IR 05000280/2015007
| ML15303A370 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/30/2015 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | Heacock D Virginia Electric & Power Co (VEPCO) |
| Linda K. Gruhler 404-997-4633 | |
| References | |
| IR 2015007 | |
| Download: ML15303A370 (11) | |
Text
October 30, 2015
SUBJECT:
SURRY POWER STATION - U.S. NUCLEAR REGUALTORY COMMISSION EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000280/2015007 AND 05000281/2015007
Dear Mr. Heacock:
On October 1, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Surry Power Station, Units 1 and 2, and discussed the results of this inspection with Mr. R. Simmons and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report (IR).
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 (10 CFR) 2.390, Public inspections, exemptions, requests for withholding of the NRCs "Agency Rules of Practice and Procedure," a copy of this letter, and its Enclosure, will be available electronically for public inspection in the NRC Public Document Room, or from the Publicly Available Records (PARS)
component of NRC's Agencywide Documents Access and Management System (ADAMS);
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37
Enclosure:
NRC IR 05000280 and 281/2015007 w/Attachment: Supplementary Information
REGION II==
Docket Nos:
50-280 and 50-281
License Nos:
Report Nos:
05000280/2015007 and 05000281/2015007
Licensee:
Virginia Electric and Power Company (VEPCO)
Facility:
Surry Power Station, Units 1 and 2
Location:
5850 Hog Island Road Surry, VA 23883
Dates:
September 14, 2015, through October 1, 2015
Inspectors:
Robert N. Patterson, Acting Senior Reactor Inspector (Team Leader)
Michael S. Coursey, Reactor Inspector Jasmine A. Gilliam, Reactor Inspector Nicholas J. Hansing, Technical Reviewer, HQ
Approved by:
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
SUMMARY
Inspection Report (IR) 05000280/2015007 and 05000281/2015007; 9/14/2015 - 10/1/2015;
Surry Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications
This report covers a 2-week onsite inspection by one senior reactor inspector, two reactor inspectors, and one technical reviewer. No findings or violations were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 5.
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 of the Code of Federal Regulations (10 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 16 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
- 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, Rev. 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.
Permanent Plant Modifications: The team reviewed six permanent plant modifications that had been installed in the plant during the last 3 years. The modifications reviewed are listed below:
- DCP 06-045, Replace SW Carbon Steel Piping With Copper-Nickel Pipe Class or Coated Piping/Surry/ Unit 1
- DC SU-10-01041, High Head Safety Injection MOV Valve Pressure Locking Modifications/S/1&2
- DC SU-11-01108, Set Point Change For Emergency Service Water Temperature Switches
- DC SU-11-00015, Reactor Coolant Pump (RCP) Seal Replacement (2-RC-P-1B)
/S/2
- DC SU-11-01049, Loop Stop MOV Stem Connection MOD/S/1&2 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
- 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.
b. Findings
No findings were identified.
4OA6 Meetings, Including Exit
On October 1, 2015, the team presented inspection results to Mr. Simmons 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
- R. Simmons, Plant Manager
- D. Lawrence, Director of Nuclear Safety and Licensing
- J. Rosenberger, Director of Nuclear Engineering
- B. Garber, Licensing Supervisor
- J. Pollard, Engineer III, Licensing
- N. Dodenhoff, Electrical Design Supervisor
- B. Day, Design Manager
- R. Scanlan, Maintenance Manager
NRC personnel
- S. Rose, Chief, Projects Branch 5, Division of Reactor Projects
- P. McKenna, Senior Resident Inspector, Division of Reactor Projects
- C. Jones, Resident Inspector, Division of Reactor Projects