IR 05000269/2007501
| ML072550254 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/12/2007 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | Brandi Hamilton Duke Energy Carolinas, Duke Power Co |
| References | |
| IR-07-501 | |
| Download: ML072550254 (11) | |
Text
September 12, 2007
SUBJECT:
OCONEE NUCLEAR STATION - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000269/2007501, 05000270/2007501, AND 05000287/2007501
Dear Mr. Hamilton:
On August 17, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at your Oconee Nuclear Station. The enclosed inspection report documents the inspection results, which were discussed on August 17, 2007, with Mr. D.
Baxter, Station Manager, and other members of your staff.
The inspection examined activities conducted under your license 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/
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-269, 50-270, 50-287 License Nos. DRP-38, DRP-47, DRP-55
Enclosure:
NRC Inspection Report No. 05000269/2007501, 05000270/2007501 AND 05000287/2007501 w/Attachment: Supplemental Information
REGION II==
Docket Nos:
50-269, 50-270, 50-287 License Nos:
DRP-38, DRP-47, DRP-55 Report Nos:
05000269/2007501, 05000270/2007501, AND 05000287/2007501 Licensee:
Duke Energy Corporation Facility:
Oconee Nuclear Station Location:
7812B Rochester Highway Seneca, SC 29672 Dates:
August 13 - 17, 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 05000369/2007-501, 05000270/2007-501, 05000287/2007-501;08/13/2007 - 08/17/2007;
Oconee Nuclear Station; 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
None
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) Augmentation System
a. Inspection Scope
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, Emergency Response Organization (ERO) Augmentation System.
The applicable planning standard, 10 CFR 50.47(b)(2) and its related 10 CFR 50, Appendix E requirements were used as reference criteria.
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 October 24, 2006, unannounced off-hours augmentation drill and reviewed the backup notification systems. The qualification records of key position ERO personnel were 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 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, implementing procedures and EAL changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector also evaluated the associated 10 CFR 50.54(q)reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Emergency Plan Revisions 2006-04 and 2007-01 were reviewed and covered the period from July 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 (PS), 10 CFR 50.47(b)(4) and its related 10 CFR 50, Appendix E requirements were used as reference criteria. The criteria contained in NUMARC/NESP-007, Methodology for Development of Emergency Action Levels, Revision 2 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, 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 and Deficiencies. The applicable planning standard, 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 July 2006 to June 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 17, 2007, the lead inspector for the emergency preparedness inspection presented the inspection results to Mr. D. Baxter, Station 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
- D. Baxter, Station Manager
- L. Nicholson, Safety Assurance Manager
- R. Brown, Emergency Preparedness Manager
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None