IR 05000390/2006009: Difference between revisions
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==4OA6 Meetings, including Exit== | ==4OA6 Meetings, including Exit== | ||
Revision as of 11:38, 22 December 2019
| ML063010016 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 09/22/2006 |
| From: | Brian Bonser NRC/RGN-II/DRS/PSB2 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-06-009 | |
| Download: ML063010016 (13) | |
Text
ber 22, 2006
SUBJECT:
WATTS BAR NUCLEAR PLANT - NRC INSPECTION REPORT 05000390/2006009
Dear Mr. Singer:
On September 7, 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 September 7, 2006, with Mr. M. Skaggs 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:
(See page 2)
TVA 2 Enclosure: NRC Inspection Report 05000390/200609 w/Attachment: Supplemental Information
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: Sept 5-8, 2006 Inspector: Lee Miller, Senior Emergency Preparedness Inspector Section 1EP2,1EP3, 1EP4, 1EP5, 4OA1 Approved by: Brian R. Bonser, Chief Plant Support Branch 2 Division of Reactor Safety Enclosure
SUMMARY OF FINDINGS
IR 05000390/2006009; 09/5-8/2006; Watts Bar Nuclear Power Plant, Units 1; Baseline
Inspection The report covered an announced inspection by a team of one emergency preparedness inspector. The Nuclear Regulatory Commissions (NRC) program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC-Identified and Self-Revealing Findings
Cornerstone: Emergency Preparedness
None
Licensee-Identified Violations
None
REPORT DETAILS
REACTOR SAFETY
Cornerstone: Emergency Preparedness
1EP2 Alert and Notification System Testing
a. Inspection Scope
The inspectors evaluated the adequacy of licensee 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 Code of Federal Regulation (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 references.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP3 Emergency Response Organization (ERO) Augmentation
a. Inspection Scope
The inspectors reviewed the ERO augmentation staffing requirements and the process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The results of the April 20, 2006, unannounced off-hours augmentation drill was reviewed. The inspectors conducted a review of the backup notification systems. The qualification records of key position ERO personnel was 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, 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 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 (EAL) and Emergency Plan Changes
a. Inspection Scope
The inspectors evaluated the associated 10 CFR 50.54(q) reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The Radiological Emergency Plan (Generic part Revision 82 and the Appendix C Watts Bar Nuclear Plant, Revision 80) were reviewed and covered the period from June 9, 2006 to August 5, 2006.
The inspection was conducted in accordance with NRC Inspection Procedure 71114, 01, 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, NUMARC/NESP-007, Methodology for Development of Emergency Action Levels, Revision 2, Regulatory Guide 1.101 were also used as references.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
1EP5 Correction of Emergency Preparedness (EP) Weaknesses and Deficiencies
a. Inspection Scope
The inspectors reviewed the corrective actions identified through the EP program to determine the significance of the issues and to determine if repeat problems were occurring. The facilitys self-assessments and audits were reviewed to assess the licensees ability to be self-critical, thus avoiding complacency and degradation of their EP program. In addition, inspectors reviewed licensees 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.
The inspectors reviewed various documents which are listed in the Attachment to this report.
b. Findings
No findings of significance were identified.
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 April 2005 to June 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 DEP 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 verified the accuracy of the PI for ANS 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, Revisions 3 and 4, 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 September 8, 2006, the team lead for the Emergency Preparedness Inspection presented the inspection results to Mr. M. Skaggs, Watts Bar Site Vice President, and other members of his staff. The inspectors confirmed that proprietary information was not provided or taken during the inspection.
ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- M. Skaggs, Site Vice President
- B. Marks, Manager, Emergency Services
- P. Pace, Licensing and Industry Affairs
- J. Bushnell, Licensing and Industry Affairs
- J. Young, Emergency Preparedness Manager
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
Discussed
None Attachment