (Distractors C & D) If NI flow is verified then at Step 3 you are directed to return to procedure and step in effect. Starting at Step 4 actions are being made to establish ND flow to Hot Legs (Distractors A & B). Documentation states that ONE train is adequate to provide Question should be modified or a new question provided. Determined that question should have been accepted. Not a U. Addeded sufficent to question.

5 H 1 B S LOD. Accepted question. Applicant must know limits in order to answer the question.

6 S (OK) 7 H S (OK) 8 H 2 N U Distractors B and C are not plausible. You stated in the stem that there were no equipment malfunctions. Therefore, based on E

understanding of system knowledge one would know that AMSAC would provide for turbine trip and the plant would respond as expected. Removed assuming no equipment malfunction from the stem. Question should not have been a U. Should have been_an_E._Question is OK.

Instructions

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

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
2. Enter the level of difficulty (LOD) of each question using a 1 5 (easy difficult) rating scale (questions in the 2 4 range are acceptable).
3. Check the appropriate box if a psychometric flaw is identified:
  • The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
  • The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4. Check the appropriate box if a job content error is identified:
  • The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
  • The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
  • The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
  • The question requires reverse logic or application compared to the job requirements.
5. Check questions that are samqled 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).

ES-401 2 Form ES-401-9

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 9 H 2 N S (OK) 10 H 2 N S Correct answer provided with question is different than answer provided with distractor analysis. Made change. (OK) 11 H 3 X X B/M U As written the question doesnt match K/A. K/A asks for effects of feedwater introduction. Question ask how is flow reestablished.

Also, as written there appears to by three correct answers if we focus on as required by FR-Hi. Revised question stem and distracters. Question is OK with revisions.

12 F 2 N S (OK) 13 F 2 N S (OK) 14 H 3 M/B S? Provide learning objective to verify that this is required knowledge for RO. Provided objective. (OK) 15 H 3 B/M S (OK) 16 H 3 X B/M 5? Need to make sure this is not an SRO only question. Modified stem distractor (minor changes) (OK) 17 H 2 X X N E The stem asks (2) how will the PORVs be operated. Distractors discuss motive forces available for valve operation. Made changes to address concerns. (OK) 18 H 2 X X X N U Need to reword stem to get a more direct match to K/A. Second part of stem appears to provide reason for action taken (maintain ECCS pump suction). Are you saying that actions taken in distractors A & C ensures this? Are there reasons in the basis which you expect the RO to know? Distractors B & C are weak. Make sure this is not an SRO only question. Wrote a new question. It addresses the K/A.

(OK) 19 H 2 X B/M E Add Rod Control in AUTOMATIC to the stem. Consider adding For the above condition, control bank D rods will Added nformation to the stem. (OK) 20 H 3 N S

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK L0D (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 21 X N U K/A ask for reason. Question failed to do so. Provided information as the why the question matches kIA. Made minor changes to E

the stem. Question should not have been a U. Should have been an E. (OK) 22 X E Provide additional informationa as to why you consider distractors A and D plausible. Do not think shutting down the system with the monitor in it first cant prevent an unmonitored release.

D is not plausible because if I shut down the ventilation system first, there is no way to create the vacuum.

Look at the following for consideration:

A Establish Containment Closure l Prevent an unmonitored release to the environment.

B Establish Containment Closure l Prevent an unfiltered release to the environment.

C Shutdown VP jst To prevent drawing a vacuum in containment D Shutdown VP 1 st To terminate any release as soon as possible.

Modified the distracters. (OK)..

23 F 2 N S (OK) 24 H X N U Please explain where the ability to prioritize is addressed in this question. Made changes to the stem. Will Change K/A. Selected 2.4.35. Provide new question. Reviewed new question. (OK).

25 H 2 X X N E Stem and distractors do not match. The stem ask: (1) to describe the operation of 1 EMF and (2) where is the sample drawn from and (3) which event can IEMF be used to diagnose. Distractors provide answers to where the sample is drawn from and which event can it be used to diagnose. Made changes to address concern (OK)

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 I #1 Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link juits ward K/A Only 26 H 3 X S? Do you need to identify an RCS pressure in the stem? If you are below a certain pressure would the PORV not be closed? Licensee stated that a pressure is not required. Agreed with iustification.

Added minor information in the stem (RVLIS) (OK) 27 F 2 S (OK) 28 F 2 X B E Add the procedure to the stem. Need to discuss the interlocks associated with local operation. Also need to discuss parameters associated with the alarms. Revised stem and distractors. (OK) 29 H 2 B/M S (OK) 30 H 2 N S (OK) 31 F 2 X N E Procedure states GREATER THAN 50 Mm. Also consider using a second criteria described in Step 8: greater that 3 psig. Need to discuss the plausibility of distractors C & D (bothe ND pumps must be in operation. Made change as suggested (OK) 32 F 2 B S (OK) 33 F 2 X X B/M E Consider rewording the stem: Based on the above conditions (1) which accumulator isolation valves can be should be/can be energized and (2) what action should be taken once the valves are energized modify distractors to match stem. Revised stem.

LQiL 34 F 2 B S (OK) 35 H 2 N S (OK) 36 F 2 B S (OK) 37 H 2 B S (OK) 38 B E Correct wording in the stem affect SSPS Train A and Train B?

Made changes to address concern (minor). (OK) 39 H 2 B S (OK) 40 H 2 N S (OK)

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 41 F 2 N S? Identify the conditions that would render the ice condenser inoperable. (question is OK as provided) 42 F 2 B S (OK) 43 H 2 B S (OK) 44 H 3 N S (OK) 45 H X N E Distractor D is not plausible. Nothing identified in LP which would indicate switch in AUATO is normal alignment. (need to make sure that C is not correct) 46 H 3 B S (OK) 47 F 2 N S (OK) 48 H 2 B S (OK) 49 H 2 B S (OK) 50 H 2 N S (OK) 51 F 2 B/M S (OK) 52 F 1 N S LOD (validation of question showed that the question was more than a level 1. Convensed us to accept the question ) (OK).

53 F 2 N S (OK) 54 H I N S LOD (There are unit differences need to know that in order to answer questions. Agreed that it makes it more than a 1. (OK))

55 H 2 N S (OK) 56 H 2 B S (OK) 57 H 2 N S (OK) 58 F 2 B S (OK) 59 F 2 B/M S (OK)

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK L0D (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 60 H 2 B S (OK) 61 F 2 B 5? Need clarification on EMF 1 1 and 36. How are they tied to causing containment isolation. Accepted question as provided based on discussion (OK 62 H 3 B/M S 63 H N U Xxxxx Distractors C and D are not plausible. No reason to suspect problem with Gen B. Also, I know of no case where you would attempt to close a breaker once it trips open, without an investigation.

(Changed distractors C and D(OK)).

64 H 2 N E Distractor B is not plausible. If a high radiation signal is in, why would the pumps be expected to start then trip? (Convensed us that it was plausible. (OK).

65 F I N S LOD Based on discussion we determined that LOD should not have been a 1. Made it at 2. (OK).

66 F 2 N S (OK) 67 H 2 N S (OK) 68 F 1 N U LOD. It appears that distractor A might be correct.. Could an alarm result from the light being out? Information provided addressed concerns for distractor A. Question is OK Not a U.

69 F 1 N U LOD. Not sure of any instances when a problem is identified where you would not stop the procedure and notify the supervisor.

Distractors A and C do not appear to be plausible. Wrote new question. (OK) 70 H 2 X N S/E Stem is confusing. Consider rewording the stem: Based on the above conditions... (1) can the release be manually re-initiated (take out the word again)... (2) which valve automatically closed to terminate the lease. Made changes (OK) 71 H 2 N S (OK) 72 H 1 N S LOD Changes made added some distractors more plausible.

Slightly increased LOD fQK1

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 BIM/N UIE/S Explanation Focus Dist. Link units ward KIA Only 73 F 2 N S (OK) 74 F I N S LOD Wrote new question (OK)

U 75 H 3 B S (OK) 76 H 3 N S Qj 77 H 3 N S OK 78 F 2 B S 79 H 3 N SI? Need additional information as to why this is a K/A match. Question is OK as provided.

80 H 2 N S Will make a revision and look at on 11/1612010. Reviewed revised question. Revisions acceptable.

81 H 3 N S (OK) 82 H 3 X N E Consider asking what is the required TS action for the given condition and then the basis. Reword distractors to reflect question asked.

Made changes. All agreed 83 H 2 X X N U Appears to be teaching in the stem. Distractors C and D are not plausible. Not sure that there are any alarm response procedures that provide detailed instructions on how to return a system to normal status/alignment. Made changes to question to address concerns. Accepted changes as proposed by licensee. Check to see is public can enter areallocation 2.

84 H 2 N S (OK) 85 H 3 N S (OK) 86 H 2 N S (OK) 87 F 2 N S (OK)

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem cuesi TIE Cred. Partial Job- Minutia #1 Back- Q= SRO BIM/N U/E/S Explanation Focus j Dist. Link units ward KIA Only 88 H 2 N S? Can this question be answered with system knowledge only? ffl revisit on Tuesday 1111612010. Question should have been an E.

Added once part to the stem. Accepted question.

89 H X N U It appears that this question can be answered with system knowledge only and directions contained within the immediate actions. Need to provide additional information as to why you consider this SRO only.

Licensee provided additional information indicating that it was OK. Question should have been SAT.

90 H 3 N S (OK) 91 F X U Distractors C and D are not plausible. Provide information that supports TS bases being made based on history of known valve leakage or component problem. Provided information to show that distractor are plausible. Information not previously provided. Question should have been SAT.

92 H X X X X N U Given the alarm that is received, should WL -124 auto close? Who is performing this procedure? Based on the fact that an auto action did not occur, the ARPs immediate action directs the operator to verify release has been terminated. Operation of the system, including how to/why is identified in the procedure being perform. RL flow is given, why would one expect the applicant to conclude that you need to implement a procedure requiring RL flow to be determined?

new question. Accepted question.

93 H X X N 13 The ARP provides directions as to what procedure should be entered. Not sure if after being instructed by ARP to enter a E

procedure, this is considered SRO only. ARP are typically referred to by the operators. Made two changes to question. Accepted licensees comments. Question should not have been UNSAT.

94 F 1 N S LOD Made changes the stem and the distractors. Accepted results.

95 H 2 S? Consider rewording stem: Which one of the following (1) describes the actions the SRO should direct the crew to perform in order to control void growth without interrupting natural circulation and (2) what procedure will Change distractors to two parts. Made changes as suggested. Ok with change.

96 F 2 E Add component. Do not identify component as TS or not TS. Add components and let the applicant decide if there are TS concerns.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK L0D (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 97 H 2 X X N E Consider rewording the second part of the stem. As written the question appears to ask, and as given in the distractors, the applicant to identify the TS that addresses Containment Air Locks. The answer then states that the Bases for that TS provides the reason.

Distractors do not provide any indications of what the bases state/are.

98 H 2 M S Q!

99 H 2 B S Changed distractors C and D.

100 F I B/M S LOD Rewrote gueston to address issue. Increased level of difficult

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist acility: Catawba Nuclear Station Date of Exam: 12/21/2010 Exam Level: ROISRO Initials Item Description a b c

1. Clean answer sheets copied before grading L

47 J

2. Answer key changes and question deletions justified and documented f
3. Applicants scores checked for addition errors 1 (reviewers spot check> 25% of examinations) Zf,L..
4. Grading for all borderline cases (80 +/-2% overall and 70 or 80, as applicable, +/-4% on the SRO-only) reviewed in detail JsV...
5. All other failing examinations checked to ensure that grades are justified ,4c.
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions_missed_by_half or_more_of the_applicants Printed Name/Signature Date
a. Grader p) J/JebD,/

/ j/ 1/

I /

b. Facility Reviewer(*) A//A (

M i I I

c. NRC Chief Examiner (*) Ed&z,i gp j /

1

d. NRC Supervisor (*) 4lDVJlDWsA1Aj/ I

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

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