IR 05000390/2006008
| ML061840045 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/30/2006 |
| From: | Brian Bonser NRC/RGN-II/DRP/RPB2 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-06-008 | |
| Download: ML061840045 (11) | |
Text
SUBJECT:
WATTS BAR NUCLEAR PLANT - NRC INSPECTION REPORT 05000390/200608
Dear Mr. Singer:
On June 9, 2006, the US Nuclear Regulatory Commission (NRC) completed an inspection at your Watts Bar Nuclear Plant. The enclosed inspection report documents the inspection results, which were discussed on June 9, 2006, with Mr. J. Laughlin 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).
Should you have any questions concerning this letter, please contact us.
Sincerely,
/RA/
Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Docket Nos. 50-390 License No. NPF-90
Enclosure:
NRC Inspection Report 05000390/200608 w/Attachment: Supplemental Information
TVA 2
REGION II==
Docket No.: 50-390 License No.: NPF-90 Report No: 05000390/2006008 Licensee: Tennessee Valley Authority Facility: Watts Bar Nuclear Power Plant Location: 1260 Nuclear Plant Road Spring City, TN 37381 Dates: June 5 - 9, 2006 Inspectors: Lee Miller Senior Emergency Preparedness Inspector Section 1EP1,1EP4 James Kreh Emergency Preparedness Inspector Section 1EP1, 4OA1 Nathan Sanfilippo Emergency Preparedness Specialist Section 1EP1, 4OA1 Approved by: Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS IR 05000390/2006008; 06/5-9/2006; Watts Bar Nuclear Power Plant, Units 1; Baseline Inspection The report covered an announced inspection by a team of three emergency preparedness inspectors. The NRCs 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 Cornerstone: Emergency Preparedness None B. Licensee-Identified Violations.
None Enclosure
1. REACTOR SAFETY Cornerstone: Emergency Preparedness 1EP1 Exercise Evaluation a. Inspection Scope Prior to the inspection activity, an in-office review was conducted 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 was reviewed and assessed regarding the implementation of the risk-significant planning standards (RSPS) in 10 CFR 50.47 (b) (4), (5), (9), and (10), which are 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), Operational 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 FEMA 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 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.
Enclosure
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 for determining that changes had not decreased the effectiveness of the plan. The inspectors also evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Radiological Emergency Plan revision 80 was reviewed.
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 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 Preparedness in Support of Nuclear Power Plants, Revision 1, Regulatory Guide 1.101 were also used as references. This inspection activity represents one sample on an annual basis.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings No findings of significance were identified.
4. OTHER ACTIVITIES 4OA1 Performance Indicator (PI) Verification a. Inspection Scope The inspectors reviewed the licensees 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 inspectors examined data reported to the NRC for the period 10/01/2005 to 03/31/2006. Procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspectors verified the accuracy of the PI for ERO drill and exercise performance through review of a sample of drill and event records. The inspectors 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 inspectors Enclosure
verified the accuracy of the PI for alert and notification system 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 planning standard, Nuclear Energy Institute (NEI) 99-02, Revision 3, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria. This inspection activity represents three samples on an annual basis.
The inspectors 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 June 9, 2006, the team lead for the Emergency Preparedness Inspection presented the inspection results to Mr. J. Laughlin, Watts Bar Nuclear Plant Manager, and other members of his staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection.
ATTACHMENT: SUPPLEMENTAL INFORMATION Enclosure
SUPPLEMENTAL INFORMATION KEY POINTS OF CONTACT J. Laughlin, Plant Manager B. Marks, Manager, Emergency Services P. Pace, Manger, Licensing D. Voeller, Manager, Maintenance/Modifications J. Young, Emergency Preparedness Manager J. Parshall, Exercise Coordinator D. White, Operations Manager M. DaRoche, Site Nuclear Assurance Manager LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None LIST OF DOCUMENTS REVIEWED Section 1EP1: Exercise Evaluation Plans and Procedures Tennessee Valley Authority Nuclear Radiological Emergency Plan, Rev. 81 Problem Evaluation Reports 104697, Handling Sensitive Information 104681, Dose Assessment 104686, Search and Rescue 104685, Paperwork accuracy 104684, On-site Pager Repeater failed to activate on-site pagers 104683, Classification made using wrong EAL 104625, Fire Truck Improperly parked Section 1EP4: Emergency Action Level (EAL) and Emergency Plan Changes Plans and Procedures Tennessee Valley Authority Nuclear Radiological Emergency Plan, Rev. 80 CECC EPIP-1, Central Emergency Control Center (CECC) Operations, Rev. 43 A-1 Attachment
CECC EPIP-3, Operations Duty Specialist Procedure for Alert, Rev. 34 CECC EPIP-7, CECC Radiological Assessment, Staff Procedure for Alert, Site Area Emergency, and General Emergency, Rev. 30 CECC EPIP-8, Dose Assessment Staff Activities during Nuclear Plant Radiological Emergencies, Rev. 28 EPIP-3, Alert, Rev. 27 EPIP-4, Site Area Emergency, Rev. 28 EPIP-5, General Emergency, Rev. 33 Change Packages 10 CFR 50.54(q) change package Radiological Emergency Plan, Rev. 80 Section 4OA1: Performance Indicator (PI) Verification Records and Data Q4 2005 DEP evaluation sheets and ERO participation logs Q1 2006 DEP evaluation sheets and ERO participation logs Drill package and scenario - 3/14/06 Documentation of ANS tests, 10/01/2005 - 03/31/2006 LIST OF ACRONYMS ANS Alert and Notification System CFR Code of Federal Regulations DEP Drill and Exercise Performance EAL Emergency Action Level EOF Emergency Operations Facility EP Emergency Plan ERO Emergency Response Organization NRC Nuclear Regulatory Commission OSC Operational Support Center PI Performance Indicator RSPS Risk Significant Planning Standard TSC Technical Support Center FEMA Federal Emergency Management Agency A-2 Attachment