IR 05000348/2007501

IR 05000348-07-501, 05000364-07-501, on 09/10-14/2007, Joseph M. Farley Nuclear Plant, Baseline Inspection

ML072880597
Person / Time
Site:	Farley
Issue date:	10/12/2007
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Jerrica Johnson Southern Nuclear Operating Co
References
IR-07-501
Download: ML072880597 (12)

Text

ber 12, 2007

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000348/2007501 AND 05000364/2007501

Dear Mr. R. Johnson:

On September 14, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed an Emergency Preparedness inspection at your Joseph M. Farley Nuclear Plant, Units 1 and 2.

The enclosed inspection report documents the inspection results, which were discussed on September 14, 2007, 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 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).

Sincerely,

/RA/

Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos. 50-348, 50-364 License Nos. NPF-2, NPF-8

Enclosure:

NRC Inspection Report No. 05000348/2007501, 05000364/2007501w/Attachment:

Supplemental Information

REGION II==

Docket Nos: 50-348, 50-364 License Nos: NPF-2, NPF-8 Report Nos: 05000348/2007501, 05000364/2007501 Licensee: Southern Nuclear Operating Company Facility: J. M. Farley Nuclear Plant Location: Columbia, AL 36319 Dates: September 10 - 14, 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 05000348/2007501, 05000364/2007501;09/10-14/2007;Joseph M. Farley Nuclear Plant;

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.

NRC-Identified and Self-Revealing Findings

No findings of significance were identified.

Licensee-Identified Violations

.

None

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness

1EP2 Alert and Notification System Evaluation

a. Inspection Scope

The inspector evaluated the adequacy of licensees 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 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 a reference.

The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the alert and notification system on an biennial basis.

b. Findings

No findings of significance were identified.

1EP3 Emergency Response Organization (ERO) Staffing and Augmentation System

a. Inspection Scope

The inspector reviewed the licensees ERO augmentation staffing requirements and process for notifying the ERO to ensure the readiness of key staff for responding to an event and timely facility activation. The qualification records of key position ERO personnel were 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 inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the ERO staffing and augmentation system on an biennial basis.

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 to determine that changes had not decreased the effectiveness of the plan. The inspector evaluated the associated 10 CFR 50.54(q)reviews associated with non-administrative emergency plan, implementing procedures and EAL changes. The inspector reviewed Farley Emergency Plan Revisions 46, 47, and 48 and changes to the implementing procedures from September 2006 to September 2007.

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, Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, and Regulatory Guide 1.101 were also used as references.

The inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the EAL and emergency plan changes on an annual basis.

b. Findings

No findings of significance were identified.

1EP5 Correction of Emergency Preparedness Weaknesses

a. Inspection Scope

The inspector reviewed the corrective actions identified through the Emergency Preparedness (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, inspector 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 inspector reviewed various documents which are listed in the Attachment to this report. This inspection activity satisfied one inspection sample for the correction of emergency preparedness weaknesses on an biennial basis.

Findings No findings of significance were identified.

4OA1 Performance Indicator Verification

a. Inspection Scope

The inspector sampled licensee submittals for the three performance indicators (PIs)listed below for units one and two. For each of the submittals reviewed, the inspector looked at the period from third quarter 2006 through the second quarter 2007. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Indicator Guideline, Revision 4, 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 inspector 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.

The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. The applicable PI, 10 CFR 50.9 and NEI 99-02, Revision 4, Regulatory Assessment Performance Indicator Guidelines, were used as reference criteria.

The inspector reviewed various documents which are listed in the Attachment to this report. This inspection satisfied three inspection samples for PI verification on an annual basis.

b. Findings

No findings of significance were identified.

4OA6 Meetings, including Exit

On September 14, 2007, the lead inspector presented the inspection results to you, and other members of your staff. The inspector confirmed that proprietary information was not provided during the inspection.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee personnel

R. Johnson, Vice President - Farley

W. Bargeron, Plant Manager

B. Moore, Site Support Manager

R. Wells, Operations Manager

J. Horn, Training Manager

S. Chestnut, Engineering Support Manager

C. Thornell, Maintenance Manager

R. Bayne, Performance Improvement Supervisor

W. Oldfield, Quality Assurance Supervisor

R. Vanderbye, Emergency Preparedness Coordinator