IR 05000369/2006009

IR 05000369-06-009, 05000370-06-009; on 10/23/2006 - 10/27/2006; McGuire Nuclear Station; Emergency Preparedness Baseline Inspection

ML063200447
Person / Time
Site:	Mcguire, McGuire
Issue date:	11/13/2006
From:	Gordon Peterson Duke Energy Carolinas, Duke Power Co
To:	Brian Bonser NRC/RGN-II/DRS/PSB1
References
IR-06-009
Download: ML063200447 (13)

Text

November 13, 2006Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC ATTN:Mr. G. R. PetersonVice President McGuire Nuclear Station12700 Hagers Ferry Road Huntersville, NC 28078-8985SUBJECT:McGUIRE NUCLEAR STATION - NRC INSPECTION REPORT NOS. 05000369/2006009 AND 05000370/2006009

Dear Mr. Peterson:

On October 23-27, 2006, the U. S. Nuclear Regulatory Commission (NRC) conducted aninspection at your McGuire Nuclear Station, Units 1 and 2. The enclosed inspection report documents the inspection findings, which were discussed on October 27, 2006 with you and other members of your staff.The inspection examined activities conducted under your license as they relate to safety andcompliance with the Commission's rules and regulations and with the conditions of your license.

The inspector 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 itsenclosure will be available electronically for public inspection in the NRC Public DocumentRoom 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).Should you have any questions concerning this letter, please contact us.

Sincerely,

/RA/Brian R. Bonser, ChiefPlant Support Branch 1 Division of Reactor SafetyDocket Nos. 50-369, 50-370License Nos. NPF-9, NPF-17

Enclosure:

(See page 2)

Duke Power Company LLC 2Enclosure: NRC Inspection Report 05000369/2006009 and 05000370/2006009 w/Attachment: Supplemental Information

REGION IIDocket Nos:50-369, 50-370 License Nos:NPF-9, NPF-17 Report Nos:05000369/2006009, 05000370/2006009 Licensee:Duke Energy Corporation Facility:McGuire Nuclear Station, Units 1 and 2 Location:Huntersville, NC 28078 Dates:October 23-27, 2006 Inspector:J. Kreh, Emergency Preparedness Inspector Approved by:Brian R. Bonser, ChiefPlant Support Branch 1 Division of Reactor Safety

SUMMARY OF FINDINGS

IR 05000369/2006009, 05000370/2006009; 10/23-27/2006; McGuire Nuclear Station, Units 1and 2; Emergency Preparedness Baseline InspectionThis report covers an announced inspection conducted by a Region II emergency preparednessinspector. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.A.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

B.Licensee-Identified Violations

.

None

REPORT DETAILS

1.REACTOR SAFETYCornerstone: Emergency Preparedness 1EP2 Alert and Notification System (ANS) Evaluation

a. Inspection Scope

The inspector evaluated the adequacy of licensee methods for testing the alert andnotification system in accordance with NRC Inspection Procedure 71114, 02, "Alert and Notification System Evaluation." The applicable planning standard 10 CFR 50.47(b)(5) and related requirements contained in Section IV.D of Appendix E to 10 CFR Part 50 were used as reference criteria. The evaluation 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; and Federal Emergency Management Agency (FEMA) Report REP-10, "Guide for the Evaluation of Alert and Notification Systems for Nuclear Power Plants" were also applied. This inspection activity represents one sample on a biennial cycle.The inspector reviewed various documents which are listed in the Attachment to thisreport.

b. Findings

No findings of significance were identified.1EP3 Emergency Response Organization (ERO) Augmentation

a. Inspection Scope

The inspector reviewed the ERO augmentation staffing requirements and the processfor notifying ERO personnel to ensure the readiness of key staff for responding to an event and the capability for timely facility activation. The results of the annual ERO augmentation drills were reviewed. The inspector examined the provisions for a backup notification system. A sample of problems identified from augmentation drills and ERO pager system tests was reviewed to assess the effectiveness of corrective actions. The inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 03, "Emergency Response Organization Augmentation." The applicable planning standard 10 CFR 50.47(b)(2) and related requirements contained in Appendix E to 10 CFR Part 50 were used as reference criteria. This inspection activity represents one sample on a biennial cycle.The inspector reviewed various documents which are listed in the Attachment to thisreport.

b. Findings

No findings of significance were identified.1EP4 Emergency Action Level (EAL) and Emergency Plan Changes

a. Inspection Scope

The inspector reviewed the Emergency Plan changes made in Revisions 05-1, 06-1,and 06-2 (the latter was the version in effect at the time of the inspection). The EAL modifications made in Revisions 06-1 (to address NRC Bulletin 2005-02) and 06-2 were reviewed in detail.The inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 04, "Emergency Action Level and Emergency Plan Changes." The applicable planning standard 10 CFR 50.47(b)(4) and related requirements contained in 10 CFR 50.54(q) and Appendix E to 10 CFR Part 50 were used as reference criteria.

This inspection activity represents one sample on an annual cycle.The inspector reviewed various documents which are listed in the Attachment to thisreport.

b. Findings

No findings of significance were identified.1EP5 Correction of Emergency Preparedness (EP) Weaknesses and Deficiencies

a. Inspection Scope

The inspector reviewed the corrective actions identified through the EP program in aneffort to ascertain the significance of the issues and to determine whether repetitive problems were occurring. The facility's self-assessments and audits were reviewed to evaluate the licensee's ability to be self-critical, thus avoiding complacency and degradation of its EP program, and to assess the completeness and effectiveness of a sample of EP-related corrective actions. No emergency declarations were made since the last inspection of this program area (September 2004).The inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 05, "Correction of Emergency Preparedness Weaknesses and Deficiencies." The applicable planning standard 10 CFR 50.47(b)(14) and related requirements contained in Appendix E to 10 CFR Part 50 were used as reference criteria. This inspection activity represents one sample on a biennial cycle.The inspector reviewed various documents which are listed in the Attachment to thisreport.

b. Findings

No findings of significance were identified.4.OTHER ACTIVITIES 4OA1Performance Indicator (PI) Verification

a. Inspection Scope

The inspector reviewed the licensee's procedure for developing the data for the EP PIs,which are:

(1) Drill and 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 five-quarter period July 1, 2005 to September 30, 2006. 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 training 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 licensee's records of periodic system tests. The inspection was conducted in accordance with NRC Inspection Procedure 71151,"Performance Indicator Verification." The applicable planning standard 10 CFR 50.9 and NEI 99-02,"Regulatory Assessment Performance Indicator Guidelines," Revisions 3 and 4, were used as reference criteria. This inspection activity represents three samples on an annual cycle.The inspector reviewed various documents which are listed in the Attachment to thisreport.

b. Findings

No findings of significance were identified.4OA6Meetings, including ExitOn October 27, 2006, the inspector presented the inspection results to Mr. G. Peterson,Vice President, and other members of his staff.

The inspector confirmed that proprietary information was not provided during the inspection.ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

A. Beaver, Emergency Planner

J. Cooke, Emergency Planner

J. Kammer, Safety Assurance Manager

K. Murray, Emergency Planning Manager

J. Painter, Emergency Planner

G. Peterson, Site Vice President

J. Thomas, Regulatory Compliance Manager

ITEMS OPENED, CLOSED, AND DISCUSSED

None

Section 1EP2: Alert and Notification System EvaluationPlans and ProceduresEmergency Planning Functional Area Manual (FAM), Section 3.3, Alert and Notification System

(Siren Program), Rev. 6