IR 05000324/2017301: Difference between revisions

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{{Adams
{{Adams
| number = ML17277A330
| number = ML17318A067
| issue date = 10/03/2017
| issue date = 11/08/2017
| title = Brunswick Steam Electric Plant - NRC Examination Report 05000325/2017301 and 05000324/2017301
| title = Brunswick Steam Electric Plant - Notification Of Licensed Operator Retake Initial Examination 05000325/2017301 And 05000324/2017301
| author name = McCoy G J
| author name = Guthrie E F
| author affiliation = NRC/RGN-II/DRS
| author affiliation = NRC/RGN-II
| addressee name = Gideon W R
| addressee name = Gideon W R
| addressee affiliation = Progress Energy Carolinas, Inc
| addressee affiliation = Progress Energy Carolinas, Inc
| docket = 05000324, 05000325
| docket = 05000324, 05000325
| license number = DPR-062, DPR-071
| license number = NPF-068, NPF-081
| contact person =  
| contact person =  
| document report number = IR 2017301
| document report number = IR 2017301
| document type = Letter, License-Operator Examination Report
| document type = Letter
| page count = 11
| page count = 4
}}
}}


Line 19: Line 19:
=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:
[[Issue date::October 3, 2017]]
[[Issue date::November 8, 2017]]


William Site Vice President Brunswick Steam Electric Plant 8470 River Road, SE (M/C BNP001) Southport, NC 28461
William Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001)
Southport, NC 28461


SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC EXAMINATION REPORT 05000325/2017301 AND 05000324/2017301
SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NOTIFICATION OF LICENSED OPERATOR RETAKE INITIAL EXAMINATION 05000325/2017301 AND 05000324/2017301


==Dear Mr. Gideon:==
==Dear Mr. Gideon:==
During the period July 24 through August 1, 2017, the Nuclear Regulatory Commission (NRC)
During a telephone conversation on October 31, 2017, between Mr. Robert Bolin, Senior Nuclear Station Instructor - Operations and Mr. Daniel Bacon, Senior Operations Engineer, arrangements were made for the administration of a retake licensing examination at the Brunswick Steam Electric Plant. The on-site preparation and administration of the simulator scenario portion of the operating test are scheduled for the week of December 11, 2017.
administered operating tests to employees of your company who had applied for licenses to operate Brunswick Steam Electric Plant. At the conclusion of the tests, the examiners discussed preliminary findings related to the operating tests and the written examination submittal with those members of your staff identified in the enclosed report. The written examination was administered by your staff on August 8, 2017.


Seven Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One SRO applicant passed the written examination while the operating test was waived. One SRO applicant failed the scenario portion of the examination. There was one JPM post-examination comment. Thirteen applicants were issued licenses commensurate with the level of examination administered. A Simulator Fidelity Report is included in this report as Enclosure 3.
As agreed during the telephone conversation, your staff will prepare the simulator scenario portion of the operating test based on the guidelines in Revision 11 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 examination is administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination.


All examination changes agreed upon between the NRC and your staff were made according to NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 10.
Your staff submitted the outline for the simulator scenario portion of the operating test on October 31, 2017. The simulator scenario portion of the operating test and the supporting reference materials identified in Attachment 3 to ES-201 will be due by November 28, 2017.


In accordance with 10 CFR 2.390 of the NRC's "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 NRC's document system (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html (the Public Electronic Reading Room). If you have any questions concerning this letter, please contact me at (404) 997-4551.
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 outline, examination, 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. 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 NRC takes licensing action on all the applications and any adjudicatory actions on any hearing demands are complete.


Sincerely,/RA/ Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety Docket Nos.: 50-325, 50-324 License Nos.: DPR-71, DPR-62
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.


===Enclosures:===
To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator waiver and/or excusal requests (Office of Management and Budget (OMB) approval number 3150-0090) at least 60 days before the first examination date (if possible). Contact Mr. Bacon to determine the method for submission of the waiver or excusal requests. Preliminary reactor operator and senior reactor operator license applications (OMB approval number 3150-0090) and medical certifications (OMB approval number 3150-0024) should be submitted at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Final signed applications certifying that all training has been completed and requesting any waivers or excusals, as applicable, should be submitted at least 14 days before the first examination date.
1. Report Details 2. Facility Post-Examination Comments and NRC Resolutions 3. Simulator Fidelity Report cc: Distribution via Listserv


SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC EXAMINATION REPORT 05000325/2017301 AND 05000324/2017301 Distribution: P. Capehart, RII J. Viera, RII M. Emrich, TTC G. McCoy, RII
Although the guidelines for receiving waiver or excusal requests call for at least 30 days before the first examination date (preliminary) and 14 days before the first examination date (final), the requests should be submitted as early as possible in the process (see the 60-day guideline above). Resolutions resulting from verbal inquiries by the licensee to the NRC are not binding. Submittals addressing waivers or excusals, or both, should be in writing (i.e., using NRC Form 398, "Personal Qualifications Statement-Licensee," or as directed by Mr. /Ms. [name of Chief Examiner] when contacting him to determine the method for submission). The NRC will document its final decision on whether to grant a waiver or excusal on the final (not preliminary) NRC Form 398 submitted for the applicant. The NRC will not provide its decision until the final application is submitted to the agency.


PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:__ ___________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS SIGNATURE PGC1 VIA EMAIL JXV3 VIA EMAIL MPE1 VIA EMAIL GJM1 NAME PCAPEHART JVIERA MEMRICH GMCCOY DATE 9/28/2017 10/02/2017 9/28/2017 10/3 /2017 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\BRUNSWICK EXAMINATIONS\INITIAL EXAM 2017-301 (PHIL)\CORRESPONDENCE\BRUNSWICK 2017 301 EXAM REPORT.DOCX Enclosure 1 U.S. NUCLEAR REGULATORY COMMISSION REGION II
Paperwork Reduction Act Statement This letter contains information collection requirements that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget, approval number 3150-0018.


Docket No.: 50-325, 50-324
The burden to the public for these mandatory information collections is estimated to average 2,250 hours per examination, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collections. You may submit comments on any aspect of the information collections, including suggestions for reducing the burden, to FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by electronic mail to infocollects.resource@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. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information, unless the document requesting or requiring the collection displays a currently valid OMB control number.


License No.: DPR-71, DPR-62
In accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding,"
of the agency's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection through the Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html. Thank you for your cooperation in this matter. Mr. 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. Bacon at (404) 997-4518, (Internet E-mail: Daniel.Bacon@nrc.gov), or me at (404) 997-4662, (Internet E-mail: Eugene.Guthrie@nrc.gov).


Report No.: 05000325/2017301, 05000324/2017301
Sincerely,/RA/ Eugene F. Guthrie, Chief Operations Branch 2 Division of Reactor Safety Docket Nos.: 50-424, 50-425 License Nos.: NPF-68, NPF-81


Licensee: Duke Energy Progress, Inc.
cc: Distribution via ListServ SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NOTIFICATION OF LICENSED OPERATOR RETAKE INITIAL EXAMINATION 05000325/2017301 AND 05000324/2017301 Distribution: D. Bacon, RII, DRS E. Guthrie, RII, DRS Public


Facility: Brunswick Steam Electric Plant, Units 1 and 2
PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:_ ____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE DXB2 GXG NAME BACON GUTHRIE DATE 11/ 8 /2017 11/ 8 /2017 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\BRUNSWICK EXAMINATIONS\RETAKE EXAM 2017-302\CORRESPONDENCE\CORPORATE NOTIFICATION LETTER.DOCX
 
Location: Southport, NC
 
Dates: Operating Test - July 24 through August 1, 2017 Written Examination - August 8, 2017
 
Examiners: Phillip Capehart, Chief Examiner, Senior Operations Engineer Joe Viera, Operations Engineer Matthew Emrich, Senior Reactor Technology Instructor
 
Approved by: Gerald J. McCoy, Chief Operations Branch 1 Division of Reactor Safety
 
=SUMMARY=
ER 05000325/2017301, 05000324/2017301; operating test July 24 through August 1, 2017 & written exam August 8, 2017; Brunswick Steam Electric Plant, Units 1 and 2; Operator License Examinations.
 
Nuclear Regulatory Commission (NRC) examiners conducted an initial examination in accordance with the guidelines in Revision 10 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors."  This examination implemented the operator licensing requirements identified in 10 CFR §55.41, §55.43, and §55.45, as applicable.
 
The operating tests and written examinations were developed by the NRC.
 
The NRC administered the operating tests during the period July 24 through August 1, 2017. Members of the Brunswick Steam Electric Plant training staff administered the written examination on August 8, 2017. Seven Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One SRO passed the written examination while the operating test was waived. One SRO applicant failed the simulator scenario portion of the examination. Thirteen applicants were issued licenses commensurate with the level of examination administered.
 
There was one JPM post-examination comment.
 
No findings were identified.
 
=REPORT DETAILS=
 
==OTHER ACTIVITIES==
{{a|4OA5}}
==4OA5 Operator Licensing Examinations==
 
====a. Inspection Scope====
The NRC reviewed the licensee's examination security measures while preparing and administering the examinations in order to ensure compliance with 10 CFR §55.49, "Integrity of examinations and tests."
 
The NRC administered the operating tests during the period July 24 through August 1, 2017. The NRC examiners evaluated seven Reactor Operator (RO) and six Senior Reactor Operator (SRO) applicants using the guidelines contained in NUREG-1021. Members of the Brunswick Steam Electric Plant training staff administered the written examination on August 8, 2017 to seven SRO applicants and seven RO applicant.
 
Evaluations of applicants and reviews of associated documentation were performed to determine if the applicants, who applied for licenses to operate the Brunswick Steam Electric Plant, met the requirements specified in 10 CFR Part 55, "Operators' Licenses."
 
The NRC evaluated the performance and fidelity of the simulation facility during the preparation and conduct of the operating tests.
 
====b. Findings====
No findings were identified.
 
The NRC developed the written examination sample plan outline, the written examination, and the operating test. All examination material was developed in accordance with the guidelines contained in Revision 10 of NUREG-1021. The licensee reviewed the proposed examination. Examination changes agreed upon between the NRC and the licensee were made per NUREG-1021 and incorporated into the final version of the examination materials.
 
Seven Reactor Operator (RO) and five Senior Reactor Operator (SRO) applicants passed both the operating test and written examination. One SRO passed the written examination while the operating test was waived. One SRO applicant failed the simulator scenario portion of the examination.Twelve applicants passed both the operating test and written examination and one applicant passed the written examination while the operating test was waived. Seven RO and six SRO applicants were issued licenses.
 
Copies of all individual examination reports were sent to the facility Training Manager for evaluation of weaknesses and determination of appropriate remedial training.
 
The licensee submitted one post-examination comment concerning an administrative JPM on the operating portion of the examination. A copy of the final RO and SRO written examinations and answer keys, with all changes incorporated, and the licensee's post-examination comment may be accessed not earlier than August 8, 2019 in the ADAMS system (ADAMS Accession Numbers ML17263A601, ML17263A604, and ML17263A622, respectively).
 
{{a|4OA6}}
==4OA6 Meetings, Including Exit==
 
=====Exit Meeting Summary=====
 
On August 1, 2017, the NRC examination team discussed generic issues associated with the operating test with Karl Moser, Plant General Manager, and members of the Brunswick Steam Electric Plant staff. The examiners asked the licensee if any of the examination material was proprietary, or if any of the examination material received should be withheld from public disclosure. No proprietary information was identified.
 
KEY POINTS OF CONTACT  Licensee personnel Karl Moser, Plant Manager Kurt Kruger, Nuclear Operations Manager Jon Hicks, Nuclear Training Manager Bryan Wooten, Nuclear Organizational Effectiveness Director Andy Padleckas, Assistant Operations Manager, Support Mark Similey, Nuclear Operations Training Manager Ed Rau, Nuclear Operations Training Supervisor James Buckingham, Nuclear Operations Training Supervisor John Miller, Assistant Operations Training Manager  Craig Oliver, Nuclear Control Room Supervisor Lee Grzeck, Nuclear Regulatory Affairs Manager Michael Braden, Senior Nuclear Engineer Mike Gibson, Nuclear Operations Training Instructor Brian Stetson, Nuclear Operations Training Instructor Josh Ashcroft, Nuclear Operations Training Instructor 2
 
=FACILITY POST-EXAMINATION COMMENTS AND NRC RESOLUTIONS=
A complete text of the licensee's post-examination comments can be found in ADAMS under Accession Number ML17263A622. Item  Admin JPM: RC-1 determining TEDE while working in a High Airborne Area. Comment:
The licensee commented that the standard for step 2 and step 4 was inadequate.
Below is the explanation for step 2 and step 4 of RC-1  Step 2 - Determine internal dose while wearing a respirator. STANDARD-Internal dose with respirator determined to be 0 mrem  Explanation: For step two, internal exposure is assumed to be zero based on using a powered air purifying respirator which due to positive pressure is assumed to allow no internal exposure.
However, if using AD-RP-ALL-2019, to calculate internal dose it would actually be calculated to be .0521 mrem.
Below is an explanation of how to determine this value.
Given in the stem is a weighted DAC of 50.
IAW attachment 3 step 4 this weighted DAC is the equivalent of all the individual respective nuclide DAC
values.
This weighted DAC of 50 is then used in the following equation from attachment 3 step 7b to calculate
DAC-hours for internal dose.
 
The respirator protection factor is 1000 for all duke PAPRs based on attachment 1 note 7    The exposure time is 25 minutes which is given in the initial conditions.
Therefore the equation is solved as follows:
DAC-Hours= [(50/1000) x 25/60] DAC-Hours= .0208
Internal Dose = DAC-Hours x 2.5
Internal Dose=.0208 x 2.5
Internal dose=.0521 mrem
This internal does of .0521 mrem is ~0. Step 4 - Determine total exposure while wearing a respirator. STANDARD-Total dose with respirator determined to be 193.8 mrem (Acceptable range is 193. 7
mrem to 195.3 mrem). (see key)  Explanation:
Total dose is the sum of external exposure and internal exposure. This total dose can be solved using AD-RP-ALL-2019 Attachment 2.
External exposure is calculated as follows based on the above equation:
Dose rate is given as 465 mrem/hr
Work time is 25 minutes ATF for PAPRs is 1 465 x (25/60) x 1 =193.7 to 195.3 mrem Therefore external exposure=193.7 to 195.3 mrem
Internal exposure was calculated above in step 2 as either 0 or .0521 mrem.
Total exposure is (193.7 to 195.3 mrem external dose) + (0 to .0521 mrem internal dose)
Therefore total exposure= 193.7 mrem to 195.821 mrem. NRC Resolution
The licensee's recommendation was accepted. The NRC agrees with the new standard as determined by the licensee and incorporated the new standards into the final revision of the JPM.
The JPM has been changed to reflect the new standards for step 2 and step 4. 
 
SIMULATOR FIDELITY REPORT
Facility Licensee: Brunswick Steam Electric Plant
Facility Docket No.: 05000325, 05000324
Operating Test Administered: July 24- August 1, 2017  This form is to be used only to report observations. These observations do not constitute audit
or inspection findings and, without further verification and review in accordance with Inspection
Procedure 71111.11 are not indicative of noncompliance with 10 CFR 55.46. No licensee
action is required in response to these observations. No simulator fidelity or configuration issues were identified.
}}
}}

Revision as of 17:06, 18 February 2018

Brunswick Steam Electric Plant - Notification Of Licensed Operator Retake Initial Examination 05000325/2017301 And 05000324/2017301
ML17318A067
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/08/2017
From: Guthrie E F
NRC/RGN-II
To: Gideon W R
Progress Energy Carolinas
References
IR 2017301
Download: ML17318A067 (4)


Text

November 8, 2017

William Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE (M/C BNP001)

Southport, NC 28461

SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NOTIFICATION OF LICENSED OPERATOR RETAKE INITIAL EXAMINATION 05000325/2017301 AND 05000324/2017301

Dear Mr. Gideon:

During a telephone conversation on October 31, 2017, between Mr. Robert Bolin, Senior Nuclear Station Instructor - Operations and Mr. Daniel Bacon, Senior Operations Engineer, arrangements were made for the administration of a retake licensing examination at the Brunswick Steam Electric Plant. The on-site preparation and administration of the simulator scenario portion of the operating test are scheduled for the week of December 11, 2017.

As agreed during the telephone conversation, your staff will prepare the simulator scenario portion of the operating test based on the guidelines in Revision 11 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 examination is administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination.

Your staff submitted the outline for the simulator scenario portion of the operating test on October 31, 2017. The simulator scenario portion of the operating test and the supporting reference materials identified in Attachment 3 to ES-201 will be due by November 28, 2017.

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 outline, examination, 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. 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 NRC takes licensing action on all the applications and any adjudicatory actions on any hearing demands are complete.

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 waiver and/or excusal requests (Office of Management and Budget (OMB) approval number 3150-0090) at least 60 days before the first examination date (if possible). Contact Mr. Bacon to determine the method for submission of the waiver or excusal requests. Preliminary reactor operator and senior reactor operator license applications (OMB approval number 3150-0090) and medical certifications (OMB approval number 3150-0024) should be submitted at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination date, a postponement may be necessary. Final signed applications certifying that all training has been completed and requesting any waivers or excusals, as applicable, should be submitted at least 14 days before the first examination date.

Although the guidelines for receiving waiver or excusal requests call for at least 30 days before the first examination date (preliminary) and 14 days before the first examination date (final), the requests should be submitted as early as possible in the process (see the 60-day guideline above). Resolutions resulting from verbal inquiries by the licensee to the NRC are not binding. Submittals addressing waivers or excusals, or both, should be in writing (i.e., using NRC Form 398, "Personal Qualifications Statement-Licensee," or as directed by Mr. /Ms. [name of Chief Examiner] when contacting him to determine the method for submission). The NRC will document its final decision on whether to grant a waiver or excusal on the final (not preliminary) NRC Form 398 submitted for the applicant. The NRC will not provide its decision until the final application is submitted to the agency.

Paperwork Reduction Act Statement This letter contains information collection requirements that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the Office of Management and Budget, approval number 3150-0018.

The burden to the public for these mandatory information collections is estimated to average 2,250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per examination, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collections. You may submit comments on any aspect of the information collections, including suggestions for reducing the burden, to FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by electronic mail to infocollects.resource@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. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information, unless the document requesting or requiring the collection displays a currently valid OMB control number.

In accordance with 10 CFR 2.390, "Public Inspections, Exemptions, Requests for Withholding,"

of the agency's "Rules of Practice," a copy of this letter and its enclosures will be available electronically for public inspection through the Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm.adams.html. Thank you for your cooperation in this matter. Mr. 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. Bacon at (404) 997-4518, (Internet E-mail: Daniel.Bacon@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.: 50-424, 50-425 License Nos.: NPF-68, NPF-81

cc: Distribution via ListServ SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NOTIFICATION OF LICENSED OPERATOR RETAKE INITIAL EXAMINATION 05000325/2017301 AND 05000324/2017301 Distribution: D. Bacon, RII, DRS E. Guthrie, RII, DRS Public

PUBLICLY AVAILABLE NON-PUBLICLY AVAILABLE SENSITIVE NON-SENSITIVE ADAMS: Yes ACCESSION NUMBER:_ ____________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS SIGNATURE DXB2 GXG NAME BACON GUTHRIE DATE 11/ 8 /2017 11/ 8 /2017 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\OLEXAMS\BRUNSWICK EXAMINATIONS\RETAKE EXAM 2017-302\CORRESPONDENCE\CORPORATE NOTIFICATION LETTER.DOCX