ML17212B168
| ML17212B168 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/31/2017 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| Download: ML17212B168 (57) | |
Text
ES-201 Examination Preparation Checklist Form ES-201 -1 FaciIity: gOA)M.S Date of Examination: At j Zll Developed by:
Written:
Facility NRC
/1 Operating Facility NRC Target Task Description (Reference)
Exarrs Date Initials
-180 1.
Examination administration date confirmed (Cia; C.2.a and b) I019_ It,
-150 2.
NRC examiners and facility contact assigned (C.1.d; C.2.e)
/0 f/,
-150 3.
Facility contact briefed on security and other requirements (C.2.c) 1 -//
-150 4.
Corporate notification letter sent (C.2.d) 10 -.7-J6 i.
[-120]
5.
Reference material due (C.1.e; C.3.c; Attachment 3)
/O3)I/
{-90}
6.
Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1 ES-301-2, ES-301-5, ES-D-1, ES-401-i/2, ES-401N-112, ES-401-3, ES-401N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d)
(0 3/,fl,,
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(-85]
7.
Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)
/( il,6
{-60}
8.
Proposed examinations (including written, walk-through JPM5, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, ES-401N-6, and any Form ES-201-2, ES-201-3, ES-3d-i, orES-301-2 updates), and reference materials due (C.1.e, f, g and h; C.3.d)
-45 9.
Written exam and operating test reviews completed. (C.3.f)
/1
-30 10.
Preliminary license applications (NRC Form 398s) due (Cli: C.2.gS-2) i7
-21 ii.
Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)
-21 12.
Examinations reviewed with facility licensee (Cli; C.2.f and h; C.3.g) ?/oi7 3-21-i
-14 13.
Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)
-14 14.
Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h) 7j
-7 15.
Facility licensee management queried regarding the licensees views on the examination. (C.2j) 3to /7
-7 16.
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;
-7 17.
Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)
- 4. 24-iT
-7 18.
Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)
- fO IT
- 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 onlyJ {Does not apply} to examinations prepared by the NRC.
ES-201, Page 25 of 28
ES-201 Examination Outline Quality Checklist Form ES-201 -2 Facility: Browns Ferry Nuclear Station Date of Examination:
4/10/2017 Initials Item Task Description
b c#
1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES4CI N.
,4
?ii.
R b.
Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 or ES-401N and whether all K/A categories are appropriately sampled.
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
4,4 73L N
d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
4 2.
a.
Using Form ES-301-5. verify that the proposed scenario sets cover the required number of
-J normal evolutions, instrument and component failures, technical specifications, and major S
M 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 NJ,
L without compromising exam integrity, and ensure that each applicant can be tested using at A
least one new or significantly modified scenario, that no scenarios are duplicated from the 7
T 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
,% f 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 distributed W
among the safety functions as specified on the form
/
A (2) task repetition from the last two NRC examinations is within the limits specified on the form fr L
(3) no tasks are duplicated from the applicants audit test(s) 1 K
(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 T
the form.
H R
b.
Verify that the administrative outline meets the criteria specified on Form ES-301-1:
o (1) the tasks are distributed among the topics as specified on the form 4
U (2) at least one task is new or significantly modified
G (3) no more than one task is repeated from the last two NRC licensing examinations
H 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.
,L I
4.
a.
Assess whether plant-specific priorities (including PRA and IPE insights) are coveted in the 4
appropriate exam sections.
f G
E b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
ft
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.
.4 1L L
e.
Check the entire exam for balance of coverage.
l f.
Assess whether the exam fits the appropriate job level (RO or SRO).
4 ;c Date
- a. Author Michael Barton / c4/V 5-29,7
- b. Facility Reviewer f)
Keith Nichols /
5-.
- /7
- c. NRC Chief Examiner (#)
IL° 4-4-17
- d. NRC Supervisor E1_tt.i._k.
(iAfLii-/ iu.4%f LIf.Ct/
Note:
- Independent NRC reviewer initial items in Column crn; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines.
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
Date of Examination: 4 1& - 17 Initials Item Task Description
a b*
c#
I a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N.
ØJfc M 4/4.
b.
Assess whether the outline was systematically and randomly prepared in accordance with T
Section D. 1 of ES-401 or ES-401 N and whether all K/A categories are appropriately sampled.
c.
Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
tiA t,4
N d.
Assess whether the justifications for deselected or rejected K/A statements are appropriate.
Nk NM
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, and major AJA A.M S
M 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 L
without compromising exam integrity, and ensure that each applicant can be tested using at FsS,4 iJ4 A
least one new or significantly modified scenario, that no scenarios are duplicated from the T
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
,Jk quantitative criteria specified on Form ES-301-4 and described in Appendix D.
I 3.
a.
Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks distributed W
among the safety functions as specified on the form A
(2) task repetition from the last two NRC examinations is within the limits specified on the form
,4i L
(3) no tasks are duplicated from the applicants audit test(s)
I K
(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 I
the form.
H R
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 U
(2) at least one task is new or significantly modified
74 G
(3) no more than one task is repeated from the last two NRC licensing examinations H
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.
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
/,
t1 R
d.
Check for duplication and overlap among exam sections.
A L
e.
Check the entire exam for balance of coverage.
$4 f.
Assess whether the exam fits the appropriate job level (RO or SRO).
Printed NemeSure.-/
7 Date a.
Author Mirirtci Ek/--
4i?-f7 b.
Facility Reviewer (*)
K.;$
tV/.o)r,/a g/-T c.
NRC Chief Examiner (#)
WW(t40 d.
NRC Supervisor vu LI/I )i7 Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines.
-(
13 FrzM E5-7-Di-2 doames cTPt1 ote ES-201, Page 26 of 28
1.
Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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.
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- 1. S6ft 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 04-10-17 through 04-24-17. 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-Examlnation I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 04-10-17 through 04-24-17. From the date thatl 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-Examjnation I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 schedule 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 04-10-17 through 04-24-17. 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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Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 04-10-17 through 04-24-17. 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 a Examination Security Agreement Form ES-201-3 PRINT NAME 2.
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Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 04-10-17 through 04-24-17. 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.
.SJGNATURE(1)
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ES-201 Examination Security Agreement Form E-2O1-3 1.
Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 PRINT NAME 1.
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2.
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 04-10-17 through 04-24-17. 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 04-10-17 through 04-24-17 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.
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[5-2 C) I Examination Security Agreement Si A/A7U/Zt Form ES-201-3 1.
P re-ExamInation I acknowledqe that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 04-10-17 through 04-24-17 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 it the individual does not select the training content or provide director indirect feedback).
Furthermore.
I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations andlor an enforcement action against me or the facility licensee.
I will irimediately 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 04-10-17 thro9_Q424I7. From the date that I entered into this security agreement until the completion of examination administration, I did not instinct, 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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/17 NOTTS
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 04-10-17 through 04-24-1 7 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 04-10-17 through 04-24-17. 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.
PRINT NAME JOB TITLE / RESPONSIBILITY SIGNATURE(1)
DATE SIGNATURE (2)
DA E NOTE NOTES
ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Browns Ferry Nuclear Station Date of Examination:
4/10/2017 Operating Test Number:
17-03 Initials
- 1. General Criteria
b c#
a.
The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
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.)
4
$1C 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 4
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
,4 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- /( 4 3ol4andacopyisattached.
ZI..
Prin,Na e / S n ture Date a.
Author Michael Barton /
J2i7 Z//
b.
Facility Reviewer(*)
Keith Nichols /
/'
c.
NRC Chief Examiner(#)
tt 44%
d.
NRC Supervisor (c_
LI/ 5/, 7 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 Operating Test Quality Checklist Form ES-301-3 Facility:
Date of Examination:
4-/-/7 Operating Test Number: t7 03 Initials 1.
General Criteria
b*
c#
a.
The operating test conforms with the previously approved outline changes are consistent with
/,
y 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.)
T*t d.
Overlap with the written examination and between different parts of the operating test is within t%i3 4 acceptable limits.
e.
It appears that the operating test will differentiate between competent and less-than-competent A
.//j,(
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
,_-,! 4 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
() /i flit 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 j4
,4J1 S4}/
ES-301-4 and a copy is attached.
Printed Name Si atur
Date a.
Author Mi
i 17 b.
Facility Reviewer(*)
/(Jj6 AL.-
c.
NRC Chief Examiner (#)
4 1d1
d.
NRC supervisor
( f ii (i 7 NOTE:
The facility signature is not applicable for NRC-developed tests.
Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
1-
-301-3 tD Jfl,Y7
(-tL ES-301, Page 24 of 27
ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facility:
BFNS Date of Exam: 4/10/17 Scenario Numbers:
2 I 3 ( 5! 6 Operating Test No.: 17-03 QUALITATIVE ATTRIBUTES Initials b
c#
1 The initial conditions ate realistic, in that some equipment and/or instrumentation may be out of service, ( /,f but it does not cue the operators into expected events.
2.
The scenarios consist mostly of related events.
/
?L 3.
Each event description consists of a
the point in the scenario when it is to be initiated J
a the malfunction(s) or conditions that are entered to initiate the event f,%,%
a the symptoms/cues that will be visible to the crew the expected operator actions (by shift position) the event termination point (if applicable)
4.
The events ate valid with regard to physics and thermodynamics.
./
PC 5.
Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
6.
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.
4,(
Cues are given.
7.
The simulator modeling is not altered.
4 8.
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
(,t fidelity is maintained while wnning the planned scenarios.
9.
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.
10.
All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the
,ç/ /
form along with the simulator scenarios).
I
- 11. The scenario set provides the opportunity for each applicant to be evaluated in each of the applicable rating factors. (Competency Rating factors as described on forms ES-303-1 and ES.303-3.)
12.
Each applicant will be significantly involved in the minimum number of transients and events specified
,/
on Form ES-301-5 (submit the form with the simulator scenarios).
13.
The level of difficulty is appropriate to support licensing decisions for each crew position.
/4 Target Quantitative Attributes (Per Scenario; See Section D.5.d)
Actual Attributes
213/516 1.
Malfunctions after EOP entry (1-2) 1 I
2 I 2 / 2 4
2.
Abnormal events (2-4) 2 /
2 / 3
/ 2
(
C 3.
Major transients (12) 1 /
1
/
1
/ 2 si 4.
EOPs entered/requiring substantive actions (12) 2 / 2 /
2
/ 2
)
5.
EOP contingencies requiring substantive actions (0-2) 1 I 0
/
1
/
1
. (.
6.
EOP based Critical tasks (23) 2 I
2 I 2 / 2 NOTE:
The facility signature is not applicable for NRC-developed tests.
Independent NRC reviewer initial items in Column flc; chief examiner concurrence required.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Browns F4PP Date of Exam:
April 10, 2017 Operating Test No.: ILT 1703 Scenarios P
E 2
3 6
5 T
M CREW CREW CREW CREW 0
c POSITION POSITION POSITION POSITION T
A T
S A
B S
A B
S A
B S
A B
A M
R T
0 R
T 0
R T
0 R
T 0
L U
E 0
C P
0 C
P 0
C P
0 C
P R
I U
r RX 2
2
5
3 1
NOR 1
1 1
SRO-I
- 1 Bennett I/C 46 12 4
5,8 6,8,9 r
MAJ 7
7 7
3 2
TS 35 2
2 RX 2
5 2
1 NOR 1
1 1
SRO-I
- 2 Ultlsap I/C
4,6 8
4 MAJ 7
7 2
2 TS 3,5 2
2 RX 2
5 2
1 SRO-t NOR 1
1 1
- 3 Rose I/C 4,6 8
4 MAJ 7
7 2
2 TS 3,5 2
2 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 (BOPY 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 semen in the SOP 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 Appendie 0. (( Reactivity and normal evolutions maybe replaced with additional instrument or Component maffunctions on a 1-for-i basis.
3 Whenever practical, both instrument and component malfunctions should be included, oniy those that require veritable actions that provide insight to the applicants competence count toward the minimum requirements specifed for the applicants license level in the right-hand columns,
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Browns FXPP Date_of_Exam:
April_10,_2017 Operating Test_No.:_ILT_1703 Scenarios P
E 2
3 6
5 T
M CREW CREW CREW CREW 0
c POSITION POSITION POSITION POSITION T
I A
T S
A B
S A
B S
A B
S A
B A
M R
T 0
R T
0 R
T 0
R T
0 L
U E
0 C
P 0
C P
0 C
P 0
C P
R I
U RX 2
2 2
1 NOR 1
1 1
SRO-I
- 4 Spears I/C 8
4, 5 3.4,6,8 10 4
MAJ 7
7 7
3 2
TS 2,4 2
2 r
RX 2
2 2
1 NOR 1
2 1
SRO-I
- 5 Yarbrough I/C 4, 5 3,4,6,8 10 4
MA]
7 7
7 3
2 TS 2,4 2
2 pJ(
0 0
NOR 1
1 1
SRO-U
- 1 Alsup I/C C
3,4 3.4.6,8 6
2 MAJ 5
7 2
1 TS 2,4 2
2 RX 2
1 0
NOR 1
1 2
1 SRO-U
- 2 Cobb I/C 359 3 6, 8, 7
2 7
7 2
1 TS 4,6 2
2 e
RX 2
1 0
NOR 1
1
2 1
SRO-U
- 3 Humphries I/C 3,5,9 3 6, 8, 7
2 r
MAJ 7
7 2
1 TS 4.6 2
2 RX 2
1 0
NOR 1
1 2
1 SRO-U
- 4 KnIght ic 359 3, 6, 8, 7
2 MAJ 7
7 2
1 IS 4,6 2
2 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/Cl malfunctions and one maior 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 0. () 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 malfunctionu 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.
ES3O1 Transient and Event Checklist Form ES-301-5 Facility: Browns F!1PP Date_of_Exam:
April_10,_2017 Operating Test_No.:_ILT_1703 Scenarios P
E 2
3 6
5 T
M CREW CREW CREW CREW 0
c POSITION POSITION POSITION POSITION T
I A
T S
A B
S A
B S
A B
S A
B A
M R
T 0
R T
0 R
T 0
R T
0 L
U e
0 C
P 0
C P
0 C
P 0
C P
R I
U RX 0
0 NOR 1
1 2
1 SRO-U
- 5 Lambert I/C 4,6,7,8 3,9 6
2 MAJ 5,9 7
3 1
TS 2,3 2
2 RX 0
0 NOR 1
1 2
1 SRO-U
- 6 Maye I/C 4,6,7,8 3,9 6
2 MAJ 111 59 7
3 1
TS i!.
2,3 2
2 RX 0
0 NOR 1
1 2
1 SRO-U
- 7 Stephenson I/C 4,6,7,8 3,9 6
2 MAJ 5,9 7
3 1
TS 2,3 2
2 Check the applicant level and enter the operating tent 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 SRO5 must serve in both the SRO and the ATC positions, including at least two instrument or component (I/Cl 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 0.5 d) but must be significant per Section C.2.a of Appendix 0. rt 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 Competencies Checklist Form ES-301 -6 Facility:
BEN Date of Examination:
4/10/2017 Operating Test No.:
17-03 APPLI CANTS RD El RO El RD El RD El SRO-l 1 RZ SRD-l 2 Ri SRD-l 3 [
SRO-I 4
[1 SRO-U El SRO-U El SRO-U El SRO-U El Competencies SCENARIO SCENARIO SCENARIO SCENARIO i+/-
I
+1 2,1,3, 2,4,5, 2,38, 2,1,3, 2,4, 3,1,5, 2,1,3, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, inerpreu iagnose 4,9,7, 7
6 4,9,7, 5,7 7,6 4,9,7, 5,7 5,7, 4,5, 4,5,6, 6
Events and Conditions 5,6 5,6 5,6 6
8,7, 8,9,7 C
I
!9I+k
,4 2,1,3, 2,4,5, 2,3,8, 2,1,3, 2,4, 3,1,5, 2,1,3, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, ompy k
anu 497 7
6 4,9,7, 5,7 7,6 4,9,7, 5,7 5,7, 4,5, 4,5,6, 6
UseProcedures(1)
6 87,87 C
l 4
N/A 2,3,8, N/A 2,4, 3.1,5.
N/A 2,4, 3.1, 2,3, 2.1,3, 2.3,8, perace ontro 6
5.7 7,6 5,7 5.7, 4,5, 4,5,6, 6
Boards (2) 6 8,7, 8,9,7 C
+
2.1,3, 1-10 2.3,8, 2.1,3, 1-3,1.5, 2,1,3.
1-3,1, 2,3, 2,1,3.
2.3,8, ommunlcate 4,9.7, 6
4.97.
10 7,6 4,9,7.
10 5.7, 4,5, 4,5,6, 6
and Interact 5.6 5,6 5,6 6
8,7.
8.9,7 Demonstrate 2,1,7 2,1,7 2,1,7 1,2,6 Supervisory Ability (3)
Comply With and 5,6 4
4 5,6 4
4 5,6 4
4 5,6 3,5 4
Use Tech. Specs. (3)
=
=
=
=
=
Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant. (This includes all rating factors for each competency.) (Competency Rating factors as described on forms ES-303-I and ES-303-3.)
Facility:
BEN Date of Examination:
4/10/2017 Operating Test No.:
17-03 APPLICANTS RO El RO El RO El RO El SRO-I El SRO-I El SRO-I El SRO-I El SRO-U 4 SRO-U 5 El SRO-U 6 El SRO-U 7 El Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1234123412341234 I
1, 21,3, 2,4,5, 2,3,8, 2,1,
- 245, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, I rnerpre iagnose 4,9,7, 7
6 3,4, 7
7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6
Events and Conditions 5,6 9j 9,7, 6
8,7, 8,9,7 C
I Ai+k
,4 2,1,3, 2,4,5, 2,3,8, 21, 2,4,5, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, ompy IL I anu 4,9,7, 7
6 3,4, 7
7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6
Use Procedures (1) 5,6 6
8,7, 89,7 O
I N/A 2,3,8, N/A 2,4,5, 3,1,5, N/A 2,4, 3,1, 2,3, 2,1,3, 2,3,8, perace onLrol 6
7 7.6 5,7 5,7, 4,5, 45,6, 6
Boards(2)
C 2,1,3, 1-10 2,3,8, 2,1, 1-10 3,1,5, 2,1, 1-3,1, 2,3, 2,1,3, 2,3,8, ommunicaLe 4,9,7, 6
3,4, 7,6 3,4, 10 5,7, 4.5, 4,5,6, 6
and Interact 5,6 9
9,7, 6
8,7, 8,9,7 Demonstrate 2,1,7 2,
2, 1,2,6 Supervisory Ability (3)
Camply With and 5.6 4
4 5,6 4
4 5.6 4
4 5.6 3.5 4
Use Tech. Specs. (3)
=
=
Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Forv as3o-c
Facility:
BFN Date of Examination:
4/10/2017 Operating Test No.:
17-03]
APPLICANTS RO El RO El RO El RO El SRO-I 5 SRO-I El SRO-I El SRO-I El SRO-U El SRO-U 1 El SRO-U 2 El SRO-U 3 Competencies SCENARIO SCENARIO SCENARIO SCENARIO 1234123412341234 I
4 4/
2,1,3, 2,45.
2,3,8, 2,1, 2,4,5, 3,1,5.
2,1, 2,4, 3,1, 2,3, 2,1.3.
2.3,8, InLerpreu iagnose 4,9,7.
7 6
3,4, 7
7.6 3,4.
5,7 5,7, 4.5, 4,5,6.
6 Events and Conditions 5.6 9J 9,7, 6
8,7, 8.9,7 C
I AI+k 2,1,3, 2,4,5, 2,3,8, 2,1, 2,4,5, 3,1,5, 2,1, 2,4, 3,1, 2,3, 2,1,3, 2,3,8, ompy i an 4,9,7, 7
6 3,4, 7
7,6 3,4, 5,7 5,7, 4,5, 4,5,6, 6
Use Procedures (1) 5,6 9j 9,7, 6
8,7, 8,9,7 O
4 I
N/A 2,3,8, N/A 2,4,5, 3,1,5, N/A 2,4, 3,1, 2,3, 2,1,3, 2,3,8, perace ontroi 6
7 7,6 5,7 5,7, 4,5, 4,5,6, 6
Boards(2) 68,7,87 C
2,1,3, 1-/0 2,3,8, 2,1.
1-10 3,1,5.
2,1, 1-3,1, 2,3, 2,1,3, 2,3,8, ommunica1e 4,9,7, 6
3.4.
7.6 3,4, 10 5.7, 4,5, 4,5,6, 6
and Interact 5.6 9J 9
6 8,7, 8,9,7
Demonstrate 2,1,7 2,
7,1, 1.2.6 Supervisory Ability (3)
Comply VVith and 5,6 4
4 5,6 4
4 5,6 4
4 5,6 3,5 4
Use Tech. Specs. (3)
Notes:
(1)
Includes Technical Specification compliance for an RD.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Foryw S4Q
EXAM SmnPLE IAN ouijtY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
t3Ro,jAJ5 /,j*y Date of Examination:,%nRit Initials Item Task Description
1.
a.
Verifythatthe outline(s)fit(s)the appropriate model, in accordance with ES-401 or ES-401N. 7 7.
R b.
Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 or ES-401N and whether all K/A categories are appropriately sampled.
/ :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.
4 Z_
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, and major S
M 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 L
without compromising exam integrity, and ensure that each applicant can be tested using at A
least one new or significantly modified scenario, that no scenarios are duplicated from the T
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 thatthe 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 distributed W
among the safety functions as specified on the form A
(2) task repetition from the last two NRC examinations is within the limits specified on the form L
(3) no tasks are duplicated from the applicants audit test(s)
K (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 I
the form.
H R
b.
Verity 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 u
(2) at least one task is new or significantly modified G
(3) no more than one task is repeated from the last two NRC licensing examinations
H 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
,.i
- 9iL.
appropriate exam sections.
fIf ft E
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
4 N/4 1K_
R d.
Check for duplication and overlap among exam sections.
L e.
Check the entire exam for balance of coverage.
7
/L;in 2_
f.
Assess whether the exam fits the appropriate job level (RO or SRO).
a Author 4c//4&PrNam&S/L
- b. Facility Reviewer (*)
A 4
- c. NRC Chief Examiner (#)
RL41JO CAak1-L,2 7 1W:&4O 4-/5/
- d. NRC Supervisor 3çflc, Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
- Not applicable for NRC-prepared examination outlines.
FE4OI-1 ES-401, Rev. 10 BWR Examination Outline Facility
ØgO4.IAJ PEI>
Date of Exam:
14P,Q/L c
RO K/A Category Points SRO-Only Points Tier Group
K K
KJKKKAAAAG A2 G*
Total 1
2 3f4 5
6 1
2 3
4 Total 1.
1 3
3 4
4 3
20 4
3 7
Emergency&
2 12 1
1 1
1 7
2 1
3
Abnormal Plant I
N/A N/A
Evolutions Tier Totals 4
5 5 f 5
4 4
27 6
4 10 I
II I
I 1
22 232232323 26 3
2 5
2.
Plant 2
1 1
1 1
2 1
1 1
1 1
12 0
2 1
3 Systems Tier Totals 3
3 3
4 3
4 4
3 4
3 4
38 5
3 8
- 3. GenericKnowledgeandAbilities I
2 3
4 10 1
2 j
3 4
7 Categories I
I I
T I
2 J 3 J 2
3 2Jj1j 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO
,Øf.,
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). (One Tier 3 Radiation Control KIA is allowed if the K/A is replaced by a K/A from another Tier 3 Category.)
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
pf, 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
,yl1r not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
7VvG 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.
,r31 5.
Absent a plant-specific priority, only those K/As having an importance rating fIR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
,I. 6.
Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.
7.
- The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance 73i..
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
- I does not apply).
Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, 17?
and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401 2
Form ES-401-1 ES-401 BWR Examination Outline Emergency and Abnorm ant Evolutions
- Tier 1/Group 1 Form ES-401-1 EIAPE # / Name I Safety Function K
K K
A A
G*
K/A Topic(s)
IR 1231 2
295001 Partial or Complete Loss of Forced
RA2 02.
Core Flow Circulation / 1 & 4
fl-AAI.
£ - 2.l. 2
295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6
R Al. o I
295005 Main Turbine Generator Trip / 3
R
- k 3.04 5 AA2.. 03
295006 SCRAM / 1
- AA I. 0
295016 Control Room Abandonment /7
R
Ag3.o
295018 Partial or Total Loss of CCW / 8
R - AK. 0 -
S A AZ. 02
295019 Partial or Total Loss of Inst. Air / 8
S
A K3. 3 S
AA%.02.
295021 Loss of Shutdown Cooling / 4
A K L.o
295023 Refueling Acc / 8
P.
AJ<. Q.
295024 High Drywell Pressure/5
g, - EAt. f 295025 High Reactor Pressure / 3
R -
2.4. 50
295026 Suppression Pool High Water
R
Temp. / 5 295027 High Containment Temperature / 5
295028 High Drywell Temperature / 5
R
E A. 0..
295o3oLowSuppression Pool WtrLvl/5
2.4-. I t 2. 2.44
295031 Reactor Low Water Level / 2
1<1.o S
- 2. 4.. I
295037 SCRAM Condition Present and
R E J41.
Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9
R - E 1(2.0 g
600000 Plant Fire On Site I 8
R R
- 2. 4. 30
700000GeneratorVoltageand ElectricGrid
ft
s AAZo7
Disturbances / 6 K/A Category Totals:
1J14fj Group Point Total:
=
20/7 sRo 4:;
ES-401, Page 34 of 50
LIL LI DLI
]LI DLI DLI DLI DLI DLI EiD DLI LI LI LI LI LI LI LI LI LI LI LI ES-401, REV 10 AC SRO TJG1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
295001 AA2.02 3.1 3.2 FORM ES-407-1 Partial or Complete Loss of Forced LI LI LI LI LI LI Core Flow Circulation / 1 & 4 295003AA1.01 Partial or Complete Loss of AC /6 3.7 3.8 LI LI LI LI LI LI 295005AK3.04 Main Turbine Generator Trip / 3 3.2 3.2 LI LI LI LI LI 295006AA1.06 SCRAM / 1 3.5 3.6 LI LI LI LI LI LI 295016AK3.02 Control Room Abandonment/7 3.7 3.8 LI LI LI LI LI 295018AK2.02 Partial or Total Loss of CCW / 8 3.4 3.6 LI LI LI LI LI 295019AK3.03 Partial or Total Loss of Inst. Air / 8 3.2 3.2 LI LI ] LI LI LI 295021AK1.01 Loss of Shutdown Cooling / 4 3.6 3.8 LI LI LI LI LI 295023AK202 Refueling Ace Cooling Mode / 8 2.9 3.2 LI LI LI LI LI 295024EA1.14 High Drywell Pressure/5 3.4 3.5 LI LI LI LI LI LI 295025G2.4.50 High Reactor Pressure / 3 4.2 4.0 LI LI LI LI LI LI LILI LID DLI DLI LILI LID LID LID LID LID LI Neutron monitoring A.C. electrical distribution system Main generator trip CRD hydraulic system Turbine trip Plant operations Service air isolations: Plant-Specific Decay heat Fuel pool cooling and cleanup system Drywell ventilation system Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Page 1 of 2 04/13/2016 9:32 AM
295026EA2.02 Suppression Pool High Water Temp. /
5 295028EA2.02 High Drywell Temperature / 5 295030G2.4.1 Low Suppression Pool Wtr Lvi / 5 295037EK1.02 SCRAM Condition Present and Power Above APRM Downscale or Unknown
/1 295038EK2.08 High Off-site Release Rate I 9 600000G2.4.35 Plant Fire On Site / 8 295004AA1.O1 Partial or Total Loss of DC Pwr / 6 295031EK1.03 Reactor Low Water Level / 2 FORM ES-401-1 Suppression pooi level Reactor pressure Knowledge of EOP entry conditions and immediate action steps.
Reactor water level effects on reactor power SPDS/ERIS/CR1DS/GDS: Plant-Specific Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects D.C. electrical distribution systems Water level effects on reactor power ES-407, REV 10 RO SRO T1GJ BWR EXAMINATION OUTLINE 3.8 3.9 KA NAME / SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
DDDDDDDDDD 3.8 4
4.8 414.3 2.6 3.1 3.8 4.0 a33.4 3.7 4.1 700000AK3.02 Generator Voltage and Electric Grid Distrurbancecs 3.6 3.9 Actions contained in abnormal operating procedures for voltage and grid disturbances Page 2 of 2 04/13/2016 9:32 AM
Ability to explain and apply all system limits and precautions.
Ti-valve-position.
Cooling water temperature 29501 9AA2.02 Partial or Total Loss of Inst. Air / 8 3.63.7 Status of safety-related instrument air system loads (see AK2.1
- AK2.19)
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 Knowledge of annunciators alarms, indications or response procedures 700000AA2.07 Generator Voltage and Electric Grid 3.6 4.0 D
Distrurbancecs DDE DDE D ED Operational status of engineered safety features ES-401, REV 10 (T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 295003G2132 Partial or Complete Loss of AC /6 3.8 4.0 5005AP03 MatrrTuriT G&iera or rip / 3
-&-13:t Z9p24AZo3 thy JetIPw FORM ES-401-1 29501 8AA2.02 Partial or Total Loss of CCW / 8 3.1 3.2 D D D D D D D [ D D D 295030G2.2.44 Low Suppression Pool Wtr Lvl / 5 4.2 44D 295031G2.431 ReactorLowWaterLevel/2 4.2 4.1 D D D D D D D D D El Page 1 of 1 04/13/2016 9:32AM
ES4OI 3
Form ES-401-f ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions
- Tier 1/Group 2) SRO)
E/APE # / Name / Safety Function K
K K
A A
G*
KIA Topic(s)
IR 12312 295002 Loss of Main Condenser Vac / 3
- S C 2. 4. g R
295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2
- 2.. 1. 32.
2 95009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperatute / 5 P.
295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cant. Isolation / 5 & 7 f
P..-
Aj4I.° 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr LvI / 5 295032 High Secondary Containment Area Temperature / 5
a R-6A.oi 295033 High Secondary Containment Area Radiation Levels/9 S - BA2..03 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High R
P..
l43. Op.
Differential Pressure / 5 295036 Secondary Containment High S
03 Sump/Area Water Level / 5
500000 High CTMT Hydrogen Conc. / 5
K/A Category Point Totals:
I Group Point Total:
7/3 ES-401, Page 35 of 50
FORM ES-407-1 ES-401, REV 70 T1G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G RO Sf0 295007AK2.03 High Reactor Pressure / 3 3.1 3.2 El El El El El El El El El L]
295008G2.1.32 High Reactor Water Level / 2 3.8 4.0 El El El El El El El Li El El 29501 3AK0l High Suppression Pool Temp./5 3.6 3.7 El [l El El El El El El El El El 295015AA1.04 lncompleteSCRAM/l El El El El El El El El El El 295022AK1 02 Loss of CRD Pumps / 1 3.6 El El El El El El El El El El 295033EA2.01 High Secondary Contaiment Area 3.8 3.9 El El El El El El El [ El El El Radiation Levels I 9 295035EK3.02 Secondary Containment High 3.3 El El El El El El El El El El Differential Pressure / 5 TOPIC:
RHR/LPCI: Plant-Specific Ability to explain and apply all system limits and precautions.
Suppression pool cooling Rod control and information system: Plant-Specific...
Reactivity control Area radiation levels Secondary containment ventilation response Page 1 of 1 04/13/2016 9:32 AM
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ES-401 4
Form ES-401-1 ES-401 BWR Examination Oflie F
ES 4 1
=
Plant Systems-]ier 2/Gp 1 orm 1 System #1 Name K
K K
K K
K A
A A
A G*
K/A Topic(s) 203000 RHR/LPCI:
Injection
R
Mode 205000 Shutdown Cooling 1
R..o
2O6000HPCI
S SA 207000 Isolation (Emrgency)
Condenser
2O9001LPCS
209002 HPCS
211000SLC
R-3P3 Sc...4.4j
212000 RPS
R R-G2..4.4
R-J3.O 2150031RM
c
215004 Source Range Monitor
R
R 1(2.01
215005APRM/LPRM
217000RCIC
R-I4.D3 S
Pi2..15
218000 ADS
c2.4.%
223002 PCIS/Nuclear Steam
R A2.D$
Supply Shutoff 239002SRVs t5o4-
259002 Reactor Water Level g
A I. 03
Control 261000 SGTS R
- JLI.o3
262001 AC Electrical
A3.o
Distribution 262002 UPS (AC/DC)
R AJ.D.-
263000 DC Electrical
A I.
I
Distribution
I.4. D.
264000 EDG5 R
ICI.V4 5-A2.D2.
300000 lnstwment Air
400000 Component Cooling
Water K/A Category Point Totals:
2I i 13 2 3 Group Point Total:
26/5 ES-401, Page 36 of 50
ES-401, REV 10 T2G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 2o3000A2.02 3.5 3.5 Pump trips FORM ES-401-1 RHR/LPCI: Injection Mode El El El El El El El El El El 205000K2O1 Shutdown Cooling 3.1 3.1 El F El El El El El El El El El Pump motors 206000A3.02 HPCI 3.8 3.8 El El El El El El El El [ El El System Flow: BWR-2,3,4 2O6OOO4 HPCI
-&4 3*4DElElElElElElDElEl 4z 4,3 209001G2.1.23 LPCS 4.3 4.4 El El El El El El El El El El Ability to perform specific system and integrated plant procedures during all modes of plant operation.
21 1000K3.03 SLC 2.6 2.7 El El El El El El El El El El Core plate differential pressure indication 212000G2.4.46 RPS 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.
212000K3.06 RPS 4.0 4.1 El El El El El El El El El El Scram air header solenoid operated valves 215003A4.02 IRM 2.9 2.8 El El El El El El El El El El CRT display indications: Plant-Specific 215003K4.02 IRM 4.0 4.0 El El El El El El El El El El Reactor SCRAM signals 215004K2.O1 Source Range Monitor 2.6 2.8 El El El El El El El El El El SRM channels/detectors Page 1 of 3 04/13/2016 9:32AM
262001A3.01 AC Electrical Distribution 262002A1.02 UPS (AC/DC) 263000A1.01 DC Electrical Distribution LPRM back panel switches, meters and indicating lights Prevents pump over heating Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Surveillance testing Reactor water level Tail pipe temperature monitoring
! k)L tr) IIG/L ;-d1I?
Suppression pool Breaker tripping Motor generator outputs Battery charging/discharging rate ES-401, REV 10 RO SRO 2G1 BWR EXAMINATION OUTLINE 21 5005A4.04 APRM / LPRM 3.2 3.2 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
217000K4.03 RCIC 218000G2.4.35 ADS FORM ES-401-7 223002A2.08 PCIS/Nuclear Steam Supply Shutoff 239002A3.07 SRVs 239002K5.04 SRVs 259O02M0e Reactor Water Level Control 3t Aio1-261000K1.03 SGTS DDDDDDDD 2.9 3.0
2.7 3.1 3.8 3.9 DL1E1L1DL 3.3 3.5
-34 3, 2.9 3.1 3.1 3.2 a52.9 5
2.8DDDDD DDE Page 2 of 3 04/13/2016 9:32 AM
ES-407, REV 10 KA NAME I SAFETY FUNCTION:
263000K4.02 DC Electrical Distribution 264000K1.04 EDGs 300000K5.O1 Instrument Air 4000001<6.05 Component Cooling Water (A.f)
çLO T2G1 BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G P0 SRO 3.1 3.5 3.2 3.3 2.5 2.5 ao3.1 FORM ES-401-7 TOPIC:
Breaker interlocks,permissives, bypasses and cross ties:
Plant Specific Emergency generator cooling water system Ah compressors Pumps Page 3 of 3 04/13/2016 9:32AM
FORM ES-407-7 (T2G7 BWR EXAMINATION OUTLINE IA Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
AC SRO 3.9 4.2 THigh suppression pooi temperature: BWR-2,3,4 classtficattons.
r f/%*
L4-e 4-Ls 11-e.
Ability to diagnose and recognize trends in an accurate
and timely manner utilizing the appropriate control room reference material.
3.8 3.8 jj Steam line break
- z;;;
,1\\2,o7 ES-401,_REV 10 KA NAME I SAFETY FUNCTION:
206000A2.08 HPCI 211OOOG,4,43-. SLC 215003G2.447 lAM 4.2 4.2 217000A2.15 RCIC 264OOOAe EDGs A27 6, 7Of/
34&1
.36 3,(;7 Page 1 of 1 04/13/2016 9:32 AM
ES-401 5
Form ES-401-1 ES-401 BWR Examination OuSin Form ES-401-1
=
Plant Stems -Tier 2/Grop2=
System # / Name K
K K
K K
K A
A A
A G*
K/A Topic(s)
IR 201001 CRD Hydraulic
201002 RMCS 201003 Conttol Rod and Drive Mechanism 201004 RSCS 201005 RCIS
201006 RWM 202001 Recirculation
202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 3
-A3.3
-2.4,sO 215001 Traversing In-Core Probe 215002 RBM 216000 Nuclear Boiler Inst.
219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Al. 0+
Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment R-AdQ 239001 Main and Reheat Steam 239003 MSIV_Leakage_Control 241000 Reactor/Turbine Pressure Regulator
245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate 259001 Reactor_Feedwater 268000 Radwaste AO!
271000 Offgas 272000 Radiation Monitoring
c
46.2.Df-
286000 Fire_Protection 288000 Plant Ventilation 290001 Secondary CTMT 0+
290003 Control Room HVAC 290002 Reactor Vessel Internals K/A Category Point Totals:
PD I
I [ t I
- 2. [ I j I I
[ If Group Point Total:
12)3 I
ES-401, Page 37 of 50
ES-407, REV 70 T2G2 BWR EXAMINATION OUTLINE FORM ES-407-7 KA NAME/SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
ELIDED ELIDED ELIDED DDD1D DDDED DDED ED ED DDED ELIDED DE1DD RO SRO 201006K5.07 RWM 2.8 2.9 3.5 3.5 202001 K4.07 Recirculation 202002K2.02 Recirculation Flow Control 215001A3.03 Traversing In-core Probe 226007 K3.02 RHR/LPCI: CTMT Spray Mode 230000A1.o4 RHR/LPCI: Torus/Pool Spray Mode 239001 K6.06 Main and Reheat Steam 245000K6.04 Main Turbine Gen. / Aux.
268000G2.1.32 Radwaste 271000A2.01 Otfgas 288000A4.02 Plant Ventilation EDDD 2.8 2.9 DDDE 2.6 2.6 EEL1D 2.5 2.6 ELIDED ED LIE ELIDED ELIDED ELIDED 8
3.1 3.3 ELIDED 3.2 3.3 3.8 3.9 Latch groups: P-Spec(Not-SWR6)
Motor generator set trips: Plant-Specific CVFb -Fv-p.)
LI Hydraulic power unit: Plant-Specific (VFI)
Valve operation: Not-BWR1 E
LI LI Hydrogen cooling Ability to explain and apply all system limits and precautions.
Low condenser vacuum Containmentldrywell/suppression chamber temperature System flow 2.6 2.7 MSIV isolation signal 2.8 2.8 DEELIELIDLILID Area temperature Page 1 of 2 04/13/2016 9:32 AM
T2G2 BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G HO SRO 3.7 3.9 ES-401, REV 70 KA NAME I SAFETY FUNCTION:
290001 Ki.04 Secondary CTMT TOPIC:
SBGT FORM ES-407-1 Page 2 of 2 04/13/2016 9:32AM
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ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401 -3 Facility:
ROLL) li5 PEI4.I Date of Exam:
/4PR L 9_C)i 7 Category K/A #
Topic RO SRO-Only 2.1.5 t %
iR IR 2.1.
Ad.1 1-inJer re md&, 9toh ed:.
3.9 1
2.1.
Conduct of 2.1. 17 4tc.L4.rt-, Leac) CXh6.Q1TYfS
.0 Operations 2.1. %2 3.
2.1.
Subtotal 2.2. 4r (iti c-2.2.43 Prv-ces5 4o k-3 w)4te iLjt 2.
2.2.44 37t C4c4flt,.
r?I.f sh7IzLc...
4.2 Equipment 2.2.
Control 2.2. 6 a
2.2.3S c
c/Lkdot ;tc&1j La 45 Subtotal 2.3.12 Aa1S4djprrcptespe4zi7iitq-/v L0. dds.Z 2.3. P5 RiL nwii*rf IcrLc 3.
2.3.
23 16 Ri). m1l*rsn.f S4e*ix
- 3. /
Subtotal 2.4,f proet&feC 3.4..
2.4. ST t.hf a.cttwriiy 4cr?f -i1a 3.t 4.
2.4.3Y p.o rf.p4Jrhe6-E-pla.ei 3..?
Emergency Procedures /
2.4.
Plan 2.4.2 ceA-vt., ka4 A -A-dw 2.4.40 Subtotal Tier3PointTotal (7)
ES-401, Page 43 of 50
T3 BWR EXAMINATION OUTLINE 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
j Knowledge of shift or short term relief turnover practices.
j (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.
Knowledge of the process used to track inoperable alarms 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 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties 2.9 3.1 Knowledge of radiation monitoring systems(eAe1.1 a4d-tIk) as 3.4 3.9 Knowledge of fire in the plant procedures.
3.0 4.1 Knowledge of the lines of authority during implamentation of an emergency plan.
3.9 3.8 Knowledge of the ROs responsibilities in emergency plan implementation.
ES-407, REV 70 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
PC SRO G2.1.25 FORM ES-401-3 Conduct of operations G2.1.3 Conduct of operations 62.2.4 Equipment Control 3.6 3.6 G2.2.43 Eqpment Control 3.0 3.3 62.2.44 Equipment Control 4.2 4.4 LIDD 62.3.12 Radiation Control 3.7 3.9 LID ED ED DDE DEE DDE DDE G2.3.15 Radiation Control G2.4.27 Emergency Procedures/Plans G2.4.37 Emergency Procedures/Plans 62.4.39 Emergency Procedures/Plans Page 1 of 1 04/13/2016 9:32AM
ES-407, REV 10 (T3 BWR EXAMINATION OUTLINE FORM ES-407-3 KA NAME / SAFETY FUNCTION:
JR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO G2.1.17 Conductof operations 3.9 4.0 G2.1.26 Conduofopemtions 3.4 3.6
[]
Ga2.38 Equipment Control 3.6 El El El El El El El El El El G2.2.5 Equipment Control 2.2 3.2 El El El El El El El El El El G2.3.15 Radiation Control 2.9 3.1 El El El El El El El El El El Emergency Procedures/Plans 45 4S El El El El El El ElElEl 4-G2A.40 Emergency Procedures/Plans 2.7 4.5 El El El El El El El El El El TOPIC:
Abthtyto make accurate, clear and concise verbal reports.
Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
Knowledge of conditions and limitations in the facility license.
Knowledge of the process for making design or operating changes to the facility Knowledge of radiation monitoring systems (r.ç, p(a.t wkk ccn1itiQn
)ie,,ud Knowledge of the SROs responsibilities in emergency plan implementation.
Page 1 of 1 04/13/2016 9:32 AM
ES-403 Written Examination Grading Form ES-403-1 Quality Checklist Facility:
Date of Exam:
Exam Level:
RO SRO Item Description Initials a
b c
1.
Clean answer sheets copied before grading fr_
2.
Answer key changes and question deletions justified and documented 3.
Applicants scores checked for addition errors (reviewers spot check> 25% of examinations) 4.
Grading for all borderline cases (80 +/-2% overall and 70 or 80, JJ as applicable, +/-4% on the SRO-only) reviewed in detail
/4 5.
All other failing examinations checked to ensure that grades are justified 6.
Performance on missed questions checked for training p1 deficiencies and wording problems; evaluate validity of 1
7 questions missed by half or more of the applicants (V
a.
Grader b.
Facility Reviewer(*)
Printed Name/Signature lAc,JA 7.i9)Jl2Y t Date
- 17
//7 c.
NRC Chief Examiner (*)
RL4Mb d.
NRC Supervisor(*)
t(t7
(*)
The facility reviewers signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
ES-403, Page 6 of 6
hlU Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 February 6, 2017 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention:
Mr. Eugene F. Guthrie 10 CFR4O(b)(3) 10 CFR 55.5 10 CFR 55.49
Subject:
Browns Ferry Nuclear Plant, Units 1, 2, and 3 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Submittal of Initial Operator Licensing Examination
Reference:
Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant - Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, and 05000296/2017301, dated October 27, 2016 In accordance with the referenced letter and NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, the Tennessee Valley Authority is providing the written test and supporting reference materials for the upcoming license examination.
The Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Initial Operator Licensing Examination is scheduled for the week of April 10, 2017.
In order to meet the examination schedule, the NRC requested that BFN furnish this examination material by February 6, 2017.
See the attached enclosure for the Reactor Operators and Senior Reactor Operators examinations.
I,.
Ms. Catherine Haney Page 2 February 6, 2017 In accordance with Title 10 of the Federal Code of Regulations (10 CFR) 55.49, and NUREG-1 021, appropriate measures have been taken to ensure examination integrity and security. Accordingly, it is requested that this letter and the enclosed documents will be withheld from public disclosure until the examinations are completed.
There are no commitments contained in this submittal. Should you have any questions regarding this matter, please contact Mr. Michael Barton, at (256) 729-2783.
Written Examination and Supporting Reference Materials
- Operator License Examination Scheduled for the Week of April 24, 2017
Enclosure:
Ms. Catherine Haney Page 3 February 6, 2017 MWO: RWC bcc: (wlo Enclosure)
M. A. Barton A. S. Bergeron G. A. Boerschig D. L. Hughes W. L. Parker G.E.Pry J. W. Shea C. L. Vaughn EDMS
Withhold the Enclosure from Public Disclosure in Accordance with NUREG-f 021 Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1,2, and 3 Written Examination and Supporting Reference Materials - Operator License Examination Scheduled for the Week of April 24, 2017 This enclosure contains the following information:
- 1. A notebook containing the following:
ES-201-1, Examination Preparation Checklist ES-201-2, Examination Outline Quality Checklist ES-201-3, Examination Security Agreement ES-301-J, Administrative Topic Outline ES-301-2, Control Room/In-Plant Systems Outline ES-301-3, Operating Test Quality Checklist ES-301-4, Simulator Scenario Quality Checklist ES-301-5, Transient and Event Checklist ES-301-6, Competencies Checklist ES-401-4, Record of Rejected K/As ES-40J-6, Written Examination Quality Checklist ES-DI, Scenario Outline ES-D2, Required Operator Actions Written Examination with References
- 2. Compact disk containing the examination and references
s I I 1i Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Match 10, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention:
Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos, DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Preliminary Senior Reactor Operator (SRO) Licensee Application Information
Reference:
Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, 05000296/2017301, dated October 27, 2016 In accordance with the above referenced NRC letter dated October 27, 2016, the Tennessee Valley Authority (WA) is providing preliminary Senior Reactor Operator (SRO) Licensee application information that is to be submitted 30 days prior to the SRO examination date of April 10, 2017.
The enclosure contains the preliminary (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.
The enclosure to the letter is considered by the WA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
Ms. Catherine Haney Page 2 March 10, 2017 There are no new regulatory commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.
Respectfully, Vice President
Enclosure:
Preliminary Senior Reactor Operator (SRO) Licensee Application Information
Jdim Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 March 23, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention:
Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Final Senior Reactor Operator (SRO) Licensee Application Information
Reference:
Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 05000260/2017301, 05000296/2017301, dated October 27, 2016 In accordance with the above referenced NRC letter dated October 27, 2016, the Tennessee Valley Authority (TVA) is providing finalized Senior Reactor Operator (SRO) Licensee application information that is to be submitted 14 days prior to the SRO examination date of April 10, 2017.
The enclosure contains the final (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.
The enclosure to the letter is considered by the WA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
MAR 2 4.U ii
Ms. Catherine Haney Page 2 March 23, 2017 There are no new regulatory commitments in this letter. Should you have any questions regarding this matter, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.
Respectfully,
Enclosure:
Final Senior Reactor Operator (SRO) Licensee Application Information
-J
Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 April 4, 2017 10 CFR 55.5 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 Attention:
Mr. Eugene F. Guthrie Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Updated final Senior Reactor Operator (SRO) Licensee Application Information
References:
1.
Letter from the Nuclear Regulatory Commission to the Tennessee Valley Authority, Browns Ferry Nuclear Plant Notification of Licensed Operator Initial Examination 05000259/2017301, 0500026012017301, 05000296/2017301, dated October 27, 2016 2.
Letter from the Tennessee Valley Authority to the Nudear Regulatory Commission, Final Senior Reactor Operator (SRO) Licensee Application Information, dated March 23, 2017 In accordance with the above referenced NRC letter dated October 27, 2016 (Reference 1), the Tennessee Valley Authority (WA) provided finalized Senior Reactor Operator (SRO) Licensee application information that was to be submitted 14 days prior to the SRO examination date of April 10, 2017 (Reference 2).
However, due to an administrative error, the personal qualification statement forms (NRC Form 398) were unsigned by the applicants.
The enclosure contains the final (signed) personal qualification statement form (NRC Form 398) and certification of medical examination form (NRC Form 396), for the SRO candidates.
Ms. Catherine Haney Page 2 April 4, 2017 The enclosure to the letter is considered by the TVA to be of a personal nature and, as such, is to be withheld from public disclosure in accordance with 10 CFR 2.390fa)(6).
There are no new regulatory commitments in this letter. Should you have any questions regarding this mailer, please contact Mr. Christopher L. Vaughn, at (256) 729-3439.
Enclosure:
Final Senior Reactor Operator (SRO) Licensee Application Information
Ms. Catherine Haney Page 3 April 4, 2017 MWO:RWC bcc: (wlo Enclosure)
A. S. Bergeron R. A. Evans D. L. Hughes W. L. Parker G.E.Pry J.W. Shea M. C. Tharpe C. L. Vaughn EDMS
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 May 1,2017 Ms. Catherine Haney Regional Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1 257 Attention: Mr. Eugene F. Guthrie 10 CFR 55.5 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Subject:
Senior Reactor Operator Initial License Written Examinations
- Post Examination Response The Tennessee Valley Authority (WA) administered the final NRC Written Examination for the Browns Ferry Nuclear Plant Senior Reactor Operator Initial License Training (ILT) on April 10, 2017. The supporting documentation specified by Section ES-501 of NUREG 1021, Revision 10, Operator Licensing Examination Standards for Power Reactors, for Initial Post-Examination Activities is enclosed. The enclosures content listing is provided at the end of this letter.
The NRC Form ES-201-3, will be forwarded to the NRC as soon as it is completed.
The enclosures to this letter are considered by WA to be of a personal nature and, as such, are requested to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
There are no commitments contained within this letter.
Ms. Catherine Haney Page 2 May 1,2017 Should you have any questions regarding this matter, please contact Mr. Michael Barton, at (256) 729-2783.
- Form ES-403-1, Written Examination Grading Quality Checklist
- Graded Written Examinations (Each Applicants Original Answer and Examination Cover Sheets) and a Clean Copy of Each Applicants Answer Sheet
- Questions Asked By and Answers Given to the Applicants During the Written Examination
- Examination Seating Chart
- Results of Written Examination Performance Analysis that was Performed
- Master Examination Answer Key, Annotated to Indicate any Changes Made While Administering and Grading the Exam inations
- Facility Comments made in accordance with ES-501
- Correction to Nuclear Regulatory Commission Letter dated April 17, 2017 List of Applicants
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Enclosures:
Ms. Catherine Haney Page 3 May 1,2017 MWO:MNK Enclosures bcc: (wlo Enclosure)
M. A. Barton G. A. Boerschig A. S. Bergeron D. L. Hughes J. W. Shea C. L. Vaughn EDMS