IR 05000259/2011501
| ML12009A148 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/06/2012 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR-11-501 | |
| Download: ML12009A148 (12) | |
Text
January 6, 2012
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000259/2011501, 05000260/2011501 AND 05000296/2011501
Dear Mr. Shea:
December 9, 2011
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000259/2011501, 05000260/2011501 AND 05000296/2011501
Dear Mr. Shea:
On December 9, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Browns Ferry Plant. The enclosed inspection report documents the inspection results, which were discussed on December 9, 2011, with Mr. K. Polson and other members of licensee 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.: 50-259, 50-260, 50-296 License No.: DPR-33, DPR-52, DPR-68
Enclosure:
Inspection Report 05000259/2011501, 05000260/2011501 and 05000296/2011501 w/Attachment: Supplemental Information
REGION II==
Docket Nos.:
05000259, 05000260, 05000296
License Nos.:
Report No.:
05000259/2011501, 05000260/2011501 AND 05000296/2011501
Licensee:
Tennessee Valley Authority
Facility:
Browns Ferry Nuclear Plant, Units 1, 2 and 3
Location:
Athens, AL 35611
Dates:
December 5, 2011, through December 9, 2011
Inspectors:
M. Speck, Senior Emergency Preparedness Inspector
J. Beavers, Emergency Preparedness Inspector
K. Korth, Reactor Technology Instructor
C. Fontana, Emergency Response Coordinator
Approved by:
Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety
Enclosure
SUMMARY OF FINDINGS
IR 05000259, 05000260, 05000296/2011501; 12/05/2011 - 12/09/2011; Browns Ferry Nuclear
Plant, Units 1, 2, and 3; Exercise and Baseline Inspection.
The report covered an announced inspection by two emergency preparedness inspectors, an emergency response coordinator, and one reactor technology instructor. 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
None
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 December 7, 2011, 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 Central Emergency Control Center (CECC).
- 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 December 8, 2011, to evaluate the licensees self-assessment of its ERO performance during the exercise and to ensure compliance with 10 CFR 50 Appendix E.Section IV.F.2.g.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings were identified.
1EP4 Emergency Action Level and Emergency Plan Changes
a. Inspection Scope
Since the last NRC inspection of this program area, revisions 92, 93, and 94 to the Tennessee Valley Authority Nuclear Radiological Emergency Plan were implemented.
The licensee determined that in accordance with 10 CFR 50.54(q), 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 10CFR Part 50. The inspectors conducted a sampling review of the implementing procedure changes made between May 1, 2010, and November 30, 2011, 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, 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 inspectors reviewed the documents 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 were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
Cornerstone: Emergency Preparedness
The inspectors sampled licensee submittals for the three performance indicators (PI)listed below. For each of the submittals, the inspectors reviewed the period from January 1, 2010, through September 30, 2011. 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 6, 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 were identified.
4OA6 Meetings, including Exit
On December 9, 2011, the lead inspector presented the inspection results to Mr. K.
Polson and other members of station management. The inspector confirmed that proprietary information was not provided during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- J. Addison, Manager, Drills and Exercises
- S. Austin, Licensing Engineer
- A. Feltman, Emergency Preparedness Manager
- C. Gannon, Plant Manager
- J. Kulisek, Operations Training
- J. Parshall, Manager, EP Program Planning and Implementation
- K. Polson, Site Vice President
- B. Tidwell, EP Specialist
- R. Waldrep, EP Specialist