IR 05000325/2007501
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December 18, 2007
Carolina Power and Light CompanyATTN: Mr. J. ScarolaVice PresidentBrunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461
SUBJECT: BRUNSWICK STEAM ELECTRIC PLANT - NRC EMERGENCYPREPAREDNESS INSPECTION REPORT 05000325/2007501 and 05000324/2007501
Dear Mr. Scarola:
On November 30, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed anEmergency Preparedness inspection at your Brunswick Steam Electric Plant. The enclosed inspection report documents the inspection results, which were discussed on November 29, 2007, 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 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 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).
Sincerely,/RA/Brian R. Bonser, ChiefPlant Support Branch 1 Division of Reactor SafetyDocket Nos. 50-325, 50-324License Nos. DPR-71, DPR-62
Enclosure:
NRC Inspection Report No. 05000325/2007501, 05000324/2007501
w/Attachment:
Supplemental Informationcc w/encl: Se Page 2 CP&L2Benjamin C. Waldrep, DirectorSite Operations Brunswick Steam Electric Plant Carolina Power & Light Company Electronic Mail DistributionJ. Paul Fulford, ManagerPerformance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company Electronic Mail DistributionTerry D. Hobbs, Plant General ManagerBrunswick Steam Electric Plant Carolina Power & Light Company P. O. Box 10429 Southport, NC 28461J. Paul Fulford, ManagerPerformance Evaluation and Regulatory Affairs PEB 5 Carolina Power & Light Company P. O. Box 1551 Raleigh, NC 27602-1551Donald L. GriffithManager - Training Progress Energy Carolinas, Inc.
Brunswick Steam Electric Plant Electronic Mail DistributionRandy C. IveyManager - Support Services Progress Energy Carolinas, Inc.
Brunswick Steam Electric Plant Electric Mail DistributionGarry D. Miller, ManagerLicense Renewal Progress Energy Electronic Mail DistributionAnnette H. Pope, SupervisorLicensing/Regulatory Programs Carolina Power and Light Company Electronic Mail DistributionDavid T. ConleyAssociate General Counsel - Legal Dept.
Progress Energy Service Company, LLC Electronic Mail DistributionJames RossNuclear Energy Institute Electronic Mail DistributionJohn H. O'Neill, Jr.Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Washington, DC 20037-1128Beverly Hall, Chief, RadiationProtection Section N. C. Department of Environment and Natural Resources Electronic Mail Distribution Peggy ForceAssistant Attorney General State of North Carolina Electronic Mail DistributionChairman of the North Carolina Utilities Commission c/o Sam Watson, Staff Attorney Electronic Mail DistributionRobert P. GruberExecutive Director Public Staff NCUC 4326 Mail Service Center Raleigh, NC 27699-4326cc: Continued on Page 3 CP&L3cc: Continued from Page 2Public Service CommissionState of South Carolina P. O. Box 11649 Columbia, SC 29211David R. SandiferBrunswick County Board of Commissioners P. O. Box 249 Bolivia, NC 28422Warren LeeEmergency Management Director New Hanover County Department of Emergency Management 230 Government Center Drive Suite 115 Wilmington, NC 28403NRC Resident InspectorU.S. Nuclear Regulatory Commission 8470 River Road, SE Southport, NC 28461 December 18, 2007 Carolina Power and Light CompanyATTN: M
SUMMARY OF FINDINGS
IR 05000325/2007501, 05000324/2007501;11/26-30/2007;Brunswick Steam Electric Plant,
Units 1 and 2; Baseline Inspection.The report covered an announced inspection by one emergency preparedness inspector. TheNRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process."A.NRC-Identified and Self-Revealing FindingsNo findings of significance were identified.
B.Licensee-Identified Violations
. None Enclosure
REPORT DETAILS
1.REACTOR SAFETYCornerstone: Emergency Preparedness 1EP2 Alert and Notification System Testing
a. Inspection Scope
The inspector evaluated the adequacy of licensee's methods for testing the alert and notification system in accordance with NRC Inspection Procedure 71114, Attachment 02, "Alert and Notification System (ANS) Testing". 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 thisreport. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis.
b. Findings
No findings of significance were identified.1EP3 Emergency Response Organization (ERO) Staffing and Augmentation System
a. Inspection Scope
The inspector reviewed the licensee's ERO augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. 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 inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 03, "Emergency Response Organization (ERO) Augmentation Testing."
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 various documents which are listed in the Attachment to thisreport. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on an biennial basis.
4Enclosureb.FindingsNo findings of significance were identified.1EP4 Emergency Action Level (EAL) and Emergency Plan Changes
a. Inspection Scope
The inspector's review of revisions to the emergency plan, implementing proceduresand EAL changes was performed to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q)reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The inspector reviewed Brunswick Emergency Plan Revision 69 and changes to the implementing procedures from November 1, 2006 to November 7, 2007. The inspection was conducted in accordance with NRC Inspection Procedure 71114,Attachment 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 NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans" and Regulatory Guide 1.101 were also used as references.The inspector reviewed various documents which are listed in the Attachment to thisreport. This inspection activity satisfied one inspection sample for the EAL and emergency plan changes on an annual basis.
b. Findings
No findings of significance were identified. 1EP5 Correction of Emergency Preparedness Weaknesses
a. Inspection Scope
The inspector reviewed the corrective actions identified through the Emergency Preparedness (EP) program to determine the significance of the issues and to determine if repeat problems were occurring. The facility's self-assessments and audits were reviewed to assess the licensee's ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspector reviewed licensee's 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.
5EnclosureThe inspector reviewed various documents which are listed in the Attachment to thisreport. This inspection activity satisfied one inspection sample for the correction of emergency preparedness weaknesses on an biennial basis.
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1Performance Indicator Verification
a. Inspection Scope
The inspector sampled licensee submittals for the three Performance Indicators (PIs) listedbelow for units one and two. For each of the submittals reviewed, the inspector looked at the period from October 1, 2006 to September 30, 2007. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Indicator Guideline," Revision 5, were used to verify the basis in reporting for each data element.
- Emergency Response Organization Drill/Exercise Performance (DEP)* Emergency Response Organization Readiness (ERO)
- Alert and Notification System Reliability (ANS) The inspectors reviewed portions of the raw PI data developed from monthly performanceindicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspector also independently screened drill and exercise opportunity evaluations, drill participation reports, and drill evaluations.
Selected reported values were calculated to verify their accuracy. The inspectors compared graphical representations from the most recent PI report to the raw data to verify that the data was correctly reflected in the report.The inspection was conducted in accordance with NRC Inspection Procedure 71151,"Performance Indicator Verification." The inspector reviewed various documents which are listed in the Attachment to this report. This inspection satisfied three inspection samples for PI verification on an annual basis.
b. Findings
No findings of significance were identified.
6Enclosure4OA6Meetings, including ExitOn November 30, 2007, the lead inspector presented the inspection results to Mr. J. Scarola,Vice President - Brunswick Nuclear Plant , and other members of his staff. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT: