IR 05000327/2007501

IR 05000327-07-501 and 05000328-07-501, on 05/05/07 - 05/11/07, Sequoyah Nuclear Power Plant

ML071550130
Person / Time
Site:	Sequoyah
Issue date:	06/01/2007
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Campbell W Tennessee Valley Authority
References
IR-07-501
Download: ML071550130 (14)

Text

une 1, 2007

SUBJECT:

SEQUOYAH NUCLEAR POWER PLANT - NRC INSPECTION REPORT 05000327/2007501 AND 05000328/2007501

Dear Mr. Campbell:

On May 11, 2007, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Sequoyah Nuclear Power Plant. The enclosed inspection report documents the inspections results, which were discussed 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 inspector 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 1 Division of Reactor Safety Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79

Enclosure:

(See page 2)

TVA 2 Enclosure: NRC Inspection Report 05000327/2007501 and 05000328/2007501 w/Attachment: Supplemental Information

REGION II==

Docket Nos.: 50-327, 50-328 License Nos.: DPR-77, DPR-79 Report Nos.: 05000327/2007501, 05000328/2007501 Licensee: Tennessee Valley Authority Facility: Sequoyah Nuclear Power Plant Location: 2600 Igou Ferry Soddy-Daisy TN 37379 Dates: May 5 - 11, 2007 Inspector: L. Miller, Senior Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000327/2007501, 05000328/2007501; 05/07-11/2007; Sequoyah Nuclear Power Plant,

Units 1 and 2; routine baseline inspection.

The report covered an announced inspection by one emergency preparedness inspector. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4, dated December 2006.

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 inspector 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 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 evaluation 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; and Federal Emergency Management Agency (FEMA) Report REP-10, Guide for the Evaluation of Alert and Notification Systems for Nuclear Power Plants were also applied. This inspection satisfied one inspection sample for Alert and Notification System Testing on a biennial cycle.

The inspector 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 inspector 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 18, 2007, unannounced off-hours augmentation drill were reviewed. The inspector conducted a review of the backup notification systems. The qualification records of key position ERO personnel were reviewed to ensure 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. This inspection satisfied one inspection sample for Emergency Response Organization (ERO) Augmentation on a biennial cycle.

The inspector 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

Since the last NRC inspection of this program area, Radiological Emergency Plan Appendix B revision 84 and Radiological Emergency Plan revisions 82 and 84 were implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that the changes resulted in no decrease in 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 50. The inspector conducted a sampling review of the Emergency Plan changes to evaluate for potential decreases in effectiveness of the Plan. 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 criteria contained in NUMARC/NESP-007, Methodology for Development of Emergency Action Levels, Revision 2, and Regulatory Guide 1.101 were also used as references. This inspection satisfied one inspection sample for Emergency Action Level (EAL) and Emergency Plan Changes on an annual cycle.

The inspector 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 Weaknesses and Deficiencies

a. Inspection Scope

The inspector 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, the inspector reviewed licensee self-assessments and audits to assess the completeness and effectiveness of a sample of its 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. This inspection satisfied one inspection sample for Correction of Emergency Preparedness Weaknesses and Deficiencies on a biennial cycle.

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

Findings No findings of significance were identified.

4OA1 Performance Indicator (PI) Verification

a. Inspection Scope

The inspector reviewed the licensees procedure for developing the data for the three Emergency Preparedness PIs which are:

(1) Drill/Exercise Performance (DEP);

(2) ERO Drill Participation; and

(3) Alert and Notification System (ANS) Reliability. The inspector examined data reported to the NRC for the period July, 2006 to March, 2007. The procedural guidance for reporting PI information and records used by the licensee to identify potential PI occurrences were also reviewed. The inspector verified the accuracy of the PI for ERO DEP through review of a sample of drill and event records.

The inspector 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 inspector 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, 10 CFR 50.9 and Nuclear Energy Institute (NEI) 99-02,Regulatory Assessment Performance Indicator Guidelines, Revision 4, were used as reference criteria. This inspection satisfied three inspection samples for Performance Indicator (PI) Verification on an annual cycle.

The inspector 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 May 11, 2007, the lead inspector for the emergency preparedness inspection presented the inspection results to R. Douet, Site Vice President, and other members of the licensees staff. The inspector confirmed that proprietary information was not provided or taken during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

R. Douet, Site Vice President

D. Kulisek, Plant Manager

B. Marks Emergency Services Manager, Corporate

K. Wilkes, Emergency Preparedness Manager

T. Niessen, Site Quality Manager

R. Proffitt, Nuclear Engineer

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

None

Closed

None

Discussed

None Attachment