IR 05000338/2014007

IR 05000338-14-007, 05000339-14-007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications

ML14136A331
Person / Time
Site:	North Anna
Issue date:	05/15/2014
From:	Nease R NRC/RGN-II/DRS/EB1
To:	Heacock D Virginia Electric & Power Co (VEPCO)
References
IR-14-007
Download: ML14136A331 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 May 15, 2014 Mr. David President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT: NORTH ANNA POWER STATION - NRC EVALUATION OF CHANGES, TESTS, AND EXPERIMENTS AND PERMANENT PLANT MODIFICATIONS INSPECTION REPORT 05000338/2014007 AND 05000339/2014007

Dear Mr. Heacock:

On April 17, 2014, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your North Anna Power Station Units 1 and 2, and discussed the results of this inspection with Mr. Mladen 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 (PARS) component of NRC's Agencywide Documents Access and Managem ent 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.: 05000338, 05000339

License Nos.: NPF-4, NPF-7

Enclosures:

Inspection Report 05000338/2014007 and 05000339/2014007 w/Attachment: Supplementary Information

REGION II==

Docket Nos.: 50-338, 50-339

License Nos.: NPF-4, NPF-7

Report Nos.: 05000338/2014007, 05000339/2014007

Licensee: Virginia Electric and Power Company (VEPCO)

Facility: North Anna Power Station, Units 1 and 2

Location: Mineral, Virginia 23117

Dates: March 31, 2014 - April 17, 2014

Inspectors: E. Stamm, Senior Reactor Inspector (Team Leader) M. Riley, Reactor Inspector J. Dymek, Reactor Inspector

Approved by: Rebecca L. Nease, Chief Engineering Branch 1 Division of Reactor Safety

SUMMARY

Inspection Report (IR) 05000338/2014007, 05000339/2014007; 03/31/2014-04/17/2014; North Anna Power Station, Units 1 and 2; Evaluations of Changes, Tests, and Experiments and Permanent Plant Modifications.

This report covers a two-week, on-site inspection by one senior reactor inspector and two reactor inspectors. 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 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

(71111.17T)

a. Inspection Scope

Evaluations of Changes, Tests, and Experiments

The team reviewed seven safety evaluations performed pursuant to Title 10, Code of Federal Regulations (CFR) 50.59 to determine if the evaluations were adequate and that prior NRC approval was obtained as appropriate. The team also reviewed 15 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 seven samples of evaluations and 15 samples of screenings as defined in Inspection Procedure (IP) 71111.17-04.

Permanent Plant Modifications: The team reviewed six permanent plant modifications that had been installed in the plant during the last three years. The modifications reviewed are listed below:

• DCP-04-116 - Replacement of RWST Refrigeration Units

• DCP-08-101 - Emergency Condensate Storage Tank Level Indicator Replacements

• NA-09-00170 - EDG Lube Oil S-line Flexible Connections

• NA-11-00006 - Phase 2 to Install Alternate Power Supply to Spent Fuel Pit Cooling Pump 1-FC-P-1A

• NA-12-00053 - Replacement and Elimination of 1H Undervoltage Relays

• NA-13-00041 - Appendix R - Emergency Switchgear Isolation Switch for Service Water 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 standar ds 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 April 17, 2014, the team presented inspection results to Mr. Mladen and other members of the licensee's 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

J. Bischof, Site Vice President

F. Mladen, Plant Manager

J. Daugherty, Director, Nuclear Station Safety & Licensing

E. Hendrixson, Director, Nuclear Site Engineering

R. Garver, Manager, Nuclear Design Engineering, Site Engineering

R. Klearman, Manager, Nuclear Oversight

P. Kemp, Supervisor, Station Licensing

P. Saksvig, Supervisor, Procurement Engineering

R. Kimble, Nuclear Engineer III, Site Engineering

M. Whalen, Technical Specialist, Licensing

NRC personnel

G. Kolcum, Senior Resident Inspector, North Anna

R. Clagg, Resident Inspector, North Anna

LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED

Opened

None

Closed

None

Discussed

None Updated None