IR 05000338/2013007

Errata to IR 05000338-13-007 and 05000339-13-007; 03/11/2013 - 03/25/2013; North Anna Power Station Units 1 and 2; Biennial Inspection of the Problem Identification and Resolution Program

ML13135A406
Person / Time
Site:	North Anna
Issue date:	05/15/2013
From:	Curtis Rapp NRC/RGN-II/DRP/RPB2
To:	Heacock D Virginia Electric & Power Co (VEPCO)
References
IR-13-007 Errata
Download: ML13135A406 (12)

Text

UNITED STATES May 15, 2013

SUBJECT:

ERRATA - NORTH ANNA POWER STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000338/2013007 AND 05000339/2013007

Dear Mr. Heacock:

On May 9, 2013, the US Nuclear Regulatory Commission (NRC) issued the subject inspection report for North Anna Power Plant, ADAMS ML13129A204. In reviewing this report, it was noted that we inadvertently issued it with report number 05000338, 339/2013008. The correct report number is 05000338, 339/2013007. Accordingly, we are enclosing the corrected pages to this report 05000338, 339/2013007 that documents the above change.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," 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 document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (The Public Electronic Reading Room).

I apologize for any inconvenience this error may have caused. If you have any questions, please contact me at 404-997-4674.

Sincerely,

/RA/

Curtis W. Rapp, Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos. 50-338, 50-339 License Nos. NPF-4, NPF-7

Enclosure:

As stated

_________________________ X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRP SIGNATURE /RA/

NAME CRapp DATE 5/16/2013 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

REGION II==

Docket Nos.: 05000338, 05000339 License Nos.: NPF-4, NPF-7 Report Nos.: 05000338/2013007 and 05000339/2013007 Licensee: Virginia Electric and Power Company Facility: North Anna Power Station, Units 1 and 2 Location: Mineral, VA Dates: March 11 - 15, 2013 March 25 - 29, 2013 Inspectors: R. Taylor, Senior Project Inspector, Team Leader R. Clagg, Resident Inspector, North Anna S. Ninh, Senior Project Engineer J. Quinones, Project Engineer C. Scott, Resident Inspector, Robinson Approved by: C. Rapp, Chief, Reactor Projects Branch 7 Division of Reactor Projects Enclosure

SUMMARY OF FINDINGS IR 05000338/2013-007 and 05000339/2013-007; March 11, 2013 - March 25, 2013; North Anna Power Station Units 1 and 2; Biennial Inspection of the Problem Identification and Resolution Program.

The inspection was conducted by a senior project inspector, senior project engineer, project engineer, and two resident inspectors. One Green Finding was identified. The significance of inspection findings are identified by their color i.e. (greater than Green, or Green, White, Yellow, or Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP) dated June 2, 2011. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy dated June 7, 2012. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4.

Identification and Resolution of Problems The inspectors concluded that, in general, problems were properly identified, evaluated, prioritized, and corrected. The licensee was effective at identifying problems and entering them into the corrective action program (CAP) for resolution, as evidenced by the relatively few number of deficiencies identified by external organizations (including the NRC) that had not been previously identified by the licensee, during the review period. Generally, prioritization and evaluation of issues were adequate, formal root cause evaluations for significant problems were adequate, and corrective actions specified for problems were acceptable. Overall, corrective actions developed and implemented for issues were generally effective and implemented in a timely manner.

The inspectors determined that overall, audits and self-assessments were adequate in identifying deficiencies and areas for improvement in the CAP, and appropriate corrective actions were developed to address the issues identified. Operating experience usage was found to be generally acceptable and integrated into the licensees processes for performing and managing work, and plant operations.

Based on discussions and interviews conducted with plant employees from various departments, the inspectors determined that personnel at the site felt free to raise safety concerns to management and use the CAP to resolve those concerns.

Cornerstone: Initiating Events Green: A self-revealing finding was identified for failure to establish and implement appropriate periodic preventive maintenance for replacement frequency of the C4 capacitor on the Speed Error Amplifier card B (1A08D) in accordance with VPAP-803, Preventive Maintenance Program. Consequently, the C4 capacitor failed due to age related degradation and caused an automatic reactor trip from 100 percent reactor power.

The licensees failure to establish and implement appropriate periodic preventive maintenance for replacement frequency of the C4 was a performance deficiency. The finding was more than minor because it was associated with the Initiating Events cornerstone attribute of equipment performance and adversely affected the associated cornerstone in that a reactor trip occurred Enclosure

corrective action to prevent recurrence was to revise VPAP-803 to ensure that component level replacement recommendations are obtained from component manufacturer guidance.

Analysis: The inspectors determined that the licensees failure to establish and implement appropriate periodic preventive maintenance for replacement frequency of the C4 capacitor on the Speed Error Amplifier card B (1A08D) in accordance with the vendors recommendations was a performance deficiency. The PD was more than minor because it was associated with the Initiating Events cornerstone attribute of equipment performance and adversely affected the associated cornerstone objective in that age-related failure of the C4 capacitor resulted in a reactor trip. Using NRC Manual Chapter 0609.04, SDP - Phase 1 screening dated June 19, 2012, the finding was determined to be of very low safety significance (Green) because it was a transient initiator, but did not contribute to both the likelihood of a reactor trip and the likelihood that mitigation equipment or functions would not be available. The finding did not have a cross-cutting aspect because the performance deficiency was not indicative of current plant performance.

Enforcement: This finding did not involve enforcement action. This finding was determined to be of very low safety significance (Green) and was entered into the licensees CAP as CR493091. This finding is identified as FIN 05000339/2013007-01, Failure to Implement Vendor Recommendations Causes an Automatic Reactor Trip.

4OA6 Exit Exit Meeting Summary On March 28, 2013, the inspectors presented the inspection results to Mr. G. Bischof and other members of the site staff. The inspectors confirmed that all proprietary information examined during the inspection had been returned to the licensee.

ATTACHMENT: SUPPLEMENTAL INFORMATION Enclosure

KEY POINTS OF CONTACT Licensee personnel:

G. Bischof, Site Vice President F. Mladen, Plant Manager B. Anhold, Component Engineer J. Daugherty, Manager Maintenance F. Errico, CAP Supervisor P. Harper, CAP Coordinator E. Hendrixson, Site Engineering Director P. Kemp, Licensing Supervisor J. Leberstien, Licensing S. Morris, Engineering Programs Manager J. Schleser, Organizational Effectiveness Manager NRC personnel:

G. Kolcum, Senior Resident Inspector G. Hopper, Chief, Branch 7, Division of Reactor Projects LIST OF REPORT ITEMS Opened and Closed 05000339/2013-007-01 FIN 05000339/2013007-01 Failure to Implement Vendor Recommendations Causes an Automatic Reactor Trip Closed 05000339/2012-001-00 LER Automatic Reactor Trip Resulting From A Card Failure (Section 4OA3)

LIST OF DOCUMENTS REVIEWED Procedures ER-AA-MRL-10, Maintenance Rule Program, Revision 4 ER-AA-PRS-1002, Equipment Reliability Health Report, Revision 7 ER-AA-SYS-1002, System Engineering Walkdowns, Revision 4 ER-AA-SYS-1001, System Health Report, Revision 6 ER-AA-SYS-1003, System Performance Monitoring, Revision 3 OP-AA-101, Operational Decision Making, Revision 10 PI-AA-10, Performance Improvement Process, Revision 0 PI-AA-100-1007, Operating Experience Program, Revision 3 PI-AA-200-2001, Trending, Revision 3 PI-AA-300-3004, Cause Evaluation Methods, Revision 2 PI-AA-300-3003, Common Cause Evaluation, Revision 0 PI-AA-200-2002, Effectiveness Reviews, Revision 5 PI-AA-300-3001, Root Cause Evaluation, Revision 3 OP-AA-102, Operability Determination, Revision 9 PI-AA-100, Performance Monitoring, Revision 4 PI-AA-200, Corrective Action, Revision 20 Attachment