IR 05000324/2008501

IR 05000325-08-501 and 05000324-08-501,on 11/17/2008 - 11/20/2008, Brunswick Steam Electric Plant, Units 1 and 2; Baseline Inspection

ML083570226
Person / Time
Site:	Brunswick
Issue date:	12/22/2008
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Waldrep B Carolina Power & Light Co
References
IR-08-501
Download: ML083570226 (12)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION ber 22, 2008

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000325/2008-501 AND 05000324/2008-501

Dear Mr. Waldrep:

On November 20, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Brunswick Steam Electric Plant, Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on November 20, 2008, with you 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, its enclosure, and your response, if any, 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 Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Brian Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket No. (s): 50-325, 50-324 License No.(s): DPR-71, DPR-62

Enclosure:

Inspection Report 05000325/2008-501 and 05000324/2008-501 w/Attachment: Supplemental Information (

REGION II==

Docket Nos.: 05000325, 05000324 License Nos.: DPR-71, DPR-62 Report No.: 05000325/2008-501 and 05000324/2008-501 Licensee: Carolina Power and Light Company Facility: Brunswick Steam Electric Plant, Units 1 and 2 Location: Southport, NC Dates: November 17, 2008 through November 20, 2008 Inspectors: Lee Miller, Senior Emergency Preparedness Inspector Jim Dodson, Senior Project Engineer Joe Austin, Senior Resident Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000325/2008-501 and 05000324/2008-501; 11/17/2008 - 11/20/2008; Brunswick Steam

Electric Plant, Units 1 and 2; Baseline Inspection.

The report covered an announced inspection by an emergency preparedness inspector, a project engineer, and a resident inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

Licensee-Identified Violations

None

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP1 Exercise Evaluation

a. Inspection Scope

Prior to the inspection activity, the inspectors conducted an in-office review of the exercise objectives and scenario submitted to the NRC to determine if the exercise would test major elements of the emergency plan as required by 10 CFR 50.47(b)(14).

This inspection activity represents one sample on a biennial cycle.

The onsite inspection consisted of the following review and assessment:

• The adequacy of the licensees performance in the biennial exercise conducted on November 18, 2008, was reviewed and assessed regarding the implementation of the Risk Significant Planning Standards (RSPSs) in 10 CFR 50.47 (b)(4), (5), (9),and (10), which address emergency classification, offsite notification, radiological assessment, and protective action recommendations, respectively.

• The overall adequacy of the licensees emergency response facilities with regard to NUREG-0696, Functional Criteria for Emergency Response Facilities and Emergency Plan commitments. The facilities assessed were the Control Room simulator, Technical Support Center (TSC), Operations Support Center (OSC) and Emergency Operations Facility (EOF).

• Other performance areas besides the RSPS, such as the emergency response organizations (ERO) recognition of abnormal plant conditions, command and control, intra- and inter-facility communications, prioritization of mitigation activities, utilization of repair and field monitoring teams, interface with offsite agencies, and the overall implementation of the emergency plan and its implementing procedures.

• Past performance issues from NRC inspection reports and Federal Emergency Management Agency (FEMA)/Department of Homeland Security (DHS) exercise reports to determine effectiveness of corrective actions as demonstrated during this exercise to ensure compliance with 10 CFR 50.47(b)(14).

• The post-exercise critique process and the presentation to the licensee's senior management conducted on November 20, 2008, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.IV.F.2.g.

The inspectors reviewed various documents which are listed in the Attachment to this report.

b. Findings

No findings of significance were identified.

1EP4 Emergency Action Level and Emergency Plan Changes

a. Inspection Scope

Since the last NRC inspection of this program area, Revision 70 of the Radiological Emergency Response Plan was implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in the effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR Part 50. The inspectors conducted a sampling review of the Plan changes and implementing procedure changes made between September 30, 2007 and October 31, 2008 to evaluate for potential decreases in effectiveness of the Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes.

Therefore, these changes remain subject to future NRC inspection in their entirety.

The inspection was conducted in accordance with NRC Inspection Procedure 71114, 04, AEmergency 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 inspectors reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the emergency action level and emergency plan changes on an annual basis.

b. Findings

No findings of significance were identified.

4OA1 Performance Indicator Verification

Cornerstone: Emergency Preparedness

The inspectors sampled licensee submittals for three Performance Indicators (PI) listed below. For each of the submittals reviewed, the inspectors reviewed the period from October 1, 2007 through September 30, 2008. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in Nuclear Energy Institute (NEI) 99-02, ARegulatory 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 performance indicator reports and discussed the methods for compiling and reporting the PIs with cognizant emergency preparedness personnel. The inspectors 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.

Reviewed documents are listed in the Attachment to this report.

b. Findings

No findings of significance were identified.

4OA5 Other Activities

.1 (Closed) NRC Temporary Instruction (TI) 2525/175, Emergency Response Organization,

Drill/Exercise Performance Indicator, Program Review The inspectors completed Temporary Instruction TI 2515/175, Emergency Response Organization, Drill/Exercise Performance Indicator, Program Review. Appropriate documentation of the results was provided to NRC, HQ, as required by the TI.

This completes the Region II inspection requirements for this TI for Brunswick Steam Electric Plant.

4OA6 Meetings, including Exit

On November 20, 2008, the lead inspector presented the inspection results to Mr. B.

Waldrep and other members of his staff. The inspectors confirmed that proprietary information was not provided during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

B. Waldrep, Vice President

E. Wills Plant General Manager

P. Mental Manager, Support Services

J. Titrington Manager, Nuclear Assessment Section

M. Williams Manager, Training

G. Atkinson Supervisor, Licensing/Regulatory Programs

K. Crocker Supervisor, Emergency Preparedness