ML17181A334
| ML17181A334 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/2017 |
| From: | Eugene Guthrie Division of Reactor Safety II |
| To: | William Gideon |
| References | |
| ER 2015301 | |
| Download: ML17181A334 (48) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 15, 2015 William R. Gideon Brunswick Steam Electric Plant Vice President Brunswick Steam Electric Plant P.O. Box 10429 Southport, NC 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - NOTIFICATION OF LICENSED OPERATOR INITIAL EXAMINATION 05000325/2015301 AND 05000324/2015301
Dear Mr. Gideon:
In a telephone conversation on May 12, 2015, between Mr. Robert Bolin, Examination Development Coordinator, Mr. Louis Sosler, Examination Author, and Mr. Richard S. Baldwin, Senior Operations Engineer, arrangements were made for the administration of licensing examinations at the Brunswick Steam Electric Plant. The operating test is scheduled to be administered during the weeks of November 30, 2015 and December 7, 2015. The written examination is scheduled to be administered the week of December 14, 2015. The on-site preparatory week is scheduled for the week of November 2, 2015.
As agreed during the telephone conversation, your staff will prepare both the operating test and written examinations based on the guidelines in Revision 10, of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The U.S. Nuclear Regulatory Commission (NRC) regional office will discuss with your staff any changes that might be necessary before the examinations are administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination.
To meet the above schedule, it will be necessary for your staff to furnish the operating test outlines by September 1, 2015. Mr. Philip Capehart provided written examination outlines to your staff in February 2015. The written examinations, operating test and the supporting reference materials identified in Attachment 3 to ES-201 will be due by October 1, 2015.
Pursuant to Title 10, Section 55.40(b)(3), of the Code of Federal Regulations (10 CFR 55.40(b)(3)), an authorized representative of the facility licensee shall approve the examinations, and test before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use.
We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Any delay in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.
R. Gideon 2
In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.
Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.
To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),
and waiver requests (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the first examination date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.
This letter contains information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by OMB under approval number 3150-0018, which expires on April 30, 2016. The public reporting burden for this collection of information is estimated to average 2500 hours0.0289 days <br />0.694 hours <br />0.00413 weeks <br />9.5125e-4 months <br /> per response, including the time for reviewing instructions, gathering and maintaining the data needed, writing the examinations, and completing and reviewing the collection of information. Send comments on any aspect of this collection of information, including suggestions for reducing the burden, to the Information and Records Management Branch (T-6 F33), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by Internet electronic mail at BJS1@nrc.gov; and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and Budget, Washington, DC 20503.
The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection, unless it displays a currently valid OMB control number.
In accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRCs Rules of Practice, a copy of this letter and its enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room).
R. Gideon 3
Thank you for your cooperation in this matter. Mr. Robert Bolin has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the NRC's examination procedures and guidelines, please contact Mr. Richard S. Baldwin at (404) 997-4642, (Internet E-mail: Richard.Baldwin@nrc.gov), or me at (404) 997-4662, (Internet E-mail:
Eugene.Guthrie@nrc.gov)
Sincerely,
/RA/
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62 cc: Distribution via Listserv
_ML15138A340________________
SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE VIA EMAIL EFG NAME BALDWIN GUTHRIE DATE 5/13/2015 5/ 15 /2015 5/ /2015 5/ /2015 5/ /2015 5/ /2015 5/ /2015 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO
ES-201 Examination Preparation Checklist Form ES-201-1 Facility:
Brunwick Date of Examination:
12/2015 Developed by:
Written:
Facility NRC II Operating Facility NRC Chief Target Task Description (Reference)
Examiners a e Initials
-180 1.
Examination administration date confirmed (Cia; C.2.a and b)
RSB
-150 2.
NRC examiners and facility contact assigned (C.1.d; C.2.e)
RSB
-150 3.
Facility contact briefed on security and other requirements (C.2.c)
RSB
-150 4.
Corporate notification letter sent (C.2.d)
RSB
[-jj 5.
Reference material due fC.i.e; C.3.c; Attachment 3)
RSB
{-9Q}
6.
Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-3d-i, RSB ES-3o1-2, ES-301-5, ES-D-1, ES-401-1/2, ES-401 N-1/2, ES-401-3, ES-401 N-3, ES-401-4, and ES-401N-4, as applicable (C.1.e and f; C.3.d)
{-I 7.
Examination outline(s) reviewed by NRC and feedback provided to facility licensee RSB (C.2.h; C.3.e)
{-
8.
Proposed examinations (including written, walk-through JPMs, and scenarios, as RSB 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-301-1, or ES-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)
RSB
-30 10.
Preliminary license applications (NRC Form 398s) due (Cli; C.2.g; ES-202)
RSB
-21 11.
Examination approved by NRC supervisor for facility licensee review(C.2.h; C.3.f)
RSB
-21 12.
Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)
RSB
-14 13.
Final license applications due and Form ES-201-4 prepared (Cli; C.2.i; ES-202)
RSB
-14 14.
Written examinations and operating tests approved by NRC supervisor (C.2.i; RSB C.3.h)
-7 1 5.
Facility licensee management queried regarding the licensees views on the RSB examination. (C.2 j)
-7 16.
Final applications reviewed; 1 or 2 (if >10) applications audited to confirm RSB qualifications I eligibility; and examination approval and waiver letters sent (C.2.i; ; ES-202, C.2.e; ES-204)
-7 17.
Proctoring/written exam administration guidelines reviewed with facility licensee RSB (C.3.k)
-7 18.
Approved scenarios, job performance measures, and questions distributed to NRC RSB examiners (C.3.i)
- Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter.
They are for planning purposes and may be adjusted on a case-by case basis in coordination with the facility licensee.
[Applies only] {Does not apply} to examinations prepared by the NRC.
ES-201, Page 25 of 28
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Brunswick Nuclear Plant Date of Examination: Dec 2015 Initials Item Task Description
a b*
c#
-t-1.
a.
Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401 or ES-401 N. /. tJ IA b.
Assess whether the outline was systematically and randomly prepared in accordance with T
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.
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, 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 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 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 T
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 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 appropriate exam sections.
G E
b.
Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
c.
Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.
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,j 1ev I (RO o SRO).
- a. Author Lou Sosler n
i
- b. Facility Reviewer (*)
Jerry Pierce
- 4. /
Chf Examiner (#)
co Note:
- Independent NRC reviewer initial items in Column c; chief examiner concurrence required.
Not applicable for NRC-prepared examination outlines.
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U ES-201 Examination Security Agreement Form ES-201-3 1.
Pre-Examination If ii5 I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of
/
as of the date of my signature.
I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner.
I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2.
Post-Examination To the best of my k,noled, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of :!)t
- ?,D Q/5From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or prdvide 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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D 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 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 PRINTED NAME 1.
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To the best of mj.knowJeq/I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of t2//.S/tY.
From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or prdvidé performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
C vL S GNATURE (1)
DATE SIGNL)RE(2) 7/74 Jck:,
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a ES-201 Examination Security Agreement Form ES-207-3 7.
Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature.
I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner.
I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2.
Post-Examination To the best of my know)edge,,l SJi. not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) ott//7Z/tc7i5 From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or p(ovide prformance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)
DATE SIGNATURE (2)
DATE NOTE 1.
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a ES-201 Examination Security Agreement Form ES-207-3 1.
Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of as of the date of my signature.
I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner.
I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.
I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
2.
Post-Examination To the best of my knovledg, j,dj-not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) 0V/,%i2/tc/6S. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or roviUetperformance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.
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NOTES:
ES-301 Operating Test Quality Checklist Form ES-301-3 Facility Brunswick Dale of Examinalion:
1 1!3W201 5 Operating Test Number:
- 1. General Criteria Intals a,
The operating lest conforms with the previously approved outline, changes are consistent with sampling requirements (e.g., 10 CFR 55A5 operational Importance, safety function distribution).
I b
There is no day-to.day repetition between this and other operating tests to be administered during this examination c.
The operating test shah not dupilcata items from the applicants audit test(s). Isee Section D.1.a.) 4 ZL d
Overlap with the written examination end between different parts of the operating test is within acceptable lknlts.
a.
It appears that the operating test will differentiate between competent and less.than-compelent afiplicants at the designated license level
- 2. WaIk-Thtou9h 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 stepsff 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., Hem 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 3Ol4andacopylsattached.
ii
a Author
-t-b.
Facility Revlewer()
Jerry Pirc L%p
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c.
NRC Chief Examiner (N) C Li j.1J)&I j/, 4zL44 Z_
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d.
NRC Supervisor Qf,1c(I ii (LSE NOTE:
The facility signature is not applicable for NRC-developed tests
- Independent NRC reviewer initial items In Column c: chief examiner concurrence reqtired.
ES-301 Simulator Scenario Quality Checklist Form ES-307-4 Facility: Brunswick Date of Exam 11)30/2015 Scenario Numbers, 1 / 2/3)4 Operatinc Test No.:
QUAUTATIVE ATtRIBUTES lniaIs a
b cii 1.
The Initial conditions are realistic. In that some equipment and/or Instrumentation may be out at service, z7) but It does not cue the operators Into expected events.
2.
The scenarios consist mostly of related events 3.
Each event description consists of the point In the scenario when It is to be Initiated the malfunction(s) or conditions 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.
The events are valid with regard to physics and thermodynamics.
I 5.
Sequencing and timing of events Is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
b 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.
Cues are given.
7.
The snulator modeling Is not altered.
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 fidelity Is maintained while running the planned scenarios.
9.
Every operator will be evaluated using at least one new or significantly modified scenario. All other 4/
scenarios have been altered In accordance with Section D.5 of ES-3d.
10.
All Individual operator competencles can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
1 1. 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 jt on Form ES-301 -5 (submit the form with the simulator scenarios).
L_
- 13. The level of difficulty Is appropriate to support licensing decisions for each crew position.
Target Quantitative Attributaz (Per Scenario; See Section D.5.d)
Actual Attributes
1.
MalfunctIons after EOP entry (1.2) 2 / 3/2/2 2.
Abnonnalevents(2-4) 2/4/4/2 3.
Majortranslents(12) 1/2/2/2 4.
EOPs entered/requiring substantive actions f 12) 2 / 2 / 2 / 2
5.
EOP contingencies requiring substantive actions (0-2) 1 / 2 / 2 / 2 6.
EOPbasedCnticaltasks(23) 3/2/2/2 NOTE:
The facility signature Is not applicable for NRC-developed tests.
N Independent NRC reviewer initial items In Column c; chief examiner concurrence required.
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Brunswick Nuclear Plant Date of Exam: Nov/Dec 2015 Operating Test No.: Final A
E Scenarios P
V
P E
1 2
3 4
T M
1j CREW POSITION CREW POSITION CREW POSITION CREW POSITION I
C T
A T
S A
B S
A B
S A
B S
A B
A M
N Y
R T
0 R
T 0
R T
0 R
T o
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T P
0 C
P 0
C P
0 C
P 0
C p
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E RX 3
3 2110 NOR 1
1 2
3 1
1 1
SRO-I1 I/C 2,4,5,6, 2,4,5,6, 1,4,5,6, 17 4
4 2
9 9
7910 Roel
Brusselmans MAJ 6,7 7,8,10, 8,11,13 9
2 2
1 11 TS 2,5 4,6 4
0 2
2 RX 5
3 3
3110 SROI2 NOR 1
1 2
1 1
1 I/C 2,3,4,5, 4,6,9 1,4 12 4
4 2
Patrick 6,8,9 Sena MAJ 6,7 7,8 8,11,13 7
2 2
1 TS 3,4 2022 RX 3
1110 NOR 1
1111 SRO-U2
I/C 2,4,5,6, 5
4 4
2 Heather
Edwards MAJ 7,8,10, 4
2 2
1 11 TS 2,5 2022 RX 5
1110 RO-4 NOR 1
1 1
1 1
I/C 3,5,8 4,6,9 6
4 4
2 Kimberly
Embrey MAJ 6,7 7,8 4
2 2
1 TS 0022 RX 5
1 1
1 0
RO-5 NOR 1
2 1
1 1
1 I/C 3,5,8 4,6,9 5,7 8
4 4
2 Justin Sibson MA]
6,7 7,8 8,11,13 7
2 2
1 TS 0022
ES-301 Transient and Event Checklist Form ES-301-5 Facility: Brunswick Nuclear Plant Date of Exam: Nov/Dec 2015 Operating Test No.: Final A
E Scenarios P
V
P E
1 2
3 4
T M
L N
CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0
I C
S A
B S
A B
S A
B S
A B
I A
T R
T 0
R T
0 R
T 0
R T
o A
M N
Y 0
C P
0 C
P 0
C P
o c
p L
u T
P M(*)
E RX 3
1 110 NOR
1 1111 SRO-U1
I/C 2,4,5,6, 5
4 4
2 Eric
Beachum MAJ 7,8,10, 4
2 2
1 11 TS 2,5 2022 RX 5
1110 RO-1 NOR
1 1111 Charles I/C 3,5,8
6 4
4 2
Brookshire MAJ 6,7 7,8 4
2 2
1 TS 0022 RX 1
110 RO-2 NOR
1
1 1
1 1
I/C 2,4,5,6, 2,5,6, 4
2 Freddie 9
11 Bunnell MAJ
6,7
TS 0022 RX 5
1110 NOR 1
j 111 SROU3 I/C 2,3,4,5 7
4 4
2
,6,8,9 Holly West
MA]
67
2 2
2 1
TS 34 2022 RX 5
1 110 SRO U4 NOR 1
1 1
1 1
I/C 2,3,4,5 7
4 4
2 Dwayne
,6,8,9 Wolf MAJ
2 2
2 1
iS II I
II I
I II I
I 2022 RX 3
1 110 RO-3 NOR 1
1 111 I/C 2,4,5,6, 2,5,6, 9
4 4
2 Jacob 9
11 Bush MAJ 6,7 7,8,10 5
2 2
1 TS 0022
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 (SRO-l) 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 SRO-l 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 one-for-one 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.
4.
For licensees that use the ATC operator primarily for monitoring plant parameters, the chief examiner may place SRO-l applicants in either the ATC or BOP position to best evaluate the SRO-I in manipulating plant controls.
ES-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: Nov/Dec 2015 Operating Test No.:Final APPLICANTS SRO-I1 SRO-12 SRO-U2 Roel Brusselmans Patrick Sena Heather Edwards Competencies SNAIO 1
234 1
2341 234 2,5, Interpret/Diagnose 2,5, 2,5, 1,4, 2,4, 2,5, 1,4, Events and 6,7 11 5,6, 5,6 11 5,6, Conditions Comply With and 2,5, 2,5, 1,2, 1,2, 2,5, 1,2, 710 Use Procedures (1) 7 7,10 3,5, 4,5, 7,10 3,5, 8
6 8
2,5, Operate Control 1,2, NA 2,5, NA 2,5, NA 78 Boards (2) 7,9, 7,8, 10 6
10 10 ALL Communicate ALL ALL ALL ALL ALL ALL and Interact 1,3, Demonstrate NA 1,3, NA 2,3, NA 1,3, Supervisory Ability (3) 5,7, 4,5,
8,9, 8,9, 6,7, 8,9, 10,1 10,1 8,9 10,1 1 12 1,12 1,12 2,5 Comply With and NA 2,5 NA 3,4 NA 4,6 Use Tech. Specs. (3)
=
= = =
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-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: October 2014 Operating Test No.:Final APPLICANTS RO-4 RO-5 SRO-U1 RO-J Kimberly Embrey Justin Sibson Eric Beachum Charles Brooksh ire Competencies SNAO 1
2341 2341 2341 234 Interpret/Diagnose 3,5, 4,6, 3,5, 4,6, 1,4, 5
3,5, 4,6, Events 7,8, 9
7,8, 9
5,7, 7,8, 9
and Conditions 1
9 1,12 25 Comply With and 2,5 1,3, 2,5 1,3, 1,2, 7,10 2,5 1,3, Use Procedures (1) 4,6, 4,6, 3,5, 4,6, 9
9 8
9 25 Operate Control 3,5, 1,3, 3,5, 1,3, NA 7,8, 3,5, 1,3, Boards (2) 7,8, 4,6, 7,8, 4,6, 10 7,8, 4,6, 9
9 9
9 9
9 ALL Communicate ALL ALL ALL ALL ALL ALL ALL and Interact 13 Demonstrate NA NA NA NA NA NA NA Supervisory Ability 8,9, (3) 10,1 1,12 25 Comply With and NA NA NA NA NA NA NA UseTech.Specs.(3)
Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: October 2014 Operating Test No.:Final APPLICANTS RO-2 SRO-U3 SRO-U4 RO-3 Freddie Bunnell Holly West Dwayne Wolf Jacob Bush Corn petencies SNO SNAO_
1 2
3 41 2
3 41 2341 234 Interpret/Diagnose 3,5, 2,5,1 2,4, 2,4, 2,4, 2,5, Events 7,8, 1
5,6 5,6 5,6 11 and Conditions Comply With and 2,5 2,5,7, 1,2, 1,2, 1,2, 2,5, Use Procedures (1) 10 4,5, 4,5, 4,5, 7,10 6
6 6
Operate Control 3,5, 2,5,7, NA NA NA 2,5, Boards (2) 7,8, 8,10 7,8, 9
10 Communicate ALL ALL ALL ALL ALL ALL and Interact Demonstrate NA NA 2,3, 2,3, NA NA Supervisory Ability 13\\
6,7, 6,7,
89 8,9 Comply With and NA NA 3,4 3,4 3,4 2,5 Use Tech. Specs. (3) = =
= = =
=
Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-301 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: Nov/Dec 2015 Operating Test No.:Final APPLICANTS SRO-l1 SRO-12 SRO-13 SRO-U2 Roel Brusselmans Doug Just Patrick Sena Heather Edwards Competencies 1
2341 2341 2341 234 Interpret/Diagnose 2,5, 2,5, 3,5, 3,4, 4,6, 2,4, 4,6, 2,4, 2,5, 3,4, Events and 6,7 11 7,8, 5,6, 9
5,6 8,9 5,6, 6,7 5,6, Conditions 9
7,8, 7,11 7,8, Comply With and 2,5, 2,5, 2,5 5,6, 1,3, 1,2, 1,4, 2,4, 2,5, 5,6, Use Procedures (1) 7 7,10 7
4,6, 4,5, 6,7 5,7, 7
7 9
6 10 Operate Control NA 2,5, 3,5, NA 1,3, 1,2, 1,2, NA NA NA Boards (2) 7,8, 7,8, 4,6, 4,5, 4,6, 10 9
9 6
7,9 Communicate ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate 2,3, NA NA 2,3, NA NA NA 2,3, 2,3, 2,3, Supervisory Ability (3) s 4,5, 4,5, 4,5, 4,5, 6,7, 6,7, 6,7, 6,7, 6,7, 8,9 8,10 8,10 8,9 8,10 Comply With and 3,4 NA NA 4,5 NA NA NA 2,5 3,4 4,5 Use Tech. Specs. (3)
=
Notes:
(1)
Includes Technical Specification compliance for an RO.
(2)
Optional for an SRO-U.
(3)
Only applicable to SROs.
Instructions:
Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
ES-301 Competencies Checklist Form ES-301 -6 Facility: Brunswick Date of Examination: October 2074 Operating Test No.:Final APPLICANTS RO-4 RO-5 SRO-U1 RO-1 Kimberly Embrey Justin Sibson Eric Beachum Charles Brookshire Competencies 1
2341 234 1
234 1
234 Interpret/Diagnose 3,5, 3,5, 4,6, 2,4, 4,6, 2,5, 3,5, 3,5, Events 7,8, 6,7 9
5,6 8,9 6,7 7,8, 6,7 and Conditions Comply With and 2,5 1,3, 1,3, 1,2, 1,4, 2,5, 2,5 1,3, Use Procedures (1) 5,6, 4,6, 4,5, 6,7 7
5,6, 7
9 6
7 Operate Control 3,5, 1,3, 1,3, 1,2, 1,2, NA 3,5, 1,3, Boards (2) 7,8, 5,6, 4,6, 4,5, 4,6, 7,8, 5,6, 9
7 9
6 7,9 9
7 Communicate ALL ALL ALL ALL ALL ALL ALL ALL and Interact Demonstrate NA NA NA NA NA 2,3, NA NA Supervisory Ability 6,7, 1
89 Comply With and NA NA NA NA NA 3,4 NA NA 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 evenj applicable competency for every applicant.
ES-307 Competencies Checklist Form ES-301-6 Facility: Brunswick Date of Examination: October2014 Operating Test No.: Final APPLICANTS RO-2 SRO-U3 SRO-U4 RO-3 Freddie Bunnell Holly West Dwayne Wolf Jacob Bush Competencies 1
2 3
41 2
3 41 2341 234 Interpret/Diagnose 2,4, 4,6, 3,4, 2,4, 3,5, 2,5, Events 5,6 8,9 5,6, 5,6, 6,7 11 and Conditions 7,8, 7,11 Comply With and 1,2, 1,4, 5,6, 2,4, 1,3, 2,5, Use Procedures (1) 4,5, 6,7 7
5,7, 5,6, 7,10 6
10 7
Operate Control 1,2, 1,2, NA NA 1,3, 2,5, Boards (2) 4,5, 4,6, 5,6, 7,8, 6
7,9 7
10 Communicate ALL ALL ALL ALL ALL ALL and Interact Demonstrate NA NA 2,3, 2,3, NA NA Supervisory Ability 4,5, 4,5, 6,7, 6,7,
8,10 8,10 Comply With and NA NA 4,5 2,5 NA NA 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 evenj applicable competency for every applicant.
ES4OI, Rev. 9 BWR Examination Outline Rev.1 (Shown in red)
Form ES4OI-f Facility Brunswick Date of Exam:
December 2015 RO KIA Category Points SRO-OnIy Points Tier Group K
K K
K KKAAAAG A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total 1.
i 434 J3f3 3f20 4
3 7
Emergency &
2 I
i I i Tt 2
1 3
Abnormal Plant
N/A NIA I
Evolutions Tier Totals 6
4 27 6
4 10 1
233231 23322 26 3
2 5
2.
2 1
2 1
11 1
11 1
1 1
12 0
2 1
3 Plant Systems Tier Totals 5
4 3
4 2
3 4
4 3
3 38 5
3 8
- 3. GenericKnowledgeandAbilities 1
2 3
4 10 1
2 3
4 7
Categories 2
3 3
2 2
2 1
2 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 ATier Totals in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3.
Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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 I 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.
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 ES4OI-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 295001AK1.04 Partial or Complete Loss of Forced 2.5 3.3 D
Limiting cycle oscillation: Plant-Specific Core Flow Circulation / 1 & 4 295003G2.4.50 Partial or Complete Loss of AC / 6 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
295004AK3.02 Partial or Total Loss of DC Pwr / 6 2.9 3.3 Ground isolation/fault determination 295005AA1.07 Main Turbine Generator Trip / 3 3.3 3.3 A.C. electrical distribution 295006M2.02 SCRAM / 1 4.3 4.4 Control rod position 295016AK2.01 Control Room Abandonment / 7 4.4 4.5 Remote shutdown panel: Plant-Specific 295018AK3.02 Partial or Total Loss of CCW / 8 3.3 3.4 Reactor power reduction 295019AA1.04 Partial or Total Loss of Inst. Air / 8 3.3 3.2 Service air isolations valves: Plant-Specific 295021AK3.02 Loss of Shutdown Cooling / 4 3.3 3.4 Feeding and bleeding reactor vessel 295023AA2.O1 Refueling Acc Cooling Mode I B 3.6 4.0 Area radiation levels 295024G2.4.50 High Drywell Pressure / 5 4.2 4.0 DEED EEEEEE Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Page 1 of 2 12/18/2014 11:49AM
ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO SRO 295025EK2.05 High Reactor Pressure / 3 4.1 4.2 Safety/relief valves: Plant-Specific 295026EK1.02 Suppression Pool High Water Temp./
3.5 3.8 Steam condensation 5
2950282K1.O1 High Drywell Temperature / 5 3.5 3.7 Reactor water level measurement 295030EK1.02 Low Suppression Pool WtrLvl / 5 3.5 3.8 Pimp NPSH 295031G2.2.37 ReactorLowWaterLevel/2 3.6 4.6
AbHitytodetermineoperabilityand/oravailabilityofsafety related equipment 295037EK3.07 SCRAM Condition Present and Power 4.2 4.3 Various alternate methods of control rod insertion: Plant-Above APRM Downscale or Unknown Specific
/1 2950382A2.02 High Off-site Release Rate / 9 2.5 3.3 Total number of curies released 600000AK2.O1 Plant Fire On Site / 8 2.6 2.7 Sensors / detectors and valves 7OOOOOA1.O2 GeneratorVoltage and Electric Grid 3.8 3.7 Turbine/generator controls Distrurbancecs Page2of2 12/18/2014 11:49AM
2950 I7AK 1.03 295020AK3.02 500000EA1.02 D
TIG2 BWR EXAMINATION OUTLINE IR Ki k2 K3 K4 K5 K6 Al A2 A3 A4 C
SRO 4.2 2.7 3.4 3.3 3.5 3.3 3.2 ES-401, REV 9 KA NAME / SAFETY FUNCTION:
RO 295007G2.4.11 High Reactor Pressure / 3 4.0 295008AK1.02 High Reactor Water Level /2 2.8 2.8 FORM ES-401-1 295010AK2.02 High Drywell Pressure / 5 3.3 3.5 295014AA2.04 Inadvertent Reactivity Addition / 1 4.1
4.4 TOPIC
Knowledge of abnormal condition procedures.
Component erosion/damage Drywell/suppression chamber differential pressure:
Mark l&ll Violation of fuel thermal limits High Off-site Release Rate / 9 Inadvertent Cont. Isolation / 5 & 7 High CTMT Hydrogen Conc. / 5 Meteorological effects on off-site release Drywell/containment pressure response Primary containment oxygen instrumentation Page 1 of 1 12/18/2014 11:50AM
ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
JR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RD SRO 203000A4.06 RHR/LPCI: Injection Mode 3.9 3.9 System reset following automatic initiation: Plant-Specific 205000K3.02 Shutdown Cooling 3.2 3.3 Reactor water level: Plant-Specific 205000K5.03 Shutdown Cooling 2.8 3.1 Heat removal mechanisms 206000G2.2.36 HPCI 3.1 4.2 Ability to analyze the effect of maintenance actMDes, such as degraded power sources, on the status of limiting conditions of operations 209001A3.03 LPCS 3.5 3.5 System pressure 21 1000G2.4.9 SLC 3.8 4.2 1
Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
212000K1.03 RPS 3.4 3.6 Recirculation system 215003K2.O1 IRM 2.5 2.7 1
IRM channels/detectors 21 5004K5.O1 Source Range Monitor 2.6 2.6 Detector operation 215005K1.1O APRM / LPRM 3.3 3.3 1J Reactor manual control system: Plant-Specific 217000K6.O1 RCIC 3.4 3.5 Electrical power Page 1 of3 12/18/2014 11:50AM
ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 218000A3.03 ADS 3.7 3.8 ADS valve acoustical monitor noise: Plant-Specific 218000K2.O1 ADS 3.1 3.3 ADS logic 223002A2.09 PCIS/Nuclear Steam Supply Shutoff 3.6 3.7 System initiation 223002A4.05 PCIS/Nuclear Steam Supply Shutoff 2.5 2.8 jj SPDS/ERISICRIDS/GDS: Plant-Specific 239002K4.04 SRVs 3.4 3.6 Ensures even distribution of heat load to suppression pool,and adequate steam condensing 259002A2.06 Reactor Water Level Control 3.3 3.4 Loss of controller signal output 261000K3.04 SGTS 3.1 3.1 D E LI I High pressure coolant injection system: Plant-Specific 262001A1.05 AC Electrical Distribution 3.2 3.5 LI I LI LI LI ] LI LI LI Breaker lineups 262002A2.O1 UPS (AC/DC) 2.6 2.8 LI LI LI LI LI LI LI I LI LI Under voltage 262002A3.O1 UPS (AC/DC) 2.8 3.1 LI LI LI LI LI LI LI LI LI LI Transfer from preferred to alternate source 263000A1.O1 DC Electrical Distribution 2.5 2.8 LI LI LI LI LI LI LI LI LI LI Battery charging/discharging rate Page2of3 12/18/2014 11:50AM
ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR K1 K2 K3 K4 KS K6 Al A2 A3 A4 G
TOPIC:
RO SRO 264000K3.03 EDGs 4.1 4.2 Major loads powered from electrical buses fed by the emergency generator(s) 264000K5.05 EDGs 3.4 3.4 D
Paralleling AC. power sources 300000K2.O1 Instrument Air 2.8 2.8 D
D D D D D D D D D Instrument air compressor 400000K4.01 Component Cooling Water 3.4 3.9 D D D D D D D D D D Automatic start of standby pump Page3of3 12/18/2014 11:50AM
T2G2 BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 C
RO SRO 201001K4.03 CRD Hydraulic 2.7 2.7 Control rod drive mechanism cooling water flow 201002A1.04 RMCS 3.6 3.5 Overall reactor power 201003A2.01 Control Rod and Drive Mechanism 3.4 3.6 E D D
Stuck rod 204000A4.O1 RWCU 3.1 3.0 System pumps 215002K2.03 RBM 2.8 2.9 APRM channels: BWR-3,4,5 219000G2.2.37 RHR/LPCI: Tows/Pool Cooling Mode 3.6 4.6 fl 1
Ability to determine operability and/or availability of safety related equipment 233000K2.02 Fuel Pool Cooling/Cleanup 2.8 2.9 RHR pumps 241000K6.1O Reactor/Turbine Pressure Regulator 3.6 3.7 Bypass valves 256000A3.07 Reactor Condensate 2.9 2.9 E
j Feedwater heater level 271000K1.03 Offgas 2.7 3.0 Elevated release point 290002K5.05 Reactor Vessel Internals 3.1 3.3 Brittle fracture ES-401,_REV 9 KA NAME I SAFETY FUNCTION:
TOPIC:
FORM ES-401-1 Page 1 of 2 12/18/2014 11:50AM
ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 290003K3.02 Control Room HVAC 3.3 3.6 Computer/instrumentation: Plant-Specific Page2of2 12/18/2014 11:50AM
Ability to locate and operate components, including local controls.
Knowledge of new and spent fuel movement procedures Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Ability to apply technical specifications for a system.
Knowledge of the process used to track inoperable alarms Ability to control radiation releases.
Knowledge of radiation monitoring systems Ability to comply with radiation work permit requirements during normal or abnormal conditions Knowledge of EOP terms and definitions.
Knowledge of emergency response facilities.
ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME/SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO G21.30 Conduct of operations 4.4 4.0 G2.1.42 Conductof operations 2.5 3.4 G2.2.25 Equipment Control 3.2 4.2 G2.2.40 Equipment Control 3.4 4.7 G2.2.43 Equipment Control 3.0 3.3 G2.3.11 Radiation Control 3.8 4.3 G2.3.15 Radiation Control 2.9 3.1 G2.3.7 Radiation Control 3.5 3.6 G2.4.17 Emergency Procedures/Plans 3.9 4.3 G2.4.42 Emergency Procedures/Plans 2.6 3.8 Page 1 of 1 12/18/2014 11:50AM
ES-401, REV 9 KA NAME / SAFETY FUNCTION:
295003M2.04 Partial or Complete Loss of AC I 6 295016G2.1.7 Control Room Abandonment? 7 29501 8G2.1.23 Partial or Total Loss of CCW I 8 295021AA2.06 Loss of Shutdown Cooling / 4 295023G2.4.11 Refueling Acc Cooling Mode? 8 295025EA2.05 High Reactor Pressure / 3 295037EA2.07 SCRAM Condition Present and Power Above APRM Downscale or Unknown I SRO TIGI BWR EXAMINATION OUTLINE IR K1K2K3K4K5K6A1A2A3A4G RO SRO 3.5 3.7 4.4 4.7 4.3 4.4 3.2 3.3 4.0 4.2 3.4 3.6 4.0 4.2 FORM ES-401-1 TOPIC:
System lineups Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
Ability to perform specific system and integrated plant procedures during all modes of plant operation.
Reactor pressure Knowledge of abnormal condition procedures.
Decay heat generation Containment conditions/isolations Page 1 of 1 12/18/2014 11:51AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
29501 5G2.4.5 Incomplete SCRAM /1 295022fA2.01 Loss of CRD Pumps /1 3.5 3.6 295034EA2.02 Secondary Containment Ventilation 3.7 4.2 High Radiation / 9 SRO TIG2 BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RD SRO 3.7 4.3 f
Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.
Accumulator pressure E E D D E Cause of high radiation levels FORM ES-401-1 Page 1 of 1 12/18/2014 11:51 AM
ES-401, REV 9 SRO T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 203000G2.4.6 RHR/LPCI: Injection Mode 3.8 4.5 E E E E E E E E E Knowledge of EOP mitigation strategies.
209001A2.07 LPCS 2.6 2.8 E
Loss of room cooling 212000A2.O6 RPS 4.1 4.2 High reactor power
217000G2.4.47 RCIC 4.2 4.2 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
261000A2.05 SGTS 3.0 3.1 El El El El El El El El Fan trips Page 1 of 1 12/18/2014 11:51 AM
ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION:
IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO 219000G2.1.25 RHR/LPCI: Tows/Pool Cooling Mode 3.9 4.2 E
Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
256000A2.07 Reactor Condensate 2.9 2.9 High hotwell level
290002A2.04 Reactor Vessel Internals
3.7 4.1 Excessive heatup/cooldown rate Page lofi 12/18/2014 11:51AM
ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:
IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G
TOPIC:
RO SRO G2.1.26 Conduct of operations 3.4 3.6 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
G2.1.38 Conduct of operations 3.7 3.8 U
U Knowledge of the stations requirements for verbal communication when implamenting procedures G2.2.17 Equipment Control 2.6 3.8 Knowledge of the process for managing maintenance activities during power operations.
G2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.
G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits G2.4.13 Emergency Procedures/Plans 4.0 4.6 Knowledge of crew roles and responsibilities during EOP usage.
G2.4.46 Emergency Procedures/Plans 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.
Page 1 of 1 12/18/2014 11:51 AM
ES403 Written Examination Grading Form ES403-1 Quality Checklist Facility: 4lJ47/c/
Date of Exam:
Exam Level:
RO SRO Item Description Initials a
b c
1.
Clean answer sheets copied before grading
,v jJb 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, 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 S
deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed Name/Signature Date a.
Grader
%7g& &;
/Z
//7/zi b.
Facility Reviewer(*)
Zo/ L c.
NRC Chief Examiner (*) iia 11/4/2e1 d.
NRC Supeisor f*)
A/
if zo) 2)
(*)
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
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 November 30, 2015 Duke Energy Progress, Inc.
ATTN: Mr. Jonathan L. Hicks Manager, Training Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429
SUBJECT:
BRUNSWICK NUCLEAR POWER PLANT - OPERATOR LICENSING OPERATING EXAMINATION APPROVAL 05000325/2015301 AND 05000324/2015301
Dear Mr. Hicks:
The purpose of this letter is to confirm the final arrangements for the upcoming operator licensing operating examination at the Brunswick Nuclear Power Plant.
The U.S. Nuclear Regulatory Commission (NRC) has completed its review of the operator license applications submitted in connection with this examination and separately provided a list of approved applicants to your office. The NRC staff will administer the operating tests to individuals, as applicable, the weeks of November 30, 2015, and December 7, 2015. Note that any examination waivers and application denials have been addressed in separate correspondence.
This examination has undergone extensive review by my staff and representatives responsible for operator training at your facility. Based on this review, I have concluded that the examination meets the guidelines of NUREG-1021 for content, operational, and discrimination validity. By administering this examination, you also agree that it meets NUREG-1021 guidelines, and is appropriate for measuring the qualifications of licensed operators at your facility. If you determine that this examination is not appropriate for licensing operators at your facility, do not administer the examination and contact me at (404) 997-4642.
Please contact the Chief Examiner, Mr. Richard S. Baldwin, at (404) 997-4642, if you have any questions or identify any errors or changes in license level (RO or SRO) or type of examination (operating examination) specified for each applicant on the list of approved applicants.
Sincerely,
/RA/
Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62
ML15335A557 X SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS RII:DRS SIGNATURE Jcb Rsb efg NAME JVINCENT RBALDWIN EGUTHRIE DATE 11/ 24 /15 11/ 30 /15 11/30/15 E-MAIL COPY?
YES NO YES YES NO
DUKE Enclosure Contains Operator Examination Material ENERGY.
Withhold in Accordance with 10 CFR 2.390 Southport, NC 28461 AUG 2 1 2015 Serial: BSEP 15-0070 U. S. Nuclear Regulatory Commission, Region II AHN: Mr. Victor M. McCree, Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Operating Test Outline tot Licensed Operator Initial Examination 50-325/2015-301 and 50-324/2015-301
Reference:
Letter from Eugene F. Guthrie (NRC) to William R. Gideon (Duke Energy),
Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 05000325/2015301 and 05000324/2015301, dated May 15, 2015, ADAMS Accession Number ML15138A340
Dear Mr. McCree:
In accordance with the guidelines in Revision 10, of NUREG-1 021, Operator Licensing Examination Standards for Power Reactors, Duke Energy Progress, Inc., is providing the examination outline supporting the operating test, which is scheduled to be administered during the weeks of November 30, 2015, and December 7, 2015.
In accordance with the schedule contained in the NRCs letter dated May 15, 2015, a copy of the outline for the operating test is being provided only to Mr. Richard S. Baldwin, the assigned NRC chief examiner. In accordance with 10 CFR 55.40(b)(3), Mr. Jerry Pierce, as the designated authorized representative of the Brunswick Steam Electric Plant, Units 7 and 2, has approved the outline for the examinations of the applicants.
In accordance with Revision 10, of NUREG-1021, Section ES-201, Initial Operator Licensing Examination Process, please ensure that the outline for the operating test is withheld from public disclosure until after the examinations are complete.
This document contains no regulatory commitments.
Enclosure Contains Operator Examination Material Withhold in Accordance with 10 CFR 2.390
U. S. Nuclear Regulatory Commission, Region II Page 2 of 3 Please refer any questions regarding this submittal to Mr. Bob Bolin, Senior Nuclear Operations Instructor, at (910) 457-3078, or Mr. Jerry Pierce, Assistant Operations Manager - Support, at (910) 454-7931.
Sincerely, AH P/mkb H. Pope Directbr Organizational Effectiveness Brunswick Steam Electric Plant
Enclosure:
Outline for Operating Test (Enclosure only being sent to Chief Examiner)
U. S. Nuclear Regulatory Commission, Region II Page 3 of 3 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II AUN: Mr. Richard S. Baldwin, Chief Examiner 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 cc (without enclosure):
U. S. Nuclear Regulatory Commission AUN: Document Control Desk Washington, DC 20555-0001 U. S. Nuclear Regulatory Commission, Region II AUN: Mr. Eugene F. Guthrie Chief, Operations Branch 2 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U. S. Nuclear Regulatory Commission AUN: Mr. Andrew Hon (Mail Stop OWFN 8G9A)
(Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission AHN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair
- North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
%DUKE ENERGY OCT 29 2015 Serial: BSEP 15-0087
Subject:
References:
p3YX1*tIILp *p.n William R. Gideon Vice President Brunswick Nuclear Plant P.O. Box 10429 Southport, NC 28461 0: 910.457.3698 OCT 3020]5 U.S. Nuclear Regulatory Commission, Region II ATTN: Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Preliminary Reactor Operator and Senior Reactor Operator License Applications 1.
Letter from Eugene F. Guthrie (NRC) to William R. Gideon (Duke Energy), Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 05000325/2015301 and 05000324/2015301, dated May 15, 2015, ADAMS Accession Number ML15138A340 2.
Letter from Annette H. Pope (Duke Energy) to Victor M. McCree (NRC), Operating Test Outline for Licensed Operator Initial Examination 50-325/201 5-301 and 50-324/2015-301, dated August 24, 2015 3.
Letter from Annette H. Pope (Duke Energy) to NRC Region II, Regional Administrator, Operating Test, Written Exam, and Reference Materials for Licensed Operator Initial Examination 50-325/2015-301 and 50-324/2015-301, dated September 29, 2015
Dear Regional Administrator:
In accordance with the schedule contained in the NRCs letter dated May 15, 2015 (i.e.,
Reference 1), Duke Energy Progress, Inc., is submitting preliminary reactor operator and senior reactor operator license applications and medical certifications for individuals participating in the operating test that is scheduled to be administered during the weeks of November 30, 2015, and December 7, 2015, and the written examination that is scheduled to be administered during the week of December 14, 2015, at the Brunswick Steam Electric Plant. Submittal of the preliminary reactor operator and senior reactor operator license applications and medical certifications is required at least 30 days before the first examination date. provides a list of the applicants who are currently scheduled to participate in the license examination. Enclosure 2 provides preliminary, unsigned license applications for each applicant (i.e., NRC Form 398, Personal Qualification Statement Licensee). Enclosure 3 provides signed medical certifications for each applicant (i.e., NRC Form 396, Certification of Medical Examination by Facility Licensee). Enclosure 4 provides the physicians letter for only a few specific individuals.
XLI IflTfltI n nnnI_I
U.S. Nuclear Regulatory Commission, Region II Page 2 of 3 Duke Energy requests that the information in the enclosures be withheld from public disclosure, in accordance with 10 CFR 2.390(a)(6), since disclosure of this information would constitute a clearly unwarranted invasion of personal privacy.
This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager Regulatory Affairs, at (910) 457-2487.
Sincerely, William R. Gideon WRG/mkb
Enclosures:
1.
List of Applicants Scheduled for License Examinations i, I-JAIl ti..
tit6))
2.
Preliminary NRC Form 398, Personal Qualification Statement Licensee Ii.I1:_jt_..L:...
w:ii.i._ij :..-i.__--- ujth 1 r
M
..1.LI_ LL....JL_
icm:ti.i -.
A_..._,
3.
NRC Form 396,Certification of Medical Examination by Facility Licensee
(
..Jl, 1-S lCfl LIr(j())
4.
Physicians Letters - I-.- rmtwfl Withhfi in AiJrn. ilviLil ii., 8fflIJeS(t.44.6))
U.S. Nuclear Regulatory Commission, Region II Page 3 of 3 cc (with enclosures):
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission, NRC Region II ATTN: Mr. Richard S. Baldwin, Chief Examiner 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 cc (without enclosures):
U.S. Nuclear Regulatory Commission, NRC Region II ATTN: Mr. Gerald J. McCoy Chief, Operations Branch 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1 257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWEN 8G9A)
(Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission AUN: Ms. Michelle P. Catts, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
William R. Gideon DUKE Vice President ENERGY Brunswick Nuclear Pnt Southport, NC 28461 910.457.3698 December 21, 2015 Serial: BSEP 15-01 05 U.S. Nuclear Regulatory Commission, Region II ATTN: Regional Administrator 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-71 and DPR-62 Docket Nos. 50-325 and 50-324 Reactor Operator and Senior Reactor Operator License Post-Examination Documentation and Comments
Reference:
Letter from Eugene F. Guthrie (NRC) to William R. Gideon (Duke Energy),
Brunswick Steam Electric Plant Notification of Licensed Operator Initial Examination 05000325/2015301 and 05000324/2015301, dated May 15, 2015, ADAMS Accession Number ML15138A340
Dear Regional Administrator:
In accordance with the guidance contained in Revision lOot NUREG-1021, Operator Licensing Standards for Power Reactors, Section ES-402, Administering Initial Written Examinations, and ES-501, Initial Post-Examination Activities, Duke Energy Progress, Inc., is providing the NRC the specified documentation for the reactor operator and senior reactor operator written examinations, which were administered at the Brunswick Steam Electric Plant on Tuesday, December 15, 2015. The examination documentation enclosures are being provided only to Mr.
Eugene Guthrie, with his copy of this letter. Duke Energy has five post exam comments relating to the written examination included with this submittal letter as Enclosure 2.
The master examination and answer key are provided in Enclosure 6 of this letter, with annotations. All substantive comments made by the applicants following the written examination are included with Enclosure 2. Lastly, the original ES-201-3 forms, Examination Security Agreement, with all the pre-and post-examination signatures will be provided via email, as previously discussed with the NRC chief examiner on December 21, 2015.
U.S. Nuclear Regulatory Commission, Region II Page 2 of 3 This document contains no regulatory commitments.
Please refer any questions regarding this submittal to Mr. Lee Grzeck, Manager Regulatory Affairs, at (910) 457-2487.
- S1y, William R. Gideon WRG/mkb
Enclosures:
1.
Completed ES-403-1, Written Examination Grading Quality Checklist 2.
Written Examination Performance Analysis Results (with recommended substantive changes) 3.
Graded Written Examinations and Applicants Answer Sheets 4.
Applicants Questions Asked and Answers Given During the Written Examination 5.
Written Examination Seating Chart 6.
Master Examination and Answer Key
U.S. Nuclear Regulatory Commission, Region II Page 3 of 3 cc (with enclosures):
U.S. Nuclear Regulatory Commission, Region II ATTN: Mr. Eugene F. Guthrie Chief, Operations Branch 2 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 cc (without enclosures):
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission, Region II ATTN: Mr. Gerald J. McCoy Chief, Operations Branch 1 245 Peachtree Center Aye, NE, Suite 1200 Atlanta, GA 30303-1257 U.S. Nuclear Regulatory Commission ATTN: Mr. Andrew Hon (Mail Stop OWEN 8G9A)
(Electronic Copy Only) 11555 Rockville Pike Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission AHN: Ms. Michelle P. Catts, NRC Senior Resident Inspector
$470 River Road Southport, NC 28461-8869 Chair
- North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC