IR 05000302/2007501

IR 05000302-07-501; 04/23-27/07; Crystal River Unit 3; Routine Baseline Inspection

ML071490369
Person / Time
Site:	Crystal River
Issue date:	05/25/2007
From:	Brian Bonser NRC/RGN-II/DRS/PSB1
To:	Young D Florida Power Corp, Progress Energy Florida
References
IR-07-501
Download: ML071490369 (14)

Text

SUBJECT:

CRYSTAL RIVER UNIT 3 - NRC EMERGENCY PREPAREDNESS INSPECTION REPORT 05000302/2007501

Dear Mr. Young:

On April 27, 2007, the U. S. Nuclear Regulatory Commission (NRC) completed an inspection at your Crystal River Unit 3 Plant. The enclosed inspection report documents the inspection findings, which were discussed on April 27, 2007, with you and 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).

FPC 2 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 No.: 50-302 License No.: DPR-72

Enclosure:

NRC Inspection Report 05000302/2007501 w/Attachment: Supplemental Information

REGION II==

Docket No: 50-302 License No: DPR-72 Report No: 05000302/2007501 Licensee: Progress Energy Florida (Florida Power Corporation)

Facility: Crystal River Unit 3 Location: 15760 West Power Line Street Crystal River, FL 34428-6708 Dates: April 23-27, 2007 Inspector: James L. Kreh, Emergency Preparedness Inspector Approved by: Brian R. Bonser, Chief Plant Support Branch 1 Division of Reactor Safety Enclosure

SUMMARY OF FINDINGS

IR 05000302/2007501; 04/23-27/2007; Crystal River Unit 3; Routine Baseline Inspection

This report covers an announced inspection conducted by a Region II 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.

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 (ANS) Evaluation

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, 02, Alert and Notification System Evaluation. The applicable planning standard 10 CFR 50.47(b)(5) and related requirements contained in Section IV.D of Appendix E to 10 CFR Part 50 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 activity represents one sample 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) Staffing and Augmentation System

a. Inspection Scope

The inspector reviewed the ERO augmentation staffing requirements and the process for notifying ERO personnel to ensure the readiness of key staff to respond to an event and the capability for timely activation of emergency response facilities (ERFs).

The results of an unannounced off-hours augmentation drill (which included actual travel and staffing of ERFs) conducted on October 25, 2006 were reviewed. The inspector evaluated the licensees provisions for a backup notification system. A sample of problems identified from augmentation drills was reviewed to assess the effectiveness of corrective actions.

The inspection was conducted in accordance with NRC Inspection Procedure 71114, 03, Emergency Response Organization Staffing and Augmentation System. The applicable planning standard 10 CFR 50.47(b)(2) and related requirements contained in Appendix E to 10 CFR Part 50 were used as reference criteria. This inspection activity represents one sample 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, Revision 26 of the Radiological Emergency Response Plan was implemented based on the licensees determination, in accordance with 10 CFR 50.54(q), that 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 10 CFR Part 50. The inspector conducted a sampling review of the Plan changes 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 10 CFR 50.47(b)(4) and related requirements contained in 10 CFR 50.54(q) and Appendix E to 10 CFR Part 50 were used as reference criteria. This inspection activity represents one sample 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

a. Inspection Scope

The inspector reviewed a sample of the corrective actions identified through the emergency preparedness (EP) program in order to ascertain the significance of the issues and to determine whether repetitive problems were occurring. The facilitys self-assessments and audits were reviewed to evaluate the licensees ability to be self-critical, thus avoiding complacency and degradation of its EP program, and to assess the completeness and effectiveness of a sample of EP-related corrective actions. The inspector reviewed documentation associated with the one emergency declaration made since the last inspection of this program area.

The inspection was conducted in accordance with NRC Inspection Procedure 71114, 05, Correction of Emergency Preparedness Weaknesses. The applicable planning standard 10 CFR 50.47(b)(14) and related requirements contained in Appendix E to 10 CFR Part 50 were used as reference criteria. This inspection activity represents one sample 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.

4OA1 Performance Indicator (PI) Verification

Cornerstone: Emergency Preparedness

The inspector reviewed the licensees process for developing the data for the three EP PIs listed below, and examined data reported to the NRC for the four-quarter period April 1, 2006 - March 31, 2007. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 4, were used to verify the basis in reporting for each data element.

• Drill and Exercise Performance (DEP)

• ERO Drill Participation

• ANS Reliability The inspector verified the accuracy of the PI for 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 records of periodic system tests.

The inspection was conducted in accordance with NRC Inspection Procedure 71151, Performance Indicator Verification. This inspection activity represents three samples 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 April 27, 2007, the inspector presented the inspection results to Mr. W. Brewer, Acting Plant Manager, and other members of his staff. The inspector confirmed that although certain proprietary information was reviewed during the inspection, no proprietary information was retained by the inspector, and none appears in this report.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

M. Annacone, Manager, Engineering

W. Brewer, Manager, Maintenance (Acting Plant Manager)

P. Dixon, Manager, Nuclear Assessment

J. Stephenson, Supervisor, Emergency Preparedness

M. Van Sicklen, Superintendent, Operations Training

D. Young, Vice President, Crystal River Nuclear Plant

NRC Personnel

T. Morrissey, Senior Resident Inspector

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

None

Closed

None

Discussed

None