ML15247A428
| ML15247A428 | |
| Person / Time | |
|---|---|
| Site: | Oconee |
| Issue date: | 09/04/2015 |
| From: | NRC/RGN-II |
| To: | Duke Energy Carolinas |
| References | |
| Download: ML15247A428 (51) | |
Text
ES-201, Rev. 9 Examination Preparation Checklist Form ES-201-1 Facility:
Oconee Date of Examination:
6/8/15 Developed by: Writtenlit)
NRC II Operating(Iit NRC Target Chief Date*
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.1.e; C.3.c; Attachment 2)]
{-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-1s, ES-401 -1 /2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d)
{-70}
{7.Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)}
{-45}
8.Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3d)
-30 9.Preliminary license applications (NRC Form 398s) due (C.1.I; C.2.g; ES-202)
-14 10.Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)
-14 11.Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)
-14 12.Examinations reviewed with facility licensee (Ci.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 I eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)
-7 15.Proctoringlwritten 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.
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
Date of Examination: /8/ IS Initials Item Task Descnption
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.
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
-X; z.
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, 7.
S and major transients.
t)
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.
0 c.
To the extent possible, assess whether the outline(s) conform(s) with the qualitative R
and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
5L.
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.
Verifythatthe 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
/
y of applicants and ensure that no items are duplicated on subsequent days.
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
N c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
d.
Check for duplication and overlap among exam sections.
51.
A e.
Check the entire exam for balance of coverage.
L f.
Assess whether the exam fits the appropriate job level (RO or SRO).
jt a
Author 5f4M 6
/Da.
- b. Facility Reviewer (*)
- J
- c. NRC Chief Examiner (#)
- d. NRC SupeMsor s
()
Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
.* 4 1
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ES-201, Page 26 of 28
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
Date of Examination:
Initials Item Task Description
1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.
(J-l4 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.
41-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 of applicants and ensure that no items are duplicated on subsequent days.
- /
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
G E
b.
Assesswhetherthe 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.
R d.
Check for duplication and overlap among exam sections.
L e.
Check the entire exam for balance of coverage.
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
a Author bS:(2/
- b. Facility Reviewer (*)
A//A
- c. NRC Chief Examiner (#)
. L. / Q1)Q cV flfa/2cx/f
- d. NRCSupervisor c2(ZAi Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines
F; ES-201 Examnaton Security Agreement jLT47 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 9LJ4as 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 1,-)I3-) 5 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 1LT47 Form ES-201 -3 1.
Pre-Examination 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 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 L-Is-))(t 5
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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JLTft 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) ofur18) 2015 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) ofio8i5_J5 From the date that I entered into this security agreement until the completion of examination adn[nistration, 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, Page 27 of 28
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) ofIMS) 2
°I5as 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) ofo815J5 From the date that I entered into this securit.yagreement until the completion of examination adninistration, 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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L/s4 (fi&f ES-201, Page 27 of 28
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6/08/15 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations G2.1.25 (3.9/4.2)
M,R ADM-105, Perform a Power Imbalance Verification (RO Only) (27 min)
Conduct of Operations G2.1.37 (4.3/4.6)
M,R ADM-102, Calculate Requirements to Makeup to the BWST (BOTH) (15 min)
Equipment Control G2.2.42 (3.9/4.6)
D,R ADM-201, Determine SSF RCMUP Operability (RO Only) (10 min)
Radiation Control G2.3.12 (3.2/3.7)
M,R ADM-301a, Determine Posting and Access requirements of LPI Room based on Plan View (BOTH) (10 min)
Emergency Plan N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
X
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6/08/15 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note)
Type Code*
Describe activity to be performed Conduct of Operations G2.1.25 (3.9/4.2)
M,R ADM-S105, Perform a Power Imbalance Verification and Determine any Required Actions and Completion Times (SRO Only) (35 min)
Conduct of Operations G2.1.37 (4.3/4.6)
M,R ADM-102, Calculate Requirements to Makeup to the BWST (BOTH) (15 min)
Equipment Control G2.2.40 (3.4/4.7)
D,R ADM-S201, Determine Tech Spec Requirements for Inoperable PZR Heaters (SRO Only) (15 min)
Radiation Control G2.3.12 (3.2/3.7)
M,R ADM-301a, Determine Posting and Access Requirements of LPI Room based on Plan View (BOTH) (10 min)
Emergency Plan G2.4.38 (2.4/4.4)
D,R ADM-S401, Determine Emergency Classification (SRO Only) (15 min)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
X
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/08/15 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. RO-101a, Align Emergency Boration During an ATWS Unit 1 EOP Rule 1 KA: BW/E13 EA1.1 (3.4/3.2) (10 min)
A, M, S 1
- b. RO-301a, Align Post LOCA Boron Dilution Flowpath Unit 1 EOP LOCA CD tab KA: EPE011 EA1.11 (4.2/4.2) (15 min)
A, D, L, S 3
KA: 103 A4.04 (3.5*/3.5*) (10 min)
A, M, EN, L, S
5
- d. RO-201a, Respond to a Leak on the RCP Seal Injection Header AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection)
KA: APE 022 AA1.09 (3.2/3.3) (15 min)
A, N, S 2
- e. RO-S401, Alignment of Condensate Recirc Unit 1 EOP Encl. 5.23 (Alignment of Condensate Recirc)
KA: APE 054 G2.1.20 (4.6/4.6) (15 min)
A, D, L, S 4S
- f. RO-601, Energize Main Feeder Buses from CT-4 Unit 1 EOP Encl. 5.38 (Restoration of Power)
KA: EPE 055 EA2.03 (3.9/4.7) (15 min)
M, L, S 6
- g. RO-701, Adjust RIA-40 setpoints AP/1/A/1700/031 (Primary To Secondary Leakage)
Encl. 5.8 (Resetting 1RIA-40 and OAC Setpoints)
KA: APE 061 AA2.03 (3.0/3.3) (15 min)
D, S 7
- h. RO-801, OATC Actions for Control Room Evacuation Following a Fire AP/1/A/1700/050 (Challenging Plant Fire)
KA: APE068 AA1.02 (4.3/4.5) (10 min)
N, L, S 8
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-601, Makeup to Unit 1 CBAST from Unit 1 & 2 BAMT During a Unit 2 Blackout Unit 2 EOP Encl. 5.39 (Makeup to the BWST During Blackout)
KA: B/WE14 EA1.1 (3.8/3.6) (12 min)
D, E, R 6
- j.
AO-S401, Align Main Vacuum Pumps AP/1/A/1700/027 Encl. 5.1 (Main Vacuum Pump Alignment)
KA: APE 051 G2.1.23 (4.3/4.4) (15 min)
D, E 4S
- k. AO-801, Start Diesel Air Compressors and Align to Service Air Header AP/2/A/1700/022 (Loss of Instrument Air) Encl. 5.4 (Emergency Start of the Diesel Air Compressor) and 5.7 (Manual Start of Diesel Air Compressors)
KA: APE 065 AA1.04 (3.5*/3.4*) (20 min)
D, E 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/08/15 Exam Level: RO SRO-I X SRO-U Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. RO-101a, Align Emergency Boration During an ATWS Unit 1 EOP Rule 1 KA: BW/E13 EA1.1 (3.4/3.2) (10 min)
A, M, S 1
- b. RO-301a, Align Post LOCA Boron Dilution Flowpath Unit 1 EOP LOCA CD tab KA: EPE011 EA1.11 (4.2/4.2) (15 min)
A, D, L, S 3
KA: 103 A4.04 (3.5*/3.5*) (10 min)
A, M, EN, L, S
5
- d. RO-201a, Respond to a Leak on the RCP Seal Injection Header AP/1/A/1700/014 (Loss of Normal HPI Makeup and/or RCP Seal Injection)
KA: APE 022 AA1.09 (3.2/3.3) (15 min)
A, N, S 2
- e. RO-S401, Alignment of Condensate Recirc Unit 1 EOP Encl. 5.23 (Alignment of Condensate Recirc)
KA: APE 054 G2.1.20 (4.6/4.6) (15 min)
A, D, L, S 4S
- f. RO-601, Energize Main Feeder Buses from CT-4 Unit 1 EOP Encl. 5.38 (Restoration of Power)
KA: EPE 055 EA2.03 (3.9/4.7) (15 min)
M, L, S 6
- g. N/A
- h. RO-801, OATC Actions for Control Room Evacuation Following a Fire AP/1/A/1700/050 (Challenging Plant Fire)
KA: APE068 AA1.02 (4.3/4.5) (10 min)
N, L, S 8
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-601, Makeup to Unit 1 CBAST from Unit 1 & 2 BAMT During a Unit 2 Blackout Unit 2 EOP Encl. 5.39 (Makeup to the BWST During Blackout)
KA: B/WE14 EA1.1 (3.8/3.6) (12 min)
D, E, R 6
- j.
AO-S401, Align Main Vacuum Pumps AP/1/A/1700/027 Encl. 5.1 (Main Vacuum Pump Alignment)
KA: APE 051 G2.1.23 (4.3/4.4) (15 min)
D, E 4S
- k. AO-801, Start Diesel Air Compressors and Align to Service Air Header AP/2/A/1700/022 (Loss of Instrument Air) Encl. 5.4 (Emergency Start of the Diesel Air Compressor) and 5.7 (Manual Start of Diesel Air Compressors)
KA: APE 065 AA1.04 (3.5*/3.4*) (20 min)
D, E 8
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/08/15 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. RO-101a, Align Emergency Boration During an ATWS Unit 1 EOP Rule 1 KA: BW/E13 EA1.1 (3.4/3.2) (10 min)
A, M, S 1
- b. RO-301a, Align Post LOCA Boron Dilution Flowpath Unit 1 EOP LOCA CD tab KA: EPE011 EA1.11 (4.2/4.2) (15 min)
A, D, L, S 3
KA: 103 A4.04 (3.5*/3.5*) (10 min)
A, M, EN, L, S
5
- d. N/A
- e. N/A
- f. N/A
- g. N/A
- h. N/A
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- i.
AO-601, Makeup to Unit 1 CBAST from Unit 1 & 2 BAMT During a Unit 2 Blackout Unit 2 EOP Encl. 5.39 (Makeup to the BWST During Blackout)
KA: B/WE14 EA1.1 (3.8/3.6) (12 min)
D, E, R 6
- j.
AO-S401, Align Main Vacuum Pumps AP/1/A/1700/027 Encl. 5.1 (Main Vacuum Pump Alignment)
KA: APE 051 G2.1.23 (4.3/4.4) (15 min)
D, E 4S
- k. N/A All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1
- / - / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1
ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: QOt Date of Examination: /B /15 Operating Test Number: I Initials
- 1. General Criteria a
b*
a.
The operating test conforms with the previously approved outline; changes are consistent with
(
sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
b.
There is no day-to-day repetition between this and other operating tests to be administered during this examination.
c.
The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1.a.)
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.
- 2. Walk-Through Criteria a.
Each JPM includes the following, as applicable:
initial conditions initiating cues references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:
detailed expected actions with exact criteria and nomenclature
system response and other examiner cues
statements describing important observations to be made by the applicant
criteria for successful completion of the task
identification of critical steps and their associated performance standards
restrictions on the sequence of steps, if applicable
b.
Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.
- 3. Simulator Criteria
The associated simulator operating tests (scenario sets) have been reviewed in accordance with
Form ES-301-4 and a copy is attached.
a Author M [APriedN
/yte b.
Facility Reviewer(*)
Iob..
c.
NRC Chief Examiner (#)
(
/,
d.
NRC Supervisor (a Ii )zo 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 Scenario Quality Checklist Form ES-301-4 Facility: Oconee Date of Exam: 06/08/15 Scenario Numbers:
1 I 2 I 3 Operating Test No.: 1 QUALITATIVE ATTRIBUTES Initials
a b*
c#
1.
The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events.
2.
The scenarios consist mostly of related events.
Zt_
3.
Each event description consists of the point in the scenario when it is to be initiated the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable) 4.
No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.
5.
The events are valid with regard to physics and thermodynamics.
6.
Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
7.
If time compression techniques are used, the scenario summary clearly so indicates.
Operators have sufficient time to carry out expected activities without undue time constraints.
/
are given.
8.
The simulator modeling is not altered.
9.
The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
10.
Every operator will be evaluated using at least one new or significantly modified scenario.
All other scenarios have been altered in accordance with Section D.5 of ES-301.
11.
All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios).
12.
Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-3d -5 (submit the form with the simulator scenarios).
13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
A.)
Target Quantitative Attributes (Per Scenario; See Section D5.d)
Actual Attributes 1.
Total malfunctions (58) 7 5
6 7
7, 2.
Malfunctions after EOP entry (12) 1 1
1 2
3.
Abnormal events (24) 3 3
3 3
4.
Major transients (12) 2 1
1 2
5.
EOPs entered/requiring substantive actions (12) 1 1
1 2
7 6.
EOP contingencies requiring substantive actions (02) 1 1
1 1
/
7, 7.
Critical tasks (23) 3 2
2 2
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Oconee Date of Exam: 06/08/15 Operating Test No.: 1 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RO X
SRO-I SRO-U RX 6
5 2
1 1 0 NOR 1
1 1 I/C 2,5 3,4 2,5 4,6 4
4 2 MAJ 7,8 7
6 7
2 2 1 TS 0
2 2 RO X
SRO-I SRO-U RX 1
1 0 NOR 1
6 1
1 1
1 1 I/C 3,4 1,3 3,4 3,5 4
4 2 MAJ 7,8 7
6 7
2 2 1 TS 0
2 2 RO SRO-I SRO-U X
RX 6
5 2
1 1 0 NOR 1
6 1
1 1
1 1 I/C 2,3,4 5
1,2,3 4
2,3,4 5
3,4,5 6
4 4 2 MAJ 7,8 7
6 7
2 2 1 TS 1,2,6 2,3 1,3,4 3,4,5 0
2 2 Instructions:
- 1.
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
- 2.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
- 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.
ES-301 Competencies Checklist Form ES-301-6 Facility: Oconee Date of Examination: 06/08/15 Operating Test No.: 1 Competencies APPLICANTS RO X
SRO-I SRO-U RO X
SRO-I SRO-U RO SRO-I SRO-U X RO SRO-I X
SRO-U SCENARIO SCENARIO SCENARIO SCENARIO 1
2 3
4 1
2 3
4 1
2 3
4 1
2 3
4 Interpret/Diagnose Events and Conditions 2,5 6,7 8
3,4 5,7 2,5 6
2,4 6,7 1,3 4,7 8
1,2 3,6 7
1,3 4,6 1,3 5,7 1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
2,5 6,7 8
3,4 5,7 2,5 6
2,4 6,7 Comply With and Use Procedures (1) 2,5 6,7 8
3,4 5,7 2,5 6
2,4 6,7 1,3 4,7 8
1,2 3,6 7
1,3 4,6 1,3 5,7 1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 7,8 3,4 5,7 2,5 6
2,4 6,7 Operate Control Boards (2) 2,5 6,7 8
3,4 5,7 2,5 6
2,4 6,7 1,3 4,7 8
1,3 6,7 1,3 4,6 1,3 5,7 2,5 6,7 8
3,4 5,7 2,5 6
2,4 6,7 Communicate and Interact 1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
Demonstrate Supervisory Ability (3) 1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
1,2, 3,4, 5,6, 7,8 1,2, 3,4, 5,6 7
1,2, 3,4, 5,6, 1,2, 3,4, 5,6, 7
Comply With and Use Tech. Specs. (3) 1,3 6
2,3 1,3 4
3,4 5
1,3 6
2,3 1,3 4
3,4 5
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-401 PWR Examination Outline Form ES-401-2 Facility: Oconee Date of Exam:
June, 2015 Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1.
Emergency &
Abnormal Plant Evolutions 1
3 3
3 N/A 3
3 N/A 3
18 3
3 6
2 2
1 2
2 1
1 9
2 2
4 Tier Totals 5
4 5
5 4
4 27 5
5 10
- 2.
Plant Systems 1
3 3
3 3
3 2
3 2
3 1
2 28 3
2 5
2 1
1 1
1 1
1 1
1 1
1 0
10 2
1 3
Tier Totals 4
4 4
4 4
3 4
3 4
2 2
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
2 3
2 2
1 2
Note:
- 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, 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-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A2 G
K/A Topic(s)
IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X
007EK1.04; Knowledge of the operational implications of the decrease in reactor power following reactor trip (prompt drop and subsequent decay) as it applies to the reactor trip.
3.6 000008 Pressurizer Vapor Space Accident / 3 X
008AG2.4.31; Knowledge of annunciator alarms, indications, or response procedures.
4.2 000009 Small Break LOCA / 3 X
X 009EK2.03; Knowledge of the interrelations between the small break LOCA and S/Gs.
009EA2.11; Ability to determine or interpret containment temperature, pressure, and humidity as they apply to a small break LOCA.
3.0 4.1 000011 Large Break LOCA / 3 X
011EK2.02; Knowledge of the interrelations between pumps and a Large Break LOCA.
2.6 000015/17 RCP Malfunctions / 4 X
015AK2.07; Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the RCP seals.
2.9 000022 Loss of Rx Coolant Makeup / 2 X
022AK1.02; Knowledge of the operational implications of the relationship of charging flow to pressure differential between charging and RCS as they apply to Loss of Reactor Coolant Makeup 2.7 000025 Loss of RHR System / 4 X
025G2.2.44; 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.
4.4 000026 Loss of Component Cooling Water / 8 X
026AA2.06; Ability to determine and interpret the length of time after the loss of CCW flow to a component before that component may be damaged as it applies to the Loss of Component Cooling Water.
2.8 000027 Pressurizer Pressure Control System Malfunction / 3 X
027AG2.2.25; Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
4.2 000029 ATWS / 1 X
029EG2.4.18; Knowledge of the specific bases for EOPs.
3.3 000038 Steam Gen. Tube Rupture / 3 X
038EK3.01; Knowledge of the reasons for equalizing pressure on primary and secondary sides of ruptured S/G as it applies to a SGTR.
4.1 000040 (BW/E05; CE/E05; W/E12)
Steam Line Rupture - Excessive Heat Transfer / 4 X
040AA1.18; Ability to operate and / or monitor the control rod position indicators as they apply to the Steam Line Rupture.
4.2 000054 (CE/E06) Loss of Main Feedwater / 4 X
054AA2.06; Ability to determine and interpret AFW adjustments needed to maintain proper Tavg and S/G level as it applies to the Loss of Main Feedwater (MFW).
4.0 000055 Station Blackout / 6 X
055AG2.2.44; 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.
4.4 000056 Loss of Off-site Power / 6 X
056AA1.05; Ability to operate and / or monitor the Initiation (manual) of safety injection process as it applies to the Loss of Offsite Power.
3.8 000057 Loss of Vital AC Inst. Bus / 6 X
057AK3.01; Knowledge of the reasons for the Actions contained in EOP for loss of vital ac electrical instrument bus as they apply to the Loss of Vital AC Instrument Bus.
4.1
000058 Loss of DC Power / 6 X
X 058AA1.03; Ability to operate and / or monitor vital and battery bus components as they apply to the Loss of DC Power.
058AA2.01; Ability to determine and interpret that a loss of dc power has occurred; verification that substitute power sources have come on line as they apply to the Loss of DC Power.
3.1 4.1 000062 Loss of Nuclear Svc Water / 4 X
X 062AG2.2.42; Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
062AA2.02; Ability to determine and interpret the cause of possible SWS loss as it applies apply to the Loss of Nuclear Service Water.
3.9 3.6 000065 Loss of Instrument Air / 8 X
065AA2.08; Ability to determine and interpret failure modes of air-operated equipment as they apply to the Loss of Instrument Air.
2.9 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X
BE04EK1.2; Knowledge of the operational implications of normal, abnormal and emergency operating procedures associated with (Inadequate Heat Transfer) as they apply to the (Inadequate Heat Transfer).
4.0 000077 Generator Voltage and Electric Grid Disturbances / 6 X
077AK3.01; Knowledge of the reasons for the reactor and turbine trip criteria as they apply to Generator Voltage and Electric Grid Disturbances.
3.9 K/A Category Totals:
3 3
3 3
3/3 3/3 Group Point Total:
18/6
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)
E/APE # / Name / Safety Function K
1 K
2 K
3 A
1 A2 G
K/A Topic(s)
IR 000001 Continuous Rod Withdrawal / 1 X
001AA1.02; Ability to operate and / or monitor the Rod in-out-hold switch as it applies to the Continuous Rod Withdrawal.
3.6 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 X
A08AK3.2; Knowledge of the reasons for the Normal, abnormal and emergency operating procedures associated with Refueling Canal Level Decrease as they apply to the Refueling Canal Level Decrease.
3.2 000037 Steam Generator Tube Leak / 3 X
037AA2.03; Ability to determine and interpret That the expected indications on main steam lines from the S/Gs should show increasing radiation levels as they apply to the Steam Generator Tube Leak.
3.9 000051 Loss of Condenser Vacuum / 4 X
051AG2.4.20; Knowledge of the operational implications of EOP warnings, cautions, and notes.
4.3 000059 Accidental Liquid RadWaste Rel. / 9 X
059AA2.03; Ability to determine and interpret the failure modes, their symptoms, and the causes of misleading indications on a radioactive-liquid monitor as they apply to the Accidental Liquid Radwaste Release.
3.1 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 X
067AK1.02; Knowledge of the operational implications of fire fighting as they apply to Plant Fire on Site.
3.1 000068 (BW/A06) Control Room Evac. / 8 X
BA06AK1.3; Knowledge of the operational implications of the annunciators and conditions indicating signals, and remedial actions associated with the (Shutdown Outside Control Room) as they apply to the (Shutdown Outside Control Room).
3.4 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 X
074EA1.02; Ability to operate and monitor the RCS cooldown rate as it applies to an Inadequate Core Cooling.
3.9 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5
W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 X
BA01AK3.3; Knowledge of the reasons for the manipulation of controls required to obtain desired operating results during abnormal, and emergency situations as they apply to the (Plant Runback).
3.6 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 X
BA04AK2.2; Knowledge of the interrelations between the (Turbine Trip) and the Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
3.3 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 X
BE08EA2.2; Ability to determine and interpret the adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments as they apply to the (LOCA Cooldown).
3.3 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X
BE09AG2.2.4; (multi-unit license)
Ability to explain the variations in control board/control room l layouts, systems, instrumentation, and procedural actions between units at a facility.
3.6 BW/E13&E14 EOP Rules and Enclosures X
BE14EG2.4.50; Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
4.2 CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:
2 1
2 2
1/2 1/2 Group Point Total:
9/4
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
K/A Topic(s)
IR 003 Reactor Coolant Pump X
003K6.04; Knowledge of the effect of a loss or malfunction on the starting requirements will have on the RCPS.
2.6 004 Chemical and Volume Control X
004A2.15; Ability to (a) predict the impacts of High or low PZR level on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions.
3.5 005 Residual Heat Removal X
X 005K4.08; Knowledge of RHRS design feature(s) and/or interlock(s) which provide for the lineup for "piggy-back" mode with high-pressure injection.
005G2.1.30; Lineup for "piggy-back" mode with high-pressure injection.
3.1 4.0 006 Emergency Core Cooling X
006K2.04; Knowledge of bus power supplies to the ESFAS-operated valves.
3.6 007 Pressurizer Relief/Quench Tank X
X 007K3.01; Knowledge of the effect that a loss or malfunction of the PRTS will have on the containment.
007K5.02; Knowledge of the Method of forming a steam bubble in the PZR of the following concepts as they apply to PRTS.
3.3 3.1 008 Component Cooling Water X
008A1.01; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including CCW flow rate.
2.8 010 Pressurizer Pressure Control X
X 010K5.01; Knowledge of the operational implications of the Determination of condition of fluid in PZR, using steam tables as they apply to the PZR PCS.
010A3.01; Ability to monitor automatic operation of the PZR PCS, including PRT temperature and pressure during PORV testing.
3.5 3.0
012 Reactor Protection X
X 012A3.05; Ability to monitor automatic operation of the RPS, including single and multiple channel trip indicators.
012A2.05; Ability to (a) predict the impacts of faulty or erratic operation of detectors and function generators on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
3.6 3.2 013 Engineered Safety Features Actuation X
X 013G2.2.39; Knowledge of less than or equal to one hour Technical Specification action statements for systems.
013A2.02; Ability to (a) predict the impacts of excess steam demand on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
3.9 4.5 022 Containment Cooling X
X 022K1.01; Knowledge of the physical connections and/or cause-effect relationships between the CCS and the SWS/cooling system.
022K2.02; Knowledge of power supplies to the chillers.
3.5 2.5 025 Ice Condenser 026 Containment Spray X
X 026K2.02; Knowledge of bus power supplies to the MOVs.
026A2.08; Ability to (a) predict the impacts of safe securing of containment spray when it can be done) on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
3.4 3.7 039 Main and Reheat Steam X
X 039A1.10; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MRSS controls including Air ejector PRM.
039K5.01; Knowledge of the operational implications of the Definition and causes of steam/water hammer as they apply to the MRSS.
2.9 2.9 059 Main Feedwater X
X 059K1.07; Knowledge of the physical connections and/or cause-effect relationships between the MFW and the ICS.
059K3.03; Knowledge of the effect that a loss or malfunction of the MFW will have on the S/Gs.
3.2 3.5
061 Auxiliary/Emergency Feedwater X
X 061K6.02; Knowledge of the effect of a loss or malfunction of the pumps will have on the AFW components.
061K4.06; Knowledge of AFW design feature(s) and/or interlock(s) which provide for the following: AFW startup permissives.
2.6 4.0 062 AC Electrical Distribution X
062A4.01; Ability to manually operate and/or monitor in the control room All breakers (including available switchyard).
3.3 063 DC Electrical Distribution X
063A2.01; Ability to (a) predict the impacts of grounds on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.
2.5 064 Emergency Diesel Generator X
X 064A3.13; Ability to monitor automatic operation of the ED/G system, including Rpm controller/megawatt load control (breaker-open/breaker-closed effects).
064K1.02; Knowledge of the physical connections and/or cause/effect relationships between the ED/G system and the following systems: D/G cooling water system.
3.0 3.1 073 Process Radiation Monitoring X
073A1.01; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including radiation levels.
3.2 076 Service Water X
076K4.03; Knowledge of SWS design feature(s) and/or interlock(s) which provide for the automatic opening features associated with SWS isolation valves to CCW heat exchangers.
2.9 078 Instrument Air X
078G2.4.2; Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.
4.5 103 Containment X
X 103K3.03; Knowledge of the effect that a loss or malfunction of the containment system will have on the Loss of containment integrity under refueling operations.
103G2.2.38; Knowledge of conditions and limitations in the facility license.
3.7 4.5 K/A Category Point Totals:
3 3
3 3
3 2
3 2/3 3
1 2/2 Group Point Total:
28/5
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
K/A Topic(s)
IR 001 Control Rod Drive 002 Reactor Coolant X
002K6.07; Knowledge of the effect or a loss or malfunction on the following RCS components: Pumps.
2.5 011 Pressurizer Level Control X
011A2.11; Ability to (a) predict the impacts of failure of PZR level instrument - low on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.
3.6 014 Rod Position Indication X
014A2.06; Ability to (a) predict the impacts of the loss of LVDT on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences.
2.6 015 Nuclear Instrumentation X
015A1.08; Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including: Changes in RCS temperature.
3.3 016 Non-nuclear Instrumentation X
016K5.01; Knowledge of the operational implication of the separation of control and protection circuits as they apply to the NNIS.
2.7 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator X
035G2.2.22; Knowledge of limiting conditions for operations and safety limits.
4.7 041 Steam Dump/Turbine Bypass Control X
041K1.02; Knowledge of the Physical connections and/or cause-effect relationships between the SDS and the S/G level.
2.7 045 Main Turbine Generator 055 Condenser Air Removal X
055K3.01; Knowledge of the effect that a loss or malfunction of the CARS will have on the Main Condenser.
2.5 056 Condensate X
056A2.04; Ability to (a) predict the impacts of the loss of condensate pumps on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.
2.6
068 Liquid Radwaste 071 Waste Gas Disposal X
071A3.03; Ability to monitor automatic operation of the Waste Gas Disposal System Including: Radiation monitoring system alarm and actuating signals.
3.6 072 Area Radiation Monitoring X
072A4.03; Ability to manually operate and/or monitor in the control room:
Check source for operability demonstration.
3.1 075 Circulating Water X
073K2.03; Knowledge of bus power supplies to the Emergency/ Essential SWS pumps.
2.6 079 Station Air X
079K.4.01; Knowledge of SAS design feature(s) and/or interlock(s) which provide for cross-connect with IAS.
2.9 086 Fire Protection K/A Category Point Totals:
1 1
1 1
1 1
1 1/2 1
1 0/1 Group Point Total:
10/3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: Oconee Date of Exam: June, 2015 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.15 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memos, etc.
2.7 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 2.1.28 Knowledge of the purpose and function of major system components and controls.
4.1 2.1.40 Knowledge of refueling administrative requirements.
3.9 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.
3.8 Subtotal 3
2
- 2.
Equipment Control 2.2.3 (multi-unit license) Knowledge of the design, procedural, and operational differences between units.
3.8 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
2.6 2.2.11 Knowledge of the process for controlling temporary design changes.
3.3 2.2.23 Ability to track Technical Specification limiting conditions for operations.
4.6 2.2.
2.2.
Subtotal 2
2
- 3.
Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.
3.5 2.3.11 Ability to control radiation releases.
3.8 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.8 2.3.
2.3.
Subtotal 2
1
- 4.
Emergency Procedures /
Plan 2.4.1 Knowledge of EOP entry conditions and immediate action steps.
4.6 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire-fighting equipment usage.
3.1 2.4.29 Knowledge of the emergency plan.
3.1 2.4.19 Knowledge of EOP layout, symbols, and icons.
4.1 2.4.43 Knowledge of emergency communications systems and techniques.
3.8 2.4.
Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Group Randomly Selected K/A Reason for Rejection 1/1 BE02EG2.4.4 Overselected 1/1 15AG2.2.25 Overselected 1/1 040AG2.2.44 Overselected 1/2 067 AG2.2.4 Overselected 1/2 068AA2.04 Overselected 2/1 005K6.03 Overselected 2/1 013A3.02 Overselected 2/1 036AA1.04 Unable to write an RO question to the K/A.
2/1 076K6.03 All K/As < 2.5 2/2 028G2.2.22 Overselected 2/2 035K1.12 Overselected 3
2.1.17 Unable to write discriminating question 3
2.1.21 Unable to write discriminating question 3
2.1.20 Unable to write discriminating question 3
2.1.28 Overselected 3
2.3.11 Overselected 1/1 054AA2.08 B&W does not use feed flow/steam flow recorder. Change to AA2.06.
1/1 065AA2.05 Similar to 078G2.4.2. C hanged to 065AA2.08.
1/ 2 033AK3.02 No procedural guidance or significance to task. Changed to A08AK3.2.
2/1 003K1.08 Similar to 003K6.04. Changed to 064K1.02.
2/1 073K4.02 No L/D isolation on high activity. Changed to 061K4.06.
2/2 028K2.01 Recombiners do not exist in plant. Changed to 075K2.03 3
2.1.13 Unable to write SRO level question. Changed to 2.1.40.
2/2 086A1.03 Unable to write operationally valid question for fire doors. Changed to 015A1.08
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility:
Oconee Nuclear Station Date of Exam:
6/8/2015 Exam Level:
RO SRO Initial Item Description a
b*
c 1
Questions and answers are technically accurate and applicable to the facility.
CL j 2.
a.
NRC K/As are referenced for all questions.
b.
Facility learning objectives are referenced as available.
c4\\D 3.
SRO questions are appropriate in accordance with Section D.2.d of ES-401 4.
The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR CL program office).
74 5.
Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or
. the licensee certifies that there is no duplication; or other (explain) ei) 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 RO / SRO-only question distribution(s) at right.
38 / 13 7 /
1 30 I ii 9D 7.
Between 50 and 60 percent of the questions on the RO Memory C/A exam are written at the comprehension! analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the highercognitive levels; enter 34 /
10 41 /
15 C\\ 1 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.
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;
- :3c deviations are justified.
C, 10.
Question psychometric quality and format meet the guidelines in ES Appendix B.
CL 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
- b. Facility Reviewer(*)
U 5-19-is C. NRC Chief Examiner (#)
i)
L : /._-C)
- d. NRC Regional Supervisor I
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, Rev. 9 Written Examination Review Worksheet Form ES-401-9 Oconee June, 2015 Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 1
H 2
X E
EPE007 EK1.04, New K/A is met.
Add a third bullet to state that a particular rod remained fully withdrawn.
Make the first part of the question ask When the remainder of the rods fully insert, the SUR will be. The second part will state Subsequent Actions does or does not direct drl 3/3115 Added bullet and modified question as suggested. Modified question 1 to be past tense because with the bullet 1% and decreasing, the CRs should already be inserted and thought the term when the remainder of the rods fully insert might imply an ATWS.
Question is SAT. drl 4/28/15 2
F 2
S APE008 2.4.31, New K/A is met. drl 3/31/15 3
H 3
X E
EPE009 EK2.03, Bank K/A is met.
For the second bullet at time 0410, state that temperature went from X °F to (X-2) °F over the last minute (or twice that for 2 minutes). If there is a computer point that gives CDR info then that could be provided instead.
drl 3/31/15 Added power level for trip and changed 2nd bullet to RCS temperature = 470 degrees slowly decreasing. After a trip from power, the temperature at which RCS temp normally stabilizes =
555 degrees. Using this temperature as a starting point (conservatively), the plant has cooled down at least 85 degrees in the last 10 minutes which has exceeded the 50 degree/ 1/2 hour limit which was the intent of the bullet.
Question is SAT. drl 4/28/15 4
H 3
X E
EPE011 EK2.02, Bank K/A is met.
Change the question to ask WOOTF describes the required operator actions per Rule 6 Change A to read Throttle each HPI pump to <
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 475 gpm. I know it is kind of the same thing, but it eliminates a potential subset issue with answer C. drl 4/1/15 Modified question as suggested.
Question is SAT. drl 4/28/15 5
H 3
S APE015/017 AK2.07, Bank K/A is mostly met. drl 4/1/15 6
H 2
S APE022 AK1.02, New K/A is met. drl 4/1/15 7
H 3
S APE026 AA2.06, New K/A is met. drl 4/1/15 8
F 2
S EPE029 2.4.18, Bank K/A is met. drl 4/1/15 Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]
- 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
- 2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).
- 3. Check the appropriate box if a psychometric flaw is identified:
- The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
- The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).
- The answer choices are a collection of unrelated true/false statements.
- The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
- One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4.Check the appropriate box if a job content error is identified:
- The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).
- The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).
- The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
- The question requires reverse logic or application compared to the job requirements.
5.Check questions that are sampled 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 met the 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?
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only
- 8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).
ES-401, Rev. 9 2
Form ES-401-9 Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 9
H 2
S EPE038 EK3.01, Bank K/A is met. drl 4/1/15 10 H
3 S
APE040 AA1.18, New K/A is met. drl 4/1/15 11 H
2 S
APE054 AA2.06, Bank K/A is met. drl 4/1/15 12 H
2 X
X U/E APE056 AA1.05, New K/A is met.
The second questions parenthetical statement should be a bullet in the current conditions portion of the stem.
Modified as suggested.
The first question is not very discerning. If the training is to always initiate prior to reaching the setpoint, then why would anyone choose is NOT?
Could we go at this by testing what to do if the manual initiation and AUTO initiation does not work?
Basically modified as suggested. Asked about 1 valve not responding to manual or automatic initiation signal Could we change the second answer form 0 to 2? If the example is that the C LPI pump wont start, but the other two would, it would be more plausible to have the same setup on the HPI pumps. drl 4/1/15 Modified as suggested.
Question is SAT. drl 4/28/15 13 H
>1 X
X U
APE057 AK3.01, New K/A is kind of met. Youre not really testing why the action is taken as much as what is the power supply for the method being used. It could be argued that C is not incorrect. Rule 3 does indeed provide direction to do this.
Is it possible to state that power is lost to KVIB and ask what Rule 3 would require the operator to do? A and B could remain the same, but perhaps
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only the reason for C and D would be different. This would more closely match the K/A and provide a more discerning question. drl 4/1/15 Revised as suggested Question is SAT. drl 4/28/15 14 H
3 S
APE058 AA1.03, Bank K/A is met. drl 4/1/15 15 H
3 X
E APE062 2.2.42, New K/A is met.
Make Unit 2 defueled and change the correct answer to B. drl 4/1/1/5 We would like to leave this question as is because the note in TS 3.7.7 states that if Unit 1 or 2 is defueled and appropriate LPSW loads secured on the defueled unit so to make B correct, we would have to list the specific loads that are secured which could cue the applicants to the correct answer. Since this is an RO question, the basis knowledge is not required but could still radio the correct answer if we start listing components that are isolated. Will discuss.
Probably OK. Need to discuss. Drl 4/28/15 Question is SAT. drl 4/30/15 16 H
2 S
APE065 AA2.08, Bank K/A is met. drl 4/1/15 17 H
3 S/E BWE04 EK1.2, Modified Bank K/A is met.
Not modified enough from the original question to be considered MODIFIED. drl 4/1/15 Changed to Bank in the exam program.
Question is SAT. drl 4/28/15 18 F
2 E
APE077 AK3.01, New K/A is met.
Remove the last bullet from 0805 entry. This is teaching and redundant.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only drl 4/1/15 Removed bullet as suggested.
Question is SAT. drl 4/28/15 19 H
2 X
E APE001 AA1.02; New K/A is met.
Second question is not very discerning. Could we instead ask the relative setting for feed (higher or lower than original) instead? Not difficult, just more discerning. drl 4/1/15 Modified question as suggested. Made this the first question and moved the old first question to the second question. Also changed inserted to moved in order to maintain plausibility.
Question is SAT. drl 4/28/15 20 F
3 X
E APE036 AK3.02, Bank K/A is met.
Could we add the procedural reference for the load setpoint? Also, are you certain that the setpoint is required knowledge? If you wanted, you could ask the specific part of the assembly that you are concerned about.
That is just a suggestion, not a request. drl 4/1/15 Modified question as suggested. OK with setpoint since there is an objective for it OK if Ops is OK with this. Drl 4/28 Question is SAT. drl 4/30/15 21 H
3 X
U/E APE067 AK1.02, Bank K/A is met. Not certain how you justify down-powering as plausible.
Could you provide more information? drl 4/1/15 Provided extra information in question plausibility statements.
AP43 will direct entry into AP/25 (which will direct the trip) and entry into AP/50 which will direct the need to trip or perform a rapid shutdown (AP/29).
If this were a challenging plant fire but not in an SSF risk area then rapid shutdown would be a correct choice Overlap issue with 74.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only Revised Q74 to address overlap.
Question is SAT. drl 4/28/15 22 H
2 S
BWA06 AK1.3, New K/A is met. drl 4/1/15 23 H
3 S
EPE074 EA1.02, New K/A is met. drl 4/2/15 24 H
3 S
BWA01 AK3.3, New K/A is met. drl 4/2/15 25 H
2 S
BWA04 AK2.2, New K/A is met. drl 4/2/15 26 H
3 X
E BWE08 EA2.2, Bank K/A is met.
For the first question reword to reference the operational limits stated in the LOCA CD tab. drl 4/2/15 Revised as suggested Question is SAT. drl 4/28/15 27 H
3 S
BWE14 2.4.50, Bank K/A is met. drl 4/2/15 28 F
2 S
SYS064 K1.02, Bank K/A is met. drl 4/2/15 29 H
3 X
E SYS003 K6.04, Bank K/A is met.
Could we change A to read Trend affected RCP temperatures. RCP trip criteria have not yet been reached? I think it would be a more plausible distractor. drl 4/2/15 Revised as suggested Question is SAT. drl 4/28/15 30 H
2 S
SYS004 A2.15, Bank
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only K/A is met.drl 4/2/15 31 F
2 S
SYS005 K4.08, Bank K/A is met. 4/3/15 32 F
2 S
SYS006 K2.04, Bank K/A is met. drl 4/3/15 33 H
2 S
SYS007 K3.01, Bank K/A is met. drl 4/3/15 34 H
3 X
E SYS007 K5.02, Modified K/A is met.
Im not certain that 0.2 inches in the quench tank is really plausible. Yes you can see it on the computer, but would the gages give you this accuracy. If yes, then thats ok.
Otherwise, lets make this something like 4 inches.
QT level gage is a digital gage which reads to the tenth of an inch therefore a.2 inch change in level is definitely readable on the gage.
Also, you need to reword the first question to reference the procedure to ensure they know that were looking for the procedurally required number. Drl 4/3/15 Done Question is SAT. drl 4/28/15 35 H
2 S
SYS008 A1.01, Bank K/A is met drl 4/3/15.
36 F
2 E
SYS010 K5.01, Bank K/A is met.
Question: Bank 2 is part of the cycling heaters. I understand we are testing the saturation recovery circuit, but does Bank 2 (Groups B & D) also cycle at a higher setpoint? If so, could these heaters be on due to
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only being below setpoint? If so is NOT energized ever a truly plausible answer? drl 4/3/15 At 2155 psig Bank 2 heaters would be off based on just their response to RCS pressure since they turn on at 2140 and off at 2150 therefore Not energized is a correct answer if the Pressurizer is saturated.
Question is SAT. drl 4/28/15 37 H
3 X
U SYS010 A3.01, New K/A is met.
212 ºF is not plausible. This is the old isenthalpic expansion game.
Whatever the enthalpy of the steam in the pzr is will be the same as the enthalpy downstream of the PORV. The temperature will be based on the pressure at that point. The question is kind of flawed in that you have to make the assumption that you are at QT pressure here. I just ball-parked the math and it looked to be about 268 F to me. This needs a much closer look.
Or maybe I just need a better reason why 212 is plausible. drl 4/3/15 Changed 2nd part of A & C to 250 degrees. If the applicant doesnt convert 40 psig to 55 psia, they should determine ~ 250 degrees on the mollier diagram which will be incorrect.
Question is SAT. drl 4/28/15 38 F
2 S
SYS012 A3.05, Bank K/A is met. drl 4/7/15 39 F
2 S
SYS013 2.2.39, New K/A is met. drl 4/10/15 40 F
2 S
SYS022 K1.01, Bank K/A is met. drl 4/10/15 41 F
2 S
SYS022 K2.02, New K/A is met. drl 4/10/15 42 H
3 E/S SYS026 K2.02, Modified K/A is met.
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only How was this modified? drl 4/10/15 Should have been designates as a bank question Question is SAT. drl 4/28/15 43 H
3 S
SYS039 A1.10, Bank K/A is met. drl 4/10/15 44 H
2 S
SYS039 K5.01, Bank K/A is met. drl 4/10/15 45 H
2 S
SYS059 K1.07, Bank K/A is met. drl 4/10/15 46 H
3 S
SYS059 K3.03, Bank K/A is met. drl 4/10/15 47 H
X U
SYS061 K6.02, Bank K/A is mostly met.
B and C are not really plausible since it is pointed out explicitly in D that the 1A pump is available and running. Could this be transformed into a 2x2 question and we ask something about the limits placed on the only pump remaining (Is there a different flow rate directed from Enclosure 5.9 than you would normally have with both MDEFW Pumps running?) drl 4/10/15 Revised a suggested and changed to Modified Question is SAT. drl 4/28/15 48 H
3 X
E/U SYS062 A4.01, Bank K/A is met.
Are these breakers ever routinely in MANUAL? If not C and D are not very plausible. You could make this a 2x2 by using both parts of A and B twice. This would be a SAT question. drl 4/10/15 Revised as suggested Question is SAT. drl 4/28/15
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 49 F
3 S
SYS063 A2.01, Bank K/A is met. drl 4/10/15 50 H
2 X
E SYS064 A3.13, Bank K/A is met.
Auto Voltage Adjuster is not very plausible as presented. A better way to ask this would be to put KHU frequency below grid frequency, ensure that voltages given are procedurally acceptable. Then ask which switch is required to be adjusted in order to close the breaker IAW the procedure.
The second question is fine. drl 4/10/15 Revised first part of question as suggested. Tweaked second part to ensure not being directed to violate a procedure Still not quite right. It should be obvious to any operator (licensed or not) that to adjust the synchroscope, you use the Speed Changer.
Could you change the Keowee output voltage to 14.0 KV and just ask which switch needs to be adjusted? Drl 4/28/15 Question is SAT. drl 5/19/15 51 F
3 S
SYS073 A1.01, New K/A is met. drl 4/13/15 52 H
3 S
SYS061 K4.06, Modified K/A is met drl 4/13/15 53 H
2 S
SYS076 K4.03, New K/A is met.drl4/13/15 54 H
3 X
E SYS078 2.4.2, Bank K/A is met.
D is not very plausible. Perhaps a better distractor would be to initiate Emergency FW. drl 4/13/15 When tripping both MFWPs, EFDW pumps will start. You could argue that its correct.
Modified the question to ask if a trip is required at 63 psig and how the MFW reg valves fail when losing air.
Question is SAT. drl 4/28/15 Except reword first question. You need
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only to delete the first is.
Question is SAT. drl 4/30/15 55 F
2 S
SYS103 K3.03, Modified K/A is met. drl 4/13/15 56 F
2 S
SYS002 K6.07, Bank K/A is met. drl 4/13/15 57 F
2 S
SYS016 K5.01, New K/A is met.drl 4/13/15 58 F
2 S
SYS075 K2.03, Bank K/A is met. drl 4/13/15 59 H
>1 S
SYS041 K1.02, New K/A is met.
This is really only testing the knowledge of how ICS controls the system.
drl 4/13/15 60 F
2 S
SYS055 K3.01, New K/A is met. drl 4/13/15 61 H
3 S
SYS056 A2.04, Bank K/A is met. drl 4/13/15 62 F
3 S
SYS071 A3.03, New K/A is met. drl 4/13/15 63 F
2 X
X E
SYS072 A4.03, Bank K/A is met.
Doesnt 1RIA-37 have a continuous check source function? If the sensitivity drops, you get a statalarm and a fault shows on the monitor. Is this question still valid as written? Drl 4/13/15 Found conflicting information on RIA-37. Modified question to ask about performing a source check (Generically).
Question is SAT. drl 4/28/15
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 64 F
2 X
E SYS079 K4.01, Bank K/A is met.
C is not plausible. Why would the cross connect be open if the Diesel A/C is not running? Perhaps a simpler question asking at what maximum pressure SA-141 will open. 85 psig is fine as answer D, with all others being associated with the Diesel A/C or any other combination that can be justified. drl 4/13/15 Revised question as suggested.
Question is SAT. drl 4/28/15 65 H
3 S
SYS015 A1.08, New K/A is met. drl 4/13/15 66 F
2 X
E GEN2.1 2.1.15, New K/A is met.
As written, C is not plausible. Why would you have to announce an alarm clear if you didnt have to announce that it came in? How about if you change the first question to ask if SM permission is initially required to suspend verbal announcement. Then put some more words in afterword to state that all actions have been taken to declare the alarm expected.
Then ask if, when the alarm comes in, it has to have the ARP reviewed at that point. drl 4/13/15 Guidance in AD-OP-ALL-1000 was not specific enough to ask the question as suggested. Also trying to stay away from a question on the audit exam. Therefore, wrote a new question based on Transient Alarm Response.
Question is SAT. drl 4/28/15 67 H
3 S
GEN2.1 2.1.25, Bank K/A is met. drl 4/13/15 68 F
2 S
GEN2.1 2.1.28, Bank K/A is met. drl 4/14/15 69 H
3 S
GEN2.2 2.2.3, Bank K/A is met. drl 4/14/15
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only 70 F
>1 X
E GEN2.2 2.2.17, New K/A is met.
If I had no clue, I would guess is and is. Could you pick a power maneuver < 10% so that we will be testing their knowledge of the procedure? Drl 4/14/15 changed 2nd part of question to address CE concerns. Since there is differing procedure specific guidance regarding when a maneuvering plan is required, decreasing power level change to < 10% brings the possibility of more than one correct answer into play. Changed 2nd part to something requiring procedure knowledge to get correct.
Question is SAT. drl 4/28/15 71 H
3 X
E GEN2.3 2.3.7, Modified K/A is met.
Reword 2) to state Upon receipt of a second anticipated dose rate alarm, the AO. Otherwise you are teaching in the question. Drl 4/14/15 Revised question as suggested.
OK, remove the first anticipated in question 2. Drl 4/28/15 Question is SAT. drl 4/30/15 72 F
2 S
GEN2.3 2.3.11, Bank K/A is met. drl 4/14/15 73 F
3 S
GEN2.4 2.4.1, Bank K/A is met. drl 4/14/15 74 F
2 U/S GEN2.4 2.4.26, New K/A is met.
Too much overlap with Question 21. Knowledge that a cable tray fire is considered a challenging fire is key to both questions. drl 4/14/15 Changed 2nd question to ask reason for opening mulsifier valve before starting HPSW pump.
Question is SAT. drl 4/28/15 75 F
>1 S
GEN2.4 2.4.29, Bank
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only K/A is met. drl 4/14/15 76 H
3 S
EPE009 EA2.11, Bank Fixed time typochanged 0450 to 0455 K/A is met. drl 4/14/15 Question is SAT. drl 4/28/15 77 H
3 S
APE025 2.2.44, Bank K/A is met. drl 4/14/15 78 H
3 S
APE027 2.2.25, Bank K/A is met. drl 4/14/15 79 H
3 S
EPE055 2.2.44, New K/A is met. drl 4/14/15 80 H
3 S
APE058 AA2.01, Bank K/A is met. drl 4/14/15 81 H
3 X
E APE062 AA2.02, New K/A is met.
Remove the third bullet from the initial plant conditions. The rest of the information is adequate to determine cavitation. If there is an alarm for the suction valve going closed, it would be acceptable to provide that information. Drl 4/14/15 Revised as suggested. Added OAC point for LPSW-2 Question is SAT. drl 4/28/15 82 H
3 X
E APE037 AA2.03, New K/A will be met after editorial comment addressed.
Remove the If there is no primary to secondary leak on the 1B SG, statement from question 1. This is teaching and detracts from fully realizing the K/A. Also change the most likely due to.. statement to only due to. It is absolutely true, so there is no room for argument.
I know I pre-approved this one, but these editorial changes will make it
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only better. drl 4/14/15 Revised question as requested.
Question is SAT. drl 4/28/15 83 H
2 X
X S/E APE051 2.4.20, New K/A is met.
Knowing the setpoint is required to be > 255 psig is pretty close to minutia.
Also, although this is something deep inside a procedure, it is questionable that this can be deemed to meet the intent of the SRO only question. However, if Operations Management deems that the SROs knowing this value by heart is that important, this question can be evaluated as SAT. drl 4/14/15 Operations is ok with the question as is.
Question is SAT. drl 4/28/15 84 F
1 X
X U
APE059 AA2.03, Modified K/A is met.
This question is too convoluted. It only makes sense if they are linked (which they must be). Assuming they are linked will drive the applicant to D. Why not take 2 of the first answers and ask some kind of ODM basis for any actions that would need to be taken.
This doesnt look anything like the question 84 that you submitted for pre-screening. drl 4/15/15 Changed question to be one more in line with what was submitted as a pre-review.
Question is SAT. drl 4/28/15 85 H
2 S
BWE09 2.2.4, Bank K/A is kind of met. drl 4/15/15 86 F
2 X
U SYS005 2.1.30, New K/A is met.
Not at SRO level. Level to start a pump is RO knowledge. Why not ask a TS basis or design basis question about the need for this level? Drl 2/14/15
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only Changed 1st part as suggested. 2nd part is new to more closely relate to new first part, Question is SAT. drl 4/28/15 87 H
3 S
SYS012 A2.05, New K/A is met. drl 4/14/15 88 H
3 S
SYS013 A2.02, Bank K/A is met. drl 4/14/15 89 H
3 S
SYS026 A2.08, New K/A is met. drl 4/14/15 90 H
3 S
SYS103 2.2.38, New K/A is met. drl 4/14/15 91 H
3 S
SYS011 A2.11, New K/A is met. drl 4/14/15 92 H
3 S
SYS014 A2.06, Bank K/A is met. drl 4/15/15 93 F
2 X
E SYS035 2.2.22, New K/A is met.
Reword second answer to state lifted safety due to a trip from 100 percent power. drl 4/15/15 Done De-capitalize Trip in answer 2. Otherwise question is SAT. drl 4/28/15 Question is SAT. drl 5/19/15 94 F
3 X
X U
GEN2.1 2.1.40, Bank K/A is met.
TS 3.10.1 is not plausible. Why would anyone choose this TS which only ensures the plant can maintain MODE 3 when the question has you in Mode 4? I dont know see a viable alternative with the remainder of TSs.
This question has a wider berth as far as it being SRO only because it is
Q#
- 1.
LOK (F/H)
- 2.
LOD (1-5)
- 3. Psychometric Flaws
- 4. Job Content Flaws
- 5. Other
- 6.
U/E/S
- 7.
Explanation Stem Focus Cues T/F Cred.
Dist.
Partial Job-Link Minutia
- /
units Back-ward Q=
K/A SRO Only dealing with refueling. Perhaps a different question dealing with pre-refueling equipment checkout would work. Drl 4/15/15 New Question Question is SAT. drl 4/28/15 95 F
2 E
GEN2.1 2.1.4, Bank K/A is met.
Is a fog ever prohibited? Perhaps change wording to should or should NOT. Drl 4/15/15 Revised as suggested. Added bullet to current conditions to make only one right answer Question is SAT. drl 4/28/15 96 F
2 S
GEN2.2 2.2.11, Bank K/A is met. drl 4/15/15 97 H
3 S
GEN2.2 2.2.23, Bank K/A is met. drl 4/15/15 98 H
3 S
GEN2.3 2.3.14, Bank K/A is met. drl 4/15/15 99 H
3 S
GEN2.4 2.4.19, Bank K/A is met. drl 4/15/15 100 F
2 S
GEN2.4 2.4.43, Modified K/A is met. drl 4/15/15
ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist I Facility: Oconee Date of Exam:
June 17, 2015 Exam Level: RO/SRO Initials Item Description a
b c
1.
Clean answer sheets copied before grading
N/A :(
2.
Answer key changes and question deletions justified and documented 3.
Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) t
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
6.
Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of 7
questions_missed_by_half or more of the_applicants Printed Name/Sgpture Date
- a. Grader DanBacon
/(
4/)i5
- b. Facility Reviewer(*)
N/A
- c. NRC Chief Examiner (*)
David Lanyl
- d. NRC Supervisor (*)
/
1))5/Zo ci N
(*)
The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.