IR 05000324/2014007
| ML14357A512 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/23/2014 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | William Gideon Duke Energy Progress |
| References | |
| IR 2014007 | |
| Download: ML14357A512 (13) | |
Text
December 23, 2014
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT - U. S. NUCLEAR REGULATORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000325/2014007 AND 05000324/2014007
Dear Mr. Gideon:
On November 20, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Brunswick Unit 1 and 2 facilities, and discussed the results of this inspection with you and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
The NRC inspectors did not identify any findings or violations of more than minor significance.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response, if any, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 05000325, 05000324 License Nos.: DPR-71, DPR-62
Enclosure:
Inspection Report 05000325/2014007 and 05000324/2014007 w/Attachment: Supplementary Information
_ML14357A512________________ x SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRS RII:DRS RII:DRS RII:DRS RII:DRS RII:DRP
SAW4 TXL3 AJB1 MAR1 RLN GTH1
NAME S. WALKER T. LIGHTY A. BUTCAVAGE M. RILEY R. NEASE G. HOPPER
DATE 12/ 18 /2014 12/16 /2014 12/18 /2014 12/ 16 /2014 12/23/2014 12/22/2014
E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO
Letter to William from Rebe
REGION II==
Docket Nos.:
50-325, 50-324
License Nos.:
Report Nos.:
05000325/2014007, 05000324/2014007
Licensee:
Duke Energy Progress, Inc.
Facility:
Brunswick Steam Electric Plant, Units 1 & 2
Location:
8470 River Road, SE Southport, NC 28461
Dates:
October 27 - November 21, 2014
Inspectors:
S. Walker, Senior Reactor Inspector (Team Leader)
A. Butcavage, Reactor Inspector
T. Lighty, Reactor Inspector M. Riley, Reactor Inspector
Approved by:
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
Inspection Report (IR) 05000325/2014007, 05000324/2014007; 10/27/2014 - 11/21/2014;
Brunswick Steam Electric Plant, Units 1 & 2; NRC Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.
This report covers a two-week, on-site inspection by three regional inspectors. No findings or violations were identified. The Nuclear Regulatory Commissions (NRCs) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.
REPORT DETAILS
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R17 Evaluations of Changes, Tests, Experiments and Permanent Plant Modifications
a. Inspection Scope
Evaluations of Changes, Tests, and Experiments: The team reviewed six safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59, Changes, tests, and experiments, to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 19 screenings where licensee personnel had determined that a 10 CFR 50.59 evaluation was not necessary. The team reviewed these documents to determine if:
- the changes, tests, or experiments performed were evaluated in accordance with 10 CFR 50.59 and that sufficient documentation existed to confirm that a license amendment was not required;
- the safety issues requiring the changes, tests or experiments were resolved;
- the licensee conclusions for evaluations of changes, tests, or experiments were correct and consistent with 10 CFR 50.59; and
- the design and licensing basis documentation used to support the change was updated to reflect the change.
The team used, in part, Nuclear Energy Institute (NEI) 96-07, Guidelines for 10 CFR 50.59 Implementation, Revision 1, to determine acceptability of the completed evaluations and screenings. The NEI document was endorsed by the NRC in Regulatory Guide 1.187, Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments, dated November 2000.
This inspection constituted six samples of evaluations and 16 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.
Permanent Plant Modifications: The team reviewed five permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:
- Engineering Change (EC) 70110 - Diesel Starting Air Reliability Upgrade - DG1 (Child 1 EC 0000086675), Rev. 65
- EC 85482 -Replace 2-FO-1-2-U-6 From 7-Day Tank to 4-Day Tank 2-FOD-4-DAY-TK-1 (Child 2 EC 0000089789), Rev. 15
- EC 78861 - Replace ASCO SSPV's With AVCO Design for Document Updates Prior To Implementation (Child EC0000081957), Rev. 25
- EC 82612 - RCR VFD Software Upgrades Unit 2 (Child EC 0000087648), Rev. 9
- EC 94834 - Modify Battery Surveillance Tests To Verify Adequate Voltage NCON 630621 (Child EC 0000095578), Rev. 0
- EC 85198, Condensate Margin Confirmation, Rev. 0 The modifications were selected based upon risk significance, safety significance, and complexity. The team reviewed the modifications selected to determine if:
- the supporting design and licensing basis documentation was updated;
- the changes were in accordance with the specified design requirements;
- the procedures and training plans affected by the modification had been adequately updated;
- the test documentation as required by the applicable test programs had been updated; and
- post-modification testing adequately verified system operability and/or functionality.
The team also used applicable industry standards to evaluate acceptability of the modifications and performed walkdowns of accessible portions of the modifications.
Documents reviewed are listed in the Attachment.
This inspection constituted six permanent plant modification samples as defined in IP 71111.17-04.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On November 20, 2014, the team presented inspection results to Mr. W. Gideon and other members of the licensees staff. The team verified that no proprietary information was retained by the inspectors or documented in this report.
ATTACHMENT:
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- W. Gideon, Site Vice President
- C. Fletcher, Corporate Licensing
- L. Grzeck, Supervisor - Licensing
- J. Krakuszeski, Plant General Manager
- J. Nolin, Director - Engineering
- N. Smith, Manager - Design Engineering
- R. Zambo, Licensing
NRC personnel
- G. Hopper, Chief, Reactor Projects Branch 4
- A. Scarbeary, Senior Resident Inspector (Acting), Brunswick
- M. Schweig, Resident Inspector, Brunswick
LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED
Opened
None
Closed
None
Discussed
None
Updated
None