IR 05000338/2007501
| ML072490246 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/06/2007 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Christian D Virginia Electric & Power Co (VEPCO) |
| References | |
| IR-07-501 | |
| Download: ML072490246 (13) | |
Text
September 6, 2007
SUBJECT:
NORTH ANNA POWER STATION - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000338/2007501 AND 05000339/2007501
Dear Mr. Christian:
On August 10, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at your North Anna Power Station. The enclosed inspection report documents the inspection results, which were discussed on August 10, 2007, with Mr. L. Lane, Plant Manager, and other members of your staff.
The inspection examined activities conducted under your licenses as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
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).
Sincerely,
/RA Ruben Hamilton for/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-338, 50-339 License Nos. NPF-4, NPF-7
Enclosure:
NRC Inspection Report No. 05000338/2007501 AND 05000339/2007501 w/Attachment: Supplemental Information
REGION II==
Docket Nos:
50-338, 50-339 License Nos:
05000338/2007501 AND 05000339/2007501 Licensee:
Virginia Electric and Power Company Facility:
North Anna Power Station Location:
1024 Haley Drive Mineral, VA 23117 Dates:
August 6 - 10, 2007 Inspector:
L. Miller, Senior Emergency Preparedness Inspector Approved by:
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety
Enclosure
SUMMARY OF FINDINGS
IR 05000338/2007501 and 05000339/2007501;08/06-10/2007;North Anna Power Station Units and 2; Baseline Inspection.
The report covered an announced inspection by one emergency preparedness inspector. The 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.
NRC-Identified and Self-Revealing Findings
Cornerstone: Emergency Preparedness
No findings of significance were identified.
Licensee-Identified Violations
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP2 Alert and Notification System Evaluation
a. Inspection Scope
The inspector evaluated the adequacy of licensee methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, Alert and Notification System (ANS) Evaluation. The applicable planning standard 10 CFR Part 50.47(b)(5) and its related 10 CFR Part 50, Appendix E, Section IV.D requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Revision 1 was also used as a reference.
The inspector reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP3 Emergency Response Organization (ERO) Staffing and Augmentation System
a. Inspection Scope
The inspector reviewed the ERO augmentation staffing requirements and the process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The inspector reviewed the results of the February 22, 2005, unannounced off-hours augmentation drills and reviewed the backup notification systems. The qualification records of key position ERO personnel was reviewed to ensure all ERO qualifications were current. A sample of problems identified from augmentation drills or system tests performed since the last inspection were reviewed to assess the effectiveness of corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, Emergency Response Organization Staffing and Augmentation SystemTesting. The applicable planning standard and 10 CFR 50.47(b)(2) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP4 Emergency Action Level (EAL) and Emergency Plan Changes
a. Inspection Scope
The inspectors review of revisions to the emergency plan (EP), implementing procedures and EAL changes was performed to determine that changes had not decreased the effectiveness of the EP. The inspector also evaluated the associated 10 CFR 50.54(q) reviews associated with the non-administrative emergency plan, implementing procedures and EAL changes. The Emergency Plan, revision 33, was reviewed and covered the period from November 2006 to August 2007.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, Emergency Action Level and Emergency Plan Changes. The applicable planning standard and 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUREG-0654, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Regulatory Guide 1.101 were also used as references. This inspection activity represents one sample on an annual basis.
The inspector reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP5 Correction of Emergency Preparedness Weaknesses and Deficiencies
a. Inspection Scope
The inspector reviewed the corrective actions identified through the EP program to determine the significance of the issues and to determine if repeat problems were occurring. The facilitys self-assessments and audits were reviewed to assess the licensees ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, the inspector reviewed licensees self-assessments and audits to assess the completeness and effectiveness of all EP-related corrective actions.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, Correction of Emergency Preparedness Weaknesses. The applicable planning standard and 10 CFR 50.47(b)(14) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
The inspector reviewed various documents which are listed in the Attachment to this report.
Findings No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification
a. Inspection Scope
The inspector reviewed the licensees procedure for developing the data for the Emergency Preparedness PIs which are:
- (1) Drill/Exercise Performance (DEP);
- (2) ERO Drill Participation; and
- (3) Alert and Notification System (ANS) Reliability. The inspector examined data reported to the NRC for the period October 1, 2006 to June 30, 2007.
Procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspector verified the accuracy of the PI for ERO DEP through review of a sample of drill and event records.
The inspector reviewed selected training records to verify the accuracy of the PI for ERO drill participation for personnel assigned to key positions in the ERO. The inspector verified the accuracy of the PI for ANS reliability through review of a sample of the licensees records of periodic system tests.
The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. The applicable PI, 10 CFR 50.9 and Nuclear Energy Institute (NEI) 99-02, Revision 4, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria. This inspection activity represents three samples on an annual basis.
The inspector reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
4OA6 Meetings, including Exit
On August 10, 2007, the inspector presented the inspection results to Mr. L. Lane, Plant Manager, and other members of his staff. The inspector confirmed that proprietary information was not provided or taken during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- L. Lane, Plant Manager
- P. Kemp, Director Station Safety & Licensing (Acting)
- P. Serra, Manager Emergency Preparedness
- J. Costello, Supervisor Emergency Preparedness
- J. Leberstien, Technical Consultant - Licensing
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None